DERR-1996-013813 - 0901a068805439e7

DOE ID No.: MS-00002-MR
Property Address: 248 Silverstone West Lane
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech of Energy (DQE)
Ra-226 is < 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [ ] Lab [XV
Ra-226 is < 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2.
In-situ [ ] Lab [XV
Interior gamma is <. 20 jjR/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is < 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21.
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
[X] [ ] [ 1
Ml] [ ]
[Xl [ 1 t ]
[*1 [ ] t ]
MM t ]
[V] [ ] [ ]
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
fQne sample represents both the surface and sub surface layers.
•llllllllll llllllllll
SFCERTIFED SFMS-0e002
SCANNED
DOE ID No.: MS-00002-MR
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
22 anda Jusby
Manager^ Monticello Programs
Rust Geotech
Date
DOE EVALUATION
[/fl Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
2.-L Od; ft
Certification Official
U.S. Department of Energy
Date
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00002-MR
ADDRESS: 248 SILVERSTONE WEST LANE
MONTICELLO, UTAH 84535
APRIL 1996
Prepared for
U.S. Department of Energy
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
by
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
Wanda S. Busby
Manager, Monticello Programs
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
• 3.1.2 Post-Excavation Survey 4
3.1.3 Radon Decay-Product Concentration (RDC) Measurement .... 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
i
DOE ID No.: MS-00002-MR
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Inclusion Survey Contractor. DOE reviewed
these evaluation results and determined that the property contained mill
tailings (residual radioactive material) exceeding EPA standards. The
Remedial Action Contractor was notified of the inclusion of this property
into the MVP Project and was authorized by DOE to conduct remedial
action as required to bring the property into conformance with EPA
standards and DOE hot spot criteria.
1
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
Property Address:
Property Owners:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
DOE ID No.: MS-00002-MR
MS-00002-MR
Lot 8, Silverstone West Subdivision, City
of Monticello, County of San Juan, State
of Utah
248 Silverstone West Lane
Monticello, Utah 84535

Major Residential (MR)
Oak Ridge National Laboratory
November 6, 1992
Rust Geotech
November 30, 1994
Diamond Back Services, Inc.
9861 Titan Park Circle
Littleton, Colorado
June 15, 1995
July 27, 1995
Interior: 6 cubic yards
Exterior: 1 cubic yard
11 square meters (m2)
April 1996
2
DOE ID No.: MS-00002-MR
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of interior and exterior residual
radioactive material (Appendix Figure 2.1). Once excavation was
complete, the affected areas were resurveyed for possible remaining
residual radioactive material and, upon attaining satisfactory results, were
backfilled with uncontaminated material. The property was restored to a
physical condition comparable to that which existed prior to remedial
action activities.
2.2 Previously Unidentified Contamination
The radiological assessment identified 6 cubic yards of contamination,
ranging from 6 inches deep to 150 inches high, within the property. The
remedial action process included the removal of approximately 7 cubic
yards of residual radioactive material, ranging from 9 inches deep to
150 inches high.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID No.: MS-00002-MR
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by the Remedial Action
Contractor during July 1993, as described in the final REA dated
November 1994. Appendix Figure 2.1 shows the extent of
assessed contamination and identifies the areas recommended to
undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the exterior excavation
were collected. These samples were blended to form composite
samples representing the exterior verification areas (Appendix
Figure 2.1).
Interior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 13 to 17 microroentgens per
hour (//R/h) for the remediated portion of the lower level, and 12
to 16 //R/h for the rest of the lower level (Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 12 to 20 //R/h (Appendix
Figure 2.1). The results of analyses for radium-226 in two
composite soil samples were 1.6 and 1.8 picocuries per
gram (pCi/g), as indicated in Appendix Table 3.1.
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on the DOE-approved abbreviated-measurement method,
the RDC was 0.0084 working level (WL), as indicated in Appendix
Table 3.2. Appendix Figure 2.1 shows the measurement location
on the lower level (the lowest habitable level of the structure).
4
DOE ID No.: MS-00002-MR
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at 248 Silverstone West Lane, in
Monticello, Utah, is recommended for certification as required by DOE
guidelines, and the appropriate records should be documented.
Certification Data Summary
Applicability
Habitable Structures
Exposure Rate:
Standards
Shall not exceed 20 //R/h
above background.*
Survey Results
Ranges were 13 to
17 //R/h for the
remediated portion of the
lower level, and 12 to
16 //R/h for the rest of
the lower level.
Radon Decay-Product
Concentration:
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Average was 0.0084 WL,
based on the DOE-
approved abbreviated-
measurement method.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
< 5 pCi/g above
background.**
Soil sample results were
1.6 and 1.8 pCi/g.***
*The background exposure rate is approximately 13//R/h.
The background radium-226 concentration is approximately 2.0 pCi/g.
**Part of sample V-3 was from the 15-cm surface layer.
n*he hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-00002-MR
4.0 APPENDIX
Appendix Tables:
Table 3.1 Post-Excavation Sample/Measurement Results
Table 3.2 Radon Decay-Product Concentration Measurement
Results
Appendix Figure:
Figure 2.1 Interior and Exterior Extent of Contamination -
RADIOLOGICAL AS-BUILT
SJW:02-14-96
MS-00002.MR WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00002-MR
Address: 248 Silverstone West Lane, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (//R/h) Ticket No. Method" (pCi/g)
EXTERIOR
V-2 13-20 NCJ 029 OCS 1.8
V-3 14-16 NCJ 030 OCS 1.6
INTERIOR
V-1 13-17 Not applicable
See Appendix Figure 2.1 for the verification areas.
"OCS = Opposed Crystal System
7
Table 3.2
Radon Decay-Product Concentration Measurement Results
DOE ID No.: MS-00002-MR
Address: 248 Silverstone West Lane, Monticello, Utah
Instrument Type: Landauer Radtrak Detector
Radon
Detector Tracks Per Concentration Working
Number Start Date End Date mm2 (pCi/L) Level
3973973 07-25-95 11-15-95 5.5 1.74 0.0087
3973919 07-25-95 11-15-95 5.1 1.61 0.0081
3973826 07-25-95 11-15-95 5.3 1.67 0.0084
Average: 0.0084
See Appendix Figure 2.1 for the measurement location.
8
10
.30
12 14 16 20 22 24 26 28 3C 32 34 38 40
30
28
26
24
22
20 -
18 -
16
14
12
Y
10
V-2
13-20
r
V-2
13-20
BI-LEVEL
FRAME HOUSE
SEE DETAIL A
12-16 12-15
U)
Lu
o
U)
Ld
>
_J CO
C X 2 2
V-3
14-16
LOWER LEVEL
12-16
[56]
h©
-[150]
-[84]
Ks)
-[96]
DETAIL A
NOT TO SCALE
SCALE IN FEET
20 10 0 20 40
M:\FAS\033\0003\RM00002V 03/22/96 09:51am T50780
NORTH
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT, UTILITY LOCATION PLAT. OR OTHER IMPROVEMENT SURVEY
PLAT AND IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE, BUILDING. OR OTHER FUTURE IMPROVEMENT LINES.
V- 1
13-17
®
tv.vj
12-15
12
V-1
16-17
[12]
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN /xR/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION AREA IDENTIFIER AND
EXCAVATION EXPOSURE-RATE RANGE
RADON DECAY-PRODUCT CONCENTRATION
MEASUREMENT LOCATION
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
HEIGHT IN INCHES OF ASSESSED CONTAMINATED
MORTAR REMOVED AND REPLACED
28
26
24
22
20
18
RADIOLOGICAL AS-BUILT
FIGURE 2.1
INTERIOR AND EXTERIOR EXTENT OF CONTAMINATION
1 6
RESIOENCE-NO. OF OCCUPANTS
NON-RESIDENCC-VAN-HRS./*K.
INSTRUVENT NO.
VERIFICATION
CK. A.E. APP. NO. DATE BT CK. A.E. APP,
1 4
faff
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE, COLORADO
«ciT
248 SILVERSTONE WEST LANE
MONTICELLO, UTAH
1 2
RUST Rust Qeotech
AVMl
APPROVAL DOE
DOEIONO. MS-00002-MR
owe NO. 3-B00002-V1 1 or 1 1 0
10 12 14 1 6 18 20 22 24 26 28 30 32 34 36 38 40
OAK RIDGE NATIONAL LABORATORY PHONE: [phone]
FAX: [phone] MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
FOR THE U.S. DEPARTMENT OF ENERGY
POST OFFICE BOX 2587
GRANO JUNCTION, COLORADO 81502 JUL ? I i&6
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by
the U.S. Department of Energy for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program (FUSRAP) and Remote Surplus Facilities Management Program
Sites (SFMP) [Revision 2, March 1987]. This evaluation is based on an independent verifi-
cation review of the Remedial Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment of
the 226Ra concentration in the soil, indoor radon daughter concentration, and indoor gamma
exposure rates at this property.
This property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
Location Number:
Location Address: 248 Silverstone West Lane
MS00002-MR
Monticello, Utah 84535
Property Owner:
Owner Address:

Tenant Name: Same
Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
248 SILVERSTONE WEST LANE
MONTICELLO, UTAH (MS00002-MR)
M. J. Wilson-Nichols
July 1996
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 3
REFERENCES 6
iii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 4
2. Results of ORNL analysis of Geotech soil samples from 248 Silverstone West Lane,
Monticello, Utah (MS00002-MR) 5
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site
Decommissioning Projects, U.S. Department of Energy. The author wishes to
acknowledge M. K. Jensen for analysis of soil samples and N. F. Kirby and A. R.
Jones for technical reviews.
vii
ABSTRACT
In 1980 the site of a vanadium and uranium mill at Monticello, Utah, was accepted
into the U.S. Department of Energy's (DOE's) Surplus Facilities Management Program,
with the objectives of restoring the government-owned mill site to safe levels of radio-
activity, disposing of or containing the tailings in an environmentally safe manner, and
performing remedial actions on off-site (vicinity) properties that had been contaniinated
by radioactive material resulting from mill operations. During 1995, RUST Geotech, the
remedial action contractor designated by DOE, performed remedial action on the vicinity
property at 248 Silverstone West Lane, Monticello, Utah. The Environmental Technology
Section (ETS) of Oak Ridge National Laboratory was assigned the responsibility of veri-
fying the data supporting the adequacy of remedial action and confirming the site's compli-
ance with DOE guidelines. The ETS found that the site successfully meets the DOE re-
medial action objectives. Procedures used by the ETS are described in the Environmental
Technology Section Procedures Manual (ORNL 1993).
ix
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 248 SILVERSTONE WEST LANE
MONTICELLO, UTAH (MS00002-MR)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the U.S. government through the
Defense Plant Corporation to provide vanadium during World War U. Various govern-
ment agencies operated the mill until 1947. In 1948 the Atomic Energy Commission
(AEC) obtained the mill and operated it under contract through 1959 to provide both
uranium and vanadium. Mill operations were terminated on January 1, 1960. In 1961 the
mill tailings piles were leveled and graded, covered with rock and soil, and seeded with na-
tive grasses. During 1974 and 1975, the ore stockpiles were removed from the site, and
the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city
of Monticello, in San Juan County, Utah. The site is bordered on the south and southeast
by land held by the U.S. Bureau of Land Management. Other boundaries are the city of
Monticello and private property.
During the AEC era, the mill processed approximately one million tons of uranium
ore. Vanadium and uranium were the only substances extracted in the milling process.
Other constituents of the ore remained in the tailings and were not separated prior to dis-
posal. During the years of active mill operation, the mill tailings were normally moist, so
erosion was minimal. However, throughout the mill's operating period, area residents
used these tailings as fill material and as aggregate in mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy
(DOE) initiated the Surplus Facilities Management Program (SFMP) in 1978 to ensure
the safe caretaking and decommissioning of government facilities that had been retired
from service but still had radioactive contamination. In 1980 the mill site at Monticello
was accepted into the SFMP, and the Monticello Remedial Action Project (MRAP) was
established to restore the government-owned mill site to safe levels of radioactivity, to
dispose of or contain the tailings in an environmentally safe manner, and to perform reme-
dial actions on off-site (vicinity) properties that had been contaminated by radioactive ma-
terial resulting from mill operations. The Monticello mill site and the tailings remain in the
custody of the DOE Grand Junction, Colorado, Projects Office. In 1983 remedial actions
for vicinity properties were separated from MRAP with establishment of the Monticello
Vicinity Properties (MVP) Project (U.S. DOE 1990b).
*The verification of remedial action was performed by members of the Environmental Assessment Group in the
Environmental Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE
contract DE-AC05-96OR22464 with Lockheed Martin Energy Research Corporation.
2
During 1995, RUST Geotech Inc. (Geotech), the remedial action contractor (RAC)
designated by DOE, performed remedial action on the vicinity property that is the subject
of this report, a single family residence located at 248 Silverstone West Lane, Monticello,
Utah. The remedial action plan required excavation of all interior and exterior contamina-
tion. When the excavation was completed, the property was resurveyed, including soil
sampling, to ensure the removal of all contamination, backfilled with uncontaminated
material, and restored to a condition comparable to that which existed prior to remedial
action (Geotech 1996).
The DOE adopted a policy to assign an independent contractor to verify the data
supporting the adequacy of remedial action and to confirm the site's compliance with DOE
guidelines. The Environmental Technology Section (ETS) of Oak Ridge National Labor-
atory (ORNL) has been assigned the responsibility of this task at the 248 Silverstone West
Lane site. This report describes the methods and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available doc-
umentation adequately and accurately describes the post-remedial-action radiological
conditions of the entire property that is to be certified and (2) that the remedial action
reduced contamination to below applicable DOE guidelines (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1996) in-
dicates the property was remediated as evaluated by DOE on the basis of Environmental
Protection Agency standards and the DOE guidelines (DOE 1990a). Excess residual
radioactive materials were present, thus it was appropriate to designate this property for
remedial action.
The pre-remedial-action survey performed by Geotech identified 6 yd3 of mill tailings
6 inches deep to 150 inches high. During the actual removal process, a total of 7 yd3 of
contaminated earth and uranium mill tailings, 9 inches deep to 150 inches high, was re-
moved from an 11 m2 area. The interior portion included 6 yd3 of contaminated mortar
removed and replaced.
A post-excavation survey was performed by Geotech prior to backfilling the exca-
vated areas. This survey consisted of gamma scans with a scintillometer of the ground
level ofthe structure, a surface scan of the exterior, and soil sampling. Samples repre-
sentative of the bottom 15-cm (6-in.) soil layers of two excavated verification areas were
collected and blended to form representative composite soil samples for each verification
area.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation
levels have not been subtracted. Similarly, background concentrations have not been sub-
tracted from radionuclide concentrations in soil samples. Applicable DOE guidelines for
protection against radiation are given in Table 1.
Gamma Measurements
Gamma exposure rate measurements taken by Geotech at the ground-level of the
residence ranged from 12 to 17 uR/h. Exterior surface gamma measurements taken from
the excavated areas prior to backfilling ranged from 13 to 20 uR/h.
Soil Sample Analysis
Prior to backfilling, Geotech collected soil samples representative of the excavated
areas from the bottom 15-cm (6-in.) soil layers. These samples were blended to form a
composite soil sample representative of an average over the two exterior verification
areas. Geotech's analysis of these samples showed ^Ra concentrations ranging from
1.6 to 1.8 pCi/g in the composite samples. ORNL ETS obtained a percentage of these
samples and performed a confirmatory analysis that showed ^Ra concentrations ranging
from 1.7 to 2.4 pCi/g. Verification sample V3 included material from the surface soil
interval. This sample result is below the EPA standard of 5 pCi/g for surface soil layers
<15 cm below the surface. These values are below the EPA standard value of 15 pCi/g
for soil layers >15 cm below the surface. Gamma ranges and/or soil sample results
demonstrate compliance to the DOE Hot Spot Guidelines for area <25 m2 (Table 1).
Results of Geotech and ORNL soil sample analyses are given in Table 2.
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were deter-
mined by the Alpha-track method. To monitor radon levels, Geotech placed three alpha-
track detectors on the ground floor of the residence located on this property for a period
of approximately three months (from July 25, 1995 to November 15, 1995). The average
annual working level (WL) of radon progeny concentration, as determined by the Tech./-
Ops-Landauer Corporation, was 0.0084, which is well below the 0.03-WL guideline given
in Table 1.
CONCLUSION
Results of Geotech soil sample analysis and confirmatory split soil sample analysis
by ORNL show that radionuclide concentrations are within applicable DOE guidelines.
Based upon the results of the post-remedial-action data, which are confirmed by the veri-
fication assessment data, these radiological measurements fall below the limits prescribed
by DOE guidelines. It is concluded that the site successfully meets the DOE remedial
action objectives.
4
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Radionuclide concen-
trations in soil for
Hot Spot areas
Exposure to 222Rn
progeny
Maximum permissible con-
centration of ^Ra in soil
above background levels,
averaged over a 100-m2 area
Maximum Permissible con-
centration of Ra226 in soil
above background level, for
areas less than 25 m2
Average annual radon proge-
ny concentration (including
background)
5 pCi/g averaged over the
first 15 cm of soil below the
surface; 15 pCi/g when ave-
raged over 15-cm-thick soil
layers more than 15 cm
below the surface
Ra226 concentrations, in any
surface or subsurface area
less than 25 m2, is below the
guideline by a factor of
(100/A)*, where A is the
area of the elevated region
0.03 WL
(DOE 1990a)
5
Table 2. Results of ORNL analysis of Geotech soil samples
from 248 Silverstone West Lane, Monticello Utah (MS00002-MR)
^Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No." NbJ (cm)
X2 NCJ029 >15 2.4 1.8
X3 NCJ030 5 to 20 1.7 1.6
" An X-type sample is a split of the sample taken by the remedial action contractor.
6 Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated areas
were taken by Geotech, and these samples were blended to form a composite soil
sample, which represents an average over one of the verification areas.
6
REFERENCES
Geotech 1996. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00002-MR, Address: 248 Silverstone West Lane, Monti-
cello, Utah 84535, Geotech, Grand Junction, Colorado, April 1996.
ORNL, 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
U.S. DOE 1990a. Verification and Certification Protocolfor the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination
and Decommissioning Program, Revision 3, November 1990. U.S. Department of
Energy, Washington, D.C.
U.S. DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision
and Record of Decision Summary. U.S. Department of Energy, Grand Junction Projects
Office, Grand Junction, Colorado.
DOE ID No.: MS-00013-RS
Property Address: 381 Abajo Drive, Monticello, Utah
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech of Energy (DOE)
Ra-226 is £ 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [ ]
Ra-226 is < 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2.
In-situ [ ] Lab [X]
Interior gamma is < 20 /jR/\n
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is <, 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21.
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
[*] [ ] [ )
[y] [ ] [ ]
l>] [ ] [ ]
[X] [ ] [ ]
[ 1 [*1 [ ]
[V] [ ] [ 1
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
illinium iiiiiii
SFCERTIFED SFMS-00013
DOE ID No.: MS-00013-RS
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
suppJemental standards per 40 CFR 192.21.
Wanda S. J3usby ' Date
Manager/Monticello Programs
Rust Geotech
DOE EVALUATION
[*] Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Certification Official Date
U.S. Department of Energy
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
DOE ID NO.: MS-00013-RS
ADDRESS: 381 ABAJO DRIVE
MONTICELLO, UTAH 84535
APRIL 1996
Prepared for
U.S. Department of Energy
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
' Wanda S. Busby
Manager, Monticello Programs
FOR
by
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 4
2.1 Abstract of Remedial Action Plan 4
2.2 Previously Unidentified Contamination 4
2.3 Unanticipated Items During Remedial Action 4
2.4 Application of Supplemental Standards 4
3.0 VERIFICATION SUMMARY 5
3.1 Radiological Survey Data 5
3.1.1 Pre-Remedial Action Survey 5
3.1.2 Post-Excavation Survey 5
3.1.3 Radon Decay-Product Concentration (RDC) Measurement .... 5
3.2 Recommendation for Certification 6
4.0 APPENDIX 7
DOE ID No.: MS-00013-RS
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Inclusion Survey Contractor. DOE reviewed
these evaluation results and determined that the property contained mill
tailings (residual radioactive material) exceeding EPA standards. The
Remedial Action Contractor was notified of the inclusion of this property
into the MVP Project and was authorized by DOE to conduct remedial
action as required to bring the property into conformance with EPA
standards and DOE hot spot criteria.
1
DOE ID No.: MS-00013-RS
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
MS-00013-RS
Location No. M-382; beginning 80 rods
south and 80 rods east of the NW corner of
Section 36, T33S., R23E., Salt Lake Base
Meridian; south 292 feet, east 549 feet,
north 292 feet, west 549 feet to the point
of beginning, City of Monticello, County of
San Juan, State of Utah
Property Address: 381 Abajo Drive
Monticello, Utah 84535
Property Owners:

Residential Simple (RS)
Oak Ridge National Laboratory
November 6, 1992
Rust Geotech
September 14, 1994
Diamond Back Services, Inc.
9861 Titan Park Circle
Littleton, Colorado
2
DOE ID No.: MS-00013-RS
1.3 Summary of Remedial Action (continued)
Pre-Construction Conference
Record: May 9, 1995
Notice of Final Completion
Inspection: September 13, 1995
Volume of Material Removed: Interior: 0 cubic yards
Exterior: 2,021 cubic yards
Area Cleaned Up: 2,484 square meters (m2)
Property Completion Report
Submitted: April 1996
3
DOE ID No.: MS-00013-RS
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of exterior residual radioactive
material (Appendix Figure 2.1). Once excavation was complete, the
affected areas were resurveyed for possible remaining residual radioactive
material and, upon attaining satisfactory results, were backfilled with
uncontaminated material. The property was restored to a physical
condition comparable to that which existed prior to remedial action
activities.
2.2 Previously Unidentified Contamination
The radiological assessment identified contamination, ranging from
18 inches deep to 40 inches high, within the property. The remedial
action process included the removal of approximately 2,021 cubic yards
of residual radioactive material, ranging from 144 inches deep to
40 inches high.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
4
DOE ID No.: MS-00013-RS
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by the Remedial Action
Contractor during August 1993, as described in the final REA
dated September 1994. Appendix Figure 2.1 shows the extent of
assessed contamination and identifies the areas recommended to
undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the excavation were
collected. These samples were blended to form composite
samples representing the verification areas (Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 13 to 25 microroentgens per
hour (/yR/h), as indicated on Appendix Figure 2.1. The results of
analyses for radium-226 in 31 composite soil samples ranged from
less than 1.0 to 7.3 picocuries per gram (pCi/g), as indicated in
Appendix Table 3.1.
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on the DOE-approved abbreviated-measurement method,
the RDC was 0.0132 working level (WL), as indicated in Appendix
Table 3.2. Appendix Figure 2.1 shows the measurement location
on the ground floor (the lowest habitable level of the structure).
RDC measurements were taken before remediation of the property.
5
DOE ID No.: MS-00013-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at 381 Abajo Drive, in Monticello, Utah,
is recommended for certification as required by DOE guidelines, and the
appropriate records should be documented.
Applicability
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Certification Data Summary
Standards
Shall not exceed 20 /vR/h
above background.*
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Survey Results
Range for the ground
floor was 12 to 13 //R/h.
Average was 0.O132 WL,
based on the DOE-
approved abbreviated-
measurement method.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
< 5 pCi/g above
background.**
Soil sample results
ranged from < 1.0 to
7.3 pCi/g.**
*The background exposure rate is approximately 13 yuR/h.
The background radium-226 concentration is approximately 2.0 pCi/g.
**The hot spot criteria were met based on gamma scans and/or soil sample results.
6
DOE ID No.: MS-00013-RS
4.0 APPENDIX
Appendix Tables:
Table 3.1 Post-Excavation Sample/Measurement Results
Table 3.2 Radon Decay-Product Concentration Measurement
Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
SJW:02-22-96
MS-00013.RS WP61
REV080195
7
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00013-RS
Address: 381 Abajo Drive, Monticello, Utah
A less-than sign (<) indicates that the minimum detection limit based on Compton
background was reached.
Area
Exposure-Rate
Range (//R/h)
Soil Sample
Ticket No.
Meas.
Method"
Radium-226
(pCi/g)
V-1
V-2
V-
V-
V-
V-
V-
-3
-4
-5
-6
-7
V-8
V-9
V-10
V-11
V-12
V-13
V-14
V-15
V-16
V-17
V-18
V-19
V-20
V-21
V-22
V-23
V-24
V-25
V-26
V-27
V-28
17 -
17 -
13 -
16 -
16 -
14 -
13 -
13 -
14-
14 -
14 -
14 -
14-
14 -
14 -
14 -
14 -
14 -
14 -
13 -
14 -
13 -
14 -
13 -
13 -
13 -
13 -
14 -
21
21
18
18
18
16
16
16
17
16
17
16
17
16
18
17
21
21
25
17
17
18
17
18
21
17
20
20
NCH 733
NCH 734
NCH 735
NCH 736
NCH 737
NCK 589
NCK 588
NCK 587
NCK 586
NCK 585
NCK 584
NCK 583
NCK 582
NCK 581
NCK 580
NCK 579
NCK 846
NCK 848
NCK 849
NCK 850
NCK 851
NCK 852
NCK 853
NCK 856
NCK 854
NCK 855
NCK 857
NCK 858
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
1.0
2.2
2.4
1.0
5
9
7
3
6
0.9
2.6
7.3
1.9
3.4
1.9
2.2
1.5
0.8
1.7
2.1
2.2
2.9
1.5
1.7
1.0
2.1
1.0
1.3
"OCS = Opposed Crystal System
8
Table 3.1 (continued)
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00013-RS
Address: 381 Abajo Drive, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (//R/h) Ticket No. Method" (pCi/g)
V-29 14- 25 NCK 859 OCS 1.9
V-30 16- 20 NCK 577 OCS 3.2
V-31 16-20 NCK 578 OCS 3.5
"OCS = Opposed Crystal System
See Appendix Figure 2.1 for the verification areas.
9
Table 3.2
Radon Decay-Product Concentration Measurement Results
DOE ID No.: MS-00013-RS
Address: 381 Abajo Drive, Monticello, Utah
Instrument Type: Landauer Radtrak Detector
Detector
Number Start Date End Date
Radon
Concentration
(pCi/L)
Working
Level
3973994
3973932
3974053
03-07-95
03-07-95
03-07-95
06-06-95
06-06-95
06-06-95
2.68 0.0134
2.19 0.0110
3.05 0.0153
Average: 0.0132
See Appendix Figure 2.1 for the measurement location.
10
1 6 20 22 24 26 28 30 42 32 34 38 40 44 4 6 48 50
42
40
ABAJO DRIVE 18XS 6 X R V-JO 40 LU LU. 16-20 LLL LLL LLL M^Mm. t4,°J
38 V-27 30
13-20 V-J1 V-31 48 38 1 44 16-20 16-20
v- ia
V-26 V-28 14-21 30 • y 10 7 (A 3-17 36 72 /• 14-20
/ ^6 L_
36 V-25 V-1 7 I 44 V-16 13-21 <6> (Toj v-i
14-17
17-21
34
V-1 7
14-21 RDC 34
Li 44 13-15 V-15 V-14
V-13 V-2 ONE STORY
BRICK HOUSE
12-13
14-18 32 V-19 14-16 60 18 14-17 17-21 72 14-25 V-24
<D 0 32 13-18
v-28 © EE 0 36 14-20 30
V-3 V-10 10 12 24 v- i 30 27 V-23 96 EH 13-18 84 4-14-17 14-16 14-17 V-20
3 <D 36 13-17 28 14-21
84 I © I © GARAGE
13-16 28 18 V-28 © V-9 HI6J 9
14-20 V-7 14-17 V-6 V-4
R V-22 13-16 14-16 16-18 26 0 1J-I8
12
72 26 V-29 V-29 8 11 2X J
14-25 14-25
\Y.Y.<I 2
12 24 K X 6
V-21 \ 12 24
® 14-17
16-18 22 V-17 13-17 V-29
13-15 13-15 14-21 14-25 22
NORTH DETAIL A
20
LEGEND ABAJO DRIVE 20 SCALE IN FEET ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN fiR/h
ASSESSED AREA IDENTIFIER 1 © 20 10 18 20 40
13-15
© AVERAGE DEPTH OF ASSESSED CONTAMINATION
iL'vj AREA 0F ASSESSED CONTAMINATION
12-15 POST-REMEDIAL ACTION EXPOSURE-RATE RANGE
—— BOUNDARY OF EXCAVATION
18 THIS DRAWING IS FOR THE SOLE USE Or THE U S DEPARTMENT
Of ENERCT ANO ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT. UTILITY LOCATION PLAT. OR OTHER IMPROVEMENT SURVEY
£t*JriS£'S "0T T° BE REUED UP0N F0* '« ESTABLISHMENT OF FENCE. BUILDING. OR OTHER FUTURE IMPROVEMENT LINES
SEE DETAIL A
•
16
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
££JlAGE EXCAVATED DEPTH FOR THE DEPOSIT OF CONTAMINATION
v-i VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE-RATE RANGE 14 16 -1 7
4 RADON DECAY-PRODUCT CONCENTRATION
MEASUREMENT LOCATION ROC 13-15
- I » I ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
•"•WCt-lM. OT OCCU.MH
U.S. DEPARTMENT OF ENERGY
Cy*P iUNCTlQN PtOJCCTS OFFICE. COLORADO
nW??' ,N ,NCHES °F ASSESSED CONTAMINATED ROCK WALL REMOVED AND REPLACED [12] 381 ABAJO DRIVE
MONTICELLO. UTAH L •
1 X
NOT TO SCALE 3^ ^3 \FAS\033\0OO3\RUO0013V 04/02/96 3:32pm T307«0
10 Hull OMtech MS-00013-RS
•»•»—»-. H ~ 3-C00013-V1 1 „ 1 10 14 16 20 22 24 26 28 30 32 10 34 36 36 40 42 44 46 48 50
OAK RIDGE NATIONAL LABORATORY
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
FOR THE U.S. DEPARTMENT OF ENERGY
PHONE: [phone]
FAX: (970)24*6220
POST OFFICE BOX 2567
GRAND JUNCTION. COLORADO 81502 JUL 3 1 1996
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by
the U.S. Department of Energy for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program (FUSRAP) and Remote Surplus Facilities Management Program
Sites (SFMP) [Revision 2, March 1987]. This evaluation is based on an independent verifi-
cation review of the Remedial Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment of
the 226Ra concentration in the soil, indoor radon daughter concentration, and indoor gamma
exposure rates at this property.
This property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
Location Number:
Location Address:
Tenant Name:
MS00013-RS
381 Abajo Drive
Monticello, Utah 84535
Robert Curtis Holden
5 Property Owners:

HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
381 ABAJO DRIVE
MONTICELLO, UTAH (MS00013-RS)
N. F. Kirby
July 1996
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 4
REFERENCES 7
iii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 5
2. Results of ORNL analysis of Geotech soil samples from 381 Abajo Drive,
Monticello, Utah (MS00013-RS) 6
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site
Decommissioning Projects, U.S. Department of Energy. The author wishes to
acknowledge M. K. Jensen for analysis of soil samples and A. R. Jones and M. J.
Wilson-Nichols for technical reviews.
vii
ABSTRACT
In 1980 the site of a vanadium and uranium mill at Monticello, Utah, was accepted
into the U.S. Department of Energy's (DOE's) Surplus Facilities Management Program,
with the objectives of restoring the government-owned mill site to safe levels of radio-
activity, disposing of or containing the tailings in an environmentally safe manner, and
performing remedial actions on off-site (vicinity) properties that had been contaniinated
by radioactive material resulting from mill operations. During 1995, RUST Geotech, the
remedial action contractor designated by DOE, performed remedial action on the vicinity
property at 381 Abajo Drive, Monticello, Utah. The Environmental Technology Section
(ETS) of Oak Ridge National Laboratory was assigned the responsibility of verifying the
data supporting the adequacy of remedial action and confirming the site's compliance with
DOE guidelines. The ETS found that the site successfully meets the DOE remedial action
objectives. All deficiencies noted in the initial review have been resolved with additional
information from the RAC. Procedures used by the ETS are described in the Environmen-
tal Technology Section Procedures Manual (ORNL 1993).
ix
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 381 ABAJO DRIVE
MONTICELLO, UTAH (MS00013-RS)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the U.S. government through the
Defense Plant Corporation to provide vanadium during World War JJ. Various govern-
ment agencies operated the mill until 1947. In 1948 the Atomic Energy Commission
(AEC) obtained the mill and operated it under contract through 1959 to provide both
uranium and vanadium. Mill operations were terminated on January 1, 1960. In 1961 the
mill tailings piles were leveled and graded, covered with rock and soil, and seeded with na-
tive grasses. During 1974 and 1975, the ore stockpiles were removed from the she, and
the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city
of Monticello, in San Juan County, Utah. The site is bordered on the south and southeast
by land held by the U.S. Bureau of Land Management. Other boundaries are the city of
Monticello and private property.
During the AEC era, the mill processed approximately one million tons of uranium
ore. Vanadium and uranium were the only substances extracted in the milling process.
Other constituents of the ore remained in the tailings and were not separated prior to dis-
posal. During the years of active mill operation, the mill tailings were normally moist, so
erosion was minimal. However, throughout the mill's operating period, area residents
used these tailings as fill material and as aggregate in mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy
(DOE) initiated the Surplus Facilities Management Program (SFMP) in 1978 to ensure
the safe caretaking and decommissioning of government facilities that had been retired
from service but still had radioactive contamination. In 1980 the mill site at Monticello
was accepted into the SFMP, and the Monticello Remedial Action Project (MRAP) was
established to restore the government-owned mill site to safe levels of radioactivity, to
dispose of or contain the tailings in an environmentally safe manner, and to perform reme-
dial actions on off-site (vicinity) properties that had been contaminated by radioactive ma-
terial resulting from mill operations. The Monticello mill site and the tailings remain in the
custody of the DOE Grand Junction, Colorado, Projects Office. In 1983 remedial actions
for vicinity properties were separated from MRAP with establishment of the Monticello
Vicinity Properties (MVP) Project (U.S. DOE 1990b).
*The verification of remedial action was performed by members of the Environmental Assessment Group in the
Environmental Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE
contract DE-AC05-96OR22464 with Lockheed Martin Energy Research Corporation.
2
During 1995, RUST Geotech Inc. (Geotech), the remedial action contractor (RAC)
designated by DOE, performed remedial action on the vicinity property that is the subject
of this report, a single family residence located at 381 Abajo Drive, Monticello, Utah. The
remedial action plan required excavation of all exterior contamination. When the excava-
tion was completed, the property was resurveyed, including soil sampling, to ensure the
removal of all contamination, backfilled with uncontaminated material, and restored to a
condition comparable to that which existed prior to remedial action (Geotech 1996).
The DOE adopted a policy to assign an independent contractor to verify the data
supporting the adequacy of remedial action and to confirm the site's compliance with DOE
guidelines. The Environmental Technology Section (ETS) of Oak Ridge National Labor-
atory (ORNL) has been assigned the responsibility of this task at the 381 Abajo Drive site.
This report describes the methods and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available doc-
umentation adequately and accurately describes the post-remedial-action radiological
conditions of the entire property that is to be certified and (2) that the remedial action
reduced contamination to below applicable DOE guidelines (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1996) in-
dicates the property was remediated as evaluated by DOE on the basis of Environmental
Protection Agency standards and the DOE guidelines (DOE 1990a). Excess residual
radioactive materials were present, thus it was appropriate to designate this property for
remedial action.
The pre-remedial-action survey performed by Geotech identified mill tailings 18 inches
deep to 40 inches high. During the actual removal process, a total of 2,021 yd3 of con-
taminated earth and uranium mill tailings, 144 inches deep to 40 inches high, were re-
moved from a 2,484 m2 area.
A post-excavation survey was performed by Geotech prior to backfilling the exca-
vated areas. This survey consisted of gamma scans with a scintillometer of the ground
level of the structure, a surface scan of the exterior, and soil sampling. Samples repre-
sentative ofthe bottom 15-cm (6-in.) soil layers of 31 excavated verification areas were
collected and blended to form representative composite soil samples for each verification
area.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation
levels have not been subtracted. Similarly, background concentrations have not been sub-
tracted from radionuclide concentrations in soil samples. Applicable DOE guidelines for
protection against radiation are given in Table 1.
Gamma Measurements
Gamma exposure rate measurements taken by Geotech at the ground-level of the
residence ranged from 12 to 13 uR/h. Exterior surface gamma measurements taken from
the excavated areas prior to backfilling ranged from 13 to 25 uR/h.
Soil Sample Analysis
Prior to backfilling, Geotech collected soil samples representative of the excavated
areas from the bottom 15-cm (6-in.) soil layers. These samples were blended to form a
composite soil sample representative of an average over the 31 exterior verification areas.
Geotech's analysis of these samples showed ^Ra concentrations to range from <1 to 7.3
pCi/g in the composite samples. ORNL ETS obtained a percentage of these soil samples
and performed a confirmatory analysis which showed ^Ra concentrations ranging from
0.9 to 6.1 pCi/g. These values are below the EPA standard value of 15 pCi/g for soil
layers > 15 cm below the surface. Results of Geotech and ORNL soil sample analyses are
given in Table 2.
As a result of a meeting between the RAC and IVC on May 26, 1994, anomalous
readings, defined as > 30% above the average of the excavation, will be investigated to
show compliance to the DOE hot spot guideline. The IVC observed that eight exterior
verification areas exceeded 30% of the average; the highest reading (Area VI9) had 25
uR/h, which exceeds 30% of the excavation average of 18 uR/h. The IVC will allow a
correlation developed by the RAC to estimate ^Ra concentrations (in pCi/g) based on
gamma exposure rates. The highest anomalous reading of 25 uR/h yields a ^Ra con-
centration of 4.4 pCi/g using the RAC's correlation. This value is well below the mini-
mum concentration of 30 pCi/g needed, when assuming the maximum area under the hot
spot guideline of 25 m2, for subsurface samples. Gamma ranges and/or soil sample results
demonstrate compliance to the DOE Hot Spot Guidelines for areas <25 m2 (Table 1).
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were deter-
mined by the alpha-track method. To monitor radon levels, Geotech placed three alpha-
track detectors on the ground floor of the residence located on this property for a period
of approximately three months (from March 17, 1995 to June 6, 1995). The average
4
annual working level (WL) of radon progeny concentration, as detennined by the Tech./-
Ops-Landauer Corporation, was 0.0132, which is below the 0.03-WL guideline given in
Table 1.
CONCLUSION
Results of Geotech soil sample analysis and confirmatory split soil sample analysis
by ORNL show that radionuclide concentrations are within applicable DOE guidelines.
Based upon the results of the post-remedial-action data, which are confirmed by the veri-
fication assessment data, these radiological measurements fall below the limits prescribed
by DOE guidelines. All deficiencies noted in the initial review have been identified by the
RAC and clarification provided as discussed in a meeting between Geotech and ORNL on
June 21, 1996. It is concluded that the site successfully meets the DOE remedial action
objectives.
5
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of ^Ra in soil
above background levels,
averaged over a 100-m2 area
5 pCi/g averaged over the
first 15 cm of soil below the
surface; 15 pCi/g when ave-
raged over 15-cm-thick soil
layers more than 15 cm
below the surface
Radionuclide
concentrations in soil
for Hot Spot areas
Exposure to 222Rn
progeny
Maximum Permissible con-
centration of Ra226 in soil
above background level, for
areas less than 25 m2
Average annual radon proge-
ny concentration (including
background)
Ra concentrations, in any
surface or subsurface area
less than 25 m2, is below the
guideline by a factor of
(lOO/A)*, where A is the
area of the elevated region
0.03 WL
(DOE 1990a)
6
Table 2. Results of ORNL analysis of Geotech soil samples
from 381 Abajo Drive, Monticello Utah (MS00013-RS)
'Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No.g No^ (cm)
X4 NCH 736 >15 1.3 1.0
X12 NCK 583 >15 6.1 7.3
X20 NCK 850 >15 1.4 2.1
X27 NCK 857 >15 0.9 <1.0
X31 NCK 578 >15 2.3 3.5
" An X-type sample is a split of the sample taken by the remedial action contractor.
* Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated areas
were taken by Geotech, and these samples were blended to form a composite soil
sample, which represents an average over one of the verification areas.
7
REFERENCES
Geotech 1996. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00013-RS, Address: 381 Abajo Drive, Monticello, Utah
84535, Geotech, Grand Junction, Colorado, April 1996.
ORNL, 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
U.S. DOE 1990a. Verification and Certification Protocol for the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination
and Decommissioning Program, Revision 3, November 1990. U.S. Department of
Energy, Washington, D.C.
U.S. DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision
and Record of Decision Summary. U.S. Department of Energy, Grand Junction Projects
Office, Grand Junction, Colorado.
DOE ID No.: MS-00020-RS
Property Addresses: 220 and 222 West Fourth South Street
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech of Energy (DOE)
Ra-226 is <. 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [X]
Ra-226 is £ 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2.
In-situ [ ] Lab [X]
Interior gamma is <; 20 //R/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is s 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21,
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
[X] [ ] [ ]
MM [ 1
[*1 [ 1 I 1
[ 1 [ ]
[ ] [M [ 1
[Y] [ ] [ ]
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the ranoe
of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
•iiiiiiiiin iiiiiiiiiii
SFCERTIFED SFMS-00020
DOE ID No.: MS-00020-RS
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
tenda S./0usby Date
Manager, Monticello Programs
Rust Geotech
DOE EVALUATION
[V] Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Certification Official ' Date
U.S. Department of Energy
/3 JJ ffi
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00020-RS
ADDRESSES: 220 AND 222 WEST FOURTH SOUTH STREET
MONTICELLO, UTAH 84535
APRIL 1996
Prepared for
U.S. Department of Energy
by
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
4*
Wa
Manager,
S. Busby
lonticello Programs
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.1.3 Radon Decay-Product Concentration (RDC) Measurement .... 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
DOE ID No.: MS-00020-RS
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Inclusion Survey Contractor. DOE reviewed
these evaluation results and determined that the property contained mill
tailings (residual radioactive material) exceeding DOE hot spot criteria.
The Remedial Action Contractor was notified of the inclusion of this
property into the MVP Project and was authorized by DOE to conduct
remedial action as required to bring the property into conformance with
EPA standards and DOE hot spot criteria.
1
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
Property Addresses:
Property Owners:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:'
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
DOE ID No.: MS-00020-RS
MS-00020-RS
Beginning 862.6 feet east and 706 feet
south of the NW corner of the SW4NW4 of
Section 36, T33S., R23E., Salt Lake Base
Meridian; north 70 feet, east 72 feet, south
70 feet, east 128 feet, south 25 feet, east
90.4 feet, south 47 feet, west 290.4 feet,
north 72 feet to the beginning, City of
Monticello, County of San Juan, State of
Utah
220 and 222 West Fourth South Street
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
November 6, 1992
Rust Geotech
September 14, 1994
Diamond Back Services, Inc.
9861 Titan Park Circle
Littleton, Colorado
July 7, 1995
August 31, 1995
Interior: 0 cubic yards
Exterior: 32 cubic yards
73 square meters (m2)
April 1996
2
DOE ID No.: MS-00020-RS
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of exterior residual radioactive
material (Appendix Figure 2.1). Once excavation was complete, the
affected areas were resurveyed for possible remaining residual radioactive
material and, upon attaining satisfactory results, were backfilled with
uncontaminated material. The property was restored to a physical
condition comparable to that which existed prior to remedial action
activities.
2.2 Previously Unidentified Contamination
The radiological assessment identified 19 cubic yards of contamination,
ranging from 6 inches deep to 36 inches high, within the property. The
remedial action process included the removal of approximately 32 cubic
yards of residual radioactive material, ranging from 42 inches deep to
36 inches high.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID No.: MS-00020-RS
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by the Remedial Action
Contractor during July 1993, as described in the final REA dated
September 1994. Appendix Figure 2.1 shows the extent of
assessed contamination and identifies the areas recommended to
undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the excavation were
collected. An individual soil sample was collected for Area V-6.
The remaining samples were blended to form composite samples
representing the verification areas (Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 13 to 19 microroentgens per
hour (#R/h), as indicated on Appendix Figure 2.1. Residual
radioactive material was left in place in Area V-6 to avoid causing
permanent damage to a mature tree. The result of analysis for
radium-226 in an individual soil sample of this area was
7.4 picocuries per gram (pCi/g). The 100 m2 area average was
2.0 pCi/g (Appendix Table 3.1). Area V-6 also met the hot spot
criteria (Appendix Table 3.2). The results of analyses for
radium-226 in five composite soil samples ranged from 1.6 to
4.4 pCi/g (Appendix Table 3.3). In-situ measurement results for
radium-226 taken on the concrete footings of the assessed brick
planters in Areas V-3 and V-4 ranged from 0.5 to 1.4 pCi/g
(Appendix Table 3.3).
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on the DOE-approved abbreviated-measurement method,
the RDCs were 0.0020 working level (WL) for House 1 and
0.0026 WL for House 2 (Appendix Table 3.4). Appendix
Figure 2.1 shows the measurement location on each ground floor
(the lowest habitable level of each structure).
4
DOE ID No.: MS-00020-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at 220 and 222 West Fourth
South Street, in Monticello, Utah, is recommended for certification as
required by DOE guidelines, and the appropriate records should be
documented.
Certification Data Summary
Applicability
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Standards
Shall not exceed 20 //R/h
above background.*
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Survey Results
Ranges were 13 to
14//R/h for the ground
floor of House 1 .and
13 to 15 //R/h for the
ground floor of House 2.
Averages were
0.0020 WL for House 1
and 0.0026 WL for
House 2, based on the
DOE-approved
abbreviated-measurement
method.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
Soil sample result,
averaged over 100 m2,
was 2.0 pCi/g. In situ
measurements ranged
from 0.5 to 1.4 pCi/g.*
Soil sample results
ranged from 1.6 to
4.4 pCi/g.**
*The background exposure rate is approximately 13 //R/h.
The background radium-226 concentration is approximately 2.0 pCi/g.
**The hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-00020-RS
4.0 APPENDIX
Appendix Tables:
Table 3.1 Calculation of Average Radium Concentration
over a 100 m2 Area
Table 3.2 Hot Spot Calculation Results
Table 3.3 Post-Excavation Sample/Measurement Results
Table 3.4 Radon Decay-Product Concentration Measurement
Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
MRW:03-26-96
MS-00020.RS WP61
REV080195
6
Table 3.1
Calculation of Average Radium Concentration over a 100 m2 Area
DOE ID No.: MS-00020-RS
Address: 220 and 222 West Fourth South Street, Monticello, Utah
_ (CpXAp) + [Crx (1,076- Ap)]
Cavg = 1,076
Where:
Cava = Radium-226 concentration in picocuries per gram averaged over a
y 100 m2 (1,076 ft2) area.
Cp = Radium-226 concentration in picocuries per gram of the residual
radioactive material left in place.
Ap = Area in square feet of the residual radioactive material left in
place.
Cr = Radium-226 concentration in picocuries per gram for the
remainder of the 100 m2 area, including excavated and
unexcavated areas.
1,076 = Total area in square feet over which the EPA guideline is applied.
C_ AD Cr Cavq EPA
Meas. Depth HP » Standard
Area Method" (inches) (pCi/g) (ft2) (pCi/g) (pCi/g) (pCi/g)
V-6 OCS 00-06 7.4 8 2.0b 2.0 5.0°
Therefore, the averaged radium-226 concentration does not exceed the EPA
standard.
"OCS = Opposed Crystal System
bBackground radium-226 concentration.
The DOE-implemented EPA standard used for OCS measurements taken after
December 7, 1990, does not include the background radium concentration.
7
Table 3.2
Hot Spot Calculation Results
DOE ID No.: MS-00020-RS
Address: 220 and 222 West Fourth South Street, Monticello, Utah
Shg = [Sgx(100/A) ]
Where:
Shq = Hot Spot Limit of radium-226 concentration in picocuries per gram.
Sq = Authorized Limit of radium-226 concentration in picocuries per gram
(Sfl = 5.0 pCi/g for surface soil and 15.0 pCi/g for subsurface
sons).
100 = Total area in square meters over which the Hot Spot Limit guideline
is applied.
A = Area in square meters of the hot spot.
A Sq Shg + Radium-226 in
Meas. Depth BackgToundb Hot Spot Area
Area Method" (inches) (m2) (pCi/g) (pCi/g) (pCi/g)
V-6 OCS 00-06 1 5.0 52.0 7.4
Therefore, the radium-226 concentration in the hot spot area does not exceed the
maximum allowable concentration.
"OCS = Opposed Crystal System
bMaximum allowable radium-226 concentration (the background radium-226
concentration for Monticello is 2.0 pCi/g).
8
Table 3.3
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00020-RS
Addresses: 220 and 222 West Fourth South Street, Monticello, Utah
Area
Exposure-Rate
Range (//R/h)
Soil Sample
Ticket No.
Meas.
Method"
Radium-226
(pCi/g)
V-1
V-2
V-3
V-4
V-5
V-6
16
15
16
15
16
16
18
18
19
17
18
18
NCH 657
NCL 612
NCL 637
NCL 613
NCL 614
NCH 656
OCS
OCS
OCS
OCS
OCS
OCS
3.5
2.8
4.4b
2.6°
1.6
7.4
See Appendix Figure 2.1 for the verification areas.
"OCS = Opposed Crystal System
bln situ (delta scanner) measurement results taken on the concrete footings were
1.3 and 1.2 pCi/g.
cln situ (delta scanner) measurement results taken on the concrete footings were
0.5 and 1.4 pCi/g.
9
Table 3.4
Radon Decay-Product Concentration Measurement Results
DOE ID No.: MS-00020-RS
Addresses: 220 and 222 West Fourth South Street, Monticello, Utah
Instrument Type: Landauer Radtrak Detector
Radon
Detector Concentration Working
Number Start Date End Date (pCi/L) Level
HOUSE 1
3964177
3964193
3964117
3964361
3964375
3964333
02-28-95
02-28-95
02-28-95
02-28-95
02-28-95
02-28-95
05-31-95
05-31-95
05-31-95
HOUSE 2
05-31-95
05-31-95
05-31-95
0.46
0.33
0.38
0.60
0.46
0.52
0.0023
0.0017
0.0019
Average: 0.0020
0.0030
0.0023
0.0026
Average: 0.0026
See Appendix Figure 2.1 for the measurement locations.
10
1
42
40
38
36
34
32
30
28
26
24
22
20
18
16
14
12
10
12 14 16 18 20 22 24 26 28 30 32 34 36 38 40 42 44 46 48 so
13-14
O
DETAIL A
NOT TO SCALE
I SEE DETAIL A
.SHED
13uR/h r
V-2
15-18
METAL SHED
13-17 (Soc)
[36]
1 TWO STORY BRICK
HOUSE 2
13-15
13-14 SHED
13uR/h
ONE STORY
FRAME
HOUSE 1
CARPORT
13-14 0N V-3
16-19 ROC
V-4 GREENHOUSE
(DEMOLISHED) 42 16] 13-14 15-17
V-5 [24TD
16-18 13-14
13-14 13-14
J
WEST FOURTH SOUTH STREET
®
<D
Lv.vj
12-15
0
v-i
16-17
L
SCALE IN FEET
20 10 0 20 40
y.\FAS\OJ3\OOOJ\RU00020V 04/17/96 1:99pm T907B0
Illlllll
o
NORTH
[12]
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST—REMEDIAL ACTION EXPOSURE —RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE—RATE RANGE
RADON DECAY-PRODUCT CONCENTRATION
MEASUREMENT LOCATION
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
AREA WITH CONTAMINATION LEFT IN PLACE
HEIGHT IN INCHES OF ASSESSED CONTAMINATION
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. OEPARTUENT
OF ENERGY ANO ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT. UTILITY LOCATION PLAT, OR OTHER IMPROVEMENT SURVEY
PLAT ANO IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE. euiLOING. OR OTHER FUTURE IMPROVEMENT LINES.
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
J I J I I L
•ivoiiKt-M. or oMvuni
3CE
U.S. OEPARTUENT OF ENERGY
' ~ JUNCTION MOJCCTS OfftCt. COtOftADO
220 AND 222 WEST
FOURTH SOUTH STREET
MONTICELLO. UTAH
•nr""*- MS-00020-as
["«•-• J-C00O20-V1 JtL.
12 14 16 18 20 22 24 26 28 30 32 34 36 38 40 42 44 46 48 5<
OAK RIDGE NATIONAL LABORATORY
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
FOR THE U.S. DEPARTMENT OF ENERGY
PHONE: [phone]
FAX: [phone]
POST OFFICE BOX 2587
GRAND JUNCTION. COLORADO 81502
« z $ mi
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81S02
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by
the U.S. Department of Energy for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program (FUSRAP) and Remote Surplus Facilities Management Program
Sites (SFMP) [Revision 2, March 1987]. This evaluation is based on an independent verifi-
cation review of the Remedial Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment of
the 226Ra concentration in the soil, indoor radon daughter concentration, and indoor gamma
exposure rates at this property.
This property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
MS00020-RS
220 and 222 West Fourth South Street
Monticello, Utah 84535

Same
Location Number:
Location Address:
Property Owner:
Owner Address:
Tenant Name:
Attachments
f
t
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
220 AND 222 WEST FOURTH SOUTH STREET
MONTICELLO, UTAH (MS00020-RS)
M. J. Wilson-Nichols
June 1996
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 3
REFERENCES 6
iii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 4
2. Results of ORNL analysis of Geotech soil samples from 220 and 222 West Fourth
South Street, Monticello, Utah (MS00020-RS) 5
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site Decom-
missioning Projects, U.S. Department of Energy. The author wishes to acknowledge M.
K. Jensen for analysis of soil samples and A. R. Jones and N. F. Kirby for technical reviews.
vii
ABSTRACT
In 1980 the site of a vanadium and uranium mill at Monticello, Utah, was accepted
into the U.S. Department of Energy's (DOE's) Surplus Facilities Management Program,
with the objectives of restoring the government-owned mill site to safe levels of radio-
activity, disposing of or containing the tailings in an environmentally safe manner, and
performing remedial actions on off-site (vicinity) properties that had been contaminated
by radioactive material resulting from mill operations. During 1995, RUST Geotech, the
remedial action contractor designated by DOE, performed remedial action on the vicinity
property at 220 and 222 West Fourth South Street, Monticello, Utah. The Environmental
Technology Section (ETS) of Oak Ridge National Laboratory was assigned the responsi-
bility of verifying the data supporting the adequacy of remedial action and confirming the
site's compliance with DOE guidelines. The ETS found that the site successfully meets the
DOE remedial action objectives. All deficiencies noted in the initial review have been re-
solved in the revised completion report. Procedures used by the ETS are described in the
Environmental Technology Section Procedures Manual (ORNL 1993).
ix
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 220 AND 222 WEST FOURTH SOUTH STREET
MONTICELLO, UTAH (MS00020-RS)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the U.S. government through the
Defense Plant Corporation to provide vanadium during World War JJ. Various govern-
ment agencies operated the mill until 1947. In 1948 the Atomic Energy Commission
(AEC) obtained the mill and operated it under contract through 1959 to provide both
uranium and vanadium. Mill operations were terminated on January 1, 1960. In 1961 the
mill tailings piles were leveled and graded, covered with rock and soil, and seeded with na-
tive grasses. During 1974 and 1975, the ore stockpiles were removed from the site, and
the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city
of Monticello, in San Juan County, Utah. The site is bordered on the south and southeast
by land held by the U.S. Bureau of Land Management. Other boundaries are the city of
Monticello and private property.
During the AEC era, the mill processed approximately one million tons of uranium
ore. Vanadium and uranium were the only substances extracted in the milling process.
Other constituents of the ore remained in the tailings and were not separated prior to dis-
posal. During the years of active mill operation, the mill tailings were normally moist, so
erosion was minimal. However, throughout the mill's operating period, area residents
used these tailings as fill material and as aggregate in mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy
(DOE) initiated the Surplus Facilities Management Program (SFMP) in 1978 to ensure
the safe caretaking and decommissioning of government facilities that had been retired
from service but still had radioactive contamination. In 1980 the mill site at Monticello
was accepted into the SFMP, and the Monticello Remedial Action Project (MRAP) was
established to restore the government-owned mill site to safe levels of radioactivity, to
dispose of or contain the tailings in an environmentally safe manner, and to perform reme-
dial actions on off-site (vicinity) properties that had been contaminated by radioactive ma-
terial resulting from mill operations. The Monticello mill site and the tailings remain in the
custody of the DOE Grand Junction, Colorado, Projects Office. In 1983 remedial actions
for vicinity properties were separated from MRAP with establishment of the Monticello
Vicinity Properties (MVP) Project (U.S. DOE 1990b).
*The verification of remedial action was performed by members of the Environmental Assessment Group in the
Environmental Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE
contract DE-AC05-96OR22464 with Lockheed Martin Energy Research Corporation.
2
During 1995, RUST Geotech Inc. (Geotech), the remedial action contractor (RAC)
designated by DOE, performed remedial action on the vicinity property that is the subject
of this report, a multi-family residence located at 220 and 222 West Fourth South Street,
Monticello, Utah. The remedial action plan required excavation of all exterior contamina-
tion. When the excavation was completed, the property was resurveyed, including soil
sampling, to ensure the removal of all contamination, backfilled with uncontaminated
material, and restored to a condition comparable to that which existed prior to remedial
action (Geotech 1996).
The DOE adopted a policy to assign an independent contractor to verify the data
supporting the adequacy of remedial action and to confirm the site's compliance with DOE
guidelines. The Environmental Technology Section (ETS) of Oak Ridge National Labor-
atory (ORNL) has been assigned the responsibility of this task at the 220 and 222 West
Fourth South Street site. This report describes the methods and results of that
verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available doc-
umentation adequately and accurately describes the post-remedial-action radiological
conditions of the entire property that is to be certified and (2) that the remedial action
reduced contamination to below applicable DOE guidelines (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1996) in-
dicates the property was remediated as evaluated by DOE on the basis of Environmental
Protection Agency standards and the DOE guidelines (DOE 1990a). Excess residual
radioactive materials were present, thus it was appropriate to designate this property for
remedial action.
The pre-remedial-action survey performed by Geotech identified 19 yd3 of mill tailings
6 inches deep to 36 inches high. During the actual removal process, a total of 32 yd3 of
contaminated earth and uranium mill tailings, 42 inches deep and 36 inches high, was re-
moved from a 73 m2 area.
A post-excavation survey was performed by Geotech prior to backfilling the exca-
vated areas. This survey consisted of gamma scans with a scintillometer of the ground
level ofthe structures, a surface scan of the exterior, and soil sampling. Samples repre-
sentative of the bottom 15-cm (6-in.) soil layers of six excavated verification areas were
collected and blended to form representative composite soil samples for each verification
area.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation
levels have not been subtracted. Similarly, background concentrations have not been sub-
tracted from radionuclide concentrations in soil samples. Applicable DOE guidelines for
protection against radiation are given in Table 1.
Gamma Measurements
Gamma exposure rate measurements taken by Geotech at the ground-level of the
residence ranged from 13 to 15 uR/h. Exterior surface gamma measurements taken from
the excavated areas prior to backfilling ranged from 13 to 19 uR/h.
Soil Sample Analysis
Prior to backfilling, Geotech collected soil samples representative of the excavated
areas from the bottom 15-cm (6-in.) soil layers. These samples were blended to form a
composite soil sample representative of an average over five exterior verification areas.
Geotech's analysis of these samples showed ^Ra concentrations ranging from 1.6 to
4.4 pCi/g in the composite sample. An individual surface soil sample that was collected
for area V-6 was 7.4 pCi/g. The 100 m2 area average was 2.0 pCi/g. ORNL ETS ob-
tained a percentage of these soil samples and performed a confirmatory analysis which
showed ^Ra concentrations ranging from 3.4 to 3.6 pCi/g. These values are below the
EPA standard value of 15 pCi/g for soil layers > 15 cm below the surface. Gamma ranges
and/or soil sample results demonstrate compliance to the DOE Hot Spot Guidelines for
areas <25 m2 (Table 1). Results of Geotech and ORNL soil sample analyses are given in
Table 2.
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were deter-
mined by the Alpha-track method. To monitor radon levels, Geotech placed three alpha-
track detectors on the ground floor of the residences located on this property for a period
of approximately three months (from February 28, 1995 to May 31, 1995). The average
annual working level (WL) of radon progeny concentration, as determined by the Tech./-
Ops-Landauer Corporation, was 0.0020 for house #1 and 0.0026 for house #2, which is
well below the 0.03-WL guideline given in Table 1.
CONCLUSION
Results of Geotech soil sample analysis and confirmatory split soil sample analysis
by ORNL show that radionuclide concentrations are within applicable DOE guidelines.
Based upon the results of the post-remedial-action data, which are confirmed by the
verification assessment data, these radiological measurements fall below the limits pre-
scribed by DOE guidelines. All deficiencies noted during the initial review have been
identified by the RAC as discussed on June 18, 1996, and resolved in the revised com-
pletion report. It is concluded that the site successfully meets the DOE remedial action
objectives.
4
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Radionuclide con-
centrations in soil
for Hot Spot areas
Exposure to 222Rn
progeny
Maximum permissible con-
centration of ^Ra in soil
above background levels,
averaged over a 100-m2 area
Maximum Permissible con-
centration of Ra226 in soil
above background level, for
areas less than 25 m2
Average annual radon proge-
ny concentration (including
background)
5 pCi/g averaged over the
first 15 cm of soil below the
surface; 15 pCi/g when ave-
raged over 15-cm-thick soil
layers more than 15 cm
below the surface
Ra226 concentrations, in any
surface or subsurface area
less than 25 m2, is below the
guideline by a factor of
(100/A)*, where A is the
area of the elevated region
0.03 WL
(DOE 1990a)
Table 2. Results of ORNL analysis of Geotech soil samples from
220 and 222 West Fourth South Street, Monticello Utah (MS00020-RS)
226Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No* No* (cm)
X2 NCL 612 >15 3.6 2.8
X4 NCL 613 >15 3.4 2.6
" An X-type sample is a split of the sample taken by the remedial action contractor.
* Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated areas
were taken by Geotech, and these samples were blended to form a composite soil
sample, which represents an average over one of the verification areas.
REFERENCES
Geotech 1996. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00020-RS, Address: 220 and 222 West Fourth South Street,
Monticello, Utah 84535, Geotech, Grand Junction, Colorado, April 1996.
ORNL, 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
U.S. DOE 1990a. Verification and Certification Protocolfor the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination
and Decommissioning Program, Revision 3, November 1990. U.S. Department of
Energy, Washington, D.C.
U.S. DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision
and Record of Decision Summary. U.S. Department of Energy, Grand Junction Projects
Office, Grand Junction, Colorado.
DOE ID No.: MS-00037-CS
Property Address: 180 South Main Street
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech of Energy (DOE)
Ra-226 is s 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [ ]
Ra-226 is <. 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2.
In-situ [ ] Lab [X]
Interior gamma is s 20 //R/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is s 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21.
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ]
[ 1 [ 1
[ ] [ ]
t ] IX]
[X] [ ]
[ ]
[X]t
IX?
[ ]
[ )
YES NO NOT TAKEN
P<] [ ] I 1
[>] [ ] I 1
[ 1 [ 1 ly)
I } I } ly]
[ 1 M [ ]
[yj [ ] [ 1
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of oamma
exposure rates that do not exceed 30 percent above normal background.
fThe building was demolished during remedial action.
•llllllllll
SFCERTIFED
II
SFMS-80037
DOE ID No.: MS-00037-CS
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[XJ Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Date Wanda S. Busby /
Manager, Monticello Programs
Rust Geotech
DOE EVALUATION
[X] Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
2-£ Qj.fr f/
Certification OfficiaY Date
U.S. Department of Energy
PROPERTY COMPLETION REPORT
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
DOE ID NO.: MS-00037-CS
ADDRESS: 180 SOUTH MAIN STREET
MONTICELLO, UTAH 84535
JUNE 1996
Prepared for
U.S. Department of Energy
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
Wanda S. Busby/ /
Manager, Monticello Programs
FOR
FOR
by
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
•llllllllll Ililllllllll
SFOCPLRPTS SFMS-00037
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.1.3 Radon Decay-Product Concentration (RDC) Measurement .... 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
i
DOE ID No.: MS-00037-CS
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill. .
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Remedial Action Contractor. DOE reviewed these
evaluation results and determined that the property contained mill tailings
(residual radioactive material) exceeding DOE hot spot criteria. The
Remedial Action Contractor was notified of the inclusion of this property
into the MVP Project and was authorized by DOE to conduct remedial
action as required to bring the property into conformance with EPA
standards and DOE hot spot criteria.
1
DOE ID No.: MS-00037-CS
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
Property Address:
Property Owner:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
MS-00037-CS
Beginning 193 feet south of the NE corner
of Lot 4, Block 17, Monticello Townsite
Survey; south 76.5 feet, west 133 feet,
north 55 feet, west 81.5 feet, north
34.5 feet, east 184.5 feet, south 13 feet,
east 30 feet to point of beginning. County
of San Juan, State of Utah
180 South Main Street
Monticello, Utah 84535

Commercial Structure (CS)
Not applicable: inclusion requested by the
Remedial Action Contractor
February 14, 1994
Rust Geotech
Not applicable: streamlined remediation
procedures were followed
Keers Environmental, Inc.
5904 Florence Avenue Northeast
Albuquerque, New Mexico
August 10, 1995
August 22, 1995
Interior: 0 cubic yards
Exterior: 60 cubic yards
52 square meters (m2)
June 1996
2
DOE ID No.: MS-00037-CS
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
Streamlined remediation procedures were followed for this property. The
remedial action plan involved removal of exterior residual radioactive
material (Appendix Figure 2.1). Once excavation was complete, the
affected areas were resurveyed for possible remaining residual radioactive
material and, upon attaining satisfactory results, were backfilled with
uncontaminated material. The building on this property was demolished
during remedial action and was not replaced.
2.2 Previously Unidentified Contamination
The radiological assessment identified 18 cubic yards of contamination,
ranging from 12 inches deep to 180 inches high, within the property.
The remedial action process included the removal of approximately
60 cubic yards of residual radioactive material, ranging from 28 inches
deep to 180 inches high.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
The plan to demolish and not replace the building was approved by DOE
after the radiological assessment but prior to the development of an REA.
Demolition and remediation were performed without an REA under the
subcontract for MP-00181-OT.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID No.: MS-OO037-CS
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by the Remedial Action
Contractor during March and October 1994. Appendix Figure 2.1
shows the extent of assessed contamination and identifies the
areas recommended to undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the excavation were
collected. These samples were blended to form a composite
sample representing the verification area (Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 12 to 16 microroentgens per
hour (//R/h), as indicated on Appendix Figure 2.1. The result of
analysis for radium-226 in one composite soil sample was
2.4 picocuries per gram (pCi/g), as indicated in Appendix
Table 3.1.
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
RDC measurements were not taken because the building was
demolished during remedial action.
4
DOE ID No.: MS-00037-CS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at 180 South Main Street, in
Monticello, Utah, is recommended for certification as required by DOE
guidelines, and the appropriate records should be documented.
Certification Data Summary
Applicability
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Standards
Shall not exceed 20 //R/h
above background.
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Survey Results
Not applicable:
demolished.
Not applicable:
demolished.
building
building
Land.
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background* in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background* in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
< 5 pCi/g above
background.
Soil sample result was
2.4 pCi/g.f
*The background radium-226 concentration is approximately 2.0 pCi/g.
The hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-0O037-CS
4.0 APPENDIX
Appendix Table:
Table 3.1 Post-Excavation Sample/Measurement Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
RKJ:06-10-96
MS-00037.CS WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00037-CS
Address: 180 South Main Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (//R/h) Ticket No. Method" (pCi/g)
V-1 13-16 NCL 789 OCS 2.4
See Appendix Figure 2.1 for the verification area.
"OCS = Opposed Crystal System
7
10
.30
12 14 16 1P 20 22 24 26 28 30 32 34 36 38 40
30
28
26
24
22
20
18 -
16 -
14 -
12
Y
10
®
<£>
F7.v7l
Lv.vj
12-15
12
V-1
16-17
[12]
-X-
13-14
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN fiR/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE-RATE RANGE
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
HEIGHT IN INCHES OF ASSESSED CONTAMINATED
BRICK WALLS REMOVED BUT NOT REPLACED
BUILDING WAS REMOVED DURING REMEDIAL
ACTION
12
V-1
13-16
28
ft
NORTH
SCALE IN FEET
20 10 0 20
ONE STORY METAL
AND BRICK BUILDING"*
12-16
I I-
V-1
13-16
[180](A
28
UJ
Ld
ce
I—
CO
<
X
I—
o
CO
28
26
- 24
22
20
18
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
16
40
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT. UTILITY LOCATION PLAT, OR OTHER IMPROVEMENT SURVEY
PLAT AND IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE. BUILDING. OR OTHER FUTURE IMPROVEMENT LINES.
X M:\FAS\033\0003\RM00037V 06/10/96 12:35pm T50780
_J I I l_ I I L
RESIDENCE-NO. OF OCCUPANTS
NON-RESIDENCE-MAN-HRS /WX.
INSTRUMENT NO.
SURVCT OATE
VERIFICATION
•Y CK. A.E. APR. NO. DATE CK. A.C. APP.
14
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE. COLORADO
TT
PROMSOR!
180 SOUTH MAIN STREET
MONTICELLO. UTAH
12
APPROVAL
Rust Qeotech
DATE APPROVAL OOE
OOEIONO. MS-00037-CS
owe.NO. 3-B00037-V1 SHT 1 of 1
10
10 12 1 4 16 18 20 22 24 26 28 30 32 34 36 38 40
OAK RIDGE NATIONAL LABORATORY PHONE: [phone]
FAX: [phone] MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
FOR THE U.S. DEPARTMENT OF ENERGY
POST OFFICE BOX 2567
GRAND JUNCTION. COLORADO 81502
SEP 2 0 1996
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by the U.S.
Department of Energy for Residual Radioactive Material at Formerly Utilized Sites Remedial Action
Program (FUSRAP) and Remote Surplus Facilities Management Program Sites (SFMP) [Revision
2, March 1987]. This evaluation is based on an independent verification review ofthe Remedial
Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment of the 226Ra
concentration in the soil.
This property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
Location Number:
Location Address:
MS00037-CS
180 South Main Street
Monticello. Utah 84535
Property Owner:
Owner Address:

Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
180 SOUTH MAIN STREET
MONTICELLO, UTAH (MS00037-CS)
M. K. Jensen
September 1996
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 3
REFERENCES 6
iii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 4
2. Results of ORNL analysis of Geotech soil samples from 180 South Main Street,
Monticello, Utah (MS00037-CS) 5
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site Decom-
missioning Projects, U.S. Department of Energy. The author wishes to acknowledge A. R.
Jones and M. J. Wilson-Nichols for technical reviews.
vii
ABSTRACT
In 1980 the site of a vanadium and uranium mill at Monticello, Utah, was accepted into
the U.S. Department of Energy's (DOE's) Surplus Facilities Management Program, with the
objectives of restoring the government-owned mill site to safe levels of radioactivity, dispos-
ing of or containing the tailings in an environmentally safe manner, and performing remedial
actions on off-site (vicinity) properties that had been contaminated by radioactive material
resulting from mill operations. During 1995, RUST Geotech, the remedial action contractor
designated by DOE, performed remedial action on the vicinity property at 180 South Main
Street, Monticello, Utah. The Environmental Technology Section (ETS) of Oak Ridge
National Laboratory was assigned the responsibility of verifying the data supporting the
adequacy of remedial action and confirming the site's compliance with DOE guidelines. The
ETS found that the site successfully meets the DOE remedial action objectives. Procedures
used by the ETS are described in the Environmental Technology Section Procedures Manual
(ORNL 1993).
ix
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 180 SOUTH MAIN STREET
MONTICELLO, UTAH (MS00037-CS)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the U.S. government through the
Defense Plant Corporation to provide vanadium during World War JX Various government
agencies operated the mill until 1947. In 1948 the Atomic Energy Commission (AEC) ob-
tained the mill and operated it under contract through 1959 to provide both uranium and
vanadium. Mill operations were terminated on January 1,1960. In 1961 the mill tailings piles
were leveled and graded, covered with rock and soil, and seeded with native grasses. During
1974 and 1975, the ore stockpiles were removed from the site, and the mill foundations were
buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city of
Monticello, in San Juan County, Utah. The site is bordered on the south and southeast by
land held by the U.S. Bureau of Land Management. Other boundaries are the city of Monti-
cello and private property.
During the AEC era, the mill processed approximately one million tons of uranium ore.
Vanadium and uranium were the only substances extracted in the milling process. Other con-
stituents of the ore remained in the tailings and were not separated prior to disposal. During
the years of active mill operation, the mill tailings were normally moist, so erosion was
minimal. However, throughout the mill's operating period, area residents used these tailings
as fill material and as aggregate in mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy (DOE)
initiated the Surplus Facilities Management Program (SFMP) in 1978 to ensure the safe care-
taking and decommissioning of government facilities that had been retired from service but
still had radioactive contamination. In 1980 the mill site at Monticello was accepted into the
SFMP, and the Monticello Remedial Action Project (MRAP) was established to restore the
government-owned mill site to safe levels of radioactivity, to dispose of or contain the tailings
in an environmentally safe manner, and to perform remedial actions on off-site (vicinity)
properties that had been contaminated by radioactive material resulting from mill operations.
The Monticello mill site and the tailings remain in the custody of the DOE Grand Junction,
Colorado, Projects Office. In 1983 remedial actions for vicinity properties were separated
from MRAP with establishment of the Monticello Vicinity Properties (MVP) Project (U.S.
DOE 1990b).
*The verification of remedial action was performed by members of the Environmental Assessment Group in the
Environmental Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE
contract DE-AC05-96OR22464 with Lockheed Martin Energy Research Corporation.
2
During 1995, RUST Geotech Inc. (Geotech), the remedial action contractor (RAC)
designated by DOE, performed remedial action on the vicinity property that is the subject of
this report, a commercial structure located at 180 South Main Street, Monticello, Utah. The
remedial action plan required demolition of the structure and excavation of all exterior con-
tamination. When the demolition and excavation were completed, the property was resur-
veyed, including soil sampling, to ensure the removal of all contamination and backfilled with
uncontaminated material (Geotech 1996).
The DOE adopted a policy to assign an independent contractor to verify the data
supporting the adequacy of remedial action and to confirm the site's compliance with DOE
guidelines. The Environmental Technology Section (ETS) of Oak Ridge National Laboratory
(ORNL) has been assigned the responsibility of this task at the 180 South Main Street site.
This report describes the methods and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available documenta-
tion adequately and accurately describes the post-remedial-action radiological conditions of
the entire property that is to be certified and (2) that the remedial action reduced contami-
nation to below applicable DOE guidelines (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1996) indicates
the property was remediated as evaluated by DOE on the basis of Environmental Protection
Agency standards and the DOE guidelines (DOE 1990a). Excess residual radioactive materi-
als were present, thus it was appropriate to designate this property for remedial action using
streamlined remedial action procedures.
The pre-remedial-action survey performed by Geotech identified 18 yd3 of mill tailings
12 inches deep to 180 inches high. During the actual removal process, a total of 60 yd3 of
contaminated earth and uranium mill tailings, 28 inches deep to 180 inches high, were re-
moved from a 52 m2 area.
A post-excavation survey was performed by Geotech prior to backfilling the excavated
areas. This survey consisted of a surface gamma scans with a scintillometer of the exterior
and soil sampling. Samples representative of the bottom 15-cm (6-in.) soil layers of the exca-
vated verification areas were collected and blended to form a representative composite soil
sample.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation
levels have not been subtracted. Similarly, background concentrations have not been sub-
tracted from radionuclide concentrations in soil samples. Applicable DOE guidelines for
protection against radiation are given in Table 1.
Gamma Measurements
Exterior surface gamma exposure rate measurements taken from the excavated areas
prior to backfilling ranged from 13 to 16 uR/h.
Soil Sample Analysis
Prior to backfilling, Geotech collected soil samples representative of the excavated areas
from the bottom 15-cm (6-in.) soil layers. These samples were blended to form a composite
soil sample representative of an average over the exterior verification area. Geotech's analysis
of this sample showed a ^Ra concentration of 2.4 pCi/g. ORNL ETS obtained this sample
and performed a confirmatory analysis which showed a ^Ra concentration of 1.7 pCi/g.
These values are below the EPA standard value of 15 pCi/g for soil layers > 15 cm below the
surface. Gamma ranges and/or soil sample results demonstrate compliance to the DOE Hot
Spot Guidelines for areas <25 m2 (Table 1). Results of Geotech and ORNL soil sample
analyses are given in Table 2.
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were not deter-
mined as the building was demolished during remediation.
CONCLUSION
Results of Geotech soil sample analysis and confirmatory split soil sample analysis by
ORNL show that radionuclide concentrations are within applicable DOE guidelines. Based
on the results ofthe post-remedial-action data, which are confirmed by the verification assess-
ment data, these radiological measurements fall below the limits prescribed by DOE guide-
lines. It is concluded that the site successfully meets the DOE remedial action objectives.
4
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of 226Ra in soil
above background levels,
averaged over a 100-m2 area
5 pCi/g averaged over the
first 15 cm of soil below the
surface; 15 pCi/g when ave-
raged over 15-cm-thick soil
layers more than 15 cm
below the surface
Radionuclide con-
centrations in soil
for Hot Spot areas
Maximum Permissible con-
centration of Ra226 in soil
above background level, for
areas less than 25 m2
Ra226 concentrations, in any
surface or subsurface area
less than 25 m2, is below the
guideline by a factor of
(100/A)'7', where A is the
area of the elevated region
Exposure to 222Rn
progeny
Average annual radon proge-
ny concentration (including
background)
0.03 WL
(DOE 1990a)
5
Table 2. Results of ORNL analysis of Geotech soil samples from
180 South Main Street, Monticello, Utah (MS00037-CS)
226Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No." No^ (cm)
XI NCL 789 >15 1.7 2.4
" An X-type sample is a split of the sample taken by the remedial action contractor.
4 Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated areas
were taken by Geotech, and these samples were blended to form a composite soil
sample, which represents an average over one of the verification areas.
6
REFERENCES
Geotech 1996. Property Completion Report for Monticello Vicinity Property Remedial
ActionforDOEIDNO: MS00037-CS, Address: 180 South Main Street, Monticello, Utah
84535, Geotech, Grand Junction, Colorado, June 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment Group)
Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National Laboratory,
Grand Junction, Colorado.
U.S. DOE 1990a. Verification and Certification Protocolfor the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination and
Decommissioning Program, Revision 3, November 1990. U.S. Department of Energy,
Washington, D.C.
U.S. DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision and
Record of Decision Summary. U.S. Department of Energy, Grand Junction Projects Office,
Grand Junction, Colorado.
DOE ID No.: MS-00080-MR
Property Address: 80 South Second East Street
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech of Energy (DOE)
Ra-226 is < 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [ ]
Ra-226 is ^ 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2.
In-situ [ ] Lab [X]
Interior gamma is <. 20 //R/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is < 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21.
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
[VJ [ ] [ I
[A [ 1 [ I
[X] [ ] [ I
[ ] [yl [ ]
[/] [ I I I
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
llllllllll llllllllll
SFCERTIFED SFMS-00080
DOE ID No.: MS-00080-MR
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Manager, 'Monticello Programs
Rust Geotech
Date
DOE EVALUATION
[tf] Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Certification Official Date
U.S. Department of Energy
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
DOE ID NO.: MS-00080-MR
ADDRESS: 80 SOUTH SECOND EAST STREET
MONTICELLO, UTAH 84535
JULY 1996
Prepared for
U.S. Department of Energy
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
FOR
by
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.1.3 Radon Decay-Product Concentration (RDC) Measurement .... 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
i
DOE ID No.: MS-00080-MR
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Remedial Action Contractor. DOE reviewed these
evaluation results and determined that the property contained mill tailings
(residual radioactive material) exceeding DOE hot spot criteria. The
Remedial Action Contractor was notified of the inclusion of this property
into the MVP Project and was authorized by DOE to conduct remedial
action as required to bring the property into conformance with EPA
standards and DOE hot spot criteria.
1
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
Property Address:
Property Owners:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
DOE ID No.: MS-00080-MR
MS-00080-MR
Beginning at the SE corner of Lot 1,
Block 22, Monticello Townsite Survey,
west 70 feet, north 120 feet, east 70 feet,
south 120 feet to beginning, County of San
Juan, State of Utah
80 South Second East Street
Monticello, Utah 84535

Major Residential (MR)
Not applicable: inclusion requested by the
Remedial Action Contractor
August 2, 1994
Rust Geotech
February 8, 1995
Diamond Back Services, Inc.
9861 Titan Park Circle
Littleton, Colorado
September 6, 1995
September 8, 1995
Interior: 0 cubic yards
Exterior: 3 cubic yards
14 square meters (m2)
July 1996
2
DOE ID No.: MS-00080-MR
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of exterior residual radioactive
material (Appendix Figure 2.1). Interior assessed Area C (soil in the crawl
space) was excluded from remedial action based on ground floor gamma
exposure rates and pre-remedial radon decay-product concentration
measurements that did not exceed EPA standards, as discussed in the
REA. Once excavation was complete, the affected areas were resurveyed
for possible remaining residual radioactive material and, upon attaining
satisfactory results, were backfilled with uncontaminated material. The
property was restored to a physical condition comparable to that which
existed prior to remedial action activities.
2.2 Previously Unidentified Contamination
The radiological assessment (excluding assessed Area C) identified 2 cubic
yards of contamination, ranging from 4 to 6 inches deep, within the
property. The remedial action process included the removal of 3 cubic
yards of residual radioactive material, 6 inches deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID No.: MS-00080-MR
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by the Remedial Action
Contractor during April 1991, as described in the final REA dated
February 1995. Appendix Figure 2.1 shows the extent of
assessed contamination and identifies the areas recommended to
undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the excavation were
collected. These samples were blended to form a composite
sample representing the verification area (Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 13 to 29 microroentgens per
hour (//R/h), as indicated on Appendix Figure 2.1. The result of
analysis for radium-226 in one composite soil sample was
3.4 picocuries per gram (pCi/g), as indicated in Appendix
Table 3.1.
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on the DOE-approved abbreviated-measurement method,
the RDC was 0.0195 working level (WL), as indicated in Appendix
Table 3.2. Appendix Figure 2.1 shows the measurement location
on the ground floor (the lowest habitable level of the structure).
4
DOE ID No.: MS-00080-MR
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at 80 South Second East Street, in
Monticello, Utah, is recommended for certification as required by DOE
guidelines, and the appropriate records should be documented.
Certification Data Summary
Applicability
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Standards
Shall not exceed 20 /vR/h
above background.*
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Survey Results
Range for the ground
floor was 13 to 19 //R/h.
Average was 0.0195 WL,
based on the DOE-
approved abbreviated-
measurement method.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
< 5 pCi/g above
background.**
Soil sample result was
3.4 pCi/g.**
*The background exposure rate is approximately 14/vR/h.
The background radium-226 concentration is approximately 2.0 pCi/g.
**The hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-00080-MR
4.0 APPENDIX
Appendix Tables:
Table 3.1 Post-Excavation Sample/Measurement Results
Table 3.2 Radon Decay-Product Concentration Measurement
Results
Appendix Figure:
Figure 2.1 Interior and Exterior Extent of Contamination -
RADIOLOGICAL AS-BUILT
JEK:05-29-96
MS-00080.MR WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00080-MR
Address: 80 South Second East Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (/;R/h) Ticket No. Method8 (pCi/g)
V-1 16-29 NCL 808 OCS 3.4
See Appendix Figure 2.1 for the verification area.
"OCS = Opposed Crystal System
7
Table 3.2
Radon Decay-Product Concentration Measurement Results
DOE ID No.: MS-00080-MR
Address: 80 South Second East Street, Monticello, Utah
Instrument Type: Landauer Radtrak Detector
Detector
Number Start Date End Date
Radon
Concentration
(pCi/L)
Working
Level
4147061
4147086
4147213
02-27-96
02-27-96
02-27-96
05-28-96
05-28-96
05-28-96
3.50
4.23
3.96
0.0175
0.0212
0.0198
Average: 0.0195
See Appendix Figure 2.1 for the measurement location.
8
10
30
12 1 4 16 18 20 22 24 26 28 30 32 34 36 38 40
30
28
26
24
22
20
18 -
16 -
1 4
12
Y
10
v-1
16-29
13-16
GARAGE
13-14
O
L
77/
13-19
ONE STORY
FRAME HOUSE
W/CRAWL SPACE
SEE DETAIL A
13-16
777
EAST FIRST SOUTH STREET
n
13-16
Lu
Lu
o or
co < LU
O
Lu
in
I
o LO
J 13-16
L
777"
SCALE IN FEET
20
X
20 10 0
M:\FAS\033\0003\RM00080V 05/30/96 10:26am T50780
40 NORTH
-X-
XRAWL SPACE-
r
DETAIL A
NOT TO SCALE
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT, UTILITY LOCATION PLAT. OR OTHER IMPROVEMENT SURVEY
PLAT AND IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE, BUILDING, OR OTHER FUTURE IMPROVEMENT LINES.
I I I I I
®
<D
Fv.vvl
Lv.vj
12-15
12
V-1
16-17
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN yuR/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE-RATE RANGE
RADON DECAY-PRODUCT CONCENTRATION
MEASUREMENT LOCATION
ASSESSED AREA C (SOIL IN CRAWL SPACE)
WAS EXCLUOED FROM REMEDIAL ACTION
RADIOLOGICAL AS-BUILT
FIGURE 2.1
INTERIOR AND EXTERIOR EXTENT OF CONTAMINATION
RESIDENCE-NO. OF OCCUPANTS
N0N-RESI0ENCC-UAN-HRS./«K.
INSTRUMENT NO.
SURVEY DME
U.S. DEPARTMENT OF ENERGY
GRANO JUNCTION PROJECTS OFFICE. COLORADO
80 SOUTH SECOND EAST ST.
MONTICELLO, UTAH
Rust Qeotech
"SJifi I APPROVAL OOE
OOCIONO. MS-00080-MR
pwc.NO. 3-BQ0080-V1,HT.1 or 1
28
26
24
22
20
18
16
14
12
10
10 12 1 4 16 18 20 22 24 26 28 30 32 34 36 38 40
OAK RIDGE NATIONAL LABORATORY PHONE: <970) 24M20O
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION FAX: [phone]
FOR THE U.S. DEPARTMENT OF ENERGY
2597 B 3/4 Road
GRANO JUNCTION, COLORADO 81503 NOV 2 7 1996
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by the U.S.
Department of Energy for Residual Radioactive Material at Formerly Utilized Sites Remedial Action
Program (FUSRAP) and Remote Surplus Facilities Management Program Sites (SFMP) [Revision
2, March 1987]. This evaluation is based on an independent verification review of the Remedial
Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment of the 226Ra
concentration in the soil, indoor radon daughter concentration, and indoor gamma exposure rates at
this property.
This property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
Location Number: MS00080-MR
Location Address: 80 South 2nd East Street
Monticello. Utah 84535
Property Owner:

Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
80 SOUTH 2ND EAST STREET
MONTICELLO, UTAH (MS00080-MR)
N. F. Kirby
November 1996
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 3
REFERENCES 6
iii
4
LIST OF TABLES
1. Applicable guidelines for protection against radiation 4
2. Results of ORNL analysis of the RAC soil samples from 80 South 2nd East Street,
Monticello, Utah (MS00080-MR) 5
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site Decommissioning
Projects, U.S. Department of Energy. The author wishes to acknowledge M. K. Jensen for analysis
of soil samples and technical review and A. R. Jones for technical review.
vii
ABSTRACT
In 1980, the site of a vanadium and uranium mill at Monticello, Utah, was accepted into the
U.S. Department of Energy (DOE) Surplus Facilities Management Program, with the objectives of
restoring the government-owned mill site to safe levels of radioactivity, disposing of or containing
the tailings in an environmentally safe manner, and rjerforrning remedial actions on off-site (vicinity)
properties that had been contaniinated by radioactive material resulting from mill operations. During
1995, the Remedial Action Contractor (RAC) designated by DOE, performed remedial action on the
vicinity property at 80 South 2nd East Street, Monticello, Utah. The Environmental Technology
Section (ETS) of Oak Ridge National Laboratory was assigned the responsibility of verifying the
data supporting the adequacy of remedial action and confirming the site's compliance with DOE
guidelines. The ETS found that the site successfully meets the DOE remedial action objectives.
Procedures used by the ETS are described in the Environmental Technology Section Procedures
Manual (ORNL 1993).
ix
r *
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 80 SOUTH 2ND EAST STREET
MONTICELLO, UTAH (MS00080-MR)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the United States (U.S.) government through
the Defense Plant Corporation to provide vanadium during World War II. Various government
agencies operated the mill until 1947. In 1948, the Atomic Energy Commission (AEC) obtained the
mill and operated it under contract through 1959 to provide both uranium and vanadium. Mill
operations were terminated on January 1, 1960. In 1961, the mill tailings piles were leveled and
graded, covered with rock and soil, and seeded with native grasses. During 1974 and 1975, the ore
stockpiles were removed from the site, and the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city of
Monticello, in San Juan County, Utah. The site is bordered on the south and southeast by land held
by the U.S. Bureau of Land Management. Other boundaries are the city of Monticello and private
property.
During the AEC era, the mill processed approximately one million tons of uranium ore. Vana-
dium and uranium were the only substances extracted in the milling process. Other constituents of
the ore remained in the tailings and were not separated prior to disposal. During the years of active
mill operation, the mill tailings were normally moist, so erosion was minimal. However, throughout
the mill's operating period, area residents used these tailings as fill material and as aggregate in
mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy (DOE) initiated
the Surplus Facilities Management Program (SFMP) in 1978 to ensure the safe caretaking and de-
commissioning of government facilities that had been retired from service but still had radioactive
contamination. In 1980, the mill site at Monticello was accepted into the SFMP, and the Monticello
Remedial Action Project (MRAP) was established to restore the government-owned mill site to safe
levels of radioactivity, to dispose of or contain the tailings in an environmentally safe manner, and
to perform remedial actions on off-site (vicinity) properties that had been contaminated by
radioactive material resulting from mill operations. The Monticello mill site and the tailings remain
in the custody of the DOE Grand Junction, Colorado, Projects Office. In 1983, remedial actions for
vicinity properties were separated from MRAP with establishment of the Monticello Vicinity
Properties (MVP) Project (US DOE 1990b).
*The verification of remedial action was performed by members of the Environmental Assessment Group in the Environmental
Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE contract DE-AC05-
960R22464 with Lockheed Martin Energy Research Corporation.
2
During 1995, the Remedial Action Contractor (RAC) performed remedial action on the vicinity
property that is the subject of this report, a single family residence located at 80 South 2nd East
Street, Monticello, Utah. The remedial action plan required excavation of all exterior contarnination.
When the excavation was completed, the property was resurveyed, including soil sampling, to ensure
the removal of all contamination, backfilled with uncontaminated material, and restored to a
condition comparable to that which existed prior to remedial action (Rust Geotech 1996).
The DOE adopted a policy to assign an independent contractor to verify the data supporting the
adequacy of remedial action and to confirm the site's compliance with DOE guidelines. The Envi-
ronmental Technology Section (ETS) of Oak Ridge National Laboratory (ORNL) has been assigned
the responsibility of this task at the 80 South 2nd East Street site. This report describes the methods
and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available documentation
adequately and accurately describes the post-remedial-action radiological conditions ofthe entire
property that is to be certified and (2) that the remedial action reduced contamination to below
applicable DOE guidelines (US DOE 1990a).
Document Reviews
Review of the RAC property completion report (Rust Geotech 1996) indicates the property was
evaluated by DOE and remediated on the basis of the DOE guidelines (US DOE 1990a). Excess
residual radioactive materials were present, thus it was appropriate to designate this property for
remedial action.Interior assessed Area C was excluded from remedial action based on gamma expo-
sure rate measurements and radon decay product concentrations.
The pre-remedial-action survey performed by the RAC identified 2 yd3 of mill tailings 4 to 6
inches deep (excluding Area C). During the actual removal process, a total of 3 yd3 of contaniinated
earth and uranium mill tailings, 6 inches deep, were removed from a 14 m2 area.
The RAC performed a post-excavation survey prior to backfilling the excavated areas. This sur-
vey consisted of gamma scans with a scintillometer of the ground level of the structure, a surface
scan of the exterior, and soil sampling. Samples representative of the bottom 15-cm (6-in.) soil lay-
ers ofthe excavated verification area were collected and blended to form a representative composite
soil sample.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation levels have
not been subtracted. Similarly, background concentrations have not been subtracted from radionu-
clide concentrations in soil samples. Applicable DOE guidelines for protection against radiation are
given in Table 1.
Gamma Measurements
Gamma exposure rate measurements taken by the RAC at the ground-level of the residence
ranged from 13 to 19 uR/h. Exterior surface gamma measurements taken from the excavated areas
prior to backfilling ranged from 16 to 29 pR/h.
Soil Sample Analysis
Prior to backfilling, the RAC collected soil samples representative of the excavated areas from
the bottom 15-cm (6-in.) soil layers. These samples were blended to form a composite soil sample
representative of an average over the exterior verification area. The RAC's analysis of this sample
showed a 226Ra concentration of 3.4 pCi/g. ORNL ETS obtained this sample and performed a con-
firmatory analysis which showed a 226Ra concentration of 2.0 pCi/g. These values are below the
DOE guideline value of 15 pCi/g for soil layers >15 cm below the surface. Results ofthe RAC and
ORNL soil sample analyses are given in Table 2.
As a result of a meeting between the RAC and IVC on May 26, 1994, anomalous readings
defined as 73% above the excavation average will be investigated to show compliance to the DOE
Hot Spot guideline. An excavation control sample was taken between the door stoop and the footer
of the house. The gamma exposure rate in this area of 29 uR/h exceeded 30%. The Ra concentra-
tion for this sample was 2.6 pCi/g. The Gamma ranges and/or soil sample results demonstrate com-
pliance to the DOE Hot Spot Guidelines for areas <25 m2 (Table 1).
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were determined by the
Alpha-track method. To monitor radon levels, the RAC placed three alpha-track detectors on the
ground floor of the residence located on this property for a period of approximately three months
(from February 27, 1996 to May 28, 1996). The average annual working level (WL) of radon
progeny concentration, as determined by the Tech./Ops-Landauer Corporation, was 0.0195, which
is below the 0.03-WL guideline given in Table 1.
CONCLUSION
Results of the RAC soil sample analysis and confirmatory split soil sample analysis by ORNL
show that radionuclide concentrations are within applicable DOE guidelines. Based on the results
of the post-remedial-action data, which are confirmed by the verification assessment data, these
radiological measurements fall below the limits prescribed by DOE guidelines. It is concluded that
the site successfully meets the DOE remedial action objectives.
4
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible
concentration of 226Ra in
soil above background
levels, averaged over a
100-m2 area
5 pCi/g averaged over the first 15 cm
of soil below the surface; 15 pCi/g
when averaged over 15-cm-thick soil
layers more than 15 cm below the
surface
Radionuclide con-
centrations in soil
for Hot Spot areas
Exposure to 222Rn
progeny
Maximum Permissible
concentration of Ra226 in
soil above background
level, for areas less than
25 m2
Average annual radon
progeny concentration
(including background)
Ra226 concentrations, in any surface or
subsurface area less than 25 m2, is
below the guideline by a factor of
(100/A)'/j, where A is the area of the
elevated region
0.03 WL
(US DOE 1990a)
5
Table 2. Results of ORNL analysis of the RAC soil samples from
80 South 2nd East Street, Monticello, Utah (MS00080-MR)
226Ra concentration (pCi/g)
ORNL RAC
sample sample Depth ORNL RAC
No." No^ (cm)
XI NCL 808 >15 1.97 3.4
" An X-type sample is a split of the sample taken by the remedial action contractor.
* Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated areas were
taken by the remedial action contractor. These samples were blended to form a composite soil
sample, which represents an average over one of the verification areas.
6
REFERENCES
ORNL 1993. Environmental Technology Section (Formerly PoUutant Assessment Group)
Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National Laboratory, Grand
Junction, Colorado.
Rust Geotech 1996. Property Completion Report for Monticello Vicinity Property Remedial Action
for DOE ID NO: MS00080-MR, Address: 80 South Second East Street, Monticello, Utah 84535,
Rust Geotech, Grand Junction, Colorado, July 1996.
US DOE 1990a. Verification and Certification Protocol for the Office of Environmental Restoration,
Formerly Utilized Sites Remedial Action Programs and Decontamination and Decommissioning
Program. Revision 3, November 1990. U.S. Department of Energy, Washington, D.C.
US DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision and Record
of Decision Summary. U.S. Department of Energy, Grand Junction Projects Office, Grand Junction,
Colorado.
DOE ID No.: MS-00089-RS
Property Address: 164 East First North Street
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech of Energy (DQE)
Ra-226 is <; 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [ ]
Ra-226 is ^ 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 ma.
In-situ [ ] Lab [X]
Interior gamma is £ 20 //R/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is £ 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21.
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ 1 [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
M [ 1 [ 1
[y] [ ] [ 1
[Xl [ ] [ ]
[V] [ ] [ ]
[ ] [XI I 1
[Mil I 1
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
Ililllllllll llllllllll
SFCERTIFED SFMS-09033
DOE ID No.: MS-00089-RS
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Wanda S.<Busby Date
Manager, Monticello Programs
Rust Geotech
DOE EVALUATION
[ *] Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Certification Official '
U.S. Department of Energy
1 N U U
Date
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
DOE ID NO.: MS-00089-RS
ADDRESS: 164 EAST FIRST NORTH STREET
MONTICELLO, UTAH 84535
FEBRUARY 1996
Prepared for
U.S. Department of Energy
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
FOR
by
Wahda S. Busby
Manager, Monticello Programs
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
r
t
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.1.3 Radon Decay-Product Concentration (RDC) Measurement .... 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
i
DOE ID No.: MS-00089-RS
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Inclusion Survey Contractor. DOE reviewed
these evaluation results and determined that the property contained mill
tailings (residual radioactive material) exceeding EPA standards. The
Remedial Action Contractor was notified of the inclusion of this property
into the MVP Project and was authorized by DOE to conduct remedial
action as required to bring the property into conformance with EPA
standards and DOE hot spot criteria.
1
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
Property Address:
Property Owners:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
DOE ID No.: MS-00089-RS
MS-00089-RS
Location No. M-251; beginning at the NE
corner of Lot 4, Block H, Monticello
Townsite Survey; west 214.5 feet, south
135 feet, east 214.5 feet, north 135 feet to
beginning, County of San Juan, State
of Utah
164 East First North Street
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
February 26, 1990
Rust Geotech
September 14, 1994
Diamond Back Services, Inc.
9861 Titan Park Circle
Littleton, Colorado
July 11, 1995
August 21, 1995
Interior: 0 cubic yards
Exterior: 22 cubic yards
71 square meters (m2)
February 1996
2
DOE ID No.: MS-00089-RS
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of exterior residual radioactive
material (Appendix Figure 2.1). Once excavation was complete, the
affected areas were resurveyed for possible remaining residual radioactive
material and, upon attaining satisfactory results, were backfilled with
uncontaminated material. The property was restored to a physical
condition comparable to that which existed prior to remedial action
activities.
2.2 Previously Unidentified Contamination
The radiological assessment identified contamination, ranging from 6 to
12 inches deep, within the property. The quantity of contamination for
this property was not specified because it was assessed as part of Block
MS-09033-BK. The remedial action process included the removal of
approximately 22 cubic yards of residual radioactive material, ranging
from 6 to 18 inches deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID No.: MS-00089-RS
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by the Remedial Action
Contractor during June and August 1992, as described in the final
REA dated September 1994. Appendix Figure 2.1 shows the
extent of assessed contamination and identifies the areas
recommended to undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the excavation were
collected. These samples were blended to form composite
samples representing the verification areas (Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 12 to 27 microroentgens per
hour (//R/h), as indicated on Appendix Figure 2.1. The results of
analyses for radium-226 in two composite soil samples were
3.1 and 3.2 picocuries per gram (pCi/g), as indicated in Appendix
Table 3.1.
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on the DOE-approved abbreviated-measurement method,
the RDC was 0.0023 working level (WL), as indicated in
Appendix Table 3.2. Appendix Figure 2.1 shows the measurement
location on the ground floor (the lowest habitable level of the
structure). RDC measurements were taken before remediation of
the property.
4
DOE ID No.: MS-00089-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at 164 East First North Street, in
Monticello, Utah, is recommended for certification as required by DOE
guidelines, and the appropriate records should be documented.
Applicability
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Certification Data Summary
Standards
Shall not exceed 20 //R/h
above background.*
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Survey Results
Range for the ground
floor was 14 to 15 //R/h.
Average was 0.0023 WL,
based on the DOE-
approved abbreviated-
measurement method.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
< 5 pCi/g above
background.**
Soil sample results were
3.1 and 3.2 pCi/g.**
*The background exposure rate is approximately 13//R/h.
The background radium-226 concentration is approximately 2.0 pCi/g.
**The hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-00089-RS
4.0 APPENDIX
Appendix Tables:
Table 3.1 Post-Excavation Sample/Measurement Results
Table 3.2 Radon Decay-Product Concentration Measurement
Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
SJW: 11-30-95
MS-00089.RS WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00089-RS
Address: 164 East First North Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (jjR/h) Ticket No. Method" (pCi/g)
V-1 14-27 NCH 061 OCS 3.1
V-2 16-20 NCH 062 OCS 3.2
See Appendix Figure 2.1 for the verification areas.
aOCS = Opposed Crystal System
7
Table 3.2
Radon Decay-Product Concentration Measurement Results
DOE ID No.: MS-00089-RS
Address: 164 East First North Street, Monticello, Utah
Instrument Type: Landauer Radtrak Detector
Detector
Number Start Date End Date
Tracks Per
mm2
Radon
Concentration
(pCi/L)
Working
Level
3964236
3964150
3964305
02-28-95
02-28-95
02-28-95
05-31-95
05-31-95
05-31-95
1.4
1.3
1.0
0.52 0.0026
0.48 0.0024
0.40 0.0020
Average: 0.0023
See Appendix Figure 2.1 for the measurement location.
8
1
42
40
38
36
34
32
30
28
26
24
22
20
18
16
14
12
10
12 1 6 18 20
"T~
22 24 26 28 30 32 34 36 38 40 42 44 46 48 50
EAST FIRST NORTH STREET
v-i
14-27 GARAGE
12-15
18
v-1
u-27
V-2 10
16-20
12-16
12-16
V-1
14-27
12XB
ONE STORY
FRAME HOUSE
W/CRAWL SPACE
y- ^ 14—15
(RDC)
12-16
0
<D
FVTTI TY.VJ
12-15
12
v-1
16-17
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN /iR/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE-RATE RANGE
RADON DECAY—PRODUCT CONCENTRATION
MEASUREMENT LOCATION
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
L
SCALE IN FEET
20 10 0 20 40
y:\FAS\0J3\0003\RM00089V 01/09/96 12:39pm T50780
12 14 16 18 20
NORTH
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LANO SURVEY
PLAT. UTILITY LOCATION PLAT. OR OTHER IMPROVEMENT SURVEY
PLAT ANO IS NOT TO BE RELIEO UPON FOR THE ESTABLISHMENT
OF FENCE. BUILDING. OR OTHER FUTURE IMPROVEMENT LINES.
atuoocc-M or OCCU.MH
•M-aiittuci-MMi-iMa./m.
turner urc
U.S. OEPARTUENT OF ENERGY
GUANO JUNCTION PWOJCCTS QfflCE. COlQIUOO
164 EAST FIRST NORTH ST.
MONTICELLO. UTAH
1 ft.it itfwavgTO rs
Rust Qttttoch MS-00089-RS
22 24 26 28 30 32 34 36 38 40 42 44 46 48 5C
OAK RIDGE NATIONAL LABORATORY
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
FOR THE U.S. DEPARTMENT OF ENERGY
POST OFFICE BOX 2567
GRAND JUNCTION. COLORADO 81502
PHONE: [phone]
FAX: [phone]
my 31 \m
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by the
U.S. Department of Energy for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program (FUSRAP) and Remote Surplus Facilities Management Program
Sites (SFMP) [Revision 2, March 1987]. This evaluation is based on an independent
verification review of the Remedial Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment of
the ^Ra concentration in the soil, indoor radon concentration, and indoor gamma exposure
rates at this property.
Therefore, this property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
MS00089-RS
164 East 1st North Street
Monticello. Utah 84535

Mr. and Mrs. John Feher
Location Number:
Location Address:
Property Owner:
Owner Address:
Tenant Name:
Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
164 EAST 1ST NORTH STREET
MONTICELLO, UTAH (MS00089-RS)
M. J. Wilson-Nichols
May 1996
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 3
REFERENCES 6
iii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 4
2. Results of ORNL analysis of Geotech soil samples from 164 East 1st North Street,
Monticello, Utah (MS00089-RS) 5
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site
Decommissioning Projects, U.S. Department of Energy. The author wishes to
acknowledge M. K. Jensen for analysis of soil samples and N. F. Kirby and J. R. Sauvage
for technical reviews.
vii
ABSTRACT
In 1980 the site of a vanadium and uranium mill at Monticello, Utah, was accepted
into the U.S. Department of Energy's (DOE's) Surplus Facilities Management Program,
with the objectives of restoring the government-owned mill site to safe levels of
radioactivity, disposing of or containing the tailings in an environmentally safe manner,
and performing remedial actions on off-site (vicinity) properties that had been
contaminated by radioactive material resulting from mill operations. During 1995, RUST
Geotech, the remedial action contractor designated by DOE, performed remedial action
on the vicinity property at 164 East 1st North Street, Monticello, Utah. The
Environmental Technology Section (ETS) of Oak Ridge National Laboratory was
assigned the responsibility of verifying the data supporting the adequacy of remedial
action and confirming the site's compliance with DOE guidelines. The ETS found that
the site successfully meets the DOE remedial action objectives. All deficiencies noted in
the initial review have been resolved in the revised completion report. Procedures used
by the ETS are described in the Environmental Technology Section Procedures Manual
(ORNL 1993).
ix
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 164 EAST 1ST NORTH STREET
MONTICELLO, UTAH (MS00089-RS)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the U.S. government through the
Defense Plant Corporation to provide vanadium during World War II. Various
government agencies operated the mill until 1947. In 1948 the Atomic Energy
Commission (AEC) obtained the mill and operated it under contract through 1959 to
provide both uranium and vanadium. Mill operations were terminated on January 1,
1960. In 1961 the mill tailings piles were leveled and graded, covered with rock and soil,
and seeded with native grasses. During 1974 and 1975, the ore stockpiles were removed
from the site, and the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city
of Monticello, in San Juan County, Utah. The site is bordered on the south and southeast
by land held by the U.S. Bureau of Land Management. Other boundaries are the city of
Monticello and private property.
During the AEC era, the mill processed approximately one million tons of uranium
ore. Vanadium and uranium were the only substances extracted in the milling process.
Other constituents of the ore remained in the tailings and were not separated prior to
disposal. During the years of active mill operation, the mill tailings were normally moist,
so erosion was minimal. However, throughout the mill's operating period, area residents
used these tailings as fill material and as aggregate in mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy
(DOE) initiated the Surplus Facilities Management Program (SFMP) in 1978 to ensure
the safe caretaking and decommissioning of government facilities that had been retired
from service but still had radioactive contamination. In 1980 the mill site at Monticello
was accepted into the SFMP, and the Monticello Remedial Action Project (MRAP) was
established to restore the government-owned mill site to safe levels of radioactivity, to
dispose of or contain the tailings in an environmentally safe manner, and to perform
remedial actions on off-site (vicinity) properties that had been contaminated by
radioactive material resulting from mill operations. The Monticello mill site and the
tailings remain in the custody of the DOE Grand Junction, Colorado, Projects Office. In
1983 remedial actions for vicinity properties were separated from MRAP with
establishment ofthe Monticello Vicinity Properties (MVP) Project (U.S. DOE 1990b).
*The verification of remedial action was performed by members of the Environmental Assessment Group in the
Environmental Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE
contract DE-AC05-96OR22464 with Lockheed Martin Energy Research Corporation.
2
During 1995, RUST Geotech Inc. (Geotech), the remedial action contractor (RAC)
designated by DOE, performed remedial action on the vicinity property that is the subject
of this report, a single family residence located at 164 East 1st North Street, Monticello,
Utah. The remedial action plan required excavation of all exterior contamination. When
the excavation was completed, the property was resurveyed, including soil sampling, to
ensure the removal of all contamination, backfilled with uncontaminated material, and
restored to a condition comparable to that which existed prior to remedial action (Geotech
1996).
The DOE adopted a policy to assign an independent contractor to verify the data
supporting the adequacy of remedial action and to confirm the site's compliance with
DOE guidelines. The Environmental Technology Section (ETS) of Oak Ridge National
Laboratory (ORNL) has been assigned the responsibility of this task at the 164 East 1st
North Street site. This report describes the methods and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available
documentation adequately and accurately describes the post-remedial-action radiological
conditions of the entire property that is to be certified and (2) that the remedial action
reduced contamination to below applicable DOE guidelines (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1996)
indicates the property was remediated as evaluated by DOE on the basis of
Environmental Protection Agency standards and the DOE guidelines (DOE 1990a).
Excess residual radioactive materials were present, thus it was appropriate to designate
this property for remedial action.
This property was assessed as part of Block 33, therefore, the quantity of material
assessed is not available. During the actual removal process, a total of 22 yd3 of
contaminated earth and uranium mill tailings, 6 to 18 inches deep, were removed from a
71m2 area.
A post-excavation survey was performed by Geotech prior to backfilling the
excavated areas. This survey consisted of gamma scans with a scintillometer of the
ground level of the structure, a surface scan of the exterior, and soil sampling. Samples
representative of the bottom 15-cm (6-in.) soil layers of two excavated verification areas
were collected and blended to form representative composite soil samples for each
verification area.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation
levels have not been subtracted. Similarly, background concentrations have not been
subtracted from radionuclide concentrations in soil samples. Applicable DOE guidelines
for protection against radiation are given in Table 1.
Gamma Measurements
Gamma exposure rate measurements taken by Geotech at the ground-level ofthe
residence ranged from 12 to 15 uR/h. Exterior surface gamma measurements taken from
the excavated areas prior to backfilling ranged from 14 to 27 uR/h.
Soil Sample Analysis
Prior to backfilling, Geotech collected soil samples representative ofthe excavated
areas from the bottom 15-cm (6-in.) soil layers. These samples were blended to form a
composite soil sample representative of an average over the two exterior verification
areas. Geotech's analysis of these samples showed 226Ra concentrations ranging from 3.1
to 3.2 pCi/g in the composite sample. ORNL ETS obtained these samples and performed
a confirmatory analysis which showed 226Ra concentrations from 2.6 to 2.7 pCi/g. These
values are below the EPA standard value of 15 pCi/g for soil layers > 15 cm below the
surface. Gamma ranges and/or soil sample results in the folio demonstrate compliance to
the DOE Hot Spot Guidelines for areas <25 m2 (Table 1). Results of Geotech and ORNL
soil sample analyses are given in Table 2.
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were
determined by the Alpha-track method. To monitor radon levels, Geotech placed three
alpha-track detectors on the ground floor of the residence located on this property for a
period of approximately three months (from February 28,1995 to May 31, 1995). The
average annual working level (WL) of radon progeny concentration, as determined by
the TechVOps-Landauer Corporation, was 0.0023, which is well below the 0.03-WL
guideline given in Table 1.
CONCLUSION
Results of Geotech soil sample analysis and confirmatory split soil sample analysis
by ORNL show that radionuclide concentrations are within applicable DOE guidelines.
Based on the results of the post-remedial-action data, which are confirmed by the
verification assessment data, these radiological measurements fall below the limits
prescribed by DOE guidelines. All deficiencies noted in the initial review have been
identified by the RAC as discussed in a meeting between Geotech and ORNL on April
15,1996, and corrected in the revised completion report. It is concluded that the site
successfully meets the DOE remedial action objectives.
5
Table 2. Results of ORNL analysis of Geotech soil samples
from 164 East 1st North Street, Monticello Utah (MS00089-RS)
226Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No.a No* (cm)
XI NCH 061 >15 2.7 3.1
X2 NCH 062 >15 2.6 3.2
° An X-type sample is a split of the sample taken by the remedial action contractor.
* Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated
areas were taken by Geotech, and these samples were blended to form a composite soil
sample, which represents an average over one of the verification areas.
6
REFERENCES
Geotech 1996. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00089-RS, Address: 164 East First North Street, Monticello,
Utah 84535, Geotech, Grand Junction, Colorado, February 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
U.S. DOE 1990a. Verification and Certification Protocol for the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination
and Decommissioning Program, Revision 3, November 1990. U.S. Department of
Energy, Washington, D.C.
U.S. DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision
and Record of Decision Summary. U.S. Department of Energy, Grand Junction Projects
Office, Grand Junction, Colorado.
DOE ID NO.: MS-00100-CS
Property Address: 333 South Second East Street
DEC i 8 1996
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
RUST Geotech Inc. of Energy (DOE)
YES NO NOT TAKEN YES NO NOT TAKEN
Ra-226 is < 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [ ]
Ra-226 is < 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2.
In-situ [ ] Lab [X]
Interior gamma is < 20 fjR/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is < 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21,
Hot spot criteria met as
outlined by U.S. DOE
guidelines for FUSRAP and
Environmental Restoration
Program (Rev. 03/02/87).
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[A I ] i ]
m t 1 I 1
W [ 1 [ 1
[>} [ ] [ ]
[ ] [>] [ 1
[ ] [ ] [X] [ ] [ ] [ft
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
SFCERTIFED SFMS-00I00
DOE ID NO.: MS-001 OO-CS
RUST GEOTECH INC. RECOMMENDATION
Based on the RUST Geotech Inc. evaluation, I recommend this property for:
[X] Certification by the Department of Energy.
[ ] Certification by the Department of Energy with the concurrence of the
Nuclear Regulatory Commission because supplemental standards were
applied per 40 CFR 192.21.
farry A. Perr
Program Manager
RUST Geotech Inc
Date
DOE EVALUATION
P<] Should be certified by the Department of Energy.
[ ] Should be certified by the Department of Energy with the concurrence
of the Nuclear Regulatory Commission because supplemental
standards were applied per 40 CFR 192.21.
Environmental Restoration Program
Certification Official
Department of Energy
Date
^ 1 7 1897
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00104-VL
ADDRESS: 449 SOUTH SECOND EAST STREET
MONTICELLO, UTAH 84535
AUGUST 1996
Prepared for
U.S. Department of Energy
by
Rust Geotech
P.O. Box 14000
- Grand Junction, Colorado 81502-5504
Wanda S. Busby
Manager, Monticello Programs
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 4
2.1 Abstract of Remedial Action Plan 4
2.2 Previously Unidentified Contamination 4
2.3 Unanticipated Items During Remedial Action . . 4
2.4 Application of Supplemental Standards 4
3.0 VERIFICATION SUMMARY 5
3.1 Radiological Survey Data 5
3.1.1 Pre-Remedial Action Survey 5
3.1.2 Post-Excavation Survey 5
3.2 Recommendation for Certification 6
4.0 APPENDIX 7
DOE ID No.: MS-00104-VL
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly^ Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by DOE, which determined that the property contained mill
tailings (residual radioactive material) exceeding EPA standards. The
Remedial Action Contractor was notified of the inclusion of this property
into the MVP Project and was authorized by DOE to conduct remedial
action as required to bring the property into conformance with EPA
standards and DOE hot spot criteria.
1
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
Property Address:
Property Owner:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessments (REA):
Construction Subcontractors
Pre-Construction Conference
Records:
Notices of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
DOE ID No.: MS-00104-VL
MS-00104-VL
Beginning at the NE corner of Lot 2,
Block 1, Monticello Townsite Survey; west
214.5 feet, south 209 feet, north
88 degrees 50 minutes 40 seconds east
429.08 feet, north 200.3 feet, west
214.5 feet to beginning, County of San
Juan, State of Utah
449 South Second East Street
Monticello, Utah 84535

Vacant Lot (VL)
Not applicable: historical inclusion by DOE
June 8, 1984
Rust Geotech
July 31, 1986 - Phase I
September 12, 1995 - Phase II
Phase I:
Diamond Back Services, Inc.
9861 Titan Park Circle
Littleton, Colorado
Phase II:
Mountain Region Corporation
117 29 3/4 Road
Grand Junction, Colorado
May 4, 1987 - Phase I
November 6, 1995 - Phase II
August 6, 1987 - Phase I
November 17, 1995 - Phase II
Interior: 0 cubic yards
Exterior: 5,012 cubic yards
8,217 square meters (m2)
2
DOE ID No.: MS-00104-VL
1.3 Summary of Remedial Action (continued)
Property Completion Report
Submitted: August 1996
3
DOE ID No.: MS-00104-VL
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of exterior residual radioactive
material (Appendix Figure 2.1). Once excavation was complete, the
affected areas were resurveyed for possible remaining residual radioactive
material and, upon attaining satisfactory results, were backfilled with
uncontaminated material. The property was restored to a physical
condition comparable to that which existed prior to remedial action
activities.
2.2 Previously Unidentified Contamination
The radiological assessments identified approximately 1,756 cubic yards
of contamination, ranging from 3 to 52 inches deep, within the property.
The remedial action process included the removal of approximately
5,012 cubic yards of residual radioactive material, ranging from 6 to
156 inches deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
During the initial remedial action (Phase I), additional contamination was
encountered, primarily associated with buried utilities. The property was
reassessed and underwent additional remediation (Phase II).
An area of the Phase I excavation in the southeast part of the property
was not verified due to remaining contamination associated with afcmried
water main and a sanitary sewer. Portions of Phase I assessed Areas L,
M, and N in this previously excavated area were found to be
uncontaminated during the Phase II assessment and remediation.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted within the legal boundary of the property. Portions of
assessed Areas K, AA, and AV, associated with buried utilities located
between the west property boundary and the street, will be addressed as
supplemental standards under MS-50000-OT. The supplemental
standards area was partially remediated during Phase I.
4
DOE ID No.: MS-00104-VL
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by Bendix Field Engineering
Corporation during October 1984, as described in the original REA
dated July 1986. A radiological survey was conducted by the
Remedial Action Contractor during May 1995, as described in the
Phase II REA dated September 1995. Appendix Figure 2.1 shows
the extent of assessed contamination and identifies the areas
recommended to undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the excavation were
collected. An individual soil sample was collected for Area
V-14-2. The remaining samples were blended to form composite
samples representing the other verification areas (Appendix
Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 14 to 116 microroentgens per
hour (jjR/h), as indicated on Appendix Figure 2.1. Elevated
exposure rates in the area between the west property boundary
and the street will be addressed under supplemental standards as
discussed in Section 2.4. Elevated exposure rates in Area V-8
were associated with the property adjoining the east incfo^bti
boundary. Elevated exposure rates in Area V-14-2 were
associated with residual radioactive material left in place under a
concrete support pad for a sewer line. The result of analysis for
radium-226 in an individual soil sample of this area was
31.5 picocuries per gram (pCi/g). The 100 m2 area average was
3.8 pCi/g (Appendix Table 3.1). Area V-14-2 also met the hot
spot criteria, as indicated in Appendix Table 3.2. The results of
analyses for radium-226 in 63 composite soil samples ranged from
less than 1.0 pCi/g to 16.7 pCi/g, as indicated in Appendix
Table 3.3.
5
DOE ID No.: MS-00104-VL
3.2 Recommendation for Certification
Residual radioactive materials have been removed from within the legal
boundary of this property to the extent required by EPA standards
(40 CFR 192.12, 192.20-23) and DOE hot spot criteria, as indicated in
the Certification Data Summary below.
Therefore, the property located at 449 South Second East Street, in
Monticello, Utah, is recommended for certification as required by DOE
guidelines, and the appropriate records should be documented.
Certification Data Summary
Applicability
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Standards
Shall not exceed 20 //R/h
above background.
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Survey Results
Not applicable: vacant
lot.
Not applicable: vacant
lot.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background* in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background* in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
< 5 pCi/g above
background.
Soil sample results
ranged from < 1.0 to
16.7 pCi/g, and another
sample result, averaged
over 100 m2, was
3.8 pCi/g.
*The background radium-226 concentration is approximately 2.0 pCi/g.
The hot spot criteria were met based on gamma scans and/or soil sample results.
6
DOE ID No.: MS-00104-VL
4.0 APPENDIX
Appendix Tables:
Table 3.1 Calculation of Average Radium Concentration
over a 100 m2 Area
Table 3.2 Hot Spot Calculation Results
Table 3.3 Post-Excavation Sample/Measurement Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
JEK:07-10-96
MS-00104. VL WP61
REV080195
7
Table 3.1
Calculation of Average Radium Concentration over a 100 m2 Area
DOE ID No.: MS-00104-VL
Address: 449 South Second East Street, Monticello, Utah
(CpXAp) + [Crx (1,076-Ap)]
°av9 = 1,076
Where:
Cava = Radium-226 concentration in picocuries per gram averaged over a
a 100 m2 (1,076 ft2) area.
Cp = Radium-226 concentration in picocuries per gram of the residual
radioactive material left in place.
Ap = Area in square feet of the residual radioactive material left in
place.
Cr = Radium-226 concentration in picocuries per gram for the
remainder of the 100 m2 area, including excavated and
unexcavated areas.
1,076 = Total area in square feet over which the EPA guideline is applied.
Cn Cp C3VQ EPA
Meas. Depth Standard
Area Method" (inches) (pCi/g) (ft2) (pCi/g) (pCi/g) (pCi/g)
V-14-2 OCS 15 - 21 31.5 8 3.6b 3.8 15.0°
Therefore, the averaged radium-226 concentration does not exceed the EPA
standard.
"OCS = Opposed Crystal System
bWeighted-area average, based on 248 ft2 of Area V-8-2 at 4.4 pCi/g, 481 ft2 of
Area V-9-2 at 3.8 pCi/g, 99 ft2 of Area V-10-2 at 4.4 pCi/g, and 240 ft2 of
background area at 2.0 pCi/g.
The DOE-implemented EPA standard used for OCS measurements taken after
December 7, 1990, does not include the background radium concentration.
8
Table 3.2
Hot Spot Calculation Results
DOE ID No.: MS-00104-VL
Address: 449 South Second East Street, Monticello, Utah
Shg = [Sgx (100/A)7']
Where:
Shg = Hot Spot Limit of radium-226 concentration in picocuries per gram.
Sg = Authorized Limit of radium-226 concentration in picocuries per gram
(Sg = 5.0 pCi/g for surface soil and 15.0 pCi/g for subsurface
soils).
100 = Total area in square meters over which the Hot Spot Limit guideline
is applied.
A = Area in square meters of the hot spot.
A SQ Shg + Radium-226 in
Meas. Depth Background1" Hot Spot Area
Area Method" (inches) (m2) (pCi/g) (pCi/g) (pCi/g)
V-14-2 OCS 15-21 0.7° 15.0 152.0 31.5
Therefore, the radium-226 concentration in the hot spot area does not exceed the
maximum allowable concentration.
"OCS = Opposed Crystal System
bMaximum allowable radium-226 concentration (the background radium-226
concentration for Monticello is 2.0 pCi/g).
cAreas smaller than 1.0 m2 are calculated as if they are 1.0 m2.
9
Table 3.3
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00104-VL
Address: 449 South Second East Street, Monticello, Utah
The analytical uncertainties in the table are reported at the 95-percent confidence
interval. A less-than sign (<) indicates that the minimum detection limit based on
Compton background was reached.
Exposure- Soil
Rate Range Sample Meas. Radium-226 Potassium Thorium
Area (j/R/h) Ticket No. Method" (pCi/g) (pCi/g) (pCi/g)
V-1
V-2
V-3
V-4
V-5
V-6
V-7
V-8
V-9
V-10
V-11
V-12
V-13
V-14
V-15
V-16
V-17
V-18
V-19
V-20
V-21
V-22
V-23
V-24
V-25
V-26
V-27
16 - 21
17 - 21
18 - 21
15 - 21
18 - 21
19-24
24- 25
19 - 51
18-29
18-23
18-23
18 - 24
17- 23
18- 22
19- 22
18 - 21
18 - 21
18 - 21
18 - 21
18 - 21
20 - 22
17 - 21
18 - 21
18-25
18-23
17-22
16-23
MNF 629
MNF 630
MNF 631
MNF 632
MNF 633
MNF 634
MNF 334
MNF 636
MNF 637
MNF 638
MNF 639
MNF 640
MNF 641
MNF 642
MNF 643
MNF 644
MNF 645
MNF 646
MNF 647
MNF 648
MNF 649
MNF 650
MNF 351
MNF 352
MNF 353
MNF 354
MNF 355
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
4.3±0.7
6.0±1.0
6.5±1.1
13.3±2.0
3.5±0.5
4.1 ±0.6
3.1 ±0.
9.7±1.
.5±0.
.0±0.
.9±0.
.1 ±0.
.1 ±0.
6.
4.
3.
4.
3.
.5
.3
.9
.6
.6
.6
.5
8.7±1.2
3.8±0.5
3.5±0.5
3.0±0.5
4.6±0.7
3.7±0.6
2.5±0.5
6.9±1.1
2.7±0.5
3.2±0.5
3.4 + 0.6
2.5±0.4
7.2±1.1
6.1 ±0.9
18.6±8
16.6±8
13.9±8
20.2 ±8
15.0±3
16.2±3
11.7±3
15.1 ±3
14.5±3
16.2±3.6
17.0±3.8
15.9±3.6
16.2±3.7
17.9±3.9
18.4±3.8
16.5±3.6
16.6±3.9
17.5±4.0
17.9±4.1
17.6±4.1
18.1 ±4.2
18.8±4.2
17.6±4.3
16.9±3.9
18.6±4.1
17.3±4.1
14.4±3.5
5
4
5
5
3
3
2
3
2
1.5±0
0.5±0
0.9±0
1.2±0
0.8±0
0.7±0
0.7±0
1.0±0
0.8±0
1.1 ±0.3
1.1 ±0.3
0.9±0.3
0.7±0.2
<0.2
1.1 ±0
.1 ±0
.2
.9±0.3
.2
.2
.6±0.3
0.9±0.3
<0.2
.6±0.3
.7±0.3
.3
.9±0.3
1,
<0.
0.
<0.
<0.
0.
0.
0.
<0.
0.
.3
.3
"AL = Analytical Laboratory
10
Table 3.3 (continued)
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00104-VL
Address: 449 South Second East Street, Monticello, Utah
Exposure- Soil
Rate Range Sample Meas. Radium-226 Potassium Thorium
Area Ot/R/h) Ticket No. Method0 (pCi/g) (pCi/g) (pCi/g)
V-28
V-29
V-30
V-31
V-32
V-33
V-34
V-35
V-36
V-37
V-38
V-39
V-40
V-41
V-42
V-43
V-44
V-45
V-46
V-47
V-48
V-49
V-1-2
V-2-2
V-3-2
V-4-2
V-5-2
V-6-2
V-7-2
V-8-2
15 - 21
15-23
16 - 21
15- 25
16- 22
17- 25
17-24
17-24
18 - 21
17-22
17-24
16- 25
17- 23
17 - 30
17- 25
18- 24
18 - 21
17- 24
17 - 31
18 - 21
18- 23
18-23
15 - 17
15 - 17
15 - 18
14- 23
15 - 21
15- 23
18-23
19 - 21
MNF 356
MNF 357
MNF 358
MNF 359
MNF 360
MNF 361
MNF 362
MNF 363
MNF 364
MNF 365
MNF 366
MNF 367
MNF 329
MNF 369
MNF 370
MNF 333
MNF 372
MNF 373
MNF 374
MNF 375
MNF 326
MNF 327
NCO 455
NCO 456
NCO 457
NCO 458
NCO 459
NCO 460
NCO 115
NCO 116
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
5.1 ±0.7
3.1 ±0.5
2.1 ±0.4
7.2±1.1
5.7±0.9
5.7±0.9
8.3±1.3
8.4±1.3
6.2±1.0
9.4±1.4
8.6±1.3
16.7±2.5
10.4±1.4
6.2±1.0
7.9±1.3
8.3±1.1
7.5±1.2
11.2±1.7
6.2±1.0
11.6±1.8
16.2±2.2
15.5±2.1
2.4
<1.0
2.9
3.4
1.5
2.4
2.3
4.4
12.1 ±3.4
13.2±3.6
16.1 ±3.7
15.8±8.0
14.9±7.8
13.8±8.0
13.3±8.3
11.6±8.1
13.9±8.2
12.5±7.3
14.9±8.1
12.5±8.1
12.2±3.4
10.8±8.7
13.3±8.9
12.7±3.4
8.5±8.5
11.5±9.0
11.0±9.0
11.4±8.5
10.6±3.5
15.2±3.8
0.9±0.3
0.9±0.3
1.3±0.3
0.8±0.4
1.2±0.4
0.7±0.4
1.0±0.4
0.7±0.
0.8±0.
1.6±0.
1.1 ±0.
0.9±0.5
0.8±0.3
1.3±0.5
0.6±0.5
<0.2
1.0±0.5
0.4±0.5
1.6±0.5
0.9±0.5
1.2±0.3
1.1 ±0.3
.4
.4
.5
.4
"AL = Analytical Laboratory; OCS = Opposed Crystal System
11
Table 3.3 (continued)
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00104-VL
Address: 449 South Second East Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range O^R/h) Ticket No. Method0 (pCi/g)
V-9-2 20- 29 NCO 117 OCS 3.8
V-10-2 21 - 32 NCO 118 OCS 4.4
V-11-2 21 - 29 NCO 119 OCS 2.9
V-12-2 21 - 26 NCO 120 OCS 3.8
V-13-2 20- 23 NCO 121 OCS 3.6
V-14-2 29-43 NCO 063 OCS 31.5
V-15-2 19-21 NCO 403 OCS 4.0
See Appendix Figure 2.1 for the verification areas.
"OCS = Opposed Crystal System
12
"i—r
24
~T~
26
-T i r
30
~T
34
~T
38 40
~T~
42
1-T—r
46 48
-r~
50 52 54
-r~
56
-r~
58
T" T—r
62
~T~
66
T
68
"T"
V-30 v-28 V-26 V-10 V-3S v-36 V-32 V-42 V-48 V-46
16-22 16-21 15-21 17-22 16-23 17-24 10-21 17-24 17-31 17-25 18-23
v-4-2 v-33 V-31 v-29 V-25 v-23 V-21 V-17 V-15 V-13 V-11 V-39 V-37 V-35 V-27 V- 19 V-41 3-2 V-47 V-45 V-40 V-49
14-23 17-25 15-25 15-23 18-23 18-21 20-22 18-21 16-21 19-22 17-23 18-23 U-29 17-30 16-25 17-22 17-24 16-23 '5-16 17-24 J-2 18-23 16-21 7-23
z v-12
-Ml: © V •—r © © 1 -17 12-7
© -20 V- IB
0 0 0N 10-21 18-11 ta-ai IS-Z2
-0 ® © d> 17-116
v-a
i i 1
0 0 19-51
® © 0 i _ a ~ 8 I. 1 © © [ ) _.J
I I © 1,© © © ® © © _ J !• 1 © ® ©'
a 2 ®\ 1.1 ®
© © © - T.-.V. .• r
L4-V-7-2 1.1^
18-23
0 V-21 J . v. I v-2-2 1-2 v-6-2 20-22 t. I © 15-17 15-17 12) ' / '5-23
16-21 r 12 v-s-z
V-4-2 4-2 19-21 15-21 12XAG
a 14-23 14-23
16-21
16-21 20 17-20 © V-43 v-2
5-2 18-24 17-21
© © i J v-6-2 13-21 v-6-2
15-23 15-23
' © >JF ED
19iiR/h AIX 6 I2IAP v-3-2 V-9-2
17-21 15-21 20-29 18-21
^ © <Q on /-IS v-4-2
18-21 [24]^ 19-21
. . . . V T r r
14-23
..-iT S3 ill \^ I 56IAB
I- 12-
/-1i-; 21-20
21-29
19-20* * x
(-io-:
21-32
20
•L
SCALE IN FEET
20 10 0 20 40
U \'4S\013\0001\*MMiO«V at/jj/M Of Ita* WH
j L J L 1 l I I L J !_ j 1
©
@
©
L--J
12-15
v-1
16-17
f-14-
16-17
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN /iR/h
ASSESSED AREA IDENTIFIER
PHASE II ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSEO CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE-RATE RANCE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
ANO EXCAVATION EXPOSURE-RATE RANGE
PHASE II VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE-RATE RANGE
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
CONTAMINATION LEFT IN PLACE
SUPPLEMENTAL STANDARDS AREA (UTILITIES BETWEEN
PROPERTY BOUNDARY ANO STREET) WILL BE ADDRESSED
UNOER MS-50000-0T
UNVERIFIED AREA OF PHASE I EXCAVATION. (PORTIONS
OF AREAS L. M. ANO N NOT FOUNO D'JRING PHASE II)
J I I I I L J I
THIS DRAWING IS ron THC SOLE use OF THC U.S. OCPARTMCNT
Of ENCKCV ANO ITS CONTRACTORS. IT IS NOT A LANO SURVCY
PLAT. UTILITY VOCATION FLAT, OR OTHER lURROVCUCNT SURVCT
PLAT AM) IS NOT TO BC REUCO UPON FOR TMC ESTABLISHMENT
OF FCNCC. 9UIL0INC. OR OTHER FuTuRC IMPROVCMCNT LINCS.
J I I L J 1 j 1
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
ROHKCI-U or oecuPNtn
>HlT*V4*(NlT HO.
BY CK. A E AP*. NO. DATC
U.S. DEPARTMENT OF ENERGY
G ft ANO JUNCTION PROJECTS OFFICE. COLORADO
Wi
449 SOUTH SECONO EAST STREET
MONTICELLO, UTAH
Rust OOOttHStl OU<.IKNU KS-00104-VL
0»C. NO. 3-000104-V1
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
449 SOUTH 2ND EAST STREET
MONTICELLO, UTAH (MS00104-VL)
A. R. Jones
September 1996
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
CONCLUSION 3
REFERENCES 6
iii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 4
2. Results of ORNL analysis of Geotech soil samples from 449 South 2nd East Street,
Monticello, Utah (MSOO104-VL) 5
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site
Decommissioning Projects, U.S. Department of Energy. The author wishes to
acknowledge M. K. Jensen for analysis of soil samples and technical review and
J. R. Sauvage for technical review.
vn
ABSTRACT
In 1980 the site of a vanadium and uranium mill at Monticello, Utah, was accepted
into the U.S. Department of Energy's (DOE's) Surplus Facilities Management Program,
with the objectives of restoring the government-owned mill site to safe levels of radio-
activity, disposing of or containing the tailings in an environmentally safe manner, and
performing remedial actions on off-site (vicinity) properties that had been contaminated
by radioactive material resulting from mill operations. During 1987 and 1995, RUST
Geotech, the remedial action contractor designated by DOE, performed remedial action on
the vicinity property at 449 South 2nd East Street, Monticello, Utah. The Environmental
Technology Section (ETS) of Oak Ridge National Laboratory was assigned the responsi-
bility of verifying the data supporting the adequacy of remedial action and confirming the
site's compliance with DOE guidelines. The ETS found that the site successfully meets the
DOE remedial action objectives. All deficiencies noted in the initial review have been re-
solved with the revised completion report and additional documentation to the property
folio. Procedures used by the ETS are described in the Environmental Technology Sec-
tion Procedures Manual (ORNL 1993).
ix
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 449 SOUTH 2ND EAST STREET
MONTICELLO, UTAH (MS00104-VL)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the U.S. government through the
Defense Plant Corporation to provide vanadium during World War II. Various govern-
ment agencies operated the mill until 1947. In 1948 the Atomic Energy Commission
(AEC) obtained the mill and operated it under contract through 1959 to provide both
uranium and vanadium. Mill operations were terminated on January 1, 1960. In 1961 the
mill tailings piles were leveled and graded, covered with rock and soil, and seeded with na-
tive grasses. During 1974 and 1975, the ore stockpiles were removed from the site, and
the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city
of Monticello, in San Juan County, Utah. The site is bordered on the south and southeast
by land held by the U.S. Bureau of Land Management. Other boundaries are the city of
Monticello and private property.
During the AEC era, the mill processed approximately one million tons of uranium
ore. Vanadium and uranium were the only substances extracted in the milling process.
Other constituents of the ore remained in the tailings and were not separated prior to dis-
posal. During the years of active mill operation, the mill, tailings were normally moist, so
erosion was minimal. However, throughout the mill's operating period, area residents
used these tailings as fill material and as aggregate in mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy
(DOE) initiated the Surplus Facilities Management Program (SFMP) in 1978 to ensure
the safe caretaking and decommissioning of government facilities that had been retired
from service but still had radioactive contamination. In 1980 the mill site at Monticello
was accepted into the SFMP, and the Monticello Remedial Action Project (TvIRAP) was
established to restore the government-owned mill site to safe levels of radioactivity, to
dispose of or contain the tailings in an environmentally safe manner, and to perform reme-
dial actions on off-site (vicinity) properties that had been contaminated by radioactive ma-
terial resulting from mill operations. The Monticello mill site and the tailings remain in the
custody of the DOE Grand Junction, Colorado, Projects Office. In 1983 remedial actions
for vicinity properties were separated from MRAP with establishment of the Monticello
Vicinity Properties (MVP) Project (U.S. DOE 1990b).
*The verification of remedial action was performed by members of the Environmental Assessment Group in the
Environmental Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE
contract DE-AC05-96OR22464 with Lockheed Martin Energy Research Corporation.
2
During 1987 and 1995, RUST Geotech Inc. (Geotech), the remedial action contractor
(RAC) designated by DOE, performed remedial action on the vicinity property that is the
subject of this report, a vacant lot located at 449 South 2nd East Street, Monticello, Utah.
The remedial action plan required excavation of all exterior contamination. When the ex-
cavation was completed, the property was resurveyed, including soil sampling, to ensure
the removal of all contamination, backfilled with uncontaminated material, and restored to
a condition comparable to that which existed prior to remedial action (Geotech 1996).
The DOE adopted a policy to assign an independent contractor to verify the data
supporting the adequacy of remedial action and to confirm the site's compliance with DOE
guidelines. The Environmental Technology Section (ETS) of Oak Ridge National Labor-
atory (ORNL) has been assigned the responsibility of this task at the 449 South 2nd East
Street site. This report describes the methods and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available doc-
umentation adequately and accurately describes the post-remedial-action radiological
conditions of the entire property that is to be certified and (2) that the remedial action
reduced contamination to below applicable DOE guidelines (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1996) in-
dicates the property was remediated as evaluated by DOE on the basis of Environmental
Protection Agency standards and the DOE guidelines (DOE 1990a). Excess residual
radioactive materials were present, thus it was appropriate to designate this property for
remedial action.
The pre-remedial-action survey performed by Geotech identified 1756 yd3 of mill
tailings 3 to 52 inches deep. During the actual removal process, a total of 5012 yd3 of
contaminated earth and uranium mill tailings, 6 to 156 inches deep, were removed from a
8217 nr area.
A post-excavation survey was performed by Geotech prior to backfilling the exca-
vated areas. This survey consisted of a surface gamma scan with a scintillometer of the
exterior and soil sampling. Samples representative of the bottom 15-cm (6-in.) soil layers
ofthe excavated verification areas were collected and blended to form representative
composite soil samples for each verification area. An individual sample representative of
the bottom 15 cm soil layers of VI4-2 was collected for area averaging and to show
compliance to the Hot Spot Guideline. The RAC is unable to locate or inadvertently
disposed of several samples requested for ORNL confirmatory analysis.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation
levels have not been subtracted. Similarly, background concentrations have not been sub-
tracted from radionuclide concentrations in soil samples. Applicable DOE guidelines for
protection against radiation are given in Table 1.
Gamma Measurements
Exterior surface gamma measurements taken by Geotech from the excavated areas
prior to backfilling ranged from 14 to 116 uR/h.
Soil Sample Analysis
Prior to backfilling, Geotech collected soil samples representative of the excavated
areas from the bottom 15-cm (6-in.) soil layers. These samples were blended to form
composite soil samples representative of an average over the 63 exterior verification areas.
Geotech's analysis of these samples showed 226Ra concentrations ranging from <1.0 to
16.7 pCi/g in the composite sample. ORNL ETS obtained two of these soil samples and
performed a confirmatory analysis which showed 226Ra concentrations ranging from 6.3 to
8.4 pCi/g. These values are below the EPA standard value of 15 pCi/g for soil layers > 15
cm below the surface. Results of Geotech and ORNL soil sample analyses are given in
Table 2.
As a result of a meeting between the RAC and the IVC on May 26, 1994, anomalous
readings defined as >30% above the average of the excavation will be investigated to show
compliance to the DOE hot spot guideline. Phase I removal on this property occurred
before this procedure change. The data in the folio does not have field averages, therefore,
the IVC is unable to determine if any area exceeds 30%. The IVC will allow a correlation
developed by the RAC to estimate 226Ra pCi/g concentrations based on gamma exposure
rates. The highest gamma exposure rate inside the property boundary is 51 uR/h, using the
RAC's correlation yields a 226Ra concentration of 32 pCi/g. This value is right at the mini-
mum concentration of 32 pCi/g (including a background of 2) needed, when assuming the
maximum area under the hot spot guideline of 25 nr, for subsurface samples. Gamma
ranges and/or soil sample results demonstrate compliance to the DOE Hot Spot Guidelines
for areas <25 m2 (Table 1).
CONCLUSION
Results of Geotech soil sample analysis and confirmatory split soil sample analysis by
ORNL show that radionuclide concentrations are within applicable DOE guidelines. Based
on the results ofthe post-remedial-action data, which are confirmed by the verification
assessment data, these radiological measurements fall below the limits prescribed by DOE
guidelines. All deficiencies noted in the initial review have been identified by the RAC and
corrected in the revised completion report as discussed in a meeting between Geotech and
ORNL on August 20, 1996. It is concluded that the site successfully meets the DOE
remedial action objectives.
4
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of ^Ra in soil
above background levels,
averaged over a 100-m2 area
5 pCi/g averaged over the
first 15 cm of soil below the
surface; 15 pCi/g when ave-
raged over 15-cm-thick soil
layers more than 15 cm
below the surface
Radionuclide con-
centrations in soil
for Hot Spot areas
Exposure to "Rn
progeny
Maximum Permissible con-
centration of Ra226 in soil
above background level, for
areas less than 25 m2
Average annual radon proge-
ny concentration (including
background)
Ra concentrations, in any
surface or subsurface area
less than 25 m2, is below the
guideline by a factor of
(lOO/A)*, where A is the
area of the elevated region
0.03 WL
(DOE 1990a)
5
Table 2. Results of ORNL analysis of Geotech soil samples from
449 South 2nd East Street, Monticello, Utah (MS00104-VL)
^Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No." Nof (cm)
V33 MNF 361 >15 6:3 5.7
V38 MNF 366 >15 8.4 8.6
" An X-type sample is a split of the sample taken by the remedial action contractor.
6 Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated areas
were taken by Geotech, and these samples were blended to form a composite soil
sample, which represents an average over one of the verification areas.
REFERENCES
Geotech 1996. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00104-VL, Address: 449 South Second East Street,
Monticello, Utah 84535, Geotech, Grand Junction, Colorado, August 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
U.S. DOE 1990a. Verification and Certification Protocol for the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination
and Decommissioning Program, Revision 3, November 1990. U.S. Department of
Energy, Washington, D.C.
U.S. DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision
and Record of Decision Summary. U.S. Department of Energy, Grand Junction Projects
Office, Grand Junction, Colorado.
<iAh 1 7 1997 ^
DOE ID No.: MS-00104-VL
Property Address: 449 South Second East Street
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech of Energy (DOE)
Ra-226 is <. 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [ ]
Ra-226 is < 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2.
In-situ [ ] Lab [X]
Interior gamma is < 20 //R/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is < 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21.
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[ ] [ ] [X]
(Vacant Lot)
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
l>] [ ] [ ]
[>] t ]
[ ] [ ]
[ ]
[ ] [ ] [X] [ ] [ ] [>]
(Vacant Lot)
[ ] [>] [ 1
[/] [ ] [ 1
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
SFCERTIFED SFMS-00104
DOE ID No.: MS-00104-VL
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
rA/9t
Wanda S/Busby ' Date
Manager, Monticello Programs
Rust Geotech
DOE EVALUATION
[A] Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
CeiWicatiorfblricial
7* fid *
Date
U.S. Department of Energy
DOE ID No.: MS-00107-RS
Property Address: 249A South Third East Street
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech of Energy (DQE)
Ra-226 is <. 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [ ]
Ra-226 is <; 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2.
In-situ [ ] Lab [X]
Interior gamma is < 20 //R/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is <• 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21.
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
[y] [ ] [ 1
[Yl [ 1 [ 1
MM [ 1
M [ ] [ 1
[ ] [X] [ ]
[y] [ ] U
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
llllllllIilD Ililllllllll
SFCERTIFED SFMS-e9e28
DOE ID No.: MS-00107-RS
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
iklM
Date Wanda S/Bu =7 Jusby
Manager, Monticello Programs
Rust Geotech
DOE EVALUATION
[y] Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
%A^\^<M /1* fat fh
Certification Official ' Date
U.S. Department of Energy
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00107-RS
ADDRESS: 249A SOUTH THIRD EAST STREET
MONTICELLO, UTAH 84535
MARCH 1996
Prepared for
U.S. Department of Energy
by
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
Wanda S. Busby
Manager, Monticello Programs
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.1.3 Radon Decay-Product Concentration (RDC) Measurement .... 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
i
DOE ID No.: MS-00107-RS
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Remedial Action Contractor. DOE reviewed these
evaluation results and determined that the property contained mill tailings
(residual radioactive material) exceeding EPA standards. The Remedial
Action Contractor was notified of the inclusion of this property into the
MVP Project and was authorized by DOE to conduct remedial action as
required to bring the property into conformance with EPA standards and
DOE hot spot criteria.
1
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
Property Address:
Property Owner:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
DOE ID No.: MS-00107-RS
MS-00107-RS
Location M-220; beginning 1,329 feet
south of the NE corner of Section 36,
T33S., R23E., Salt Lake Base Meridian;
west 130.68 feet, south 271.92 feet, east
130.68 feet, north 271.92 feet to the
beginning; except beginning 1430 feet
south of the NE corner of said Section 36,
west 130 feet, south 169 feet, east
130 feet, north 169 feet to the beginning,
City of Monticello, County of San Juan,
State of Utah
249A South Third East Street
Monticello, Utah 84535

Residential Simple (RS)
Not applicable: inclusion requested by the
Remedial Action Contractor
December 7, 1992
Rust Geotech
November 11, 1993
Diamond Back Services, Inc.
9861 Titan Park Circle
Littleton, Colorado
August 9, 1994
September 15, 1994
Interior: 0 cubic yards
Exterior: 108 cubic yards
527 square meters (m2)
March 1996
2
DOE ID No.: MS-00107-RS
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of exterior residual radioactive
material (Appendix Figure 2.1). Once excavation was complete, the
affected areas were resurveyed for possible remaining residual radioactive
material and, upon attaining satisfactory results, were backfilled with
uncontaminated material. The property was restored to a physical
condition comparable to that which existed prior to remedial action
activities.
2.2 Previously Unidentified Contamination
The radiological assessment identified contamination, ranging from 6 to
12 inches deep, within the property. The quantity of contamination for
this property was not specified because it was assessed as part of Block
MS-09028-BK. The remedial action process included the removal of
approximately 108 cubic yards of residual radioactive material, ranging
from 6 to 12 inches deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID No.: MS-00107-RS
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by the Remedial Action
Contractor during April 1992, as described in the final REA dated
November 1993. Appendix Figure 2.1 shows the extent of
assessed contamination and identifies the areas recommended to
undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the excavation were
collected. These samples were blended to form composite
samples representing the verification areas (Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 13 to 23 microroentgens per
hour (yt/R/h), as indicated on Appendix Figure 2.1. The results of
analyses for radium-226 in six composite soil samples ranged from
3.6 to 9.2 picocuries per gram (pCi/g), as indicated in Appendix
Table 3.1. The composite samples representing Areas V-3
through V-6 included soil samples collected from MS-00197-VL
(Areas V-5 through V-8).
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on measurements representing an annual average, the
RDC was 0.0090 working level (WL), as indicated in Appendix
Table 3.2. Appendix Figure 2.1 shows the measurement location
on the ground floor (the lowest habitable level of the structure).
4
DOE ID No.: MS-00107-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at 249A South Third East Street, in
Monticello, Utah, is recommended for certification as required by DOE
guidelines, and the appropriate records should be documented.
Certification Data Summary
Applicability
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Standards
Shall not exceed 20 //R/h
above background.*
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Survey Results
Range for the ground
floor was 13 to 15 //R/h.
Annual average was
0.0090 WL.
Land.
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
< 5 pCi/g above
background.**
Soil sample results
ranged from 3.6 to
9.2 pCi/g.**
*The background exposure rate is approximately 14//R/h.
The background radium-226 concentration is approximately 2.0 pCi/g.
* *The hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-00107-RS
4.0 APPENDIX
Appendix Tables:
Table 3.1 Post-Excavation Sample/Measurement Results
Table 3.2 Radon Decay-Product Concentration Measurement
Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
MRW:03-01-96
MS-00107.RS WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00107-RS
Address: 249A South Third East Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Raaium-226
Area Range (//R/h) Ticket No. Method* (pCi/g)
V-1 17-22 NCB 926 OCS 4.4
V-2 15-21 NAZ 455 OCS 3.6
V-3 15-22 NAZ 456 OCS 9.2
V-4 15-23 NAZ 457 OCS 6.2
V-5 15-20 NAZ 458 OCS 4.8
V-6 16-23 NAZ 459 OCS 6.3
See Appendix Figure 2.1 for the verification areas.
"OCS = Opposed Crystal System
7
Table 3.2
Radon Decay-Product Concentration Measurement Results
DOE ID No.: MS-00107-RS
Address: 249A South Third East Street, Monticello, Utah
Instrument Type: Landauer Radtrak Detector
Detector
Number Start Date End Date
Radon
Concentration
(pCi/L)
Working
Level
3851477
3851603
3851622
10-10-94
10-10-94
10-10-94
09-27-95
09-27-95
09-27-95
1.83
1.84
1.73
0.0092
0.0092
0.0087
Annual Average: 0.0090
See Appendix Figure 2.1 for the measurement location.
8
10
'30
14 1 6 20
i—r
22
T"
24 26 28 30 32 34 36 38 40
30
28 28
26
24
22
20
18
16
14
12
LU
UJ
tr
i—
GO
I—
GO
< s
LU N
N o
ct
o oo
Y
1 2
00oO0f*Dol/ .V*--. . .-.-.-. ^•.-.•.-.T.-.-. <I 2 V-2 1 2 V-3 0? 8 La*].-?
15-21 15-22
V-4 SHED
3-15 ONE STORY
0 ,<^n STUCCO-HOUSE 15-23
fc W/ATTACHED
MOBILE HOME
RDC) 13-15 15-17
13-15 V-5
15-20
V-1
17-22
0 V-6
16-23
14-17
SCALE IN FEET
20 10 0 20 40
M:\FAS\033\0003\RM00107V 03/08/96 07:59am T50780
NORTH
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT, UTILITY LOCATION PLAT. OR OTHER IMPROVEMENT SURVEY
PLAT ANO IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE, BUILDING, OR OTHER FUTURE IMPROVEMENT LINES.
X
10 I I I
©
<D
Lv.vj
12-15
12
V-1
16-17
(RDC)
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN /xR/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE-RATE RANGE
RADON DECAY-PRODUCT CONCENTRATION
MEASUREMENT LOCATION
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
26
24
22
20
18
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
1 6
RESIDENCE-NO. OF OCCUPANTS
NON-RESIOENCE-UAN-HRS./WK.
INSTRUMENT NO.
VERIFICATION
BY CK. A.E. APP. NO. CK. A.E. APP.
14
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE. COLORADO
3aS
3& 249A SOUTH THIRD EAST ST.
MONTICELLO, UTAH
12
Rust Oeotech
TATE I APPROVAL DOC •BATE-
OOEIDNO. MS-00107-RS
o«c.N0. 3-BQQ1 07-V1 SMT 1 „, 1 10
10 12 14 16 18 20 22 24 26 28 30 32 34 36 38 40
OAK RIDGE NATIONAL LABORATORY PHONE: pro) 24*6200
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION FAX; [phone]
FOR THE UJS. DEPARTMENT OF ENERGY
POST OFFICE BOX 2987
GRAND JUNCTION, COLORADO 81502 jjyg g g T QQg
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by
the U.S. Department of Energy for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program (FUSRAP) and Remote Surplus Facilities Management Program
Sites (SFMP) [Revision 2, March 1987]. This evaluation is based on an independent verifi-
cation review of the Remedial Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment of
the 226Ra concentration in the soil, indoor radon daughter concentration, and indoor gamma
exposure rates at this property.
This property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
Location Number: MSOOT07-RS
Location Address: 249A South Third East Street
Monticello, Utah 84535
Property Owner:

Tenant Name: Same
Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
249A SOUTH TfflRD EAST STREET
MONTICELLO, UTAH (MS00107-RS)
N. F. Kirby
August 1996
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 3
REFERENCES 6
iii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 4
2. Results of ORNL analysis of Geotech soil samples from 249A South Third East
Street, Monticello, Utah (MS00107-RS) 5
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site
Decommissioning Projects, U.S. Department of Energy. The author wishes to
acknowledge M. K. Jensen for analysis of soil samples and A. R. Jones and G. A.
Pierce for technical review.
vii
ABSTRACT
In 1980 the site of a vanadium and uranium mill at Monticello, Utah, was accepted
into the U.S. Department of Energy's (DOE's) Surplus Facilities Management Program,
with the objectives of restoring the government-owned mill site to safe levels of radio-
activity, disposing of or containing the tailings in an environmentally safe manner, and
performing remedial actions on off-site (vicinity) properties that had been contaminated
by radioactive material resulting from mill operations. During 1994, RUST Geotech, the
remedial action contractor designated by DOE, performed remedial action on the vicinity
property at 249A South Third East Street, Monticello, Utah. The Environmental Tech-
nology Section (ETS) of Oak Ridge National Laboratory was assigned the responsibility
of verifying the data supporting the adequacy of remedial action and confirming the site's
compliance with DOE guidelines. The ETS found that the site successfully meets the
DOE remedial action objectives. Procedures used by the ETS are described in the Envi-
ronmental Technology Section Procedures Manual (ORNL 1993).
ix
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 249A SOUTH THIRD EAST STREET
MONTICELLO, UTAH (MS00107-RS)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the U.S. government through the
Defense Plant Corporation to provide vanadium during World War U. Various govern-
ment agencies operated the mill until 1947. In 1948 the Atomic Energy Commission
(AEC) obtained the mill and operated it under contract through 1959 to provide both
uranium and vanadium. Mill operations were terminated on January 1, 1960. In 1961 the
mill tailings piles were leveled and graded, covered with rock and soil, and seeded with na-
tive grasses. During 1974 and 1975, the ore stockpiles were removed from the site, and
the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city
of Monticello, in San Juan County, Utah. The site is bordered on the south and southeast
by land held by the U.S. Bureau of Land Management. Other boundaries are the city of
Monticello and private property.
During the AEC era, the mill processed approximately one million tons of uranium
ore. Vanadium and uranium were the only substances extracted in the milling process.
Other constituents of the ore remained in the tailings and were not separated prior to dis-
posal. During the years of active mill operation, the mill tailings were normally moist, so
erosion was minimal. However, throughout the mill's operating period, area residents
used these tailings as fill material and as aggregate in mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy
(DOE) initiated the Surplus Facilities Management Program (SFMP) in 1978 to ensure
the safe caretaking and decommissioning of government facilities that had been retired
from service but still had radioactive contamination. In 1980 the mill site at Monticello
was accepted into the SFMP, and the Monticello Remedial Action Project (MRAP) was
established to restore the government-owned mill site to safe levels of radioactivity, to
dispose of or contain the tailings in an environmentally safe manner, and to perform reme-
dial actions on off-site (vicinity) properties that had been contaminated by radioactive ma-
terial resulting from mill operations. The Monticello mill site and the tailings remain in the
custody of the DOE Grand Junction, Colorado, Projects Office. In 1983 remedial actions
for vicinity properties were separated from MRAP with establishment of the Monticello
Vicinity Properties (MVP) Project (U.S. DOE 1990b).
*The verification of remedial action was performed by members of the Environmental Assessment Group in the
Environmental Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE
contract DE-AC05-96OR22464 with Lockheed Martin Energy Research Corporation.
2
During 1994, RUST Geotech Inc. (Geotech), the remedial action contractor (RAC)
designated by DOE, performed remedial action on the vicinity property that is the subject
of this report, a single family residence located at 249A South Third East Street, Monti-
cello, Utah. The remedial action plan required excavation of all exterior contamination.
When the excavation was completed, the property was resurveyed, including soil sam-
pling, to ensure the removal of all contamination, backfilled with uncontaminated material,
and restored to a condition comparable to that which existed prior to remedial action
(Geotech 1996).
The DOE adopted a policy to assign an independent contractor to verify the data
supporting the adequacy of remedial action and to confirm the site's compliance with DOE
guidelines. The Environmental Technology Section (ETS) of Oak Ridge National Labor-
atory (ORNL) has been assigned the responsibility of this task at the 249A South Third
East Street site. This report describes the methods and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available doc-
umentation adequately and accurately describes the post-remedial-action radiological
conditions of the entire property that is to be certified and (2) that the remedial action
reduced contamination to below applicable DOE guidelines (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1996) in-
dicates the property was remediated as evaluated by DOE on the basis of Environmental
Protection Agency standards and the DOE guidelines (DOE 1990a). Excess residual
radioactive materials were present, thus it was appropriate to designate this property for
remedial action.
This property was assessed as part of Block MS09028, therefore, the quantity of
material assessed is not available. During the actual removal process, a total of 108 yd3
of contaminated earth and uranium mill tailings, 6 to 12 inches deep, were removed from
a 527 m2 area.
A post-excavation survey was performed by Geotech prior to backfilling the exca-
vated areas. This survey consisted of gamma scans with a scintillometer of the ground
level ofthe structure, a surface scan of the exterior, and soil sampling. Samples repre-
sentative ofthe bottom 15-cm (6-in.) soil layers of six excavated verification areas were
collected and blended to form representative composite soil samples for each verification
area. Verification areas V3 through V6 cross the property boundary on to MS00197.
The samples for these areas include soil from the adjacent property.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation
levels have not been subtracted. Similarly, background concentrations have not been sub-
tracted from radionuclide concentrations in soil samples. Applicable DOE guidelines for
protection against radiation are given in Table 1.
Gamma Measurements
Gamma exposure rate measurements taken by Geotech at the ground-level of the
residence ranged from 13 to 15 uR/h. Exterior surface gamma measurements taken from
the excavated areas prior to backfilling ranged from 15 to 23 uR/h.
Soil Sample Analysis
Prior to backfilling, Geotech collected soil samples representative of the excavated
areas from the bottom 15-cm (6-in.) soil layers. These samples were blended to form a
composite soil sample representative of an average over the six exterior verification areas.
Geotech's analysis of these samples showed ^Ra concentrations to range from 3.6 to 9.2
pCi/g in the composite samples. ORNL ETS obtained a percentage of these soil samples
and performed a confirmatory analysis which showed ^Ra concentrations ranging from
5.0 to 11 pCi/g. These values are below the EPA standard value of 15 pCi/g for soil
layers > 15 cm below the surface. Gamma ranges and/or soil sample results demonstrate
compliance to the DOE Hot Spot Guidelines for areas <25 m2 (Table 1). Results of
Geotech and ORNL soil sample analyses are given in Table 2.
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were deter-
mined by the Alpha-track method. To monitor radon levels, Geotech placed three alpha-
track detectors on the ground floor of the residence located on this property for a period
of approximately one year (from October 10, 1994 to September 27, 1995). The average
annual working level (WL) of radon progeny concentration, as determined by the Tech./-
Ops-Landauer Corporation, was 0.0090, which is well below the 0.03-WL guideline given
in Table 1.
CONCLUSION
Results of Geotech soil sample analysis and confirmatory split soil sample analysis
by ORNL show that radionuclide concentrations are within applicable DOE guidelines.
Based on the results of the post-remedial-action data, which are confirmed by the veri-
fication assessment data, these radiological measurements fall below the limits prescribed
by DOE guidelines. It is concluded that the site successfully meets the DOE remedial
action objectives.
4
Table 1. Applicable guidelines for protection against radiation
Mode of exposure
Radionuclide con-
centrations in soil
Exposure conditions
Maximum permissible con-
centration of 226Ra in soil
above background levels,
averaged over a 100-m2 area
Guideline value
5 pCi/g averaged over the
first 15 cm of soil below the
surface; 15 pCi/g when ave-
raged over 15-cm-thick soil
layers more than 15 cm
below the surface
Ra226 concentrations, in any
surface or subsurface area
less than 25 m2, is below the
guideline by a factor of
(100/Af, where A is the
area of the elevated region
0.03 WL
Radionuclide con-
centrations in soil
for Hot Spot areas
Maximum Permissible con-
centration of Ra226 in soil
above background level, for
areas less than 25 m2
Exposure to 222Rn
progeny
Average annual radon proge-
ny concentration (including
background)
(DOE 1990a)
5
Table 2. Results of ORNL analysis of Geotech soil samples
from 249A South Third East Street, Monticello, Utah (MS00107-RS)
226Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No." No^ (cm)
XI NCB926 >15 7.0 4.4
X3 NAZ456 >15 11 9.2
X5 NAZ458 >15 5.0 4.8
X6 NAZ459 >15 7.7 6.3
" An X-type sample is a split of the sample taken by the remedial action contractor.
b Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated areas
were taken by Geotech, and these samples were blended to form a composite soil
sample, which represents an average over one of the verification areas.
6
REFERENCES
Geotech 1996. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00107-RS, Address: 249A South Third East Street,
Monticello, Utah 84535, Geotech, Grand Junction, Colorado, March 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
U.S. DOE 1990a. Verification and Certification Protocol for the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination
and Decommissioning Program, Revision 3, November 1990. U.S. Department of
Energy, Washington, D.C.
U.S. DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision
and Record of Decision Summary. U.S. Department of Energy, Grand Junction Projects
Office, Grand Junction, Colorado.
DOE ID No.: MS-00117-VL
Property Address: Parcel No. A00170000070, North Creek Lane
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Gfintfirh of Energy (DOE)
YES NO NOT TAKEN YES NO NOT TAKEN
Ra-226 is s 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2. [X]# [ ] [ ] [*] [ ] [ 1
In-situ [X] Lab [ ]
Ra-226 is z 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2. [X]- [ ] [ ] MM [ 1
In-situ [ ] Lab [X]
Interior gamma is £ 20 //R/h
above background in any
occupied or habitable
structure..
The radon decay-product
concentration in any
occupied or habitable
structure is <. 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21.
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987). [X] [ ] [ ] [XI [ ] [ ]
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
[ 1 [X]
(Vacant Lot)
[ 1 [X]
(Vacant Lot)
[XI [ ]
[ ] [ 1 [M
[ ] [ 1
[ 1 ly] I ]
•Milium 11111111111
SFCERTIFED SFMS-00117
DOE ID No.: MS-00117-VL
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
/anda S. Busby ^ Date
Manager, Monticello Programs
Rust Geotech
DOE EVALUATION
[X] Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Date Certification Official
U.S. Department of Energy
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00117-VL
ADDRESS: PARCEL NO. A00170000070
NORTH CREEK LANE
MONTICELLO, UTAH 84535
FEBRUARY 1996
Prepared for
U.S. Department of Energy
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
by
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
Wanda' S. Busby
Manager, Monticello Programs
TABLE OF CONTENTS
Section Ease.
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan . 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
DOE ID No.: MS-00117-VL
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Inclusion Survey Contractor. DOE reviewed
these evaluation results and determined that the property contained mill
tailings (residual radioactive material) exceeding EPA standards The
Remedial Action Contractor was notified of the inclusion of this property
into the MVP Project and was authorized by DOE to conduct remedial
action as required to bring the property into conformance with EPA
standards and DOE hot spot criteria.
1
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
Property Address:
Property Owner:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
DOE ID No.: MS-00117-VL
MS-00117-VL
Lot 7, Mountain West Subdivision, County
of San Juan, City of Monticello, State of
Utah
Parcel No. A00170000070
North Creek Lane
Monticello, Utah 84535

Vacant Lot (VL)
Oak Ridge National Laboratory
November 6, 1992
Rust Geotech
July 22, 1994
Diamond Back Services, Inc.
9861 Titan Park Circle
Littleton, Colorado
May 9, 1995
July 13, 1995
Interior: 0 cubic yards
Exterior: 13 cubic yards
63 square meters (m2)
February 1996
2
DOE ID No.: MS-00117-VL
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of exterior residual radioactive
material (Appendix Figure 2.1). Once excavation was complete, the
affected areas were resurveyed for possible remaining residual radioactive
material and, upon attaining satisfactory results, were backfilled with
uncontaminated material. The property was restored to a physical
condition comparable to that which existed prior to remedial action
activities.
2.2 Previously Unidentified Contamination
The radiological assessment identified 15 cubic yards of contamination,
6 inches deep, within the property. The remedial action process included
the removal of approximately 13 cubic yards of residual radioactive
material, 6 inches deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
3.0 VERIFICATION SUMMARY
DOE ID No.: MS-00117-VL
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by the Remedial Action
Contractor during August 1993, as described in the final REA
dated July 1994. Appendix Figure 2.1 shows the extent of
assessed contamination and identifies the areas recommended to
undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the excavation were
collected. These samples were blended to form a composite
sample representing the verification area (Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 13 to 21 microroentgens per
hour (jjR/h), as indicated on Appendix Figure 2.1. The result of
analysis for radium-226 in one composite soil sample was
3.1 picocuries per gram (pCi/g), as indicated in Appendix
Table 3.1.
4
DOE ID No.: MS-00117-VL
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at Parcel No. A00170000070, North
Creek Lane, in Monticello, Utah, is recommended for certification as
required by DOE guidelines, and the appropriate records should be
documented.
Certification Data Summary
Applicability
Hahitahla Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Standards
Shall not exceed 20 //R/h
above background.
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Survey Results
Not applicable: vacant
lot.
Not applicable: vacant
lot.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background* in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background* in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
< 5 pCi/g above
background.
Soil sample result was Dil sample
.1 pCi/g.f
*The background radium-226 concentration is approximately 2.0 pCi/g.
The hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-00117-VL
4.0 APPENDIX
Appendix Table:
Table 3.1 Post-Excavation Sample/Measurement Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
MRW: 10-02-95
MS-00117.VL WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00117-VL
Address: Parcel No. A00170000070, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range ipR/h) Ticket No. Method" (pCi/g)
V-1 15-21 NCJ 017 OCS 3.1
See Appendix Figure 2.1 for the verification area.
"OCS = Opposed Crystal System
7
10
30
1 2 1 4 1 6 18 20 22 24 26 28 30 32 34 36 38 40
30
28 28
26
24
22 —
20
18
LLI
<
Ld
LU or o
o
r -X-13-15
13-15
V-1
15-21
-X-13-15 13-15
J I
®
rv.-??i
Lv.vj
12-15
12
V-1
16-17
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN fiR/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE-RATE RANGE
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
OAK RIDGE NATIONAL LABORATORY DATA
26
24
22
20
- 18
1 6
1 4
12
Y
1 0
1 0
SCALE IN FEET
20 10 0 20 40
C:\ACAD12C3\DWG-2\RM00117V 10/03/95 1:16pm T50780
1 2 1 4 1 6 1 8
NORTH
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT, UTILITY LOCATION PLAT. OR OTHER IMPROVEMENT SURVEY
PLAT AND IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE, BUILDING. OR OTHER FUTURE IMPROVEMENT LINES.
20 22 24 26 28
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
RESIOENCE-NO. OF OCCUPANTS
NON - RESIDENCE—MAN-HRS./WK.
INSTRUMENT NO.
VERIFICATION
sis:
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE, COLORADO
I. ENGR.
fO-
PARCEL NO. A00170000070
NORTH CREEK LANE
MONTICELLO, UTAH
Rust Qeotech
A WMX T«*Mtapn ConOTv
APPROVAL DOE OATE
OOEIDNO. MS-001 1 7-VL
D.O.NO 3-B0O1 17-V1 SSL.
16
14
12
10
30 32 34 36 38 40
OAK RIDGE NATIONAL LABORATORY PHONE. [phone]
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION FAX: [phone]
FOR THE U.S. DEPARTMENT OF ENERGY
POST OFFICE BOX 2567 «... „
GRAND JUNCTION, COLORADO 81502 Wflf J J
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by the
U.S. Department of Energy for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program (FUSRAP) and Remote Surplus Facilities Management Program
Sites (SFMP) [Revision 2, March 1987]. This evaluation is based on an independent
verification review of the Remedial Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment of
the 226Ra concentration in the soil at this property.
Therefore, this property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/F/C Project Manager
Environmental Assessment Group
Location Number: MS00117-VL
Location Address: A00170000070 - North Creek T^ne
Monticello. Utah 84535
Property Owner:

Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
PARCEL NO. A00170000070 - NORTH CREEK LANE
MONTICELLO, UTAH (MS00T17-VL)
M. K. Jensen
May 1996
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
CONCLUSION 3
REFERENCES 6
iii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 4
2. Results of ORNL analysis of Geotech soil samples from Parcel No. A00170000070 -
North Creek Lane, Monticello, Utah (MS00117-VL) 5
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site
Decommissioning Projects, U.S. Department of Energy. The author wishes to
acknowledge M. J. Wilson-Nichols and A. R. Jones for technical reviews.
vii
ABSTRACT
In 1980 the site of a vanadium and uranium mill at Monticello, Utah, was accepted
into the U.S. Department of Energy's (DOE's) Surplus Facilities Management Program,
with the objectives of restoring the government-owned mill site to safe levels of radio-
activity, disposing of or containing the tailings in an environmentally safe manner, and
performing remedial actions on off-site (vicinity) properties that had been contaminated
by radioactive material resulting from mill operations. During 1995, RUST Geotech, the
remedial action contractor designated by DOE, performed remedial action on the vicinity
property at Parcel No. A00170000070 - North Creek Lane, Monticello, Utah. The Envi-
ronmental Technology Section (ETS) of Oak Ridge National Laboratory was assigned the
responsibility of verifying the data supporting the adequacy of remedial action and con-
firming the site's compliance with DOE guidelines. The ETS found that the site success-
fully meets the DOE remedial action objectives. Procedures used by the ETS are
described in the Environmental Technology Section Procedures Manual (ORNL 1993).
ix
RESULTS OF THE INDEPENDENT VERD7ICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
PARCEL NO. A00170000070 - NORTH CREEK LANE
MONTICELLO, UTAH (MS00117-VL)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the U.S. government through the
Defense Plant Corporation to provide vanadium during World War U. Various
government agencies operated the mill until 1947. In 1948 the Atomic Energy
Commission (AEC) obtained the mill and operated it under contract through 1959 to
provide both uranium and vanadium. Mill operations were terminated on January 1, 1960.
In 1961 the mill tailings piles were leveled and graded, covered with rock and soil, and
seeded with native grasses. During 1974 and 1975, the ore stockpiles were removed from
the site, and the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city
of Monticello, in San Juan County, Utah. The site is bordered on the south and southeast
by land held by the U.S. Bureau of Land Management. Other boundaries are the city of
Monticello and private property.
During the AEC era, the mill processed approximately one million tons of uranium
ore. Vanadium and uranium were the only substances extracted in the milling process.
Other constituents of the ore remained in the tailings and were not separated prior to
disposal. During the years of active mill operation, the mill tailings were normally moist,
so erosion was minimal. However, throughout the mill's operating period, area residents
used these tailings as fill material and as aggregate in mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy
(DOE) initiated the Surplus Facilities Management Program (SFMP) in 1978 to ensure the
safe caretaking and decommissioning of government facilities that had been retired from
service but still had radioactive contamination. In 1980 the mill site at Monticello was
accepted into the SFMP, and the Monticello Remedial Action Project (MRAP) was
established to restore the government-owned mill site to safe levels of radioactivity, to
dispose of or contain the tailings in an environmentally safe manner, and to perform
remedial actions on off-site (vicinity) properties that had been contaniinated by radioactive
material resulting from mill operations. The Monticello mill site and the tailings remain in
the custody of the DOE Grand Junction, Colorado, Projects Office. In 1983 remedial
actions for vicinity properties were separated from MRAP with establishment of the
Monticello Vicinity Properties (MVP) Project (U.S. DOE 1990b).
*The verification of remedial action was performed by members of the Environmental Assessment Group in the
Environmental Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE
contract DE-AC05-96OR22464 with Lockheed Martin Energy Research Corporation.
2
During 1995, RUST Geotech Inc. (Geotech), the remedial action contractor (RAC)
designated by DOE, performed remedial action on the vicinity property that is the subject
of this report, a vacant lot located at Parcel No. A00170000070 - North Creek Lane,
Monticello, Utah. The remedial action plan required excavation of all exterior contamina-
tion. When the excavation was completed, the property was resurveyed, including soil
sampling, to ensure the removal of all contamination, backfilled with uncontaminated
material, and restored to a condition comparable to that which existed prior to remedial
action (Geotech 1996).
The DOE adopted a policy to assign an independent contractor to verify the data
supporting the adequacy of remedial action and to confirm the site's compliance with
DOE guidelines. The Environmental Technology Section (ETS) of Oak Ridge National
Laboratory (ORNL) has been assigned the responsibility of this task at the Parcel No.
A00170000070 - North Creek Lane site. This report describes the methods and results
of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available
documentation adequately and accurately describes the post-remedial-action radiological
conditions of the entire property that is to be certified and (2) that the remedial action
reduced contarnination to below applicable DOE guidelines (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1996)
indicates the property was remediated as evaluated by DOE on the basis of Environmental
Protection Agency standards and the DOE guidelines (DOE 1990a). Excess residual
radioactive materials were present, thus it was appropriate to designate this property for
remedial action.
The pre-remedial-action survey performed by Geotech identified 15 yd3 of mill tailings
6 inches deep. During the actual removal process, a total of 13 yd3 of contaminated earth
and uranium mill tailings, 6 inches deep, were removed from a 63 m2 area.
A post-excavation survey was performed by Geotech prior to backfilling the exca-
vated areas. This survey consisted of gamma scans with a scintillometer of the exterior
and soil sampling. Samples representative of the bottom 15-cm (6-in.) soil layers of one
excavated verification area were collected and blended to form a representative composite
soil sample.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation
levels have not been subtracted. Similarly, background concentrations have not been sub-
tracted irom radionuclide concentrations in soil samples. Applicable DOE guidelines for
protection against radiation are given in Table 1.
Gamma Measurements
Exterior surface gamma exposure rate measurements taken by Geotech from the
excavated areas prior to backfilling ranged from 15 to 21 uR/h.
Soil Sample Analysis
Prior to backfilling, Geotech collected soil samples representative of the excavated
areas from the bottom 15-cm (6-in.) soil layers. These samples were blended to form a
composite soil sample representative of an average over the exterior verification area.
Geotech's analysis of this sample showed a ^Ra concentration of 3.1 pCi/g. ORNL ETS
obtained this sample and performed a confirmatory analysis which showed a 226Ra con-
centration of 1.6 pCi/g. These values are below the EPA standard value of 15 pCi/g for
soil layers > 15 cm below the surface. Gamma ranges and/or soil sample results demon-
strate compliance to the DOE Hot Spot Guidelines for areas <25 m2 (Table 1). Results of
Geotech and ORNL soil sample analyses are given in Table 2.
CONCLUSION
Results of Geotech soil sample analysis and confirmatory split soil sample analysis
by ORNL show that radionuclide concentrations are within applicable DOE guidelines.
Based on the results of the post-remedial-action data, which are confirmed by the verifica-
tion assessment data, these radiological measurements fall below the limits prescribed by
DOE guidelines. It is concluded that the site successfully meets the DOE remedial action
objectives.
4
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of 226Ra in soil
above background levels,
averaged over a 100-m2 area
5 pCi/g averaged over the
first 15 cm of soil below the
surface; 15 pCi/g when ave-
raged over 15-cm-thick soil
layers more than 15 cm
below the surface
Radionuclide
concentrations in soil
for Hot Spot areas
Maximum Permissible
concentration of Ra226 in soil
above background level, for
areas less than 25 m2
Ra226 concentrations, in any
surface or subsurface area
less than 25 m2, is below the
guideline by a factor of
(100/A)'7\ where A is the
area of the elevated region
Exposure to 222Rn Average annual radon proge- 0.03 WL
progeny ny concentration (including
background)
(DOE 1990a)
5
Table 2. Results of ORNL analysis of Geotech soil samples
from Parcel No. A00170000070, MonticeUo Utah (MS00117-VL)
22CRa concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No." No^ (cm)
XI NCJ 017 >15 1.6 3.1
" An X-type sample is a split of the sample taken by the remedial action contractor.
* Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated areas
were taken by Geotech, and these samples were blended to form a composite soil
sample, which represents an average over one of the verification areas.
6
REFERENCES
Geotech 1996. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00117-VL, Address: Parcel No. A00170000070, North Creek
Lane, Monticello, Utah 84535, Geotech, Grand Junction, Colorado, February 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
U.S. DOE 1990a. Verification and Certification Protocol for the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination
and Decommissioning Program, Revision 3, November 1990. U.S. Department of
Energy, Washington, D.C.
U.S. DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision
and Record of Decision Summary. U.S. Department of Energy, Grand Junction Projects
Office, Grand Junction, Colorado.
DOE ID No.: MS-00125-MR
Property Address: 401 Silverstone West Lane
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech of Energy (PQE)
Ra-226 is < 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [ ]
Ra-226 is < 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2.
In-situ [X] Lab [ ]
Interior gamma is < 20 //R/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is < 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21.
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
[X] [ ] [ 1
[>] [ ] [ ]
[y] [ ] [ ]
MM [ ]
[ ] W [ 1
[;] [ ] I ]
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
iiiiiiiiiii mm
SFCERTIFED SFMS-00125
I T
DOE ID No.: MS-00125-MR
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
/anda S.Jfusby '
Manager, Monticello Programs
Rust Geotech
Date
DOE EVALUATION
Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
CemiwtrorfdfficSl ?gQcfr P
Date
U.S. Department of Energy
PROPERTY COMPLETION REPORT
DOE ID NO.: MS-00125-MR
ADDRESS: 401 SILVERSTONE WEST LANE
MONTICELLO, UTAH 84535
MAY 1996
Prepared for
U.S. Department of Energy
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
by
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.1.3 Radon Decay-Product Concentration (RDC) Measurement .... 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
i
DOE ID No.: MS-00125-MR
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Inclusion Survey Contractor. DOE reviewed
these evaluation results and determined that the property contained mill
tailings (residual radioactive material) exceeding EPA standards. The
Remedial Action Contractor was notified of the inclusion of this property
into the MVP Project and was authorized by DOE to conduct remedial
action as required to bring the property into conformance with EPA
standards and DOE hot spot criteria.
1
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
Property Address:
Property Owners:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
DOE ID No.: MS-00125-MR
MS-00125-MR
Lot 17, Silverstone West Subdivision; and
beginning at the SW corner of said Lot 17,
east 94.6 feet to SE corner of said Lot 17,
south 20 feet, west 94.6 feet, north
20 feet to beginning, City of Monticello,
County of San Juan, State of Utah
401 Silverstone West Lane
Monticello, Utah 84535

Major Residential (MR)
Oak Ridge National Laboratory
November 6, 1992
Rust Geotech
November 29, 1994
Diamond Back Services, Inc.
9861 Titan Park Circle
Littleton, Colorado
June 22, 1995
August 2, 1995
Interior: 14 cubic yards
Exterior: 1 cubic yard
107 square meters (m2)
May 1996
2
DOE ID No.: MS-00125-MR
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of interior and exterior residual
radioactive material (Appendix Figure 2.1). Once excavation and removal
were complete, the affected areas were resurveyed for possible remaining
residual radioactive material and, upon attaining satisfactory results, were
backfilled or reconstructed with uncontaminated material. The property
was restored to a physical condition comparable to that which existed
prior to remedial action activities.
2.2 Previously Unidentified Contamination
The radiological assessment identified 14 cubic yards of contamination, up
to 150 inches high, within the property. The remedial action process
included the removal of approximately 15 cubic yards of residual
radioactive material, ranging from 16 inches deep to 150 inches high. .
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID No.: MS-00125-MR
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by the Remedial Action
Contractor during July 1993, as described in the final REA dated
November 1994. Appendix Figure 2.1 shows the extent of
assessed contamination and identifies the areas recommended to
undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to
reconstruction or backfilling. Following the gamma scan, an in-situ
measurement representative of the 6-inch-thick layer at the bottom
of the exterior excavation was collected (Appendix Figure 2.1).
Interior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 13 to 16 microroentgens per
hour (//R/h) for the remediated portion of the basement, 15 to
16 //R/h for the rest of the basement, 13 to 16 //R/h for the north
and east exterior walls after removal and replacement of the brick
veneer and mortar, 15 to 16 //R/h for the remainder of the ground
floor, and 14 to 16 //R/h for the attached garage (Appendix
Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 13 to 18//R/h (Appendix
Figure 2.1). The result of analysis for radium-226 in one in-situ
measurement was 1.4 picocuries per gram (pCi/g), as indicated in
Appendix Table 3.1.
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on the DOE-approved abbreviated-measurement method,
the RDC was 0.0172 working level (WL), as indicated in Appendix
Table 3.2. Appendix Figure 2.1 shows the measurement location
in the basement (the lowest habitable level of the structure).
4
DOE ID No.: MS-00125-MR
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at 401 Silverstone West Lane, in
Monticello, Utah, is recommended for certification as required by DOE
guidelines, and the appropriate records should be documented.
Certification Data Summary
Applicability
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Standards
Shall not exceed 20 //R/h
above background.*
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Survey Results
Ranges were 13 to
16 //R/h for the
remediated portion and
15 to 16 //R/h for the
remainder of the
basement, 13 to 16 //R/h
for the remediated
portion and 15 to
16 //R/h for the remainder
of the ground floor, and
14 to 16//R/h for the
remainder of the attached
garage.
Average was 0.0172 WL,
based on the DOE-
approved abbreviated-
measurement method.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
< 5 pCi/g above
background.**
In-situ measurement
result was 1.4 pCi/g.**
*The background exposure rate is approximately 13 //R/h.
The background radium-226 concentration is approximately 2.0 pCi/g.
**The hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-00125-MR
4.0 APPENDIX
Appendix Tables:
Table 3.1 Post-Excavation Sample/Measurement Results
Table 3.2 Radon Decay-Product Concentration Measurement Results
Appendix Figure:
Figure 2.1 Interior and Exterior Extent of Contamination -
RADIOLOGICAL AS-BUILT
JEK:03-05-96
MS-00125.MR WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00125-MR
Address: 401 Silverstone West Lane, Monticello, Utah
Exposure-Rate Meas. Meas. Radium-226
Area Range U/R/h) Grid Coord. Method" (pCi/g)
EXTERIOR
V-3 16- 18 214278 DS 1.4
INTERIOR
V-1 13-15 Not applicable
V-2 13-16 Not applicable
V-4 13-16 Not applicable
See Appendix Figure 2.1 for the verification areas.
"DS = Delta Scanner
7
Table 3.2
Radon Decay-Product Concentration Measurement Results
DOE ID No.: MS-00125-MR
Address: 401 Silverstone West Lane, Monticello, Utah
Instrument Type: Landauer Radtrak Detector
Radon
Detector Concentration Working
Number Start Date End Date (pCi/L) Level
3973942 07-25-95 11-15-95 3.22 0.0161
3973997 07-25-95 11-15-95 3.31 0.0166
3973982 07-25-95 11-15-95 3.78 0.0189
Average: 0.0172
See Appendix Figure 2.1 for the measurement location.
8
42
40
38
36
34
32
30
28
26
24
22
20
18
16
14
12
10
12
T"
1 4 16 1 8 20 22 24 26 28 30 32 36 38 40 44
T
46 48
~T~
5C
GARAGE ON
GROUND LEVEL
SHED
13-15 13-16
ONE STORY
FRAME & BRICK
HOUSE WITH
BASEMENT
13-16
SEE DETAILS
A AND B v-3
16-18
[60]
13-15
13-16
13-16
15-16
BASEMENT
ROC
DETAIL A
NOT TO SCALE
[96] V-4
13-16
V- 1
13-15 [108
1
GARAGE
14-16
-<£)
GROUND FLOOR
15-16
v-2
13-16
-[150]
DETAIL B
NOT TO SCALE
L
SCALE IN FEET
20 10 0 20 40
U:\FAS\OJJ\OOOJ\RUOOI25V 09/01/99 11:53om TS07B0
NORTH
©
r?.v7i
Lv.vj
12-15
12
v-i
16-17
[12]
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN fiR/h
ASSESSED AREA IDENTIFIER
AREA OF ASSESSED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION AREA IDENTIFIER AND
EXCAVATION EXPOSURE-RATE RANGE
RAOON DECAY-PRODUCT CONCENTRATION
MEASUREMENT LOCATION
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
HEIGHT IN INCHES OF ASSESSED
CONTAMINATED LIGHT POST (ASSESSED
AREA A), BRICK VENEER (ASSESSED
AREA C), STUCCO (ASSESSED AREA D),
AND FLAGSTONE HEARTH AND FIREWALL
(ASSESSED AREA E) REMOVED AND REPLACED
HEIGHT OF ASSESSED AREA D IS SHOWN ON
DETAIL B WITH ASSESSED AREA C
RADIOLOGICAL AS-BUILT
FIGURE 2.1
INTERIOR AND EXTERIOR EXTENT OF CONTAMINATION
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT, UTILITY LOCATION PLAT, OR OTHER IMPROVEMENT SURVEY
PLAT AND IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE, BUILDING. OR OTHER FUTURE IMPROVEMENT LINES.
J L
Mtiotwc-no. o# oceuMxri
*fjwrc-iim
m
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJCCTS OfFlCC, COLORADO
401 SILVERSTONE WEST LANE
MONTICELLO, UTAH
RUST Rust OMtech MS-00125-MR
12 14 16 18 20 22 24 26 28 30 32 34 36 38 40 42 44 46 48 5i
OAK RIDGE NATIONAL LABORATORY
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
FOR THE U.S. DEPARTMENT OF ENERGY
PHONE: [phone]
FAX: [phone]
POST OFFICE BOX 2567
GRAND JUNCTION, COLORADO 81502
SEP 2 0 1996
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by the U.S.
Department of Energy for Residual Radioactive Material at Formerly Utilized Sites Remedial Action
Program (FUSRAP) and Remote Surplus Facilities Management Program Sites (SFMP) [Revision
2, March 1987]. This evaluation is based on an independent verification review of the Remedial
Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment of the 226Ra
concentration in the soil, indoor radon daughter concentration, and indoor gamma exposure rates at
this property.
This property is recommended for certification by the U.S. Department of Energy.
Sincerely,
MVP/IVC Project Manager
Environmental Assessment Group
Location Number:
Location Address:
MS00125-MR
401 Silverstone West Lane
Monticello. Utah 84535
Property Owner:
Owner Address:

Tenant Name: Same
Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
401 SILVERSTONE WEST LANE
MONTICELLO, UTAH (MS00125-MR)
M. J. Wilson-Nichols
September 1996
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 3
REFERENCES :. . 5
iii
LIST OF TABLES
Applicable guidelines for protection against radiation
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site Decommis-
sioning Projects, U.S. Department of Energy. The author wishes to acknowledge M. K.
Jensen and A. R. Jones for technical reviews.
vii
ABSTRACT
In 1980 the site of a vanadium and uranium mill at Monticello, Utah, was accepted into
the U.S. Department of Energy's (DOE's) Surplus Facilities Management Program, with the
objectives of restoring the government-owned mill site to safe levels of radioactivity,
disposing of or containing the tailings in an environmentally safe manner, and performing re-
medial actions on off-site (vicinity) properties that had been contaminated by radioactive
material resulting from mill operations. During 1995, RUST Geotech, the remedial action
contractor designated by DOE, performed remedial action on the vicinity property at 401
Silverstone West Lane, Monticello, Utah. The Environmental Technology Section (ETS) of
Oak Ridge National Laboratory was assigned the responsibility of verifying the data support-
ing the adequacy of remedial action and confirming the site's compliance with DOE guide-
lines. The ETS found that the site successfully meets the DOE remedial action objectives.
Procedures used by the ETS are described in the Environmental Technology Section Proce-
dures Manual (ORNL 1993).
ix
1
RESULTS OF THE INDEPENDENT VERD7ICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 401 SILVERSTONE WEST LANE
MONTICELLO, UTAH (MS00125-MR)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the U.S. government through the
Defense Plant Corporation to provide vanadium during World War II. Various government
agencies operated the mill until 1947. In 1948 the Atomic Energy Commission (AEC) ob-
tained the mill and operated it under contract through 1959 to provide both uranium and
vanadium. Mill operations were terminated on January 1, 1960. In 1961 the mill tailings piles
were leveled and graded, covered with rock and soil, and seeded with native grasses. During
1974 and 1975, the ore stockpiles were removed from the site, and the mill foundations were
buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city of
Monticello, in San Juan County, Utah. The site is bordered on the south and southeast by
land held by the U.S. Bureau of Land Management. Other boundaries are the city of
Monticello and private property.
During the AEC era, the mill processed approximately one million tons of uranium ore.
Vanadium and uranium were the only substances extracted in the milling process. Other con-
stituents of the ore remained in the tailings and were not separated prior to disposal. During
the years of active mill operation, the mill tailings were normally moist, so erosion was
minimal. However, throughout the mill's operating period, area residents used these tailings
as fill material and as aggregate in mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy (DOE)
initiated the Surplus Facilities Management Program (SFMP) in 1978 to ensure the safe
caretaking and decommissioning of government facilities that had been retired from service
but still had radioactive contamination. In 1980 the mill site at Monticello was accepted into
the SFMP, and the Monticello Remedial Action Project (MRAP) was established to restore
the government-owned mill site to safe levels of radioactivity, to dispose of or contain the
tailings in an environmentally safe manner, and to perform remedial actions on off-site
(vicinity) properties that had been contaminated by radioactive material resulting from mill
operations. The Monticello mill site and the tailings remain in the custody of the DOE Grand
Junction, Colorado, Projects Office. In 1983 remedial actions for vicinity properties were
separated from MRAP with establishment of the Monticello Vicinity Properties (MVP)
Project (U.S. DOE 1990b).
*The verification of remedial action was performed by members ofthe Environmental Assessment Group in the
Environmental Technology Section ofthe Health Sciences Research Division at Oak Ridge National Laboratory under DOE contract
DE-AC05-96OR22464 with Lockheed Martin Energy Research Corporation.
2
During 1995, RUST Geotech Inc. (Geotech), the remedial action contractor (RAC)
designated by DOE, performed remedial action on the vicinity property that is the subject of
this report, a single family residence located at 401 Silverstone West Lane, Monticello, Utah.
The remedial action plan required excavation of all exterior and interior contamination. When
the excavation was completed, the property was resurveyed to ensure the removal of all
contamination, reconstructed with uncontaminated material, and restored to a condition
comparable to that which existed prior to remedial action (Geotech 1996).
The DOE adopted a policy to assign an independent contractor to verify the data sup-
porting the adequacy of remedial action and to confirm the site's compliance with DOE guide-
lines. The Environmental Technology Section (ETS) of Oak Ridge National Laboratory
(ORNL) has been assigned the responsibility of this task at the 401 Silverstone West Lane
site. This report describes the methods and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available documenta-
tion adequately and accurately describes the post-remedial-action radiological conditions of
the entire property that is to be certified and (2) that the remedial action reduced contamina-
tion to below applicable DOE guidelines (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1996) indicates
the property was remediated as evaluated by DOE on the basis of Environmental Protection
Agency standards and the DOE guidelines (DOE 1990a). Excess residual radioactive materi-
als were present, thus it was appropriate to designate this property for remedial action.
The pre-remedial-action survey performed by Geotech identified 14 yd3 of building
materials contaminated with mill tailings and measuring up to 150 inches high. During the
actual removal process, a total of 15 yd3 of contaminated materials 16 inches deep to 150
inches high were removed from a 107 m2 area.
A post-excavation survey was performed by Geotech prior to reconstructing the exca-
vated areas. This survey consisted of gamma scans with a scintillometer of the basement
and ground level of the structure, a surface scan of the exterior, and in-situ delta
scintillometer measurements.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation
levels have not been subtracted. Applicable DOE guidelines for protection against radiation
are given in Table 1.
Gamma Measurements
Gamma exposure rate measurements taken by Geotech from the interior excavated areas
prior to reconstruction ranged from 13 to 15 uR/h in area VI and 13 to 16 uR/h in areas V2
and V4. The remainder of the basement had gamma exposure rates of 15 to 16 uR/h in the
basement and 14 to 16 at the ground-level of the residence. Exterior surface gamma
measurements taken from the excavated areas prior to reconstruction ranged from 16 to 18
uR/h.
Soil Sample Analysis
No soil samples were collected during verification of this property because remedial
action consisted primarily of demolition and removal of brick and decorative rock. V3, an
outdoor area, consisted of a contaminated base to a lamp post, and therefore, a soil sample
could not be collected. In-situ measurements were taken with a delta scintillometer to esti-
mate the 226Ra concentration at V3. The concentration was estimated to be 1.4 pCi/g. This
value is below the EPA standard value of 15 pCi/g for soil layers >15 pCi/g below the sur-
face. Gamma ranges and/or soil sample results demonstrate compliance to the DOE Hot Spot
Guidelines for areas <25 m2 (Table 1).
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were determined
by the Alpha-track method. To monitor radon levels, Geotech placed three alpha-track detec-
tors on the ground floor of the residence located on this property for a period of approxi-
mately three months (from July 25, 1995 to November 15, 1995). The average annual
working level (WL) of radon progeny concentration, as determined by the Tech./Ops-
Landauer Corporation, was 0.0172, which is below the 0.03-WL guideline given in Table 1.
CONCLUSION
Based on the results of the post-remedial-action data, which are confirmed by the
verification assessment data, these radiological measurements fall below the limits prescribed
by DOE guidelines. It is concluded that the site successfully meets the DOE remedial action
objectives.
4
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of 226Ra in soil
above background levels,
averaged over a 100-m2 area
5 pCi/g averaged over the
first 15 cm of soil below the
surface; 15 pCi/g when ave-
raged over 15-cm-thick soil
layers more than 15 cm
below the surface
Radionuclide con-
centrations in soil
for Hot Spot areas
Exposure to 222Rn
progeny
Maximum Permissible con-
centration of Ra226 in soil
above background level, for
areas less than 25 nr
Average annual radon proge-
ny concentration (including
background)
Ra226 concentrations, in any
surface or subsurface area
less than 25 nr, is below the
guideline by a factor of
(100/A)'/2, where A is the
area of the elevated region
0.03 WL
(DOE 1990a)
5
REFERENCES
Geotech 1996. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MSOOJ 25-MR, Address: 401 Silverstone West Lane, Monticello,
Utah 84535, Geotech, Grand Junction, Colorado, May 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment Group)
Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National Laboratory,
Grand Junction, Colorado.
U.S. DOE 1990a. Verification and Certification Protocol for the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination and
Decommissioning Program, Revision 3, November 1990. U.S. Department of Energy,
Washington, D.C.
U.S. DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision and
Record of Decision Summary. U.S. Department of Energy, Grand Junction Projects Office,
Grand Junction, Colorado.
DOE ID No.: MS-00127-MR
Property Address: 549 Circle Drive
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech of Energy (DOE)
YES NO NOT TAKEN YES NO NOT TAKEN
Ra-226 is < 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2. [X]* [ ] [ ] Ml] I ]
In-situ [X] Lab [ ]
Ra-226 is <; 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2. [X]
In-situ [ ] Lab [X]
Interior gamma is s 20 //R/h
above background in any
occupied or habitable
structure. [X]
The radon decay-product
concentration in any
occupied or habitable
structure is < 0.02
working level or, at
most, 0.03 working level. [X]
[ ] [ ] M I ] I 1
[ ] [ ] [Xl [ ] [ 1
[ ] [ ] [*] U [ 1
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21. [ ] [X] [ ] [ ] [Y] [ ]
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987). [X] [ ] [ ] Ml] ll
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
Ililllllllll llllllllll
SFCERTIFED SFMS-00127
DOE ID No.: MS-00127-MR
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
2&
Wandi
/anda S. Btfsby 7 Date
Manager, Monticello Programs
Rust Geotech
DOE EVALUATION
[x~] Should be certified by the U.S. Department of Energy
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
/3
Certification Official
U.S. Department of Energy
Date
PROPERTY COMPLETION REPORT
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
DOE ID NO.: MS-00127-MR
ADDRESS: 549 CIRCLE DRIVE
MONTICELLO, UTAH 84535
MARCH 1996
Prepared for
U.S. Department of Energy
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
f Wan* 5. Busby
Manager, Monticello Programs
FOR
FOR
by
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.1.3 Radon Decay-Product Concentration (RDC) Measurement .... 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
DOE ID No.: MS-00127-MR
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Inclusion Survey Contractor. DOE reviewed these
evaluation results and determined that the property contained mill tailings
(residual radioactive material) exceeding EPA standards. The Remedial
Action Contractor was notified of the inclusion of this property into the
MVP Project and was authorized by DOE to conduct remedial action as
required to bring the property into conformance with EPA standards and
DOE hot spot criteria.
1
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
Property Address:
Property Owners:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
DOE ID No.: MS-00127-MR
MS-00127-MR
Location No. M-313; Lot 15, Upper
Townsite Subdivision, City of Monticello,
County of San Juan, State of Utah
549 Circle Drive
Monticello, Utah 84535

Major Residential (MR)
Oak Ridge National Laboratory
November 6, 1992
Rust Geotech
September 9, 1994
Diamond Back Services, Inc.
9861 Titan Park Circle
Littleton, Colorado
May 22, 1995
July 13, 1995
Interior: 0 cubic yards
Exterior: 7 cubic yards
37 square meters (m2)
March 1996
2
2.0 OPERATIONS SUMMARY
DOE ID No.: MS-00T27-MR
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of exterior residual radioactive
material (Appendix Figure 2.1). Interior assessed Areas D (concrete stove
base) and E (cinder block chimney) were excluded from remedial action
based on averaged gamma exposure rates and pre-remedial radon decay-
product concentration measurements that did not exceed EPA standards,
as discussed in the REA. Once excavation was complete, the affected
areas were resurveyed for possible remaining residual radioactive material
and, upon attaining satisfactory results, were backfilled with
uncontaminated material. The property was restored to a physical
condition comparable to that which existed prior to remedial action
activities.
2.2 Previously Unidentified Contamination
The radiological assessment (excluding assessed Areas D and E) identified
contamination, 6 inches deep, within the property. The quantity of
contamination for this property was not specified because it was assessed
as part of Group 3. The remedial action process included the removal of
approximately 7 cubic yards of residual radioactive material, 6 inches
deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID No.: MS-00127-MR
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by the Remedial Action
Contractor during July 1993, as described in the final REA dated
September 1994. Appendix Figure 2.1 shows the extent of
assessed contamination and identifies the areas recommended to
undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the excavation were
collected. These samples were blended to form a composite
sample representing the verification area (Appendix Figure 2.1).
Interior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 11 to 51 microroentgens per
hour (//R/h) for the basement. Elevated exposure rates in excluded
assessed Area D were associated with residual radioactive material
in the concrete stove base. The room-sized area average of the
elevated exposure rates was 17 //R/h.
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 13 to 23 //R/h (Appendix
Figure 2.1). The result of analysis for radium-226 in one
composite soil sample was 4.5 picocuries per gram (pCi/g), as
indicated in Appendix Table 3.1.
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on the DOE-approved abbreviated-measurement method, the
RDC was 0.0100 working level (WL), as indicated in
Appendix Table 3.2. Appendix Figure 2.1 shows the measurement
location in the basement (the lowest habitable level of the
structure). RDC measurements were taken before remediation of
the property.
4
DOE ID No.: MS-00127-MR
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at 549 Circle Drive, in Monticello, Utah,
is recommended for certification as required by DOE guidelines, and the
appropriate records should be documented.
Certification Data Summary
Applicability
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Standards
Shall not exceed 20 //R/h
above background.*
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Survey Results
Range for the basement
was 11 to 51 //R/h. The
room-sized area average
of the elevated exposure
rates was 17 //R/h.
Average was 0.0100 WL,
based on the DOE-
approved abbreviated-
measurement method.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background1 in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
< 5 pCi/g above
background.**
Soil sample result was
4.5 pCi/g.**
*The background exposure rate is approximately 13//R/h.
The background radium-226 concentration is approximately 2.0 pCi/g.
**The hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No,: MS-00127-MR
4.0 APPENDIX
Appendix Tables:
Table 3.1 Post-Excavation Sample/Measurement Results
Table 3.2 Radon Decay-Product Concentration Measurement
Results
Appendix Figure:
Figure 2.1 Interior and Exterior Extent of Contamination -
RADIOLOGICAL AS-BUILT
SJW:09-06-95
MS-00127.MR WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00127-MR
Address: 549 Circle Drive, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (//R/h) Ticket No. Method3 (pCi/g)
V-1 15-23 NCJ 023 OCS 4.5
See Appendix Figure 2.1 for the verification area.
aOCS = Opposed Crystal System
7
Table 3.2
Radon Decay-Product Concentration Measurement Results
DOE ID No.: MS-00127-MR
Address: 549 Circle Drive, Monticello, Utah
Instrument Type: Landauer Radtrak Detector
Radon
Detector Tracks Per Concentration Working
Number Start Date End Date mm2 (pCi/L) Level
3973879 03-08-95 06-07-95
3973833 03-08-95 06-07-95
3974070 03-08-95 06-07-95
5.8 2.28 0.0114
4.8 1.88 0.0094
4.6 1.82 0.0091
Average: 0.0100
See Appendix Figure 2.1 for the measurement location.
8
42
40
38
36
34
32
30
28
26
24
22
20
18
16
14
12
10
12 16 20
T"
22 24 26 28 30 32 34 36 38 40 42 44 46 48 5C
BAS NT GROUND FLOOR
12-13
SHED
13/iR/h 15-23 6 6 X A
13-15
ROC
17-51
ONE STORY
FRAME HOUSE
W/ BASEMENT DETAIL A
NOT TO SCALE 17-25 13-15
SEE DETAILS
A AND B
v-l
15-23
B X 6 J 6
v-i 13-15
15-23
C X 6 6
12
®
<£>
tv.vj
12-15
v-i
16-17
DETAIL B
NOT TO SCALE
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN /iR/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE—RATE RANGE
RADON DECAY-PRODUCT CONCENTRATION
MEASUREMENT LOCATION
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
AREA WITH CONTAMINATION LEFT IN PLACE
ASSESSED AREAS D (CONCRETE STOVE BASE)
AND E (CINDER BLOCK CHIMNEY) WERE
EXCLUDED FROM REMEDIAL ACTION
ROOM-SIZED AREA AVERAGE OF ELEVATED
EXPOSURE RATES WAS 17 jiR/h
RADIOLOGICAL AS-BUILT
FIGURE 2.1
INTERIOR AND EXTERIOR EXTENT OF CONTAMINATION
SCALE IN FEET
20 10 0 20 40
U:\FA5\C-33\0003\RU00t27V OS/U/gs 1:44pm T5O7S0
12 14 16 18 20
NORTH
J L__
22
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT. UTILITY LOCATION PLAT, OR OTHER IMPROVEMENT SURVEY
PLAT AND IS NOT TO SE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE. BUILOING. OR OTHER FUTURE IMPROVEMENT LINES-
J L
MIJDOKC-MO O* occu'Aart
W-MHKMC(-MH-HM./W.
w*. M. Mil
U.S. DEPARTMENT OF ENERGY
C4AND JUNCTION PROJECTS OFflCC. COLMU0O
MUJ. CMC*
WMirrtb
549 CIRCLE DRIVE
MONTICELLO. UTAH
Must Qaotech <—•*• MS-00127-MR
3-C00127-V1 w 1 g 1
24 26 28 30 32 34 36 38 40 42 44 46 48 5i
OAK RIDGE NATIONAL LABORATORY
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
FOR THE U.S. DEPARTMENT OF ENERGY
PHONE: [phone]
FAX [phone]
POST OFFICE BOX 2S07
GRAND JUNCTION, COLORADO 81502
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by the
U.S. Department of Energy for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program (FUSRAP) and Remote Surplus Facilities Management Program
Sites (SFMP) [Revision 2, March 1987]. This evaluation is based on an independent
verification review of the Remedial Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment of
the 226Ra concentration in the soil, indoor radon daughter concentration, and indoor gamma
exposure rates at this property.
Therefore, this property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
Location Number: MS00127-MR
Location Address: 549 Circle Drive
Monticello, Utah 84535
Property Owner:

Tenant Name: Same
Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERD7ICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
549 CHICLE DRIVE
MONTICELLO, UTAH (MS00127-MR)
M. J. Wilson-Nichols
June 1996
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 4
REFERENCES 7
iii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 5
2. Results of ORNL analysis of Geotech soil samples from 549 Circle Drive,
Monticello, Utah (MS00127-MR) 6
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site Decom-
missioning Projects, U.S. Department of Energy. The author wishes to acknowledge M.
K. Jensen for analysis of soil samples and J. R. Sauvage for technical reviews.
vii
ABSTRACT
In 1980 the site of a vanadium and uranium mill at Monticello, Utah, was accepted
into the U.S. Department of Energy's (DOE's) Surplus Facilities Management Program,
with the objectives of restoring the government-owned mill site to safe levels of radio-
activity, disposing of or containing the tailings in an environmentally safe manner, and
performing remedial actions on off-site (vicinity) properties that had been contaminated
by radioactive material resulting from mill operations. During 1995, RUST Geotech, the
remedial action contractor designated by DOE, performed remedial action on the vicinity
property at 549 Circle Drive, Monticello, Utah. The Environmental Technology Section
(ETS) of Oak Ridge National Laboratory was assigned the responsibility of verifying the
data supporting the adequacy of remedial action and confirming the site's compliance with
DOE guidelines. The ETS found that the site successfully meets the DOE remedial action
objectives. Procedures used by the ETS are described in the Environmental Technology
Section Procedures Manual (ORNL 1993).
ix
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 549 CIRCLE DRIVE
MONTICELLO, UTAH (MS00127-MR)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the U.S. government through the
Defense Plant Corporation to provide vanadium during World War II. Various govern-
ment agencies operated the mill until 1947. In 1948 the Atomic Energy Commission
(AEC) obtained the mill and operated it under contract through 1959 to provide both
uranium and vanadium. Mill operations were terminated on January 1, 1960. In 1961 the
mill tailings piles were leveled and graded, covered with rock and soil, and seeded with na-
tive grasses. During 1974 and 1975, the ore stockpiles were removed from the site, and
the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city
of Monticello, in San Juan County, Utah. The site is bordered on the south and southeast
by land held by the U.S. Bureau of Land Management. Other boundaries are the city of
Monticello and private property.
During the AEC era, the mill processed approximately one million tons of uranium
ore. Vanadium and uranium were the only substances extracted in the milling process.
Other constituents of the ore remained in the tailings and were not separated prior to dis-
posal. During the years of active mill operation, the mill tailings were normally moist, so
erosion was minimal. However, throughout the mill's operating period, area residents
used these tailings as fill material and as aggregate in mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy
(DOE) initiated the Surplus Facilities Management Program (SFMP) in 1978 to ensure
the safe caretaking and decommissioning of government facilities that had been retired
from service but still had radioactive contamination. In 1980 the mill site at Monticello
was accepted into the SFMP, and the Monticello Remedial Action Project (MRAP) was
established to restore the government-owned mill site to safe levels of radioactivity, to
dispose of or contain the tailings in an environmentally safe manner, and to perform reme-
dial actions on off-site (vicinity) properties that had been contaminated by radioactive ma-
terial resulting from mill operations. The Monticello mill site and the tailings remain in the
custody of the DOE Grand Junction, Colorado, Projects Office. In 1983 remedial actions
for vicinity properties were separated from MRAP with establishment of the Monticello
Vicinity Properties (MVP) Project (U.S. DOE 1990b).
*The verification of remedial action was performed by members of the Environmental Assessment Group in the
Environmental Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE
contract DE-AC05-96OR22464 with Lockheed Martin Energy Research Corporation.
2
During 1995, RUST Geotech Inc. (Geotech), the remedial action contractor (RAC)
designated by DOE, performed remedial action on the vicinity property that is the subject
of this report, a single family residence located at 549 Circle Drive, Monticello, Utah. The
remedial action plan required excavation of all exterior contamination. When the excava-
tion was completed, the property was resurveyed, including soil sampling, to ensure the
removal of all contamination, backfilled with uncontaminated material, and restored to a
condition comparable to that which existed prior to remedial action (Geotech 1996).
The DOE adopted a policy to assign an independent contractor to verify the data
supporting the adequacy of remedial action and to confirm the site's compliance with DOE
guidelines. The Environmental Technology Section (ETS) of Oak Ridge National Labor-
atory (ORNL) has been assigned the responsibility of this task at the 549 Circle Drive site.
This report describes the methods and results of that verification.
PROCEDURES
Objectives
The objectives ofthe verification activities were to confirm (1) that available docu-
mentation adequately and accurately describes the post-remedial-action radiological
conditions of the entire property that is to be certified and (2) that the remedial action
reduced contamination to below applicable DOE guidelines (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1996) in-
dicates the property was remediated as evaluated by DOE on the basis of Environmental
Protection Agency standards and the DOE guidelines (DOE 1990a). Excess residual
radioactive materials were present, thus it was appropriate to designate this property for
remedial action.
This property was assessed as part of Group 3, therefore, the quantity of material
assessed is not available. During the actual removal process, a total of 7 yd3 of contami-
nated earth and uranium mill tailings, 6 inches deep, was removed from a 37 m2 area.
A post-excavation survey was performed by Geotech prior to backfilling the exca-
vated areas. This survey consisted of gamma scans with a scintillometer of the ground
level of the structure, a surface scan of the exterior, and soil sampling. Samples repre-
sentative ofthe bottom 15-cm (6-in.) soil layers of three excavated verification areas were
collected and blended to form representative composite soil samples for each verification
area.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation
levels have not been subtracted. Similarly, background concentrations have not been sub-
tracted from radionuclide concentrations in soil samples. Applicable DOE guidelines for
protection against radiation are given in Table 1.
Gamma Measurements
Gamma exposure rate measurements taken by Geotech at the ground-level ofthe
residence ranged from 11 to 13 uR/h. Exterior surface gamma measurements taken from
the excavated areas prior to backfilling ranged from 15 to 23 uR/h.
Soil Sample Analysis
Prior to backfilling, Geotech collected soil samples representative of the excavated
areas from the bottom 15-cm (6-in.) soil layers. These samples were blended to form a
composite soil sample representative of an average over the three exterior verification
areas. Geotech's analysis of this sample showed a ^Ra concentration of 4.5 pCi/g.
ORNL ETS obtained this sample and performed a confirmatory analysis which showed a
226Ra concentration of 6.2 pCi/g. These values are below the EPA standard value of 15
pCi/g for soil layers > 15 cm below the surface. Gamma ranges and/or soil sample results
demonstrate compliance to the DOE Hot Spot Guidelines for areas <25 m2 (Table 1).
As a result of a meeting between the RAC and IVC on May 26, 1994, anomalous
readings, defined as > 30% above the average of the excavation, will be investigated to
show compliance to the DOE hot spot guideline. The IVC observed that 23 uR/h exceeds
30% of the excavation average of 21 uR/h for Region C, which is attributed to contami-
nation extending into the street. The IVC will allow a correlation developed by the RAC
to estimate 226Ra pCi/g concentrations based on gamma exposure rates. The anomalous
reading of 23 uR/h on this property using the RAC's correlation yields a ^Ra concen-
tration of 4.4 pCi/g. This value is well below the minimum concentration of 30 pCi/g
needed, when assuming the maximum area under the hot spot guideline of 25 m2, for
subsurface samples. Results of Geotech and ORNL soil sample analyses are given in
Table 2.
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were deter-
mined by the Alpha-track method. To monitor radon levels, Geotech placed three alpha-
track detectors in the basement of the residence located on this property for a period of
approximately three months (from March 8, 1995 to June 7, 1995). The average annual
working level (WL) of radon progeny concentration, as detennined by the Tech./Ops-
Landauer Corporation, was 0.0100, which is well below the 0.03-WL guideline given in
Table 1.
4
CONCLUSION
Results of Geotech soil sample analysis and confirmatory split soil sample analysis
by ORNL show that radionuclide concentrations are within applicable DOE guidelines.
Based upon the results ofthe post-remedial-action data, which are confirmed by the veri-
fication assessment data, these radiological measurements fall below the limits prescribed
by DOE guidelines. It is concluded that the site successfully meets the DOE remedial
action objectives.
5
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of 226Ra in soil
above background levels,
averaged over a 100-m2 area
5 pCi/g averaged over the
first 15 cm of soil below the
surface; 15 pCi/g when ave-
raged over 15-cm-thick soil
layers more than 15 cm
below the surface
Radionuclide
concentrations in soil
for Hot Spot areas
Exposure to 222Rn
progeny
Maximum Permissible
concentration of Ra226 in soil
above background level, for
areas less than 25 m2
Average annual radon proge-
ny concentration (including
background)
Ra226 concentrations, in any
surface or subsurface area
less than 25 m2, is below the
guideline by a factor of
(100/A)14, where A is the
area of the elevated region
0.03 WL
(DOE 1990a)
6
Table 2. Results of ORNL analysis of Geotech soil samples
from 549 Circle Drive, Monticello Utah (MS00127-MR)
^Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No." Nof (cm)
XI VI 15 to 30 6.2 4.5
" An X-type sample is a split of the sample taken by the remedial action contractor.
b Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated areas
were taken by Geotech, and these samples were blended to form a composite soil
sample, which represents an average over one of the verification areas.
7
REFERENCES
Geotech 1996. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00127-MR, Address: 549 Circle Drive, Monticello, Utah
84535, Geotech, Grand Junction, Colorado, March 1996.
ORNL 1993. Environmental Technology Section (Formerly PoUutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
U.S. DOE 1990a. Verification and Certification Protocolfor the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination
and Decommissioning Program, Revision 3, November 1990. U.S. Department of
Energy, Washington, D.C.
U.S. DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision
and Record of Decision Summary. U.S. Department of Energy, Grand Junction Projects
Office, Grand Junction, Colorado.
DOE ID No.: MS-00144-MR
Property Address: 516 East Third South Street
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech of Energy (DOE)
Ra-226 is s 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [ ]
Ra-226 is ^ 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2.
In-situ [ ] Lab [X]
Interior gamma is £ 20 //R/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is £ 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21.
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ 1 [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
W I 1 [ ]
[>] I 1 [ 1
[>] [ ] [ 1
I* [ ] [ ]
[ 1 iA M
M I 1 [ 1
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of oamma
exposure rates that do not exceed 30 percent above normal background.
111 milium
SFCERTIFED SFMS-00144
DOE ID No.: MS-00144-MR
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Wanda S. /anda S. Bfusby Date
Manager, Monticello Programs
Rust Geotech
DOE EVALUATION
[X] Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Certification Official Date
U.S. Department of Energy
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00144-MR
ADDRESS: 516 EAST THIRD SOUTH STREET
MONTICELLO, UTAH 84535
FEBRUARY 1996
Prepared for
U.S. Department of Energy
by
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
Wanda S. Busby
Manager, Monticello Programs
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.1.3 Radon Decay-Product Concentration (RDC) Measurement .... 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
i
DOE ID No.: MS-00144-MR
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Inclusion Survey Contractor. DOE reviewed
these evaluation results and determined that the property contained mill
tailings (residual radioactive material) exceeding EPA standards. The
Remedial Action Contractor was notified of the inclusion of this property
into the MVP Project and was authorized by DOE to conduct remedial
action as required to bring the property into conformance with EPA
standards and DOE hot spot criteria.
1
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
Property Address:
Property Owners:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
DOE ID No.: MS-00144-MR
MS-00144-MR
Parcel No. M-601; beginning south
1,780 feet and east 936.5 feet from the
NW corner of Section 31, T33S., R24E.,
Salt Lake Base Meridian; south 180 feet,
west 180 feet, north 180 feet, east
180 feet to beginning, City of Monticello,
County of San Juan, State of Utah
516 East Third South Street
Monticello, Utah 84535

Major Residential (MR)
Oak Ridge National Laboratory
January 25, 1990
Rust Geotech
March 2, 1993
Mountain Region Corporation
117 29 3/4 Road
Grand Junction, Colorado
July 29, 1993
October 26, 1993
Interior: 0 cubic yards
Exterior: 883 cubic yards
2,395 square meters (m2)
February 1996
2
DOE ID No.: MS-00144-MR
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of exterior residual radioactive
material (Appendix Figure 2.1). Interior assessed Area E (firebrick) was
excluded from remedial action based on averaged gamma exposure rates
and pre-remedial radon decay-product concentration measurements that
did not exceed EPA standards, as discussed in the REA. Once excavation
was complete, the affected areas were resurveyed for possible remaining
residual radioactive material and, upon attaining satisfactory results, were
backfilled with uncontaminated material. The property was restored to a
physical condition comparable to that which existed prior to remedial
action activities.
2.2 Previously Unidentified Contamination
The radiological assessment (excluding assessed Area E) identified
268 cubic yards of contamination, ranging from 6 to 30 inches deep,
within the property. The remedial action process included the removal of
approximately 883 cubic yards of residual radioactive material, ranging
from 6 to 66 inches deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID No.: MS-00144-MR
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by the Remedial Action
Contractor during June and July 1990, as described in the final
REA dated March 1993. Appendix Figure 2.1 shows the extent of
assessed contamination and identifies the areas recommended to
undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the excavation were
collected. These samples were blended to form composite
samples representing the verification areas (Appendix Figure 2.1).
Interior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 13 to 15 microroentgens per
hour (//R/h) for the basement and 13 to 67 //R/h for the ground
floor (Appendix Figure 2.1). Elevated exposure rates were
associated with excluded assessed Area E. The room-sized area
average of the elevated exposure rates was 22 //R/h.
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 13 to 32 //R/h (Appendix
Figure 2.1). The results of analyses for radium-226 in
31 composite soil samples ranged from 1.0 to 12.4 picocuries per
gram (pCi/g), as indicated in Appendix Table 3.1.
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on measurements representing an annual average, the
RDC was 0.0241 working level (WL), as indicated in
Appendix Table 3.2. Appendix Figure 2.1 shows the measurement
location in the basement (the lowest habitable level of the
structure).
4
DOE ID No.: MS-00144-MR
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at 516 East Third South Street, in
Monticello, Utah, is recommended for certification as required by DOE
guidelines, and the appropriate records should be documented.
Certification Data Summary
Applicability
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Standards
Shall not exceed 20 //R/h
above background.*
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Survey Results
Ranges were 13 to
15 //R/h for the basement
and 13 to 67 //R/h for the
ground floor. The room-
sized area average of the
elevated exposure rates
was 22 //R/h.
Annual average was
0.0241 WL.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
< 5 pCi/g above
background. **
Soil sample results
ranged from 1.0 to
12.4 pCi/g.*#
*The background exposure rate is approximately 15//R/h.
'The background radium-226 concentration is approximately 2.0 pCi/g.
**The hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-00144-MR
4.0 APPENDIX
Appendix Tables:
Table 3.1 Post-Excavation Sample/Measurement Results
Table 3.2 Radon Decay-Product Concentration Measurement
Results
Appendix Figure:
Figure 2.1 Interior and Exterior Extent of Contamination -
RADIOLOGICAL AS-BUILT
JEK:09-25-95
MS-00144.MR WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00144-MR
Address: 516 East Third South Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (//R/h) Ticket No. Method" (pCi/g)
V-1
V-2
V-3
V-4
V-5
V-6
V-7
V-8
V-9
V-10
V-11
V-12
V-13
V-14
V-15
V-16
V-17
V-18
V-19
V-20
V-21
V-22
V-23
V-24
V-25
V-26
V-27
V-28
15
15
15
15
15
15
15
15
16
15
16
16
14
15
18
18
18
15
18
18
18
16
18
18
14
14
14
14
22
19
21
18
19
18
19
19
19
20
21
20
20
21
25
25
25
21
25
25
25
23
23
25
19
25
23
21
NAY 422
NAY 423
NAY 424
NAY 425
NAY 426
NAY 427
NAY 428
NCD 435
NCD 436
NCA 464
NCA 465
NCA 466
NCA 467
NCA 468
NCA 469
NCA 470
NCA 471
NCA 472
NAY 432
NAY 433
NAY 434
NAY 435
NAY 436
NAY 437
NAY 438
NAY 439
NAY 440
NCE 109
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
1.5
1.1
1.9
1.0
1.4
2.5
1.5
2.2
1.6
2.7
4.6
3.2
4.0
4.0
2.4
3.9
2.5
1.7
6.6
4.0
5.5
3.1
2.0
6.3
3.0
5.3
7.8
2.5
"OCS = Opposed Crystal System
7
Table 3.1 (Continued)
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00144-MR
Address: 516 East Third South Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range fo/R/h) Ticket No. Method* (pCi/g)
V-29 13-21 NCE 110 OCS 2.4
V-30 14-25 NCE 111 OCS 3.1
V-31 25-32 NCD 434 OCS 12.4
See Appendix Figure 2.1 for the verification areas.
"OCS = Opposed Crystal System
8
Table 3.2
Radon Decay-Product Concentration Measurement Results
DOE ID No.: MS-00144-MR
Address: 516 East Third South Street, Monticello, Utah
Instrument Type: Landauer Radtrak Detector
Radon
Detector Tracks Per Concentration Working
Number Start Date End Date mm2 (pCi/L) Level
3853798
3853816
3853875
10-28-93
10-28-93
10-28-93
10-10-94
10-10-94
10-10-94
39.7
43.0
41.0
4.62
5.02
4.79
0.0231
0.0251
0.0240
Annual Average: 0.0241
See Appendix Figure 2.1 for the measurement location.
9
42
40
38
36
34
32
30
28
26
24
22
20
18
16
14
12
10
12 1 4 1 6 18 20 22 24 26 28 30 32 36 40 44 46 48 50
V-31 V-26 V-28 V-27
25-32 14-25 14-23 14-21
iol CEMETERY ROAD A X 6
EAST THIRD SOUTH STREET
6>.
\ 50 V-29 40 (Dm 66 50 13-21
12 56 V- 1 10 1 -* © 15-22 V-2
40 15-19 V-3
15-21 ! 24K 1/ © © © 12 34 A
12 12 ® \ © 15-18 © \W © / V-4
15-18
V-5 V-6
0 15-19 15-18 12
34 V-30
C .-. 14-25
© 0 E 6 5 V-25
4 V-7 14-19
© 16 V-9 15-19 SPLIT LEVEL
FRAME AND
ROCK HOUSE
v-8 16-19 15-17 15-19
I::::;:::: 24
15-17 SEE DETAIL A V-18
© 15-21
© V-15
18-25 t 24 v-10
• V-12
15-20
7 16-20
V-22
© 16-23
• 16 © 48 24
©' © V-13
V- 1
LU 14-20 V-1 6 12 V-23 16-21 ©III} 18-25 12 18-23
V-21
18-25
6>\ V-24 12 V 24 V-17
© V-14 V-20 18-25 18-25 UJ::::© 15-21 0 18-25 15
n\ © ® |©
®
©
12-15
EU
V-1
16-17
BASEMENT
13-15
GROUND FLOOR
13-15
21-67
DETAIL A
NOT TO SCALE
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN /iR/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE —RATE RANGE
POST-REMEDIAL ACTION RADON DECAY—PRODUCT
CONCENTRATION MEASUREMENT LOCATION
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
AREA WITH CONTAMINATION LEFT IN PLACE
ASSESSED AREA E (FIREBRICK) WAS
EXCLUDED FROM REMEDIAL ACTION
ROOM-SIZED AREA AVERAGE OF ELEVATED
EXPOSURE RATES WAS 22 jiR/h
RADIOLOGICAL AS-BUILT
FIGURE 2.1
INTERIOR ANO EXTERIOR EXTENT OF CONTAMINATION
L
SCALE IN FEET
20 10 0 20 40
U:\FAS\0JJ\000J\RM00I44V 09/29/93 J:33pn> 150780
NORTH
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY ANO ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT. UTILITY LOCATION PLAT. OR OTHER IMPROVEMENT SURREY
PLAT ANO IS NOT TO 8E RELIED UPON FOR THE ESTABLISHMENT
OF FENCE, BUILDING, OR OTHER FUTURE IMPROVEMENT LINE5.
12 14 16 18 20 22 24 26 28 30 32 34
J L
36
MM-KIIKKC-NW-MM /n
U.S. DEPARTMENT OF ENERGY
CHANO JUNCTION PROJECTS OFFICE. COLORADO
"rr 516 EAST THIRD SOUTH STREET
MONTICELLO, UTAH
RUST Rust Q«ote«li
38 40 42 44 46
MS-00144-MR
48 5C
OAK RIDGE NATIONAL LABORATORY PHONE: (970) 24JW5200
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION FAX: (970) 24&«220
FOR THE U.S. DEPARTMENT OF ENERGY
POST OFFICE BOX 2567
GRAND JUNCTION, COLORADO 81502 | g 1996
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. 0. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by the U.S.
Department of Energy for Residual Radioactive Material at Formerly Utilized Sites Remedial Action
Program (FUSRAP) and Remote Surplus Facilities Management Program Sites (SFMP) [Revision
2, March 1987]. This evaluation is based on an independent verification review ofthe Remedial
Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment ofthe 226Ra
concentration in the soil, indoor radon daughter concentration, and indoor gamma exposure rates at
this property.
This property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
Location Number. MS00144-MR
Location Address: 516 East 3rd South Street
Monticello. Utah 84535
Property Owner:

Tenant Name: Same
Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE B INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
516 EAST 3RD SOUTH STREET
MONTICELLO, UTAH (MS00144-MR)
A. R. Jones
September 1996
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES v
LIST OF FIGURES v
ACKNOWLEDGMENTS vii
ABSTRACT viii
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
GEOTECH SURVEY RESULTS 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
ORNL SURVEY RESULTS 6
Gamma Measurements 6
Soil Sample Analysis 6
CONCLUSION 6
REFERENCES 8
ii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 4
2. Results of ORNL and Geotech analyses of soil samples from 516 East 3rd South
Street Monticello, Utah (MS00144-MR) 5
LIST OF FIGURES
1. Property Map 7
v
ACKNOWLEDGMENTS
Research for this project was sponsored by the U.S. Department of Energy, Office of
Environmental Restoration, Southwestern Area Programs. The author wishes to acknow-
ledge M. K. Jensen for analysis of soil samples and technical review and N. F. Kirby for
technical review.
vu
ABSTRACT
In 1980 the site of a vanadium and uranium mill at Monticello, Utah, was accepted into
the U.S. Department of Energy's (DOE's) Surplus Facilities Management Program, with the
objectives of restoring the government-owned mill site to safe levels of radioactivity, dis-
posing of or containing the tailings in an environmentally safe manner, and performing reme-
dial actions on off-site (vicinity) properties that had been contaminated by radioactive material
resulting from mill operations. During 1993, RUST Geotech Inc., the remedial action con-
tractor designated by DOE, performed remedial action on the vicinity property at 516 East
3rd South Street, Monticello, Utah. The Environmental Technology Section (ETS) of Oak
Ridge National Laboratory was assigned the responsibility of verifying the data supporting
the adequacy of remedial action and confirming the site's compliance with DOE guidelines.
The ETS found that the site successfully meets the DOE remedial action objectives.
Procedures used by ETS are described in the Environmental Technology Section Procedures
Manual (ORNL 1993).
vm
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 516 EAST 3RD SOUTH STREET
MONTICELLO, UTAH (MS00144-MR)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the U.S. government through the
Defense Plant Corporation to provide vanadium during World War II. Various government
agencies operated the mill until 1947. In 1948 the Atomic Energy Commission (AEC) ob-
tained the mill and operated it under contract through 1959 to provide both uranium and
vanadium. Mill operations were terminated on January 1, 1960. In 1961 the mill tailings piles
were leveled and graded, covered with rock and soil, and seeded with native grasses. During
1974 and 1975, the ore stockpiles were removed from the site, and the mill foundations were
buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city of
Monticello, in San Juan County, Utah. The site is bordered on the south and southeast by
land held by the U.S. Bureau of Land Management. Other boundaries are the city of Monti-
cello and private property.
During the AEC era, the mill processed approximately one million tons of uranium ore.
Vanadium and uranium were the only substances extracted in the milling process. Other con-
stituents of the ore remained in the tailings and were not separated prior to disposal. During
the years of active mill operation, the mill tailings were normally moist, so erosion was
minimal. However, throughout the mill's operating period, area residents used these tailings
as fill material and as aggregate in mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy (DOE)
initiated the Surplus Facilities Management Program (SFMP) in 1978 to ensure the safe
caretaking and decommissioning of government facilities that had been retired from service
but still had radioactive contamination. In 1980 the mill site at Monticello was accepted into
the SFMP, and the Monticello Remedial Action Project (MRAP) was established to restore
the government-owned mill site to safe levels of radioactivity, to dispose of or contain the
tailings in an environmentally safe manner, and to perform remedial actions on off-site (vicin-
ity) properties that had been contaminated by radioactive material resulting from mill opera-
tions. The Monticello mill site and the tailings remain in the custody of the DOE Grand
Junction, Colorado, Projects Office. In 1983 remedial actions for vicinity properties were
separated from MRAP with establishment of the Monticello Vicinity Properties (MVP)
Project (U.S. DOE 1990b).
The verification of remedial action was performed by members of the Environmental
Technology Section ofthe Health Sciences Research Division at Oak Ridge National Laboratory
under DOE contract DE-AC05-96OR22464 with Lockheed Martin Energy Research Corp.
2
During 1993, RUST Geotech Inc. (Geotech), the remedial action contractor (RAC)
designated by DOE, performed remedial action on the vicinity property that is the subject of
this report, a private residence located at 516 East 3rd South Street, Monticello, Utah. The
remedial action plan required excavation of all exterior contamination, backfilling with uncon-
taminated material, and restoration to a condition comparable to that which existed prior to
remedial action (Geotech 1996). When the excavation stage was completed, the property was
resurveyed, including soil sampling, by Geotech and by an independent contractor to verify
the data supporting the adequacy of remedial action and to confirm the site's compliance with
DOE guidelines. The Environmental Technology Section (ETS) of Oak Ridge National
Laboratory (ORNL) has been designated the Independent Verification Contractor for the 516
East 3rd South Street site. This report describes the methods and results of the verification
surveys.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available documenta-
tion adequately and accurately describes the post-remedial-action radiological conditions of
the entire property that is to be certified and (2) that the remedial action reduced contamina-
tion to below applicable DOE guidelines (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1996) indicates
the property was remediated as evaluated by DOE on the basis of Environmental Protection
Agency standards (DOE 1990a) and that excess residual radioactive materials were present.
Thus it was appropriate to designate this property for remedial action.
The presence of the interior area, Area E, on the ground floor of this property prompted
pre-remedial RDC placements on both the ground floor and in the basement. These pre-
remedial placements occurred during a non-approved prompt RDC window. The REA states
"These measurements indicate this property will probably not exceed the 0.02 WL EPA
guideline." The monitors placed on the ground floor near Area E yielded an average working
level (WL) of 0.0185, with one monitor greater than 0.02 WL. The monitors placed in the
basement yielded an average WL of 0.0195 with two monitors greater than 0.02 WL.
ORNL's concern is the narrow margin between the actual results and the EPA guideline
requiring remedial action, and the use of an invalid window to exclude interior removal. The
extensive exterior contamination and lack of a specific radon source in the basement probably
would not have changed the remedial process.
The pre-remedial-action survey performed by Geotech identified 268 yd3 of mill tailings
6 to 30 inches deep. However, during the actual removal process, a total of 883 yd3 of
contaminated earth and uranium mill tailings, 6 to 66 inches deep, were removed from a 2,395
nr area.
3
* A post-excavation survey was performed by Geotech prior to backfilling of the excavated
• areas. This survey consisted of gamma scans with a scintillometer of the ground-level and
basement of the building and the exterior, and soil sampling. Samples representative of the
bottom 15-cm (6-in.) soil layers of 31 excavated areas were collected and blended to form
representative composite soil samples for each verification area.
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation
levels have not been subtracted. Similarly, background concentrations have not been sub-
tracted from radionuclide concentrations in soil samples. Applicable DOE guidelines for pro-
tection against radiation are given in Table 1.
GEOTECH SURVEY RESULTS
Gamma Measurements
Gamma exposure rate measurements taken by Geotech over the ground-level of the
residence ranged from 13 to 67 ^R/h. Exterior surface gamma measurements taken from the
excavated areas prior to backfilling ranged from 13 to 32 uR/h.
Soil Sample Analysis
Prior to backfilling, Geotech collected soil samples representative of the excavated areas
from the bottom 15-cm (6-in.) soil layers. These samples were blended to form composite
soil samples representative of an average over the 31 exterior verification areas. Geotech's
analysis of these samples showed 226Ra concentrations ranging from 1.0 to 12.4 pCi/g in the
composite samples. ORNL ETS obtained a percentage of these soil samples and performed
a confirmatory analysis, which showed 226Ra concentrations ranging from 1.3 to 3.9 pCi/g.
These values are below the EPA standard value of 15 pCi/g for soil layers >15 cm below the
surface (Table 1). Gamma ranges, excon soil sample results in the folio, and soil sample
results demonstrate compliance to the DOE Hot Spot Guideline for areas < 25 m2 (Table 1).
Results of Geotech and ORNL soil sample analyses are given in Table 2.
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were determined
by the alpha-track method. To monitor radon levels, Geotech placed three Alpha-track detec-
tors in the basement of the residence located on this property for a period of approximately
one year (from October 28, 1993 to October 10, 1994). The IVC was present during place-
ment and retrieval of the detectors to verify the RDC measurements. The average annual WL
of radon progeny concentration, as determined by the Tech./Ops-Landauer Corporation, was
0.0241, which is below the 0.03-WL guideline given in Table 1. The procedures and methods
used to obtain the annual average WL are deemed adequate and the results accurate by the
IVC.
4
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of 226Ra in soil
above background levels,
averaged over a 100-m2 area
5 pCi/g averaged over the
first 15 cm of soil below the
surface; 15 pCi/g when
averaged over 15-cm-thick
soil layers more than 15 cm
below the surface.
Radionuclide con-
centrations in soil
for Hot Spot areas
Exposure to 222Rn
progeny
Maximum permissible con-
centration of 226Ra in soil
above background level, for
areas less than 25 m2.
Average annual radon
progeny concentration
(including background).
Ra226 concentration, in any
surface or subsurface area
less than 25 m2, is below the
guideline of (100/A)'/j,
where A is the area of the
elevated region.
0.03 WL
(DOE 1990a)
5
Table 2. Results of ORNL and Geotech analyses of soil samples
from 516 East 3rd South Street, Monticello, Utah (MS00144-MR)
—Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth
No. No.* (cm) Confirmatory7 ORNL Geotech
X4* NAY 425 >15
X9a NCD 436 >15
X17a NCA 471 >15
X26" NAY 439 >15
X28" NCE 109 >15
W3Cd NAY 424 >15
V3HC >15
VI lC NCA 465 >15
VllHe >15
VI5C NCA 469 >15
V15H" >15
V20C NAY 433 >15
V20HC >15
V24Cd NAY 437 >15
V24He >15
V30Crf NCE 111 >15
V30He >15
Bl' >15
1.3 1.0
2.5 1.6
1.7 2.5
3.9 5.3
3.2 2.5
1.5 1.9
5.1
5.2 4.6
4.7
3.0 2.4
32.0
3.7 4.0
2.2
6.4 6.3
7.6
2.4 3.1
6.6
27.0
" An X-type sample is a split of the sample taken by the remedial action contractor.
* Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated
areas were taken by RUST Geotech Inc., and these samples were blended to form
composite soil samples, which represent an average over verification areas.
c ORNL performed analysis on aliquots of the composite samples taken by Geotech
(confirmatory).
d Composite samples collected by ORNL from approximately the same excavated
locations sampled by Geotech.
e Individual samples collected by ORNL from the highest outdoor gamma from the
verification area.
f Individual biased sample collected to confirm compliance to the DOE Hot Spot
Guideline.
6
ORNL SURVEY RESULTS
Gamma Measurements
Measurements taken by ORNL over the ground surface in the excavated areas prior to
backfilling ranged from 14 to 32 uR/h.
Anomalous gamma exposure rates identified as Bl were detected in area V26, and
had an area of 5 nr. The area identified as V31 in the completion report was not scanned by
ORNL.
Soil Sample Analysis
ORNL sampled six of the excavated areas prior to backfilling, collecting aliquots repre-
sentative of those areas from the bottom 15-cm (6-in.) soil layers. These samples were blend-
ed to form composite soil samples representative of an average over the exterior verification
areas. ORNL's analysis of these composite samples showed 226Ra concentrations ranging
from 1.5 to 6.4 pCi/g. These values are below the DOE guideline value of 15 pCi/g for soil
layers >15 cm below the surface (Table 1). Individual soil samples were also collected from
the six excavated areas at the highest outdoor gamma (HOG) exposure rate. Each HOG sam-
ple was representative of an area 1 m2 or less. ORNL's analysis of these samples showed
226Ra concentrations ranging from 2.2 to 32 pCi/g. These values are below the DOE Hot
Spot Guideline of 150 pCi/g for subsurface soils with a 1 m2 area. An individual biased sam-
ple was collected from the anomalous area identified as Bl. Analysis of this sample yielded
a 226Ra concentration of 27 pCi/g. This value is below the DOE Hot Spot Guideline of 67
pCi/g for subsurface soils with a 5 m2 area. Results of ORNL sample analyses are given in
Table 2.
CONCLUSION
The results of all Geotech and ORNL soil sample analyses show that radionuclide con-
centrations are within applicable DOE guidelines. Based upon the results of the post-
remedial-action data, which are confirmed by the verification assessment data, these radio-
logical measurements fall below the limits prescribed by DOE guidelines. The post remedial
action RDC measurement falls between the 0.02 WL inclusion criteria and the maximum value
of 0.03 WL. If valid pre-remedial action RDC measurements had been used the remedial
process would have probably remained the same, since the RDC value is below the maximum
value of 0.03 WL. It is concluded that the site successfully meets the DOE remedial action
objectives.
CEMETERY ROAD
V
V2 V2 V3 V2 V2
VI
V5 Bl V2
V4 V6
V30 1 V9
V7 V8 Ir.
m RDC V18 VIO
1 V12 V15 ;c
V2
03
V16
V13
Vll V23
V21
V19 V24 V20 V14 V17
VI
V2
V3
V4
V5
V6
V7
V8
V9
VIO
VU
V12
V13
V14
V15
15-19 ?R/h
15-17 ?R/h
15-22 ?R/h
15-17 ?R/h
15-17 ?R/h
15-17 ?R/h
15-22 ?R/h
15-17 ?R/h
15-17 ?R/h
15-26 ?R/h
15- 29 ?R/h
16- 20 ?R/h
17- 22 ?R/h
15-22 ?R/h
15-28 ?R/h
Bl 22-32 ?R/h
Figure 1. Property Mop
V16 16-23 ?R/h'
V17 16-25 ?R/h
V18 15-22 ?R/h
\7l9 16-22 ?R/h
V20 15-22 ?R/h
V21 16-22 ?R/h
V22 15-17 ?R/h.
V23 16-19 ?R/h
V24 15-25 ?R/h,
V25 16-32 ?R/h
V26 16-25 ?R/h
V27 15-25 ?R/h
V28 14-22 ?R/h
V29 14-19 ?R/h'
V3o| 15-25 ?R/h
EXPLANATION
Concrete
Assessed
contamination
Assessed area
not found
Excavated
area
Remaining
contamination
RDC
Measurement
Area Identifier &
Composite sample
Identifier of
Bl | averaged area &
Biased sample
ft Individual sample
from V-area HDG
N.
FEET
aa so
METERS
MS00144
516 EAST 3RD SCJUTH
MDNTICELLD, UTAH
8
REFERENCES
Geotech 1996, Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00144-MR, Address: 516 East Third South Street, Monticello,
Utah 84535, Geotech, Grand Junction, Colorado, February, 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment Group)
Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National Laboratory,
Grand Junction, Colorado.
U.S. DOE 1990a. Verification and Certification Protocol for the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination and
Decommissioning Program, Revision 3, November 1990. U.S. Department of Energy,
Washington, D.C.
U.S. DOE 1990b. Moniicello Mill Tailings Site Declaration for the Record of Decision and
Record of Decision Summary. U.S. Department of Energy, Grand Junction Projects Office,
Grand Junction, Colorado.
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00148-MR
ADDRESS: 464 SOUTH SECOND EAST STREET
MONTICELLO, UTAH 84535
JUNE 1996
Prepared for
U.S. Department of Energy
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
by
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
Wanda S. Busby 1
Manager, Monticello Programs
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.1.3 Radon Decay-Product Concentration (RDC) Measurement .... 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
DOE ID No.: MS-00148-MR
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by DOE, which determined that the property contained mill
tailings (residual radioactive material) exceeding EPA standards. The
Remedial Action Contractor was notified of the inclusion of this property
into the MVP Project and was authorized by DOE to conduct remedial
action as required to bring the property into conformance with EPA
standards and DOE hot spot criteria.
1
DOE ID No.: MS-00148-MR
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
Property Address:
Property Owners:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
MS-00148-MR
Lot 1, Block 2, Monticello Townsite Survey,
County of San Juan, State of Utah
464 South Second East Street
Monticello, Utah 84535

Major Residential (MR)
Not applicable: historical inclusion by DOE
September 5, 1985
Rust Geotech
September 29, 1987
Bayless and Bayless, Inc.
435 E. 1st
Pueblo, Colorado
July 21, 1988
September 30, 1988
Interior: 87 cubic yards
Exterior: 3,362 cubic yards
4,645 square meters (m2)
June 1996
2
DOE ID No.: MS-00148-MR
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of interior and exterior residual
radioactive material (Appendix Figure 2.1). Once excavation was
complete, the affected areas were resurveyed for possible remaining
residual radioactive material and, upon attaining satisfactory results, were
backfilled with uncontaminated material. The property was restored to a
physical condition comparable to that which existed prior to remedial
action activities.
2.2 Previously Unidentified Contamination
The radiological assessment identified 1,828 cubic yards of
contamination, ranging from 6 to 39 inches deep, within the property.
The remedial action process included the removal of approximately
3,449 cubic yards of residual radioactive material, ranging from 18 to
144 inches deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
Portions of assessed Areas C and D, outside the property boundary, were
excluded from this remedial action. These areas involved contamination
surrounding three utility lines and will be addressed in a supplemental
standards application for city streets and utilities.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted within the legal property boundary.
3
DOE ID No.: MS-00148-MR
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by Bendix Field Engineering
Corporation during January and February 1986, as described in
the final REA dated September 1987. Appendix Figure 2.1 shows
the extent of assessed contamination and identifies the areas
recommended to undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the exterior excavation
were collected. These samples were blended to form composite
samples representing the exterior verification areas (Appendix
Figure 2.1).
Interior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 14 to 108 microroentgens per
hour {pR/h) for the remediated crawl space, and 13 to 24/yR/h for
the ground floor (Appendix Figure 2.1). Elevated exposure rates
were associated with residual radioactive material under concrete
support pads. This material was left in place to avoid structural
damage to the house, and did not cause exposure rates on the
ground floor to exceed the EPA standard.
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 15 to 108//R/h (Appendix
Figure 2.1). Elevated exposure rates in portions of assessed
Areas C and D outside the property boundary were associated
with residual radioactive material associated with utility lines.
These are shown on Appendix Figure 2.1 as three areas with
contamination left in place, and will be addressed under
supplemental standards. The results of analyses for radium-226 in
50 composite soil samples ranged from 0.7 to 7.3 picocuries per
gram (pCi/g), as indicated in Appendix Table 3.1.
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on measurements representing an annual average, the RDC
was 0.0083 working level (WL), as indicated in Appendix
Table 3.2. Appendix Figure 2.1 shows the measurement location
on the ground floor (the lowest habitable level of the structure).
4
DOE ID No.: MS-00148-MR
3.2 Recommendation for Certification
Residual radioactive materials have been removed from within the legal
boundary of this property to the extent required by EPA standards
(40 CFR 192.12, 192.20-23) and DOE hot spot criteria, as indicated in
the Certification Data Summary below.
Therefore, the property located at 464 South Second East Street, in
Monticello, Utah, is recommended for certification as required by DOE
guidelines, and the appropriate records should be documented.
Certification Data Summary
Applicability
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Standards
Shall not exceed 20 //R/h
above background.*
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Survey Results
Range for the ground
floor was 13 to 24//R/h.
Annual average was
0.0083 WL.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
< 5 pCi/g above
background.**
Soil sample results
ranged from 0.7 to
7.3 pCi/g.**
*The background exposure rate is approximately 21 //R/h.
The background radium-226 concentration is approximately 2.0 pCi/g.
**The hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-00148-MR
4.0 APPENDIX
Appendix Tables:
Table 3.1 Post-Excavation Sample/Measurement Results
Table 3.2 Radon Decay-Product Concentration Measurement
Results
Appendix Figure:
Figure 2.1 Interior and Exterior Extent of Contamination -
RADIOLOGICAL AS-BUILT
JEK:05-06-96
MS-00148.MR WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00148-MR
Address: 464 South Second East Street, Monticello, Utah
The analytical uncertainties in the table are reported at the 95-percent confidence
interval. A less-than sign (<) indicates that the minimum detection limit based on
Compton background was reached.
Exposure- Soil
Rate Range Sample Meas. Radium-226 Potassium Thorium
Area (//R/h) Ticket No. Method* (pCi/g) (pCi/g) (pCi/g)
EXTERIOR
V-1 19-35
V-2 18 - 24
V-3 18-21
V-4 18 - 24
V-5 21 - 35
V-6 18-19
V-7 18-21
V-8 18-32
V-9 17-26
V-10 16-32
V-11 16-19
V-12 16-32
V-13 17-26
V-14 15-18
V-15 16-24
V-16 16-18
V-17 16-28
V-18 16-21
V-19 16-18
V-20 17-21
V-21 17-25
V-22 16 - 24
V-23 17-24
V-24 16 - 20
V-25 16-21
V-26 16-18
MNK 526 AL
MNK 527 AL
MNK 528 AL
MNK 529 AL
MNK 530 AL
MNK 531 AL
MNK 532 AL
MNK 533 AL
MNK 534 AL
MNK 535 AL
MNK 536 AL
MNK 537 AL
MNK 538 AL
MNK 539 AL
MNK 540 AL
MNK 541 AL
MNK 542 AL
MNK 543 AL
MNK 544 AL
MNK 545 AL
MNK 546 AL
MNK 547 AL
MNK 548 AL
MNK 549 AL
MNK 550 AL
MNK 551 AL
6.5 ± 0.9 17.8
2.3 ± 0.4 17.8
1.4 ± 0.3 18.2
4.8 ± 0.7 16.1
1.0 ± 0.2 18.8
0.9 ± 0.2 18.3
0.8 ± 0.2 16.6
7.3 ± 1.0 16.1
1.4 ±0.3 18.1
2.9 ± 0.5 18.3
1.0 ± 0.2 16.6
6.0 ± 0.9 18.6
1.1 ± 0.2 17.3
2.4 ± 0.4 18.3
1.2 ± 0.2 16.4
0.7 ± 0.2 15.9
2.2 ± 0.4 20.0
3.5 ± 0.5 20.2
1.7 ± 0.3 17.5
6.1 ± 0.9 17.5
1.7 ± 0.3 17.8
2.3 ± 0.4 18.6
2.2 ± 0.4 15.1
1.7 ± 0.3 16.6
1.2 ± 0.2 15.9
1.5 ± 0.3 15.8
± 3.5 0.9 ± 0.3
± 3.5 0.9 ± 0.3
± 3.6 1.1 ± 0.3
± 3.4 0.9 ± 0.2
± 3.6 1.2 ± 0.3
± 3.6 1.4 ± 0.3
± 3.4 1.3 ± 0.3
± 3.4 1.-1 ± 0.3
± 3.5 1.1 ± 0.3
± 3.6 0.9 ± 0.3
± 3.4 1.0 ± 0.3
± 3.7 1.0 ± 0.3
± 3.5 1.3 ± 0.3
± 3.6 0.9 ± 0.3
± 3.5 1.1 ± 0.3
± 3.4 1.0 ± 0.3
± 3.9 < 0.2
± 3.8 1.0 ± 0.3
± 3.5 1.0 ± 0.3
± 3.5 1.0 ± 0.3
± 3.5 1.1 ± 0.3
± 3.6 1.1 ± 0.3
± 3.1 1.5 ± 0.3
± 3.3 1.0 ± 0.3
± 3.2 0.9 ± 0.3
± 3.2 0.9 ± 0.3
"AL = Analytical Laboratory
7
Table 3.1 (continued)
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00148-MR
Address: 464 South Second East Street, Monticello, Utah
Exposure- Soil
Rate Range Sample Meas. Radium-226 Potassium Thorium
Area U/R/h) Ticket No. Method' (pCi/g) (pCi/g) (pCi/g)
EXTERIOR
V-27
V-28
V-29
V-30
V-31
V-3 2
V-33
V-34
V-35
V-3 6
V-37
V-38
V-39
V-40
V-41
V-42
V-43
V-44
V-45
V-46
V-47
V-48
V-49
V-50
V-51
16-22
15- 20
16 - 19
16- 20
16-20
16-32
16-28
16- 20
17- 20
17- 20
17 - 24
18- 24
18-26
16 - 18
15 - 18
16-24
16 - 19
16- 19
17- 20
17 - 19
16-22
16-28
16-24
16-32
14 - 24
MNK 552
MNK 553
MNK 554
MNK 555
MNK 556
MNK 557
MNK 558
MNK 559
MNK 560
MNK 561
MNK 562
MNK 563
MNK 564
MNK 565
MNK 566
MNK 567
MNK 568
MNK 569
MNK 570
MNK 571
MNK 572
MNK 573
MNK 574
MNK 575
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
1.2
1.1
1.3
1.3
1.1
3.7
4.3
1.5
2.5
2.8
2.8
2,
5.
1,
2,
1,
1.1
1.2
1.
2.
2.
4.
3.
1.
0.2
0.2
0.2
0.3
0.2
0.6
0.7
0.3
0.4
0.3
0.3
2
,2
,3
A
,5
,7
,5
0.3
13.
13.
14.
13.
12.
13.
11.7
17.1
17.1
19.
16.
14.
15.
17.
16.8
16.5
14.4
13.3
12.3
15.8
14.3
12.0
13.9
16.5
.5
.7
.5
.9
.7
.3
.6
.0
.7
.6
.1
2.9
3.0
3.1
3.0
2.9
2.6
2.9
3.4
3.3
3.2
2.6
2.4
2.6
3.3
I.O
.1
0.8
.1
.2
.4
.2
.1
.6
.1
.1
.0
.1
.0
.2
.1
0.9
.3
.0
.1
0.9
0.5
0.6
< 0.2
0.3
0.3
0.2
0.3
0.3
0.3
0.3
0.3
0.3
0.3
0.3
0.3
2
3
3
3
2
2
2
INTERIOR
Not Applicable
See Appendix Figure 2.1 for the verification areas.
*AL = Analytical Laboratory
8
Table 3.2
Radon Decay-Product Concentration Measurement Results
DOE ID No.: MS-00148-MR
Address: 464 South Second East Street, Monticello, Utah
Instrument Type: Landauer Radtrak Detector
Detector
Number Start Date End Date
Radon
Concentration
(pCi/L)
Working
Level
3071132
3071166
3071146
03-13-90
03-13-90
03-13-90
03-11-91
03-11-91
03-11-91
1.76
1.48
1.76
0.0088
0.0074
0.0088
Annual Average: 0.0083
See Appendix Figure 2.1 for the measurement location.
9
42
40
38
36
34
32
30
28
26
24
22
20
18
16
1 4
12
10
3 12 14 16 18 20 22 24 26 28 30 32 34 36 .38 40 42 46 48 5C
1S-28
24
79-103-
A35-^64 A
SOUTH SECONO EAST STREET
N
v-32
16-32
f 18-
v-3i
16-20 18
v-30
16-20
18
v-29
16-19
v-23
15-20
V-27
16-22
*2-
V-26
16-18
V-25
16-21
18.
V-24
16-20
18
V-23
17-24
v-22
16-24
®®®
is:
V-21
17-25
© © V-39
13-25 '8
V-38
l3-2«
18
v-37
17-J4
18 V-36
17-20 (K)
18 V-35
17-20
18
V-34
16-20
V-20
17-2!
V-19
16-18
18
18;
V- 18
16-21
V-1 7
16-29
5HEC
:::.;y
15 V-45
17-20
18 V-44
16-19
V-43
16-19
:@©v
30
V-50
16-32
W. 18
181
16-22
life
':;.©::•:•: ONE STORY MODULAR
FRAME HOUSE
SEE DETAIL A
13-24
V-40
16-18
18
v-16
16-18
V-15
16-24
r—, ?
V- I 4
13-18
18
v-13
17-26
V-12
16-32
18
V-10
16-32
18
S
w <12> 36
V-8
18-32
18
V-7
18-21
V-6
18-19
18
18
18
V-5
21-35
18 ./
m
L
SCALE IN FEET
20 10 0 20 40
U:\fAS\OM\0003\Ry001 *8V 03/21/tt 2:l«»m TMT80
144
21-50 24-108
©•::© V-51
14-24 CRAWL SPACE
THIS DUW«C IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY ANO ITS CONTRACTORS. IT IS NOT A LANO SURVEY
PLAT, UTILITY LOCATION PLAT, OR OTHER IMPROVEMENT SURVEY
PLAT AND IS NOT TO SE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE. BUILOINC. OR OTHER FUTURE IMPROVEMENT LINES.
3 12 14 16 18 20
J !_
22 24 26 28 30 32 34 36 33
DETAIL A
NOT TO SCALE
©
rv:vi
12-15
12
v-i
16-17
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN jiR/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED OEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION AREA IDENTIFIER AND
EXCAVATION EXPOSURE —RATE RANGE
RAOON DECAY—PRODUCT CONCENTRATION
MEASUREMENT LOCATION
AREA WITH CONTAMINATION LEFT IN PLACE
RADIOLOGICAL AS-BUILT
FIGURE 2.1
INTERIOR AND EXTERIOR EXTENT OF CONTAMINATION
40
U.S. DEPARTMENT OF ENERGY
YES,
1. 464 SOUTH SECOND EAST ST.
MONTICELLO. UTAH
MKT Rust Q«et*ch US-00I4S-MR
— - 3-C00148-V1 „, 1
42 44 46 48 5(
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
464 SOUTH 2ND EAST STREET
MONTICELLO, UTAH (MS00148-MR)
A. R. Jones
August 1996
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 4
CONCLUSION 4
REFERENCES 7
iii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 5
2. Results of ORNL analysis of Geotech soil samples from 464 South 2nd East Street,
Monticello, Utah (MS00148-MR) 6
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site
Decommissioning Projects, U.S. Department of Energy. The author wishes to
acknowledge M. K. Jensen for analysis of soil samples and technical review and
N. F. Kirby for technical review.
vii
ABSTRACT
In 1980 the site of a vanadium and uranium mill at Monticello, Utah, was accepted
into the U.S. Department of Energy's (DOE's) Surplus Facilities Management Program,
with the objectives of restoring the government-owned mill site to safe levels of radio-
activity, disposing of or containing the tailings in an environmentally safe manner, and
performing remedial actions on off-site (vicinity) properties that had been contaminated
by radioactive material resulting from mill operations. During 1988 and 1995, RUST
Geotech, the remedial action contractor designated by DOE, performed remedial action on
the vicinity property at 464 South 2nd East Street, Monticello, Utah. The Environmental
Technology Section (ETS) of Oak Ridge National Laboratory was assigned the responsi-
bility of verifying the data supporting the adequacy of remedial action and confirming the
site's compliance with DOE guidelines. The ETS found that the site successfully meets the
DOE remedial action objectives. All deficiencies noted in the initial review have been re-
solved with the revised completion report. Procedures used by the ETS are described in
the Environmental Technology Section Procedures Manual (ORNL 1993).
ix
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 464 SOUTH 2ND EAST STREET
MONTICELLO, UTAH (MS00148-MR)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the U.S. government through the
Defense Plant Corporation to provide vanadium during World War II. Various govern-
ment agencies operated the mill until 1947. In 1948 the Atomic Energy Cornmission
(AEC) obtained the mill and operated it under contract through 1959 to provide both
uranium and vanadium. Mill operations were terminated on January 1, 1960. In 1961 the
mill tailings piles were leveled and graded, covered with rock and soil, and seeded with
native grasses. During 1974 and 1975, the ore stockpiles were removed from the site, and
the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city
of Monticello, in San Juan County, Utah. The site is bordered on the south and southeast
by land held by the U.S. Bureau of Land Management. Other boundaries are the city of
Monticello and private property.
During the AEC era, the mill processed approximately one million tons of uranium
ore. Vanadium and uranium were the only substances extracted in the milling process.
Other constituents of the ore remained in the tailings and were not separated prior to dis-
posal. During the years of active mill operation, the mill tailings were normally moist, so
erosion was minimal. However, throughout the mill's operating period, area residents
used these tailings as fill material and as aggregate in mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy
(DOE) initiated the Surplus Facilities Management Program (SFMP) in 1978 to ensure
the safe caretaking and decommissioning of government facilities that had been retired
from service but still had radioactive contamination. In 1980 the mill site at Monticello
was accepted into the SFMP, and the Monticello Remedial Action Project (MRAP) was
established to restore the govemment-ovvned mill site to safe levels of radioactivity, to
dispose of or contain the tailings in an environmentally safe manner, and to perform
remedial actions on off-site (vicinity) properties that had been contaminated by
radioactive material resulting from mill operations. The Monticello mill site and the
tailings remain in the custody of the DOE Grand Junction, Colorado, Projects Office. In
1983 remedial actions for vicinity properties were separated from MRAP with
establishment of the Monticello Vicinity Properties (MVP) Project (U.S. DOE 1990b).
*The verification of remedial action was performed by members of the Environmental Assessment Group in the
Environmental Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE
contract DE-AC05-96OR22464 with Lockheed Martin Energy Research Corporation.
2
During 1988 and 1995, RUST Geotech Inc. (Geotech), the remedial action contractor
(RAC) designated by DOE, performed remedial action on the vicinity property that is the
subject of this report, a single family residence located at 464 South 2nd East Street, Monti-
cello, Utah. The remedial action plan required excavation of all interior and exterior con-
tamination. When the excavation was completed, the property was resurveyed, including
soil sampling, to ensure the removal of all contamination, backfilled with uncontaminated
material, and restored to a condition comparable to that which existed prior to remedial
action (Geotech 1996).
The DOE adopted a policy to assign an independent contractor to verify the data
supporting the adequacy of remedial action and to confirm the site's compliance with DOE
guidelines. The Environmental Technology Section (ETS) of Oak Ridge National Labor-
atory (ORNL) has been assigned the responsibility of this task at the 464 South 2nd East
Street site. This report describes the methods and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available doc-
umentation adequately and accurately describes the post-remedial-action radiological
conditions of the entire property that is to be certified and (2) that the remedial action
reduced contamination to below applicable DOE guidelines (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1996) in-
dicates the property was remediated as evaluated by DOE on the basis of Environmental
Protection Agency standards and the DOE guidelines (DOE 1990a). Excess residual
radioactive materials were present, thus it was appropriate to designate this property for
remedial action.
The pre-remedial-action survey performed by Geotech identified 1828 yd3 of mill
tailings 6 to 39 inches deep. During the actual removal process, a total of 3449 yd3 of
contaminated earth and uranium mill tailings, 18 to 144 inches deep, were removed from
a 4645 m2 area.
A post-excavation survey was performed by Geotech prior to backfilling the exca-
vated areas. This survey consisted of gamma scans with a scintillometer of the ground
level of the structure, a surface scan of the exterior, and soil sampling. Samples repre-
sentative of the bottom 15-cm (6-in.) soil layers of 50 excavated verification areas were
collected and blended to form representative composite soil samples for each verification
area.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation
levels have not been subtracted. Similarly, background concentrations have not been sub-
tracted from radionuclide concentrations in soil samples. Applicable DOE guidelines for
protection against radiation are given in Table 1.
Gamma Measurements
Gamma exposure rate measurements taken by Geotech at the ground-level of the resi-
dence ranged from 13 to 24 uR/h. Gamma measurements from the remediated crawl space
ranged from 14 to 24 uR/h with anomalous gamma exposure rates of 21 to 108 uR/h
associated with contamination left in place to prevent structural damage.
Exterior surface gamma measurements taken from the excavated areas prior to
backfilling ranged from 15 to 35 uR/h. Three areas that are located in the right-of-way
adjacent to the property have contaminated utility lines. Gamma exposure rates range from
35 to 108 uR/h along these utility lines.
Soil Sample Analysis
Prior to backfilling, Geotech collected soil samples representative of the excavated
areas from the bottom 15-cm (6-in.) soil layers. These samples were blended to form a
composite soil sample representative of an average over the 50 exterior verification areas.
Geotech's analysis of these samples showed 226Ra concentrations ranging from 0.7 to 7.3
pCi/g in the composite samples. ORNL ETS obtained a percentage of these samples and
performed a confirmatory analysis which showed 226Ra concentrations ranging from 1.3 to
4.9 pCi/g. These values are below the EPA standard value of 15 pCi/g for soil layers >15
cm below the surface. Results of Geotech and ORNL soil sample analyses are given in
Table 2.
As a result of a meeting between the RAC and IVC on May 26, 1994, anomalous
readings, defined as > 30% above the average of the excavation, will be investigated to
show compliance to the DOE hot spot guideline. The RAC remediated this property
before this procedure change. The IVC observed that 22 of the areas exceed 30% of the
excavation average. The IVC will allow a correlation developed by the RAC to estimate
^Ra pCi/g concentrations based on gamma exposure rates. The highest anomalous read-
ing of 35 uR/h on this property using the RAC's correlation yields a 226Ra concentration
of 18.8 pCi/g. This value is well below the minimum concentration of 30 pCi/g needed,
when assuming the maximum area under the hot spot guideline of 25 m2, for subsurface
samples. Gamma ranges and/or soil sample results demonstrate compliance to the DOE
Hot Spot Guidelines for areas <25 m2 (Table 1).
4
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were deter-
mined by the Alpha-track method. To monitor radon levels, Geotech placed three alpha-
track detectors on the ground floor of the residence located on this property for a period
of approximately one year (from March 13, 1990 to March 11, 1991). The average an-
nual working level (WL) of radon progeny concentration, as determined by the Tech./-
Ops-Landauer Corporation, was 0.0083, which is well below the 0.03-WL guideline
given in Table 1.
CONCLUSION
Results of Geotech soil sample analysis and confirmatory split soil sample analysis
by ORNL show that radionuclide concentrations are within applicable DOE guidelines.
Based on the results of the post-remedial-action data, which are confirmed by the verifi-
cation assessment data, these radiological measurements fall below the limits prescribed
by DOE guidelines. All deficiencies noted in the initial review have been identified by
the RAC and corrected in the revised completion report as discussed in a meeting
between Geotech and ORNL on July 22, 1996. It is concluded that the site successfully
meets the DOE remedial action objectives.
5
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of 226Ra in soil
above background levels,
averaged over a 100-m2 area
5 pCi/g averaged over the
first 15 cm of soil below the
surface; 15 pCi/g when ave-
raged over 15-cm-thick soil
layers more than 15 cm
below the surface
Radionuclide con-
centrations in soil
for Hot Spot areas
Exposure to
progeny
2Rn
Maximum Permissible con-
centration of Ra226 in soil
above background level, for
areas less than 25 nr
Average annual radon proge-
ny concentration (including
background)
Ra226 concentrations, in any
surface or subsurface area
less than 25 nr, is below the
guideline by a factor of
(100/A)y', where A is the
area of the elevated region
0.03 WL
(DOE 1990a)
6
Table 2. Results of ORNL analysis of Geotech soil samples from
464 South 2nd East Street, Monticello, Utah (MS00148-MR)
ORNL
sample
No."
226Ra concentration (pCi/g)
Geotech
sample
No.*
Depth
(cm)
ORNL Geotech
X2
X4
X17
X21
X26
X33
X45
X49
X50
MNK 527
MNK 529
MNK 542
MNK 546
MNK 551
MNK 558
MNK 570
MNK 574
MNK 575
>15
>15
>15
>15
>15
>15
>15
>15
>15
2.5
4.9
2.6
1.6
1.5
4.1
1.3
1.5
2.3
4.8
2.2
1.7
1.5
4.3
1.5
3.3
1.3
° An X-type sample is a split of the sample taken by the remedial action contractor.
* Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated
areas were taken by Geotech, and these samples were blended to form a composite soil
sample, which represents an average over one of the verification areas.
7
REFERENCES
Geotech 1996. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00148-MR, Address: 464 South Second East Street,
Monticello, Utah 84535, Geotech, Grand Junction, Colorado, June 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
U.S. DOE 1990a. Verification and Certification Protocol for the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination
and Decommissioning Program, Revision 3, November 1990. U.S. Department of
Energy, Washington, D.C.
U.S. DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision
and Record of Decision Summary. U.S. Department of Energy, Grand Junction Projects
Office, Grand Junction, Colorado.
DOE ID No.: MS-00148-MR
Property Address: 464 South Second East Street
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech of Energy (DOE)
Ra-226 is < 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [ ]
Ra-226 is <; 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2.
In-situ [ ] Lab [X]
Interior gamma is <, 20 //R/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is < 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21.
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
IX] [ ] t 1
[*] I ] t 1
[X] [ ] [ ]
1*] [ ] [ ]
[ ] 01 [ ]
LY] [ ] [ 1
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
SFCERTIFED
SFMS-00148
DOE ID No.: MS-00148-MR
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
>y11 Date
ticello Programs
Wanda S. Busby
Manager, Monticello Programs
Rust Geotech
DOE EVALUATION
\A\ Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Certification Official
U.S. Department of Energy
Date
DOE JJD No.: MS-00149-RS
Property Address: 448 South Main Street
Vicinity Property Certification Summary and Recommendation
Summary Evaluation
Certification Criteria MACTEC-ERS
U.S. Department
of Energy (DOE)
Ra-226 is <. 5 pCi/g above background
in top 15-cm-thick layer of soil
averaged over 100 m2
In situ [X] Lab [ ]
Ra-226 is 5; 15 pCi/g above
background in any 15-cm-thick layer of
soil more than 15 cm below the
surface averaged over 100 m2.
In situ [ ]Lab[X]
Interior gamma is <. 20 pR/h above
background in any occupied or
habitable structure.
The radon decay-product
concentration in any occupied or
habitable structure is < 0.02 WL or, at
most, 0.03 WL.
Supplemental standards were applied
in accordance with EPA standard
40 CFR 192.21.
Hot spot criteria met as outlined by
DOE guidelines for FUSRAP (Rev.2,
March 1987)
Yes No Not Taken Yes No Not Taken
[X]a [ ]
[X] [ ]
[X] [ ]
[X] [ ]
I ] [X]
[X] [ ]
[ ]
[ ]
[ ]
[ ]
[ ]
[ ]
[tf [ ]
[XI [ ]
[ ]
[XT [ ] [ ]
[ ]
[ ]
[ 1
[ ]
"The excavations were backfilled with materials that were measured at the source indicating that the Ra-226
concentrations are in the range of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
llllllllll llllllIIHl
SFCERTIFED SFMS-09004
lof2
DOE ID No. : MS-00149-RS
MACTEC-ERS Recommendation
On the basis of the Property Completion Report evaluation, this property is recommended for
[X] Certification by DOE.
[ ] Certification by DOE with the concurrence ofthe U.S. Nuclear Regulatory Commission
because supplemental standards were applied according to 40 CFR 192.21.
tf Michael C. Butherus v Date
Manager, Monticello Programs
MACTEC-ERS
DOE Evaluation
On the basis of the Property Completion Report recommendation, this property
[V] Should be certified by DOE.
[ ] Should be certified by DOE with the concurrence of the U. S. Nuclear Regulatory
Commission because supplemental standards were applied according to 40 CFR 192.21.
Certification Official ' Date
U.S. Department of Energy
Work performed under DOE Contract No. DE-AC13-96GJ87335, Task Order No. 96-05.02.14
2 Of 2
> r
Monticello Vicinity Properties Project
Property Completion Report
for
Monticello
Vicinity Property Remedial Action
for
DOE DD No.: MS-00149-RS
Address: 448 South Main Street
Monticello, Utah 84535
November 1996
Prepared for
U.S. Department of Energy
Albuquerque Operations Office
Grand Junction Office
Prepared by
MACTEC-Environmental Restoration Services, LLC (MACTEC-ERS)*
Grand Junction, Colorado
Michael C. Butherus
Manager, Monticello Programs
Work performed under DOE Contract No. DE-AC 13-96GJ87335
Task Order No. 96-05.02.14
*MACTEC-ERS has been granted authorization to conduct remedial action by the U.S. Department of Energy.
Remedial action was done in accordance with the U.S. Environmental Protection Agency "Standards for Cleanup of
Land and Buildings Contaminated with Residual Radioactive Materials from Inactive Uranium Processing Sites,"
40 CFR 192, Subpart B; and "Implementation," in 40 CFR 192, Subpart C, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
DOE ID No.: MS-00149-RS
Contents
Page
1.0 Summary 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Remedial Action Summary 2
2.0 Operations Summary 3
2.1 Remedial Action Plan 3
2.2 Assessed and Remediated Contamination 3
3.0 Verification Summary 4
3.1 Radiological Survey Data 4
3.1.1 Preremedial Action Survey 4
3.1.2 Postexcavation Survey 4
3.1.3 Radon Decay-Product Concentration Measurements 4
3.2 Recommendation for Certification 5
Table
Table 1. Certification Data Summary 5
Appendix
Appendix A. Radiological Conditions A-1
IX)H Grand Junction Office
November IW6
MVP Property Completion Report
Page ii
DOE ID No.: MS-O0149-RS
1.0 Summary
1.1 Basis for Remedial Action
*
The Monticello Vicinity Properties (MVP) Project was established to reduce the potential hazard
to the public due to long-term exposure to low-level radioactivity associated with the offsite mill
tailings derived from the former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States Government through its agent,
the Defense Plant Corporation, to provide additional sources of vanadium needed during World
War II. Various government agencies operated the mill until 1947. The AEC obtained the mill in
1948 and operated it through 1959 under cost-type contracts to process both uranium and
vanadium ore. Mill operations were terminated on January 1, 1960.
The mill processed approximately one million tons of ore during the AEC operations. Throughout
the operating period, mill tailings from the Monticello millsite were removed from the site and
used for construction-related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for Remedial Actions at Inactive
Uranium Processing Sites" (40 CFR Part 192) for all cleanup activities under the MVP Project.
These standards were prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and open lands. Cleanup
activities also were conducted to meet the hot spot criteria established by radiological protection
guidelines in the DOE Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management Program Sites
(Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot spot criteria and
determined to contain mill tailings (radioactive material) exceeding EPA standards and/or DOE
hot spot criteria. The Remedial Action Contractor was notified of the inclusion of this property
into the MVP Project and was authorized by DOE to conduct remedial action as required to bring
the property into conformance with EPA standards and DOE hot spot criteria.
IX)l-/Grand Junction Office
November 1996
MVP Property Completion Report
Page I
.3 Remedial Action Summary
DOE ID No.:
Legal Description:
Property Address:
Property Owners:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological and Engineering Assessment (REA):
Construction Subcontractor:
Preconstruction Conference Record:
Notice of Final Completion Inspection:
Volume of Material Removed in Cubic Yards (yd3):
Area Cleaned Up in Square Meters (m2):
Property Completion Report Submitted:
DOE ID No.: MS-00149-RS
MS-00149-RS
Beginning at the NE corner of Lot 1,
Block 4, Monticello Townsite Survey
Plat A; south 93 feet, west 214.5 feet,
north 93 feet, east 214.5 feet to
beginning, County of San Juan, State
ofUtah
448 South Main Street
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
Grand Junction Office
June 19, 1990
MACTEC-ERS
November 28, 1994
Diamond Back Services, Inc.
August 22, 1995
September 20, 1995
Exterior: 4
Interior: 0
18
November 1996
IX)Ii/Orand Junction OtHce
November 1996
MW Property Completion Report
Page 2
DOE ID No.: MS-00149-RS
2.0 Operations Summary
2.1 Remedial Action Plan
The remedial action plan specified removal of radioactive material. Once excavation was
completed, the affected areas were resurveyed for possible remaining radioactive material and,
upon attaining satisfactory results, were backfilled with uncontaminated material. The property
was restored to a physical condition comparable to that which existed before remedial action
activities.
2.2 Assessed and Remediated Contamination
The radiological assessment identified contamination, ranging from 6 to 12 inches (in.) deep,
within the property boundary. The quantity of contamination for this property was not specified
because it was assessed as part of Block MS-09004-BK. The remedial action process included
removal of approximately 4 yd3 of radioactive material, ranging from 6 to 30 in. deep. The areas
of assessed and excavated contamination are shown on Figure A-1.
DOli/Grand Junction Office
November 1996
MVP Property Completion Report
Page 3
DOE ID No.: MS-00149-RS
3.0 Verification Summary
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Preremedial Action Survey
The Remedial Action Contractor conducted a radiological survey during December 1991, as
described in the final REA. Figure A-1 shows the extent of assessed contamination and identifies
the areas recommended for remedial action.
3.1.2 Postexcavation Survey
A scintillometer was used to perform a surface gamma scan after the removal of radioactive
material and before backfilling. Following the gamma scan, soil samples representative of the
6-in.-thick soil layer at the bottom of the excavation were collected. These samples, representing
the verification area, were analyzed for radium-226. The results of the gamma scans and soil
sample analyses are presented in Table A-1.
3.1.3 Radon Decay-Product Concentration Measurements
Radon decay-product concentration (RDC) measurements were taken on the lowest habitable
level ofthe house, as shown on Figure A-1. The measurement results are presented in Table A-2.
DOU/Orand Junction Oflicc
November 1996
MVP Property Completion Report
Page 4
DOE ID No.: MS-00149-RS
3.2 Recommendation for Certification
Radioactive materials have been removed from this property to the extent required by EPA
standards (40 CFR 192, Subparts B and C) and DOE hot spot criteria, as indicated in the
Certification Data Summary (Table 1). Therefore, the property located at 448 South Main Street,
in Monticello, Utah, is recommended for certification as required by DOE guidelines.
Table 1. Certification Data Summary
Applicability Standard Survey Results
Radium-226
Concentration in
Surface Soil
Radium-226
Concentration in
Subsurface Soil
Exposure Rate
Land
Shall not exceed 5 pCi/g above
background3 in the 15-cm-thick
surface layer, averaged over
100 m2.
Shall not exceed 15 pCi/g
above background3 in any
15-cm-thick soil layer more than
15 cm below the surface,
averaged over 100 m2.
Habitable Structures
< 5 pCi/g above background on the
basis of gamma exposure rates that do
not exceed 30 percent above normal
background."
Soil sample result was 2.4 pCi/g.b
Shall not exceed 20 uR/h above
background.0
Range for the ground floor was 11 to
13pR/h.
Radon Decay-
Product
Concentration
Annual average shall not
exceed 0.02 WL, to the extent
practicable, and shall in no
case exceed 0.03 WL.
Average was 0.0017 WL, on the basis
of the DOE-approved abbreviated-
measurement method.
Key: cm = centimeters; m* = square meters; pCi/g = picocuries per gram; uR/h = microroentgens per hour;
WL = working level
"The background radium-226 concentration for Monticello Vicinity Properties is approximately 2.0 pCi/g.
The hot spot criteria were met based on gamma scans and/or soil sample results.
cThe background exposure rate for this property is approximately 13 uR/h.
IX)K/Grand Junction Office
November 1996
MVP Property Completion Report
Page 5
DOE ID No.: MS-00149-RS
Appendix A
Radiological Conditions
Table A-1. Postexcavation Survey Results
Table A-2. Radon Decay-Product Concentration Measurement Results
Figure A-1 Radiological As-Built
DOE ID No.. MS-00149-RS
Table A-1. Postexcavation Survey Results
Gamma Radium-226
Verification Exposure Rate Soil Sample Measurement Concentration
Area' Range (pR/h) Ticket No. Method (pCi/g)
V-1 14-18 NCL 788 OCS 2.4
Key: OCS = opposed crystal system; pCi/g = picocuries per gram; uR/h = microroentgens per hour;
V = verification area
"See Figure A-1 for location of verification area.
DOIi/Grand Junction Office
November 13, 19%
MVP Property Completion Report
Page A 2
DOE ID No.: MS-O0149-RS
Table A-2. Radon Decay-Product Concentration Measurement Results*
Detector"
Number Start Date End Date
Radon
Concentration
(pCi/L) WL
3964348
3964309
3964222
03-01-95
03-01-95
03-01-95
05-31-95
05-31-95
05-31-95
0.33
0.33
0.33
Average:
0.0017
0.0017
0.0017
0.0017
Key: pCi/L = picocuries per liter; WL = working level
aSee Figure A-1 for measurement location.
"Terradex Radtrak Detector.
DOE/Grand Junction Office
February 12,1997
MVP Property Completion Report
Page A-3
I u
30
28
26
24
22
20
18
16
14 -
12
14 16 18 20 22 24 26 28 30 32
T
34 36 38
OOO O O
0 V-1 12
12-16
-h SHED
11-13
UJ
Lu
or SHED
13-14
RDC ROOT CELLAR
15-16
co TRAILER HOUSE W/
FRAME ADDITIONS <
11-13 1 x o r o CO J V-1
0 o
V-1
12-16
30(6X A
©
©
v7.v7l
Lv.vj
12-15
Y NORTH
12
V-10
SHED
L£G£ND
ALL DEPTHS/HEIGHTS IN INCHES
ALL EXPOSURE RATES IN /iR/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION AREA IDENTIFIER
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT, UTILITY LOCATION PLAT, OR OTHER IMPROVEMENT SURVEY
PLAT AND IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE, BUILDING, OR OTHER FUTURE IMPROVEMENT LINES.
(RDC) RADON DECAY-PRODUCT CONCENTRATION
MEASUREMENT LOCATION
M:\FAS\033\0003\RM001 49V
— X
11/13/96 1:41pm S5073O 20 10
SCALE IN FEET
20 40
10
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION OFFICE. COLORADO
•MJK! UUMM
448 SOUTH MAIN STREET
MONTICELLO, UTAH
40
30
28
26
24
22
20
18
16
1 4
COMPLETION REPORTS
—s»ir—
MONTICELLO VICINITY PROPERTIES
12
FIGURE A-1
RADIOLOGICAL AS-BUILT
MS-00149-RS
10 12 1 4 16 18 20 22 24 26 28 30 32 34
3-B00149-V1
36
1 1
10
38 40
OAK RIDGE NATIONAL LABORATORY
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
FOR THE U.S. DEPARTMENT OF ENERGY
PHONE: (970) 248-€200
FAX: [phone]
2587 BVJ Road
GRAND JUNCTION. COLORADO 81503 ftB 28 mi
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella.
Radiation levels at the property identified below do not exceed the guidelines specified by the U.S.
Department of Energy for Residual Radioactive Material at Formerly Utilized Sites Remedial Action
Program (FUSRAP) and Remote Surplus Facilities Management Program Sites (SFMP) [Revision
2, March 1987]. This evaluation is based on an independent verification review of the Remedial
Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment of the 226Ra
concentration in the soil, indoor radon daughter concentration, and indoor gamma exposure rates at
this property.
This property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
Location Number: MS00149-RS
Location Address: 448 South Main Street
Monticello. Utah 84535
Property Owner:

Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
448 SOUTH MAIN STREET
MONTICELLO, UTAH (MS00149-RS)
M. K. Jenson
February 1997
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81503
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 4
REFERENCES 7
iii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 5
2. Results of ORNL analysis of the RAC soil samples from 448 South Main Street,
Monticello, Utah (MS00149-RS) 6
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site Decommissioning
Projects, U.S. Department of Energy. The author wishes to acknowledge A.J. Jones and P.D.
Roundtree for technical reviews.
vii
ABSTRACT
In 1980, the site of a vanadium and uranium mill at Monticello, Utah, was accepted into the
U.S. Department of Energy (DOE) Surplus Facilities Management Program, with the objectives of
restoring the government-owned mill site to safe levels of radioactivity, disposing of or containing
the tailings in an environmentally safe manner, and performing remedial actions on off-site (vicinity)
properties that had been contaminated by radioactive material resulting from mill operations. During
1995, the Remedial Action Contractor (RAC) designated by DOE, performed remedial action on the
vicinity property at 448 South Main Street, Monticello, Utah. The Environmental Technology
Section (ETS) of Oak Ridge National Laboratory was assigned the responsibility of verifying the
data supporting the adequacy of remedial action and confirming the site's compliance with DOE
guidelines. The ETS found that the site successfully meets the DOE remedial action objectives.
Procedures used by the ETS are described in the Environmental Technology Section Procedures
Manual (ORNL 1993).
ix
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 448 SOUTH MAIN STREET
MONTICELLO, UTAH (MS00149-RS)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the United States (U.S.) government through
the Defense Plant Corporation to provide vanadium during World War II. Various government
agencies operated the mill until 1947. In 1948, the Atomic Energy Commission (AEC) obtained the
mill and operated it under contract through 1959 to provide both uranium and vanadium. Mill
operations were terminated on January 1, 1960. In 1961, the mill tailings piles were leveled and
graded, covered with rock and soil, and seeded with native grasses. During 1974 and 1975, the ore
stockpiles were removed from the site and the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city of
Monticello, in San Juan County, Utah. The site is bordered on the south and southeast by land held
by the U.S. Bureau of Land Management. Other boundaries are the city of Monticello and private
property.
During the AEC era, the mill processed approximately one million tons of uranium ore. Vana-
dium and uranium were the only substances extracted in the milling process. Other constituents of
the ore remained in the tailings and were not separated prior to disposal. During the years of active
mill operation, the mill tailings were normally moist, so erosion was minimal. However, throughout
the mill's operating period, area residents used these tailings as fill material and as aggregate in
mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy (DOE) initiated
the Surplus Facilities Management Program (SFMP) in 1978 to ensure the safe caretaking and de-
commissioning of government facilities that had been retired from service but still had radioactive
contamination. In 1980, the mill site at Monticello was accepted into the SFMP, and the Monticello
Remedial Action Project (MRAP) was established to restore the government-owned mill site to safe
levels of radioactivity, to dispose of or contain the tailings in an environmentally safe manner, and
to perform remedial actions on off-site (vicinity) properties that had been contaminated by radio-
active material resulting from mill operations. The Monticello mill site and the tailings remain in
the custody of the DOE Grand Junction, Colorado, Projects Office. In 1983, remedial actions for
vicinity properties were separated from MRAP with establishment of the Monticello Vicinity Proper-
ties (MVP) Project (US DOE 1990b).
*The verification of remedial action was performed by members of the Environmental Assessment Group in the Environmental
Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE contract DE-AC05-
960R22464 with Lockheed Martin Energy Research Corporation.
2
During 1995, the Remedial Action Contractor (RAC) designated by DOE, performed remedial
action on the vicinity property that is the subject of this report, a single family residence located at
448 South Main Street, Monticello, Utah. The remedial action plan required excavation of all
exterior contamination. When the excavation was completed, the property was resurveyed, including
soil sampling, to ensure the removal of all contamination, backfilled with uncontaminated material,
and restored to a condition comparable to that which existed prior to remedial action (MACTEC
1996).
DOE adopted a policy to assign an independent contractor to verify the data supporting the
adequacy of remedial action and to confirm the site's compliance with DOE guidelines. The
Environmental Technology Section (ETS) of Oak Ridge National Laboratory (ORNL) has been
assigned the responsibility of this task at the 448 South Main Street site. This report describes the
methods and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available documentation
adequately and accurately describes the post-remedial-action radiological conditions of the entire
property that is to be certified and (2) that the remedial action reduced contamination to below
applicable DOE guidelines (US DOE 1990a).
Document Reviews
Review of the RAC property completion report (MACTEC-ERS 1996) indicates the property
was remediated as evaluated by DOE on the basis of U.S. Environmental Protection Agency
standards and the DOE guidelines (US DOE 1990a). Excess residual radioactive materials were
present, thus it was appropriate to designate this property for remedial action.
This property was assessed as part of Block 4, therefore, the quantity of material assessed is not
available. During the actual removal process, a total of 4 yd3 of contaminated earth and residual
radioactive material, 6 to 30 inches deep, were removed from a 18 m2 area.
The RAC performed a post-excavation survey prior to backfilling the excavated areas. This
survey consisted of gamma scans with a scintillometer of the ground level of the structure, a surface
scan of the exterior, and soil sampling. Samples representative of the bottom 15-cm (6-in.) soil
layers of one excavated verification area were collected and blended to form a representative
composite soil sample.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation levels have
not been subtracted. Similarly, background concentrations have not been subtracted from radionu-
clide concentrations in soil samples. Applicable DOE guidelines for protection against radiation are
given in Table 1.
Gamma Measurements
Gamma exposure rate measurements taken by the RAC at the ground-level of the residence
ranged from 11 to 13 uR/h. Exterior surface gamma measurements taken from the excavated areas
prior to backfilling ranged from 14 to 18 uR/h.
Soil Sample Analysis
Prior to backfilling, the RAC collected soil samples representative of the excavated areas from
the bottom 15-cm (6-in.) soil layers. These samples were blended to form a composite soil sample
representative of an average over the exterior verification area. The RAC's analysis of this sample
showed a 226Ra concentration of 2.4 pCi/g. ORNL ETS obtained this sample and performed a
confirmatory analysis which showed a 226Ra concentration of 1.8 pCi/g. These values are below the
DOE guideline value of 15 pCi/g for soil layers > 15 cm below the surface. Results of the RAC and
ORNL soil sample analyses are given in Table 2.
As a result of a meeting between the RAC and IVC on May 26, 1994, anomalous readings,
defined as > 30% above the average of the excavation, will be investigated to show compliance to
the DOE hot spot guideline. This property was remediated after this procedure change. The IVC
observed that 18 uR/h exceeds 30% of the excavation average of 16 uR/h. The IVC will allow a
correlation developed by the RAC to estimate 226Ra pCi/g concentrations based on gamma exposure
rates. The anomalous reading of 18 uR/h on this property using the RAC's correlation yields a 226Ra
concentration of 2.7 pCi/g. This value is well below the minimum concentration of 30 pCi/g needed,
when assuming the maximum area under the hot spot guideline of 25 m2, for subsurface samples.
Gamma ranges and/or soil sample results demonstrate compliance to the DOE Hot Spot Guidelines
for areas <25 m2 (Table 1).
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were determined before
remedial action by the Alpha-track method. To monitor radon levels, the RAC placed three alpha-
track detectors on the ground floor of the residence located on this property for a period of
approximately three months (from March 1, 1995 to May 31,1995). The average annual working
level (WL) of radon progeny concentration, as determined by the Tech./Ops-Landauer Corporation,
was 0.0017, which is well below the 0.03-WL guideline given in Table 1.
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00152-VL
ADDRESS: PARCEL NO. A00150000760
CEDAR LANE
MONTICELLO, UTAH 84535
FEBRUARY 1996
Prepared for
U.S. Department of Energy
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
by
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
Manager, Monticello Programs
r
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action .' 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
i
DOE ID No.: MS-00152-VL
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Remedial Action Contractor. DOE reviewed these
evaluation results and determined that the property contained mill tailings
(residual radioactive material) exceeding EPA standards and DOE hot spot
criteria. The Remedial Action Contractor was notified of the inclusion of
this property into the MVP Project and was authorized by DOE to conduct
remedial action as required to bring the property into conformance with
EPA standards and DOE hot spot criteria.
1
DOE ID No.: MS-00152-VL
1.3 - Summary of Remedial Action
DOE ID No.:
Legal Description:
Property Address:
Property Owner:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
MS-00152-VL
Lot 76, less the south 5 feet, Blue
Mountain Heights No. 3 Subdivision,
Monticello Townsite Addition, County of
San Juan, State of Utah
Parcel No. A00150000760
Cedar Lane
Monticello, Utah 84535

Vacant Lot (VL)
Not applicable: inclusion requested by the
Remedial Action Contractor
May 20, 1994
Rust Geotech
July 22, 1994
Diamond Back Services, Inc.
9861 Titan Park Circle
Littleton, Colorado
May 9, 1995
July 13, 1995
Interior:
Exterior:
0 cubic yards
3 cubic yards
14 square meters (m2)
February 1996
2
DOE ID No.: MS-00152-VL
2.0 OPERATIONS SUMMARY ~
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of exterior residual radioactive
material (Appendix Figure 2.1). Once excavation was complete, the
affected areas were resurveyed for possible remaining residual radioactive
material and, upon attaining satisfactory results, were backfilled with
uncontaminated material. The property was restored to a physical
condition comparable to that which existed prior to remedial action
activities.
2.2 Previously Unidentified Contamination
The radiological assessment identified 3 cubic yards of contamination,
6 inches deep, within the property, within the property. The remedial
action process included the removal of approximately 3 cubic yards of
residual radioactive material, ranging from 6 to 12 inches deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID No.: MS-00152-VL
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by the Remedial Action
Contractor during August 1993, as described in the final REA
dated July 1994. Appendix Figure 2.1 shows the extent of
assessed contamination and identifies the areas recommended to
undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the excavation were
collected. These samples were blended to form a composite
sample representing the verification area (Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 13 to 17 microroentgens per
hour (/vR/h), as indicated on Appendix Figure 2.1. The result of
analysis for radium-226 in one composite soil sample was
1.9 picocuries per gram (pCi/g), as indicated in Appendix
Table 3.1.
4
DOE ID No.: MS-00152-VL
3.2 Recommendation for Certification ~~ v"" * *
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at Parcel No. A00150000760, Cedar
Lane, in Monticello, Utah, is recommended for certification as required
by DOE guidelines, and the appropriate records should be documented.
Certification Data Summary
Applicability Standards Survey Results
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Shall not exceed 20 //R/h
above background.
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Not applicable: vacant
lot.
Not applicable: vacant
lot.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background* in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background* in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
< 5 pCi/g above
background.
Soil sample result was
1.9 pCi/g.f
*The background radium-226 concentration is approximately 2.0 pCi/g.
The hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-00152-VL
4.0 APPENDIX
Appendix Table:
Table 3.1 Post-Excavation Sample/Measurement Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
MRW: 10-04-95
MS-00152.VL WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00152-VL
Address: Parcel No. A00150000760, Cedar Lane, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (pR/h) Ticket No. Method" (pCi/g)
V-1 15-17 NCJ 018 OCS 1.9
See Appendix Figure 2.1 for the verification area.
"OCS = Opposed Crystal System
7
10
J>0
28
26
24 -
22
20
18
1 6
1 4
1 2
Y
10
12 1 4 1 6 18 20
T
22 24 26 28
13-14
\
< \ 13-14
\
\ 7.
\
\
v-1
15-17
V-1
B X 6 13-14 15-17
7—7
12
SCALE IN FEET^
20 10 0 20 40
^ M:\FAS\033\0O03\RMO0152V 10/09/95 07:50am T50780
NORTH
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT. UTILITY LOCATION PLAT. OR OTHER IMPROVEMENT SURVEY
PLAT AND IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE. 8UILDING. OR OTHER FUTURE IMPROVEMENT LINES.
30
~T~
©
f77.-"vl
12-15
1 2
v-i
16-17
32 34 36 38
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN fj.R/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE-RATE RANGE
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
40
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
RESIOENCE-NO. Of OCCUPANTS
NON-RCSIOCNCE-WAN-HRS./WK.
INSTRUUENT NO.
BT CK. A.t. APP tr CK. A.C. APP.
\
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE. COLORADO
10 -Is
PARCEL NO. A00150000760
CEDAR LANE
MONTICELLO, UTAH
RLKT Rust Qeotech
OA:E APPROVAL OOE
OOE UNO. MS-001 52-VL
0.C.N0. 3-BOO 152-VI S„T 1 „, 1
30
28
26
24
22
20
18
1 6
1 4
1 2
1 0
1 A 1 B 1 8 20 22 24 26 28 30 32 34 36 38 40
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
PARCEL NO. A00150000760, CEDAR LANE
MONTICELLO, UTAH (MS00152-VL)
J. R. Sauvage
May 1996
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT... ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 3
REFERENCES 5
iii
LIST OF TABLES
Applicable guidelines for protection against radiation
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site
Decommissioning Projects, U.S. Department of Energy. The author wishes to
acknowledge M. K. Jensen and N. F. Kirby for technical reviews.
vii
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
PARCEL NO. A00150000760, CEDAR LANE
MONTICELLO, UTAH (MS00152-VL)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the U.S. government through the
Defense Plant Corporation to provide vanadium during World War II. Various govern-
ment agencies operated the mill until 1947. In 1948 the Atomic Energy Commission
(AEC) obtained the mill and operated it under contract through 1959 to provide both
uranium and vanadium. Mill operations were terminated on January 1, 1960. In 1961 the
mill tailings piles were leveled and graded, covered with rock and soil, and seeded with
native grasses. During 1974 and 1975, the pre stockpiles were removed from the site, and
the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city
of Monticello, in San Juan County, Utah. The site is bordered on the south and southeast
by land held by the U.S. Bureau of Land Management. Other boundaries are the city of
Monticello and private property.
During the AEC era, the mill processed approximately one million tons of uranium
ore. Vanadium and uranium were the only substances extracted in the milling process.
Other constituents of the ore remained in the tailings and were not separated prior to dis-
posal. During the years of active mill operation, the mill tailings were normally moist, so
erosion was minimal. However, throughout the mill's operating period, area residents
used these tailings as fill material and as aggregate in mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy
(DOE) initiated the Surplus Facilities Management Program (SFMP) in 1978 to ensure
the safe caretaking and decommissioning of government facilities that had been retired
from service but still had radioactive contamination. In 1980 the mill site at Monticello
was accepted into the SFMP, and the Monticello Remedial Action Project (MRAP) was
established to restore the government-owned mill site to safe levels of radioactivity, to
dispose of or contain the tailings in an environmentally safe manner, and to perform
remedial actions on off-site (vicinity) properties that had been contaminated by
radioactive material resulting from mill operations. The Monticello mill site and the
tailings remain in the custody of the DOE Grand Junction, Colorado, Projects Office. In
1983 remedial actions for vicinity properties were separated from MRAP with
establishment of the Monticello Vicinity Properties (MVP) Project (U.S. DOE 1990b).
•The verification of remedial action was performed by members of the Environmental Assessment Group in the
Environmental Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE
contract DE-AC05-96OR22464 with Lockheed Martin Energy Research Corporation.
2
During 1995, RUST Geotech Inc. (Geotech), the remedial action contractor (RAC)
designated by DOE, performed remedial action on the vicinity property that is the subject
of this report, a vacant lot located at Parcel No. A00150000760, Cedar Lane, Monticello,
Utah. The remedial action plan required excavation of all exterior contamination. When
the excavation was completed, the property was resurveyed, including soil sampling, to
ensure the removal of all contamination, backfilled with uncontaminated material, and re-
stored to a condition comparable to that which existed prior to remedial action (Geotech
1996).
The DOE adopted a policy to assign an independent contractor to verify the data
supporting the adequacy of remedial action and to confirm the site's compliance with
DOE guidelines. The Environmental Technology Section (ETS) of Oak Ridge National
Laboratory (ORNL) has been assigned the responsibility of this task at Parcel No.
A00150000760, Cedar Lane site. This report describes the methods and results of that
verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available docu-
mentation adequately and accurately describes the post-remedial-action radiological
conditions of the entire property that is to be certified and (2) that the remedial action
reduced contamination to below applicable DOE guidelines (DOE 1990a).
Document Reviews
Review ofthe property completion report prepared by Geotech (Geotech 1996) in-
dicates the property was remediated as evaluated by DOE on the basis of Environmental
Protection Agency standards and the DOE guidelines (DOE 1990a). Excess residual
radioactive materials were present, thus it was appropriate to designate this property for
remedial action.
The pre-remedial-action survey performed by Geotech identified 3 yd3 of mill
tailings 6 inches deep. During the actual removal process, a total of 3 yd3 of contaminat-
ed earth and uranium mill tailings, 6 to 12 inches deep, was removed from a 14 m2 area.
A post-excavation survey was performed by Geotech prior to backfilling the exca-
vated area. This survey consisted of gamma scans with a scintillometer of the exterior
and soil sampling. Samples representative of the bottom 15-cm (6-in.) soil layers of the
excavated verification area were collected and blended to form a representative composite
soil sample. The RAC is unable to locate or inadvertently disposed of the sample
requested for ORNL confirmatory analysis.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation
levels have not been subtracted. Similarly, background concentrations have not been sub-
tracted from radionuclide concentrations in soil samples. Applicable DOE guidelines for
protection against radiation are given in Table 1.
Gamma Measurements
Gamma exposure rate measurements taken of the exterior surface by Geotech from
the excavated areas prior to backfilling ranged from 15 to 17 uR/h.
Soil Sample Analysis
Prior to backfilling, Geotech collected soil samples representative of the excavated
areas from the bottom 15-cm (6-in.) soil layers. These samples were blended to form a
composite soil sample representative of an average over the exterior verification area.
Geotech's analysis of this sample showed a 226Ra concentration of 1.9 pCi/g in the com-
posite sample. ORNL ETS was unable to obtain samples for confirmatory analysis. This
value is below the EPA standard value of 15 pCi/g for soil layers > 15 cm below the
surface. Gamma ranges and/or soil sample results demonstrate compliance to the DOE
Hot Spot Guidelines for areas <25 m2 (Table 1).
Radon Measurement Results
Radon measurements were not taken at this property. It is a vacant lot.
CONCLUSION
Results of Geotech soil sample analysis show that radionuclide concentrations are
within applicable DOE guidelines. Based upon the results of the post-remedial-action
data, which are confirmed by the verification assessment data, these radiological
measurements fall below the limits prescribed by DOE guidelines. It is concluded that
the site successfully meets the DOE remedial action objectives.
4
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of 226Ra in soil
above background levels,
averaged over a 100-m2 area
5 pCi/g averaged over the
first 15 cm of soil below the
surface; 15 pCi/g when ave-
raged over 15-cm-thick soil
layers more than 15 cm
below the surface
Radionuclide
concentrations in soil
for Hot Spot areas
Maximum Permissible
concentration of Ra226 in soil
above background level, for
areas less than 25 m2
Ra226 concentrations, in any
surface or subsurface area
less than 25 m2, is below the
guideline by a factor of
(100/A)'71, where A is the
area of the elevated region
Exposure to 222Rn
progeny
Average annual radon proge-
ny concentration (including
background)
0.03 WL
(DOE 1990a)
REFERENCES
Geotech 1996. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00152-VL, Address: Parcel No. A00150000760, Cedar
Lane, Monticello, Utah 84535, Geotech, Grand Junction, Colorado, February 1996.
ORNL 1993. Environmental Technology Section (Formerly PoUutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
U.S. DOE 1990a. Verification and Certification Protocol for the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination
and Decommissioning Program, Revision 3, November 1990. U.S. Department of
Energy, Washington, D.C.
U.S. DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision
and Record of Decision Summary. U.S. Department of Energy, Grand Junction Projects
Office, Grand Junction, Colorado.
DOE ID No.: MS-00152-VL
Property Address: Parcel No. A00150000760, Cedar Lane
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech of Energy (DOE)
Ra-226 is ^ 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [ ]
Ra-226 is <. 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2.
In-situ [ ] Lab [X]
Interior gamma is £ 20 //R/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is * 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21.
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[ ] [ ] [X]
(Vacant Lot)
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
[ ] [ ] [ 1
[ ] [ ]
[ ] [ 1
[ ]
[ ]
[ ] [ ] [X] [ ] [ ] [ ]
(Vacant Lot)
[ ] [ ] [ I
[ ] [ ] [ ]
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
SFCERTIFED SFMS 00152
DOE ID No.: MS-00152-VL
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
tenda S'/Busby Date
Manager, Monticello Programs
Rust Geotech
DOE EVALUATION
[/] Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
/Z-JJ 1\>
Date Certification Official
U.S. Department of Energy
DOE ID No.: MS-00169-RS
Property Address: 417 North Creek Lane
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust nentenh nf Fnergy (DOE)
YES NO NOT TAKEN YES NO NOT TAKEN
Ra-226 is ^ 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [ ]
[X]* [ ] [ ] [>d [ ] [ ]
Ra-226 is * 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2. [ ]
In-situ [ ] Lab [ ]
Interior gamma is < 20 yt/R/h
above background in any
occupied or habitable
structure. [X]
The radon decay-product
concentration in any
occupied or habitable
structure is < 0.02
working level or, at
most, 0.03 working level. [X]
I ] [X]* [ ] [ ] [>3
[ ] [ ] [X] [ ] [ ]
[ ] [ ] [VI U t I
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21. [ ] [X] [ ] [ ] [>J [ ]
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987). [X] [ ] [ ] [y] I ] I )
COMMENTS: * Exterior areas were verified on the basis of gamma exposure rates
that do not exceed 30 percent above normal background.
»
DOE ID No.: MS-00169-RS
RUST GEOTECH RECOMMENDATION
On the basis of the Property Completion Report evaluation, this property is
recommended for
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Michael C. Butherus Date
Manager, Monticello Programs
MACTEC-ERS
DOE EVALUATION
[/<] Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Certification Official Date
U.S. Department of Energy
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00169-RS
ADDRESS: 417 NORTH CREEK LANE
MONTICELLO, UTAH 84535
FEBRUARY 1996
Prepared for
U.S. Department of Energy
by
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
' Wandii S. Busby
Manager, Monticello Programs
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
SFOCPLRPTS SFMS-00169
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY . . . 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.1.3 Radon Decay-Product Concentration (RDC) Measurement .... 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
i
DOE ID No.: MS-00169-RS
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Remedial Action Contractor. DOE reviewed these
evaluation results and determined that the property contained mill tailings
(residual radioactive material) exceeding EPA standards. The Remedial
Action Contractor was notified of the inclusion of this property into the
MVP Project and was authorized by DOE to conduct remedial action as
required to bring the property into conformance with EPA standards and
DOE hot spot criteria.
1
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
Property Address:
Property Owners:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
DOE ID No.: MS-00169-RS
MS-00169-RS
Lot 2, Mountain West Subdivision, City of
Monticello, County of San Juan, State of
Utah
417 North Creek Lane
Monticello, Utah 84535

Residential Simple (RS)
Not applicable: spillover inclusion requested
by the Remedial Action Contractor
November 6, 1992
Rust Geotech
June 23, 1994
Diamond Back Services, Inc.
9861 Titan Park Circle
Littleton, Colorado
July 11, 1995
July 12, 1995
Interior: 0 cubic yards
Exterior: 1 cubic yard
1 square meter (m2)
February 1996
2
DOE ID No.: MS-00169-RS
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of exterior residual radioactive
material (Appendix Figure 2.1). Once excavation was complete, the
affected areas were resurveyed for possible remaining residual radioactive
material. The property was restored to a physical condition comparable to
that which existed prior to remedial action activities.
2.2 Previously Unidentified Contamination
The radiological assessment identified 1 cubic yard of contamination,
48 inches high, within the property. The remedial action process included
the removal of approximately 1 cubic yard of residual radioactive material,
48 inches high.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID No.: MS-00169-RS
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by the Remedial Action
Contractor during August 1993, as described in the final REA
dated June 1994. Appendix Figure 2.1 shows the extent of
assessed contamination and identifies the areas recommended to
undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material. Following the gamma
scan, in-situ measurements were taken for Area V-1 (Appendix
Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 12 to 15 //R/h (Appendix
Figure 2.1). The results of two in-situ measurements for
radium-226 were less than 1.0 picocuries per gram (pCi/g), as
indicated in Appendix Table 3.1.
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on the DOE-approved abbreviated-measurement method,
the RDC was 0.0070 working level (WL), as indicated in
Appendix Table 3.2. Appendix Figure 2.1 shows the measurement
location on the ground floor (the lowest habitable level of the
structure). The partial basement was uninhabitable. RDC
measurements were taken before remediation of the property.
4
DOE ID No.: MS-00169-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at 417 North Creek Lane, in Monticello,
Utah, is recommended for certification as required by DOE guidelines,
and the appropriate records should be documented.
Certification Data Summary
Applicability
Habitable Structures
Exposure Rate:
Standards
Shall not exceed 20 //R/h
above background.*
Survey Results
Range was 10 to
13 //R/h for the ground
floor. The basement was
uninhabitable.
Radon Decay-Product
Concentration:
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Average was 0.0070 WL,
based on the DOE-
approved abbreviated-
measurement method.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
In-situ measurement
results were
< 1.0 pCi/g.**
< 15 pCi/g above
background.**
*The background exposure rate is approximately 14//R/h.
The background radium-226 concentration is approximately 2.0 pCi/g.
**The hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-00169-RS
4.0 APPENDIX
Appendix Tables:
Table 3.1 Post-Excavation Sample/Measurement Results
Table 3.2 Radon Decay-Product Concentration Measurement
Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
MRW: 10-10-95
MS-00169.RS WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00169-RS
Address: 417 North Creek Lane, Monticello, Utah
Meas.
Loc. Grid Meas. Depth Radium-226
Coord. Method" (inches) (pCi/g)
152252 DS 00 < 1.0
168252 DS 00 < 1.0
"DS = Delta Scanner
7
Table 3.2
Radon Decay-Product Concentration Measurement Results
DOE ID No.: MS-00169-RS
Address: 417 North Creek Lane, Monticello, Utah
Instrument Type: Landauer Radtrak Detector
Radon
Detector Tracks Per Concentration Working
Number Start Date End Date mm2 (pCi/L) Level
3964295 03-06-95 06-05-95
3964174 03-06-95 06-05-95
3964232 03-06-95 06-05-95
2.8 1.08 0.0054
3.8 1.48 0.0074
4.3 1.65 0.0083
Average: 0.0070
See Appendix Figure 2.1 for the measurement location.
8
10
, 30
12 14 16 1f 20 22 24 26 28 30 32 34 36 38 40
30
28
26
24
22
20
18
UJ
<
_J
Ld
UJ
CC
o
cc
o
V-1
3-15
TT2" 15
B¥48] [48 Y A 12-15
12-15
tn
ONE STORY
FRAME HOUSE
WITH
UNINHABITABLE
BASEMENT
10-13
SHED
12-13
12-15 _J
©
12-15
V-1
16-17
[RDC)
[12]
LEGEND
ALL EXPOSURE RATES IN /iR/h
ASSESSED AREA IDENTIFIER
AREA OF ASSESSED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
VERIFICATION AREA IDENTIFIER AND
EXPOSURE-RATE RANGE
RADON DECAY-PRODUCT CONCENTRATION
MEASUREMENT LOCATION
HEIGHT IN INCHES OF ASSESSED CONTAMINATED
BRICK COLUMNS REMOVED BUT NOT REPLACED
28
26
24
22
20
1 8
1 6
1 4
1 2
Y
1 0
SCALE IN FEET
20 10 0 20 40
M:\FAS\033\0003\RM00169V 10/17/95 2:23pm T50780
I l I I I I !_
ft
NORTH
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT, UTILITY LOCATION PLAT, OR OTHER IMPROVEMENT SURVEY
PLAT AND IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE, BUILDING, OR OTHER FUTURE IMPROVEMENT LINES.
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
RESIDENCE-NO. OF 0CCUPANT5
NON-RE5I0ENCE-UAN-HRS./WK.
INSTRUMENT NO.
SURVEY DATE
VERIFICATION
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE. COLORADO
N
IQ-4S1 41 7 NORTH CREEK LANE
MONTICELLO, UTAH
Rust Qeotech
A WUl iKtntcom Cawm*
APPROVAL OOE
OOE^NO. MS-001 69-RS
owe NO. 3-BO0169-VI SHT 1 or 1
1 6
1 4
1 2
10
10 12 1 4 1 6 18 20 22 24 26 28 30 32 34 36 38 40
OAK RIDGE NATIONAL LABORATORY
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
FOR THE U.S. DEPARTMENT OF ENERGY
POST OFFICE BOX 2567
GRAND JUNCTION. COLORADO 81502
PHONE: [phone]
FAX: [phone]
-AFB a u m
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. .0. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by the
U.S. Department of Energy for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program (FUSRAP) and Remote Surplus Facilities Management Program
Sites (SFMP) [Revision 2, March 1987]. This evaluation is based on an independent
verification review of the Remedial Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment of
the ^Ra concentration in the soil, indoor radon daughter concentration, and indoor gamma
exposure rates at this property.
Therefore, this property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
Location Number: MS00169-RS
Location Address: 417 North Creek Lane
Monticello. Utah 84535
Property Owner:

Tenant Name: Same
Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
417 NORTH CREEK LANE
MONTICELLO, UTAH (MS00169-RS)
J. R. Sauvage
April 1996
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 3
REFERENCES 5
iii
LIST OF TABLES
Applicable guidelines for protection against radiation
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site
Decommissioning Projects, U.S. Department of Energy. The author wishes to
acknowledge A. R. Jones and M. K. Jensen for technical reviews.
vii
ABSTRACT
In 1980 the site of a vanadium and uranium mill at Monticello, Utah, was accepted
into the U.S. Department of Energy's (DOE's) Surplus Facilities Management Program,
with the objectives of restoring the government-owned mill site to safe levels of radio-
activity, disposing of or containing the tailings in an environmentally safe manner, and
performing remedial actions on off-site (vicinity) properties that had been contaminated
by radioactive material resulting from mill operations. During 1995, RUST Geotech, the
remedial action contractor designated by DOE, performed remedial action on the vicinity
property at 417 North Creek Lane, Monticello, Utah. The Environmental Technology
Section (ETS) of Oak Ridge National Laboratory was assigned the responsibility of
verifying the data supporting the adequacy of remedial action and confirming the site's
compliance with DOE guidelines. The ETS found that the site successfully meets the
DOE remedial action objectives. Procedures used by the ETS are described in the
Environmental Technology Section Procedures Manual (ORNL 1993).
ix
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 417 NORTH CREEK LANE
MONTICELLO, UTAH (MS00169-RS)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the U.S. government through the
Defense Plant Corporation to provide vanadium during World War II. Various govern-
ment agencies operated the mill until 1947. In 1948 the Atomic Energy Commission
(AEC) obtained the mill and operated it under contract through 1959 to provide both
uranium and vanadium. Mill operations were terminated on January 1,1960. In 1961
the mill tailings piles were leveled and graded, covered with rock and soil, and seeded
with native grasses. During 1974 and 1975, the ore stockpiles were removed from the
site, and the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city
of Monticello, in San Juan County, Utah. The site is bordered on the south and southeast
by land held by the U.S. Bureau of Land Management. Other boundaries are the city of
Monticello and private property.
During the AEC era, the mill processed approximately one million tons of uranium
ore. Vanadium and uranium were the only substances extracted in the milling process.
Other constituents ofthe ore remained in the tailings and were not separated prior to dis-
posal. During the years of active mill operation, the mill tailings were normally moist, so
erosion was minimal. However, throughout the mill's operating period, area residents
used these tailings as fill material and as aggregate in mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy
(DOE) initiated the Surplus Facilities Management Program (SFMP) in 1978 to ensure
the safe caretaking and decommissioning of government facilities that had been retired
from service but still had radioactive contamination. In 1980 the mill site at Monticello
was accepted into the SFMP, and the Monticello Remedial Action Project (MRAP) was
established to restore the government-owned mill site to safe levels of radioactivity, to
dispose of or contain the tailings in an environmentally safe manner, and to perform re-
medial actions on off-site (vicinity) properties that had been contaminated by radioactive
material resulting from mill operations. The Monticello mill site and the tailings remain
in the custody of the DOE Grand Junction, Colorado, Projects Office. In 1983 remedial
actions for vicinity properties were separated from MRAP with establishment ofthe
Monticello Vicinity Properties (MVP) Project (U.S. DOE 1990b).
*The verification of remedial action was performed by members of the Environmental Assessment Group in the
Environmental Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE
contract DE-AC05-96OR22464 with Lockheed Martin Energy Research Corporation.
2
The remedial action plan required excavation of all exterior contamination. When the
excavation was completed the property was resurveyed, including delta-scintillometer
measurements, to ensure the removal of all contamination and restored to a condition
comparable to that which existed prior to remedial action (Geotech 1996).
The DOE adopted a policy to assign an independent contractor to verify the data
supporting the adequacy of remedial action and to confirm the site's compliance with
DOE guidelines. The Environmental Technology Section (ETS) of Oak Ridge National
Laboratory (ORNL) has been assigned the responsibility of this task at the 417 North
Creek Lane site. This report describes the methods and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available
documentation adequately and accurately describes the post-remedial-action radiological
conditions of the entire property that is to be certified and (2) that the remedial action
reduced contamination to below applicable DOE guidelines (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1996)
indicates the property was remediated as evaluated by DOE on the basis of Environmental
Protection Agency standards and the DOE guidelines (DOE 1990a). Excess residual
radioactive materials were present, thus it was appropriate to designatelhis property for
remedial action.
The pre-remedial-action survey performed by Geotech identified 1 yd3 of contami-
nation 48 inches high. During the actual removal process a total of 1 yd3 of contamina-
tion, 48 inches high, was removed from aim2 area.
A post-remedial-action survey was performed by Geotech of the remediated areas.
This survey consisted of gamma scans with a scintillometer of the exterior and in-situ ^Ra
analysis with a delta scintillometer in the areas remediated.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation
levels have not been subtracted. Similarly, background concentrations have not been
subtracted from radionuclide concentrations in soil samples. Applicable DOE guidelines
for protection against radiation are given in Table 1.
Gamma Measurements
Gamma exposure rate measurements taken by Geotech at the ground-level of the
residence ranged from 10 to 13 uR/h. Exterior surface gamma measurements taken from
the remediated areas prior to backfilling ranged from 13 to 15 uR/h.
Soil Sample Analysis
No soil samples were taken due to the contamination being brick mortar surrounding
the support post. Geotech collected two delta measurements representative of the verifi-
cation area. These measurements showed H6Ra concentrations of <1 pCi/g. These values
are below the EPA standard value of 5 pCi/g for surface soil. Gamma ranges and/or soil
sample results demonstrate compliance to the DOE Hot Spot Guidelines for areas <25 m2
(Table 1).
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were deter-
mined by the Alpha-track method. To monitor radon levels, Geotech placed three alpha-
track detectors on the ground floor of the residence located on this property for a period
of approximately 3 months (from March 6, 1995 to June 5, 1995). The average annual
working level (WL) of radon progeny concentration, as determined by the Tech./Ops-
Landauer Corporation, was 0.0070, which is well below the 0.03-WL guideline given in
Table 1.
CONCLUSION
Results of Geotech in-situ ^Ra analysis show that radionuclide concentrations are
within applicable DOE guidelines. Based on the results of the post-remedial-action data,
which are confirmed by the verification assessment data, these radiological measurements
fall below the limits prescribed by DOE guidelines. It is concluded that the site
successfully meets the DOE remedial action objectives.
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of 226Ra in soil
above background levels,
averaged over a 100-m2 area
5 pCi/g averaged over the
first 15 cm of soil below the
surface; 15 pCi/g when ave-
raged over 15-cm-thick soil
layers more than 15 cm
below the surface
Radionuclide
concentrations in soil
for Hot Spot areas
Maximum Permissible
concentration of Ra226 in soil
above background level, for
areas less than 25 m2
Ra22S concentrations, in any
surface or subsurface area
less than 25 m2, is below the
guideline by a factor of
(lOO/A)* where A is the
area of the elevated region
Exposure to 222Rn
progeny
Average annual radon proge-
ny concentration (including
background)
0.03 WL
(DOE 1990a)
REFERENCES
Geotech 1996. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00169-RS, Address: 417 North Creek Lane, Monticello,
Utah 84535, Geotech, Grand Junction, Colorado, February 1996.
ORNL 1993. Environmental Technology Section (Formerly PoUutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
U.S. DOE 1990a. Verification and Certification Protocol for the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination
and Decommissioning Program, Revision 3, November 1990. U.S. Department of
Energy, Washington, D.C.
U.S. DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision
and Record of Decision Summary. U.S. Department of Energy, Grand Junction Projects
Office, Grand Junction, Colorado.
PROPERTY COMPLETION REPORT
DOE ID NO.: MS-00174-VL
ADDRESS: 465 SOUTH FIRST EAST STREET
MONTICELLO, UTAH 84535
FEBRUARY 1996
Prepared for
U.S. Department of Energy
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
by
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
TABLE OF CONTENTS
Section Page
1.0 SUMMARY . . . . 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
i
DOE ID No.: MS-00174-VL
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Remedial Action Contractor. DOE reviewed these
evaluation results and determined that the property contained mill tailings
(residual radioactive material) exceeding EPA standards. The Remedial
Action Contractor was notified of the inclusion of this property into the
MVP Project and was authorized by DOE to conduct remedial action as
required to bring the property into conformance with EPA standards and
DOE hot spot criteria.
1
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
Property Address:
Property Owner:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
DOE ID No.: MS-00174-VL
MS-00174-VL
Location No. M-6; Lot 2, Block 2,
Monticello Townsite Survey, County of San
Juan, State of Utah
465 South First East Street
Monticello, Utah 84535

Vacant Lot (VL)
Not applicable: inclusion requested by the
Remedial Action Contractor
October 7, 1988
Rust Geotech
July 22, 1994
Diamond Back Services, Inc.
9861 Titan Park Circle
Littleton, Colorado
May 30, 1995
August 16, 1995
Interior: 0 cubic yards
Exterior: 4,027 cubic yards
4,664 square meters (mJ)
February 1996
2
DOE ID No.: MS-00174-VL
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of exterior residual radioactive
material (Appendix Figure 2.1). All of the structures on this property
(including assessed Area B, mortar between the logs of a cabin) were
assessed as contaminated; however, they were removed during remedial
action and verified to exterior standards. Once excavation was complete,
the affected area was resurveyed for possible remaining residual
radioactive material and, upon attaining satisfactory results, was backfilled
with uncontaminated material. The property was restored to a physical
condition comparable to that which existed prior to remedial action
activities.
2.2 Previously Unidentified Contamination
The radiological assessment identified 2,550 cubic yards of
contamination, ranging from 6 to 33 inches deep, within the property.
The remedial action process included the removal of approximately
4,027 cubic yards of residual radioactive material, ranging from 10 to
78 inches deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID No.: MS-00174-VL
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
Radiological surveys were conducted by the Remedial Action
Contractor during May 1993, and April and May 1994, as
described in the final REA dated July 1994. Appendix Figure 2.1
shows the extent of assessed contamination and identifies the
area recommended to undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the excavation were
collected. Soil samples were collected at the highest exposure-
rate location within each 30- by 30-foot section of the excavation
for Areas V-1 through V-5. The samples were blended to form
composite samples representing the verification areas (Appendix
Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 14 to 38 microroentgens per
hour OuR/h), as indicated on Appendix Figure 2.1. Elevated
exposure rates in Areas V-4 and V-5 were associated with material
at the bottom of the excavation that did not exceed the EPA
standards. The results of analyses for radium-226 in seven
composite soil samples ranged from 3.1 to 12.6 picocuries per
gram (pCi/g), as indicated in Appendix Table 3.1.
4
DOE ID No.: MS-00174-VL
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at 465 South First East Street, in
Monticello, Utah, is recommended for certification as required by DOE
guidelines, and the appropriate records should be documented.
Certification Data Summary
Applicability
Hahitahle Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Standards
Shall not exceed 20 //R/h
above background.
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Survey Results
Not applicable: vacant
lot.
Not applicable: vacant
lot.
Land.
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background* in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background* in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
< 5 pCi/g above
background.
Soil sample results
ranged from 3.1 to
12.6 pCi/g.f
*The background radium-226 concentration is approximately 2.0 pCi/g.
The hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-00174-VL
4.0 APPENDIX
Appendix Table:
Table 3.1 Post-Excavation Sample/Measurement Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
JEK: 11-09-95
MS-00174.VL WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00174-VL
Address: 465 South First East Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range {pR/h) Ticket No. Method* (pCi/g)
V-1 17-27 NCF162 OCS 7.3
V-2 16-27 NCJ 575 OCS 5.2
V-3 14-25 NCF169 OCS 6.1
V-4 15-36 NCF170 OCS 7.4
V-5 14-38 NAR 102 OCS 12.6
V-6 20- 27 NCF161 OCS 3.1
V-7 17-21 NCJ 574 OCS 6.3
See Appendix Figure 2.1 for the verification areas.
"OCS = Opposed Crystal System
7
1
42
40
3a
36
34
32
30
28
26
24
22
20
18
16
14
12
10
12 14
v-7
17-21
2 67
L
a.
t—
LO
Z3
O
16 18 20 22 24 26 28 30 32 34 36 38
v-s
20-27
15
05)
78 18
^•.•.•.•.•.•.•.•.•.•.•.•.•.•.•.•.•J"-.-.-jj-Nj-s<--.
!,TRA,LrR*:v-/i:-.-: STORY;.
^H°^£ v.;.;.;.;.; j.;.;,^^:;
24
.J .v//://;. /.-.-.\-.v>/;:X\-rjV-^OUTHOUSEi<:
51
: LU}: 19
08
.".". 30
10
V-3 ,
14-25
27
V-5
14-38
21
LOG CABIN*")."
<12>.
.30
V-4
15-36
<33>
34
05)
05)
V-2
16-27
16
18
26
v-i
17-27
58
34
SCALE IN FEET
20 10 0 • 20 40
U:\rtS\Oll\00OAniOOI7tV Ol/Jt/M 111 Km TM7M
' ' ' I I I L__
NORTH
40
1 0
i <D
l| Lv.vj
12-15
12
v-i
16-17
42 44 46 \ 48 5C
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN ^R/h
ASSESSEO AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE-RATE RANGE
STRUCTURES WERE; REMOVED DURING REMEDIAL
ACTION
ASSESSED AREA B (MORTAR BETWEEN LOGS)
WAS REMOVED BUT NOT REPLACED
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
THIS DRAWING IS FOR THE SOLC USC OF THC U.S. DEPARTMENT
OF ENERGY ANO ITS CONTRACTORS. IT IS NOT A UNO SURVCT
PLAT, UTIUTY LOCATION PLAT, OR OTHER IMPROVEMENT SURVCT
PLAT ANO IS NOT TO BE RCLICO UPON FOR THE ESTABLISHMENT
OF FCNCC. 8UI10INC. OR OTHER FUTURE IMPROVEMENT LINES. m
U.S. DEPARTMENT OF ENERGY
CAAMQ JUNCTttW PftQjCCTS OrfiCt. COLQJWCO
US?"
465 SOUTH FIRST EAST STREET
MONTICELLO. UTAH
RUST ««••» US-00174-VL
— - 3-C00174-VI —1,1
12 14 16 18 20 22 24 26 28 30 32 34 36 38 40 42 44 46 48 5
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
465 SOUTH 1ST EAST STREET
MONTICELLO, UTAH (MS00174-VL)
J. R. Sauvage
April 1996
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 3
REFERENCES _ 6
iii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 4
2. Results of ORNL analysis of Geotech soil samples from 465 South 1st East Street,
Monticello, Utah (MS00174-VL) 5
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site
Decommissioning Projects, U.S. Department of Energy. The author wishes to
acknowledge M. K. Jensen for analysis of soil samples and technical review and A
Jones for technical review.
vii
ABSTRACT
In 1980 the site of a vanadium and uranium mill at Monticello, Utah, was accepted
into the U.S. Department of Energy's (DOE's) Surplus Facilities Management Program,
with the objectives of restoring the government-owned mill site to safe levels of radio-
activity, disposing of or containing the tailings in an environmentally safe manner, and
performing remedial actions on off-site (vicinity) properties that had been contaminated
by radioactive material resulting from mill operations. During 1995, RUST Geotech, the
remedial action contractor designated by DOE, performed remedial action on the vicinity
property at 465 South 1st East Street, Monticello, Utah. The Environmental Technology
Section (ETS) of Oak Ridge National Laboratory was assigned the responsibility of
verifying the data supporting the adequacy of remedial action and confirming the site's
compliance with DOE guidelines. The ETS found that the site successfully meets the
DOE remedial action objectives. Procedures used by the ETS are described in the
Environmental Technology Section Procedures Manual (ORNL 1993).
ix
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 465 SOUTH 1ST EAST STREET
MONTICELLO, UTAH (MS00174-VL)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the U.S. government through the
Defense Plant Corporation to provide vanadium during World War II. Various govern-
ment agencies operated the mill until 1947. In 1948 the Atomic Energy Commission
(AEC) obtained the mill and operated it under contract through 1959 to provide both
uranium and vanadium. Mill operations were terminated on January 1,1960. In 1961 the
mill tailings piles were leveled and graded, covered with rock and soil, and seeded with
native grasses. During 1974 and 1975, the ore stockpiles were removed from the site, and
the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city
of Monticello, in San Juan County, Utah. The site is bordered on the south and southeast
by land held by the U.S. Bureau of Land Management. Other boundaries are the city of
Monticello and private property.
During the AEC era, the mill processed approximately one million tons of uranium
ore. Vanadium and uranium were the only substances extracted in the milling process.
Other constituents of the ore remained in the tailings and were not separated prior to dis-
posal. During the years of active mill operation, the mill tailings were normally moist, so
erosion was minimal. However, throughout the mill's operating period, area residents used
these tailings as fill material and as aggregate in mortar and concrete-
Under the authority of the Atomic Energy Act, the U.S. Department of Energy (DOE)
initiated the Surplus Facilities Management Program (SFMP) in 1978 to ensure the safe
caretaking and decommissioning of government facilities that had been retired from
service but still had radioactive contamination. In 1980 the mill site at Monticello was
accepted into the SFMP, and the Monticello Remedial Action Project (MRAP) was
established to restore the government-owned mill site to safe levels of radioactivity, to
dispose of or contain the tailings in an environmentally safe manner, and to perform
remedial actions on off-site (vicinity) properties that had been contaminated by radioactive
material resulting from mill operations. The Monticello mill site and the tailings remain in
the custody of the DOE Grand Junction, Colorado, Projects Office. In 1983 remedial
actions for vicinity properties were separated from MRAP with establishment ofthe
Monticello Vicinity Properties (MVP) Project (U.S. DOE 1990b).
*The verification of remedial action was performed by members of the Environmental Assessment Group in the
Environmental Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE
contract DE-AC05-96OR22464 with Lockheed Martin Energy Research Corporation.
2
During 1995, RUST Geotech Inc. (Geotech), the remedial action contractor (RAC)
designated by DOE, performed remedial action on the vicinity property that is the subject
of this report, a vacant lot located at 465 South 1st East Street, Monticello, Utah. The
remedial action plan required excavation of all exterior contamination. When the excava-
tion was completed, the property was resurveyed, including soil sampling, to ensure the
removal of all contamination, backfilled with uncontaminated material, and restored to a
condition comparable to that which existed prior to remedial action (Geotech 1996).
The DOE adopted a policy to assign an independent contractor to verify the data
supporting the adequacy of remedial action and to confirm the site's compliance with DOE
guidelines. The Environmental Technology Section (ETS) of Oak Ridge National Labora-
tory (ORNL) has been assigned the responsibility of this task at the 465 South 1st East
Street site. This report describes the methods and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available docu-
mentation adequately and accurately describes the post-remedial-action radiological
conditions of the entire property that is to be certified and (2) that the remedial action
reduced contamination to below applicable DOE guidelines (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1996) in-
dicates the property was remediated as evaluated by DOE on the basis of Environmental
Protection Agency standards and the DOE guidelines (DOE 1990a). Excess residual
radioactive materials were present, thus it was appropriate to designate this property for
remedial action.
The pre-remedial-action survey performed by Geotech identified 2550 yd3 of mill
tailings 6 to 33 inches deep. During the actual removal process a total of 4027 yd3 of
contaminated earth and uranium mill tailings, 10 to 78 inches deep, were removed from a
4664 m2 area.
A post-excavation survey was performed by Geotech prior to backfilling the excavated
areas. This survey consisted of gamma scans with a scintillometer of the exterior, and soil
sampling. Samples representative of the bottom 15-cm (6-in.) soil layers of seven
excavated verification areas were collected and blended to form representative composite
soil samples for each verification area.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation
levels have not been subtracted. Similarly, background concentrations have not been sub-
tracted from radionuclide concentrations in soil samples. Verification of this property
followed large area verification procedures. Applicable DOE guidelines for protection
against radiation are given in Table 1.
Gamma Measurements
Exterior surface gamma exposure rate measurements taken by Geotech from the
excavated areas prior to backfilling ranged from 14 to 38 uR/h.
Soil Sample Analysis
Prior to backfilling, Geotech collected soil samples representative of the excavated
areas from the bottom 15-cm (6-in.) soil layers. These samples were blended to form a
composite soil sample representative of an average over the seven exterior verification
areas. Geotech's analysis of these samples showed 226Ra concentrations ranging from 3.1
to 12.6 pCi/g in the composite sample. ORNL ETS obtained one of these soil samples and
performed a confirmatory analysis, which showed a 226Ra concentration of 7.8 pCi/g.
These values are below the EPA standard value of 15 pCi/g for soil layers >15 cm below
the surface. Results of Geotech and ORNL soil sample analyses are given in Table 2. Soil
sample results collected from areas of anomalous gamma exposure rates demonstrate
compliance to the DOE Hot Spot Guidelines for areas <25 m2 as documented in the
property folio.
Radon Measurement Results
Radon measurements were not taken at this site as all of the structures were removed
during remediation.
CONCLUSION
Results of Geotech soil sample analysis and confirmatory split soil sample analysis by
ORNL show that radionuclide concentrations are within applicable DOE guidelines.
Based upon the results of the post-remedial-action data, which are confirmed by the
verification assessment data, these radiological measurements fall below the limits
prescribed by DOE guidelines. It is concluded that the site successfully meets the DOE
remedial action objectives.
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Radionuclide
concentrations in soil
for Hot Spot areas
Exposure to 222Rn
progeny
Maximum permissible con-
centration of 226Ra in soil
above background levels,
averaged over a 100-m2 area
Maximum Permissible con-
centration of Ra226 in soil
above background level, for
areas less than 25 m2
Average annual radon proge-
ny concentration (including
background)
5 pCi/g averaged over the
first 15 cm of soil below the
surface; 15 pCi/g when ave-
raged over 15-cm-thick soil
layers more than 15 cm
below the surface
Ra226 concentrations, in any
surface or subsurface area
less than 25 m2, is below the
guideline by a factor of
(lOO/A)'"4, where A is the
area of the elevated region
0.03 WL
(DOE 1990a)
Table 2. Results of ORNL analysis of Geotech soil samples
from 465 South 1st East Street, Monticello Utah (MS00174-VL)
226Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No." No* (cm)
XI NCF162 >15 7.8 7.3
" An X-type sample is a split of the sample taken by the remedial action contractor.
* Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated areas
were taken by Geotech, and these samples were blended to form a composite soil sample,
which represents an average over one of the verification areas.
6
REFERENCES
Geotech 1995. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00174-VL, Address: 465 South First East Street,
Monticello, Utah 84535, Geotech, Grand Junction, Colorado, April 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment Group)
Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National Laboratory,
Grand Junction, Colorado.
U.S. DOE 1990a. Verification and Certification Protocol for the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination and
Decommissioning Program, Revision 3, November 1990. U.S. Department of Energy,
Washington, D.C.
U.S. DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision
and Record of Decision Summary. U.S. Department of Energy, Grand Junction Projects
Office, Grand Junction, Colorado.
DOE ID No.: MS-00174-VL
Property Address: 465 South First East Street
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech of Energy (DQE)
Ra-226 is * 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [ ]
Ra-226 is <; 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2.
In-situ [ ] Lab [X]
Interior gamma is <; 20 pR/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is £ 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21.
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
YES NO NOT TAKEN
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
IX] I 1 [ 1
[*] [ 1 [ 1
[ ] [ ] [X] [ ] [ 1 [>3
(Vacant Lot)
[ ] [ ] [X] [ ] I ] [>\
(Vacant Lot)
[ 1 r>] [ ]
\A [ 1 [ 1
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
SFCERTIFED SFMS-00174
DOE ID No.: MS-00174-VL
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Wanda S^Busby
Manager, Monticello Programs
Rust Geotech
Date
DOE EVALUATION
[X] Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Certification Official
U.S. Department of Energy
Date
t . i
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00189-RS
ADDRESS: 164 EAST THIRD SOUTH STREET
MONTICELLO, UTAH 84535
FEBRUARY 1996
Prepared for
U.S. Department of Energy
by
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504-
' Wanda S. Busby
Manager, Monticello Programs
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
Ollll I IIH Hll I " ~ MT.VMV, * 'V"atT "« V
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.1.3 Radon Decay-Product Concentration (RDC) Measurement .... 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
DOE ID No.: MS-00189-RS
SUMMARY - —
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Inclusion Survey Contractor. DOE reviewed
these evaluation results and determined that the property contained mill
tailings (residual radioactive material) exceeding EPA standards. The
Remedial Action Contractor was notified of the inclusion of this property
into the MVP Project and was authorized by DOE to conduct remedial
action as required to bring the property into conformance with EPA
standards and DOE hot spot criteria.
1
T73 STTmmaTyHDT^em^
DOE ID No.:
Legal Description:
Property Address:
Property Owners:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
DOE ID No.: MS-00189-RS
MS-00189-RS
Parcel No. M-63; beginning at the NW
corner of Lot 4, Block 9, Monticello
Townsite Survey; south 214.5 feet, west
107.25 feet, north 214.5 feet, east to the
beginning, County of San Juan, State of
Utah
164 East Third South Street
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
October 23, 1989
Rust Geotech
March 6, 1990
Sonderegger Inc.
P.O. Box 713
Monticello, Utah
July 12, 1990
August 23, 1990
Interior: 0 cubic yards
Exterior: 383 cubic yards
1,920 square meters (m2)
February 1996
2
DOE ID No.: MS-00189-RS
—2:0 -OPERATIQNS^UMMARY' ~ * —
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of exterior residual radioactive
material (Appendix Figure 2.1). Once excavation was complete, the
affected area was resurveyed for possible remaining residual radioactive
material and, upon attaining satisfactory results, was backfilled with
uncontaminated material. The property was restored to a physical
condition comparable to that which existed prior to remedial action
activities.
2.2 Previously Unidentified Contamination
The radiological assessment identified 428 cubic yards of contamination,
ranging from 6 to 12 inches deep, within the property. The remedial
action process included the removal of approximately 383 cubic yards of
residual radioactive material, 6 inches deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID No.: MS-00189-RS
-3:0 ~"VER1F1CATT0N~SUMMATTY —
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by the Remedial Action
Contractor during October 1989, as described in the final REA
dated March 1990. Appendix Figure 2.1 shows the extent df
assessed contamination and identifies the area recommended to
undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the excavation were
collected. These samples were blended to form composite
samples representing the verification areas (Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 14 to 25 microroentgens per
hour O/R/h), as indicated on Appendix Figure 2.1. The results of
analyses for radium-226 in 18 composite soil samples ranged from
2.0 to 7.2 picocuries per gram (pCi/g), as indicated in Appendix
Table 3.1.
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on measurements representing an annual average, the RDC
was 0.0050 working level (WL), as indicated in Appendix
Table 3.2. Appendix Figure 2.1 shows the measurement location
on the ground floor (the lowest habitable level of the structure).
4
DOE ID No.: MS-00189-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at 164 East Third South Street, in
Monticello, Utah, is recommended for certification as required by DOE
guidelines, and the appropriate records should be documented.
Certification Data Summary
Applicability
Hahitahle Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Standards
Shall not exceed 20 //R/h
above background.*
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Survey Results
Range for the ground
floor was 12 to 14//R/h.
Annual average was
0.0050 WL.
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
< 5 pCi/g above
background.**
Soil sample results
ranged from 2.0 to
7.2 pCi/g.**
*The background exposure rate is approximately 14 //R/h.
The background radium-226 concentration is approximately 2.0 pCi/g.
**The hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-00189-RS
4.0 APPENDIX " ~~" " — —
Appendix Tables:
Table 3.1 Post-Excavation Sample/Measurement Results
Table 3.2 Radon Decay-Product Concentration Measurement Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
JEK: 10-03-95
MS-00189.RS WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00189-RS
Address: 164 East Third South Street, Monticello, Utah
Exposure- Soil
Rate Range Sample Meas. Radium-226 Potassium Thorium
Area ipR/h) Ticket No. Method" (pCi/g) (pCi/g) (pCi/g)
V-1 18-25 NAA 660 AL 6.3 "23.3 0.7
V-2 18-25 NAA 661 AL 5.7 23.4 1.0
V-3 17-21 NAA 662 AL 3.4 23.9 0.9
V-4 17-21 NAA 663 AL 3.5 24.7 1.1
V-5 17-21 NAA 664 AL 5.2 24.7 1.4
V-6 20- 25 NAA 665 AL 7.2 24.5 1.0
V-7 18-25 NAA 666 AL 6.0 23.8 1.0
V-8 16-25 NAA 667 AL 4.8 25.1 1.2
V-9 18-21 NAA 668 AL 5.1 23.3 1.0
V-10 16-21 NAA 669 AL 2.8 24.6 1.2
V-11 17-25 NAA 670 AL 2.0 24.3 1.0
V-12 17-21 NAA 671 AL 2.6 22.9 1.1
V-13 16-21 NAA 672 AL 2.4 24.5 1.0
V-14 17-21 NAA 673 AL 4.3 24.7 1.2
V-15 17-25 NAA 674 AL 5.6 24.7 0.9
V-16 18-25 NAA 675 AL 5.7 23.3 0.8
V-17 15-25 NAA 676 AL 4.7 23.8 1.1
V-18 18-25 NAA 677 AL 4.2 23.4 1.0
See Appendix Figure 2.1 for the verification areas.
"AL = Analytical Laboratory
7
Table 3.2
Radon Decay-Product Concentration Measurement Results
DOE ID No.: MS-00189-RS
Address: 164 East Third South Street, Monticello, Utah
Instrument Type: Landauer Radtrak Detector
Radon
Detector Tracks Per Concentration Working
Number Start Date End Date mm2 (pCi/L) Level
3892293 06-13-94 06-06-95
3892230 06-13-94 06-06-95
3892161 06-13-94 06-06-95
9.1 1.00 0.0050
8.8 0.97 0.0049
9.1 1.00 0.0050
Annual Average: 0.0050
See Appendix Figure 2.1 for the measurement location.
8
42
40
38
36
34
32
30
28
26
24
22
20
18
16
14
12
10
12 16 18 20 22 24 26 28 30 32 34
1 "
36
~T~
38 40
v-i 6
18-25
SHED © © • 14-16 CELLAR v-1
14-16 0 18-25
niu< 18-25 O ®3 v-8
G 0 16-25 3DC V-1 7
15-25
ONE STORY
FRAME HOUSE
12-14
14-16 ll 0 O 0 • > 3^ V-6 V-2
©H 20-25 18-25
LT] © © v-9 CB © m 18-21
© 0
© V-3 V-5
17-21 17-2!
v-13
0 © 16-21
s Mm V-12
V-17-21
V-10 V-4 /- 1 4 17-25
16-21 17-21 E 17-21
A X 6
L
SCALE IN FEET
20 10 0 20 40
U.\FAS\0J3\0003\RU00I|9V 10/03/93 Oa.TAam T307S0
I ! I ! I ! ! L J I
©
©
rv.vj
12-15
0
v-i
16-17
42 46 48 50
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN jiR/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSEO CONTAMINATION
AREA OF ASSESSEO CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE —RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE-RATE RANGE
POST-REMEDIAL ACTION RADON DECAY-PRODUCT
CONCENTRATION MEASUREMENT LOCATION
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
THIS DRAWING IS FOR THE SOLE USE Of THE U.S OEPARTUENT
OF ENERGY ANO ITS CONTRACTORS. IT IS NOT A LANO SURVE'
PLAT. UTILITY LOCATION PLAT. OR OTHER IMPROVEMENT SUHVfT
PLAT ANO IS NOT TO BE RELIEO UPON FOR THE ESTABLISHMENT
OF FENCE BUU.DINC. OR OTHER FUTURE IMPROVEMENT LINES
M. m.
UK
U.S. DEPARTMENT OF ENERGY
6AAN0 JUNCTION MOlCCTl grttCC. C0104MO
'TT PIS 164 EAST THIRD SOUTH STREET
7~ MONTICELLO. UTAH
RUST Rust 0<ot«ch
TT
"<••• MS-0OI89-RS
I
3-CO0IB9-V1 „ 1 ,
12 14 16 18 20 22 24 26 28 30 32 34 36 38 40 42 44 46 48 50
OAK RIDGE NATIONAL LABORATORY
MANAQKUBT* LOCKHEED MARTIN EI^IEROTWESEARCH CORPORATION"
FOR THE U.S. DEPARTMENT OF ENERGY
POST OFFICE BOX 2567
GRAND JUNCTION, COLORADO 81502
PHONE: [phone]
—TWt '(970) ,848-0220
MAY 3 l 1996
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by the
U.S. Department of Energy for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program (FUSRAP) and Remote Surplus Facilities Management Program
Sites (SFMP) [Revision 2, March 1987]. This evaluation is based on an independent
verification review of the Remedial Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment of
the 226Ra concentration in the soil, indoor radon daughter concentration, and indoor gamma
exposure rates at this property.
Therefore, this property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
MS00189-RS
164 East 3rd South Street
Monticello, Utah 84535

Location Number:
Location Address:
Property Owner:
Owner Address:
Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
164 EAST 3RD SOUTH STREET
MONTICELLO, UTAH (MS00189-RS)
A. R. Jones
May 1996
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 4
REFERENCES 6
iii
LIST OF TABLES
Applicable guidelines for protection against radiation
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site
Decommissioning Projects, U.S. Department of Energy. The author wishes to
acknowledge M. J. Wilson-Nichols and M. K. Jensen for technical reviews.
vii
ABSTRACT
In 1980 the site of a vanadium and uranium mill at Monticello, Utah, was accepted
into the U.S. Department of Energy's (DOE's) Surplus Facilities Management Program,
with the objectives of restoring the government-owned mill site to safe levels of radio-
activity, disposing of or containing the tailings in an environmentally safe manner, and
performing remedial actions on off-site (vicinity) properties that had been contaminated
by radioactive material resulting from mill operations. During 1990, RUST Geotech, the
remedial action contractor designated by DOE, performed remedial action on the vicinity
property at 164 East 3rd South Street, Monticello, Utah. The Environmental Technology
Section (ETS) of Oak Ridge National Laboratory was assigned the responsibility of veri-
fying the data supporting the adequacy of remedial action and confirming the site's com-
pliance with DOE guidelines. The ETS found that the site successfully meets the DOE
remedial action objectives. All deficiencies noted in the initial review have been resolved
with additional documentation to the property folio. Procedures used by the ETS are
described in the Environmental Technology Section Procedures Manual (ORNL 1993).
ix
RESULTS OF THE-INDEPENDE^^VERlFK3ATION —
OF RADIOLOGICAL REMEDIAL ACTION
AT 164 EAST 3RD SOUTH STREET
MONTICELLO, UTAH (MS00189-RS)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the U.S. government through the
Defense Plant Corporation to provide vanadium during World War II. Various govern-
ment agencies operated the mill until 1947. In 1948 the Atomic Energy Commission
(AEC) obtained the mill and operated it under contract through 1959 to provide both
uranium and vanadium. Mill operations were terminated on January 1,1960. In 1961 the
mill tailings piles were leveled and graded, covered with rock and soil, and seeded with
native grasses. During 1974 and 1975, the ore stockpiles were removed from the site, and
the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city
of Monticello, in San Juan County, Utah. The site is bordered on the south and southeast
by land held by the U.S. Bureau of Land Management. Other boundaries are the city of
Monticello and private property.
During the AEC era, the mill processed approximately one million tons of uranium
ore. Vanadium and uranium were the only substances extracted in the milling process.
Other constituents of the ore remained in the tailings and were not separated prior to
disposal. During the years of active mill operation, the mill tailings were normally moist,
so erosion was minimal. However, throughout the mill's operating period, area residents
used these tailings as fill material and as aggregate in mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy
(DOE) initiated the Surplus Facilities Management Program (SFMP) in 1978 to ensure
the safe caretaking and decommissioning of government facilities that had been retired
from service but still had radioactive contamination. In 1980 the mill site at Monticello
was accepted into the SFMP, and the Monticello Remedial Action Project (MRAP) was
established to restore the government-owned mill site to safe levels of radioactivity, to
dispose of or contain the tailings in an environmentally safe manner, and to perform
remedial actions on off-site (vicinity) properties that had been contaminated by
radioactive material resulting from mill operations. The Monticello mill site and the
tailings remain in the custody of the DOE Grand Junction, Colorado, Projects Office. In
1983 remedial actions for vicinity properties were separated from MRAP with
establishment ofthe Monticello Vicinity Properties (MVP) Project (U.S. DOE 1990b).
*The verification of remedial action was performed by members of the Environmental Assessment Group in the
Environmental Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE
contract DE-AC05-96OR22464 with Lockheed Martin Energy Research Corporation.
During 1990, RUST Geotech Inc. (Geotech), the remedial action contractor (RAC)
designated by DOE, performed remedial action on the vicinity property that is the subject
of this report, a single family residence located at 164 East 3rd South Street, Monticello,
Utah. The remedial action plan required excavation of all exterior contamination. When
the excavation was completed, the property was resurveyed, including soil sampling, to
ensure the removal of all contamination, backfilled with uncontaminated material, and re-
stored to a condition comparable to that which existed prior to remedial action (Geotech
1996).
The DOE adopted a policy to assign an independent contractor to verify the data
supporting the adequacy of remedial action and to confirm the site's compliance with
DOE guidelines. The Environmental Technology Section (ETS) of Oak Ridge National
Laboratory (ORNL) has been assigned the responsibility of this task at the 164 East 3rd
South Street site. This report describes the methods and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available docu-
mentation adequately and accurately describes the post-remedial-action radiological
conditions of the entire property that is to be certified and (2) that the remedial action
reduced contamination to below applicable DOE guidelines (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1996) in-
dicates the property was remediated as evaluated by DOE on the basis of Environmental
Protection Agency standards and the DOE guidelines (DOE 1990a). Excess residual
radioactive materials were present, thus it was appropriate to designate this property for
remedial action.
The pre-remedial-action survey performed by Geotech identified 428 yd3 of mill
tailings from 6 to 12 inches deep. During the actual removal process, a total of 383 yd3 of
contaminated earth and uranium mill tailings, 6 inches deep, were removed from a 1920
m2 area.
A post-excavation survey was performed by Geotech prior to backfilling the
excavated areas. This survey consisted of gamma scans with a scintillometer of the
ground level of the structure, a surface scan of the exterior, and soil sampling. Samples
representative of the bottom 15-cm (6-in.) soil layers of 18 excavated verification areas
were collected and blended to form representative composite soil samples for each
verification area. The RAC is unable to locate or inadvertently disposed of the samples
requested for ORNL confirmatory analysis.
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation
levels have not been subtracted. Similarly, background concentrations have not been sub-
tracted from radionuclide concentrations in soil samples. Applicable DOE guidelines for
protection against radiation are given in Table 1.
Gamma Measurements
Gamma exposure rate measurements taken by Geotech at the ground-level of the
residence ranged from 12 to 14 pR/h. Exterior surface gamma measurements taken from
the excavated areas prior to backfilling ranged from 15 to 25 pR/h.
Soil Sample Analysis
Prior to backfilling, Geotech collected soil samples representative of the excavated
areas from the bottom 15-cm (6-in.) soil layers. These samples were blended to form a
composite soil sample representative of an average over the 18 exterior verification areas.
Geotech's analysis of these samples showed 226Ra concentrations ranging from 2.0 to
7.2 pCi/g in the composite sample. ORNL ETS was unable to obtain samples for con-
firmatory analysis. These values are below the EPA standard value of 15 pCi/g for soil
layers >15 cm below the surface.
As a result of a meeting between the RAC and IVC on May 26,1994, anomalous
readings, defined as > 30% above the average of the excavation, will be investigated to
show compliance to the DOE hot spot guideline. This property was remediated prior to
this procedure change. The IVC observed that areas V2, V3, V8, Vll, V15, V16, V17,
and VI8 exceeds 30% of the excavation average. The IVC will allow a correlation
developed by the RAC to estimate 226Ra pCi/g concentrations based on gamma exposure
rates. The highest anomalous reading of 25 pR/h on this property using the RAC's corre-
lation yields a 226Ra concentration of 4.4 pCi/g. This value is well below the minimum
concentration of 30 pCi/g, when assuming the maximum area under the hot spot
guideline of 25 m2, for subsurface samples.
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were deter-
mined by the Alpha-track method. To monitor radon levels, Geotech placed three alpha-
track detectors on the ground floor of the residence located on this property for a period
of approximately one year (from June 13,1994 to June 6,1995). The average annual
working level (WL) of radon progeny concentration, as determined by the TechVOps-
Landauer Corporation, was 0.0050, which is well below the 0.03-WL guideline given in
Table 1.
-4~
CONCLUSION
Results of Geotech soil sample analysis show that radionuclide concentrations are
within applicable DOE guidelines. Based on the results of the post-remedial-action data,
which are confirmed by the verification assessment data, these radiological measurements
fall below the limits prescribed by DOE guidelines. All deficiencies noted in the initial
review have been identified by the RAC as discussed in a meeting between Geotech and
ORNL on April 15,1996, and in a memo to the property folio from R. K. Johnson dated
May 2, 1996. It is concluded that the site successfully meets the DOE remedial action
objectives.
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of 226Ra in soil
above background levels,
averaged over a 100-m2 area
5 pCi/g averaged over the
first 15 cm of soil below the
surface; 15 pCi/g when ave-
raged over 15-cm-thick soil
layers more than 15 cm
below the surface
Radionuclide
concentrations in soil
for Hot Spot areas
Maximum Permissible con-
centration of Ra226 in soil
above background level,
for areas less than 25 m2
Ra226 concentrations, in any
surface or subsurface area
less than 25 m2, is below the
guideline by a factor of
(100/A)*, where A is the
area of the elevated region
Exposure to 222Rn
progeny
Average annual radon proge-
ny concentration (including
background)
0.03 WL
(DOE 1990a)
6
REFERENCES
Geotech 1996. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00189-RS, Address: 164 East Third South Street,
Monticello, Utah 84535, Geotech, Grand Junction, Colorado, February 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
U.S. DOE 1990a. Verification and Certification Protocol for the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination
and Decommissioning Program, Revision 3, November 1990. U.S. Department of
Energy, Washington, D.C.
U.S. DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision
and Record of Decision Summary. U.S. Department of Energy, Grand Junction Projects
Office, Grand Junction, Colorado.
DOE ID No.: MS-00189-RS
Property Address: 164 East Third South Street
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech of Energy (DQE)
Ra-226 is * 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [ ]
Ra-226 is s 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2.
In-situ [ ] Lab [X]
Interior gamma is £ 20 juR/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is <: 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21.
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
IXJ [ I I 1
LY] [ I [ 1
tX] [ ] I ]
[id [ I t 1
[ ] (Xl I 1
ry] [ ] [ ]
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
SFCERTIFED SFMS-00189
4 « * *
DOE ID No.: MS-00189-RS
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
/anda SyBusby
Manager, Monticello Programs
Rust Geotech
Date
DOE EVALUATION
P<] Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Certification Official
U.S. Department of Energy
/a JJ 7£
Date
DEC 18 1996
PROPERTY COMPLETION REPORT
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
DOE ID NO.: MS-00194-RS
ADDRESS: 280 EAST FIRST SOUTH STREET
MONTICELLO, UTAH 84535
AUGUST 1996
Prepared for
U.S. Department of Energy
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
FOR
FOR
by
Manager, Monticello Programs
Rust Geotech,has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
TABLE OF CONTENTS
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.1.3 Radon Decay-Product Concentration (RDC) Measurement .... 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
DOE ID No.: MS-00194-RS
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one .million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Inclusion Survey Contractor. DOE reviewed
these evaluation results and determined that the property contained mill
tailings (residual radioactive material) exceeding EPA standards. The
Remedial Action Contractor was notified of the inclusion of this property
into the MVP Project and was authorized by DOE to conduct remedial
action as required to bring the property into conformance with EPA
standards and DOE hot spot criteria.
1
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
Property Address:
Property Owner:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
DOE ID No.: MS-00194-RS
MS-00194-RS
Beginning at a point west 65 feet from the
NE corner of Block 20, Monticello Townsite
Survey; west 169.5 feet, south 214.5 feet,
east 234.5 feet, north 94.5 feet, west
65 feet, north 120 feet to beginning,
County of San Juan, State of Utah
280 East First South Street
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
October 23, 1989
Rust Geotech
June 21, 1991
Diamond Back Services, Inc.
9861 Titan Park Circle
Littleton, Colorado
August 3, 1995
September 14, 1995
Interior: 0 cubic yards
Exterior: 714 cubic yards
2,347 square meters (m2)
August 1996
2
DOE ID No.: MS-00194-RS
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of exterior residual radioactive
material (Appendix Figure 2.1). Once excavation was complete, the
affected areas were resurveyed for possible remaining residual radioactive
material and, upon attaining satisfactory results, were backfilled with
uncontaminated material. The property was restored to a physical
condition comparable to that which existed prior to remedial action
activities.
2.2 Previously Unidentified Contamination
The radiological assessment identified 409 cubic yards of contamination,
6 inches deep, within the property. The remedial action process included
the removal of approximately 714 cubic yards of residual radioactive
material, ranging from 4 to 30 inches deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
1
DOE ID No.: MS-00194-RS
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by the Remedial Action
Contractor during September 1990, as described in the final REA
dated June 1991. Appendix Figure 2.1 shows the extent of
assessed contamination and identifies the areas recommended to
undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the excavation were
collected. Soil samples were collected at the highest exposure-
rate location within each 30- by 30-foot section of the excavation
for Areas V-9 and V-10. These samples were blended to form
composite samples representing the verification areas (Appendix
Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 12 to 25 microroentgens per
hour (//R/h), as indicated on Appendix Figure 2.1. The results of
analyses for radium-226 in ten composite soil samples ranged from
2.0 to 5.6 picocuries per gram (pCi/g), as indicated in Appendix
Table 3.1.
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on the DOE-approved abbreviated-measurement method,
the RDC was 0.0099 working level (WL), as indicated in Appendix
Table 3.2. Appendix Figure 2.1 shows the measurement location
on the ground floor (the lowest habitable level of the structure).
4
DOE ID No.: MS-00194-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at 280 East First South Street, in
Monticello, Utah, is recommended for certification as required by DOE
guidelines, and the appropriate records should be documented.
Certification Data Summary
Applicability
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Standards
Shall not exceed 20 jt/R/h
above background.*
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Survey Results
Range for the ground
floor was 12 to 16//R/h.
Average was 0.0099 WL,
based on the DOE-
approved abbreviated-
measurement method.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
< 5 pCi/g above
background. ***
Soil sample results
ranged from 2.0 to
5.6 pCi/g.*
*The background exposure rate is approximately 16//R/h.
The background radium-226 concentration is approximately 2.0 pCi/g.
**Parts of samples V-3 and V-4 were from the 15-cm surface layer.
The hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-00194-RS
4.0 APPENDIX
Appendix Tables:
Table 3.1 Post-Excavation Sample/Measurement Results
Table 3.2 Radon Decay-Product Concentration Measurement
Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
RKJ:07-18-96
MS-00194.RS WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00194-RS
Address: 280 East First South Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (pR/h) Ticket No. Method" (pCi/g)
V-1
V-2
V-3
V-4
V-5
V-6
V-7
V-8
V-9
V-10
16
14
14
14
15
15
15
15
15
15
20
18
21
21
18
25
19
17
20
21
NCJ 544
NCL 791
NCL 792
NCL 793
NCL 712
NCL 713
NCL 714
NCL 716
NCL 717
NCL 718
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
3.5
2.3
3.0
2.0
3.8
3.
2,
2.
3.
5,
See Appendix Figure 2.1 for the verification areas.
"OCS = Opposed Crystal System
7
Table 3.2
Radon Decay-Product Concentration Measurement Results
DOE ID No.: MS-00194-RS
Address: 280 East First South Street, Monticello, Utah
Instrument Type: Landauer Radtrak Detector
Radon
Detector Concentration Working
Number Start Date End Date (pCi/L) Level
4147192 02-27-96 05-28-96 2.01 0.0101
4147319 02-27-96 05-28-96 1.76 0.0088
4147097 02-27-96 05-28-96 2.16 0.0108
Average: 0.0099
See Appendix Figure 2.1 for the measurement location.
8
42
40
38
36
34
32
30
28
26
24
22
20
18
16
14
12
10
12
T"
14 16 18 20 22 24 26 28 30
"T
32 34
EAST FIRST SOUTH STREET
./tt.
36
CLL
v-i 15-17 2
v-i
16-20
S© V-10
15-21
V-7
15-19
ONE STORY
FRAME HOUSE
12-16
13-17
ROC V-5
V-9
15-18 15-20
© V-10
15-21
fh V-3
14-21
.1 4
V-4
14-21
•©
• < 6 >••• V-6
SHED 15-25
14-18
©
30
E V-4
ED 7T7 14-21 15 V-2 SHEO
12-14 14-18
15
3 .18
V-8
© 12 15-17
I ® f<£> 15-20
V-10
15-21
CD
©r
0 i 14-17
15-20 15-18
ra ®
SCALE IN FEET
20 10 0 20 40
M:\FAS\OJJ\OOOJ\RM001f4v 07/30/M 2 47pm TS0780 NORTH
_! L
33
<
Q
CC.
o
in
THIS ORAWINC IS FOR THE SOLE USE Or THE U.S. DEPARTMENT
OF ENERGY ANO ITS CONTRACTORS. IT IS NOT A LANO SURVEY
PLAT. UTILITY LOCATION PLAT, OR OTHER IMPROVEMENT SURVEY
PLAT ANO IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE. BUILDINC. OR OTHER FUTURE IMPROVEMENT LINES
40
©
Lv.vj
12-15
12
v-i
16-17
42 44 46 48 50
i—r
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN jtR/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE-RATE RANGE
RADON DECAY-PRODUCT CONCENTRATION
MEASUREMENT LOCATION
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
•CUMMt-«0 0» KCu#wtf
••m4tKl-Mn->M
w u. «...
U.S. OEPARTUENT OF ENERGY c*»»o .faKTtow MOICCTI off'Ct. coioueo
!2Z
iii 280 EAST FIRST SOUTH STREET
MONTICELLO, UTAH
p|Jgp Rust OooUch «••"» MS-00I94-RS
— - 3-C00194-V1 .„ I „ '
12 14 16 18 20 22 24 26 28 30 32 34 36 38 40 42 46 48
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
280 EAST 1ST SOUTH STREET
MONTICELLO, UTAH (MS00194-RS)
M. K. Jensen
August 1996
"Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 4
REFERENCES 7
iii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 5
2. Results of ORNL analysis of Geotech soil samples from 280 East 1st South Street,
Monticello, Utah (MS00194-RS) 6
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site
Decommissioning Projects, U.S. Department of Energy. The author wishes to acknowledge
A. R. Jones and J. R. Sauvage for technical reviews.
vii
ABSTRACT
In 1980 the site of a vanadium and uranium mill at Monticello, Utah, was accepted into
the U.S. Department of Energy's (DOE's) Surplus Facilities Management Program, with the
objectives of restoring the government-owned mill site to safe levels of radioactivity, dis-
posing of or containing the tailings in an environmentally safe manner, and performing
remedial actions on off-site (vicinity) properties that had been contaminated by radioactive
material resulting from mill operations. During 1995, RUST Geotech, the remedial action
contractor designated by DOE, performed remedial action on the vicinity property at 280 East
1st South Street, Monticello, Utah. The Environmental Technology Section (ETS) of Oak
Ridge National Laboratory was assigned the responsibility of verifying the data supporting
the adequacy of remedial action and confirming the site's compliance with DOE guidelines.
The ETS found that the site successfully meets the DOE remedial action objectives. Proce-
dures used by the ETS are described in the Environmental Technology Section Procedures
Manual (ORNL 1993).
ix
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 280 EAST 1ST SOUTH STREET
MONTICELLO, UTAH (MS00194-RS)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the U.S. government through the
Defense Plant Corporation to provide vanadium during World War II. Various government
agencies operated the mill until 1947. In 1948 the Atomic Energy Commission (AEC) ob-
tained the mill and operated it under contract through 1959 to provide both uranium and
vanadium. Mill operations were terminated on January 1,1960. In 1961 the mill tailings piles
were leveled and graded, covered with rock and soil, and seeded with native grasses. During
1974 and 1975, the ore stockpiles were removed from the site, and the mill foundations were
buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city of
Monticello, in San Juan County, Utah. The site is bordered on the south and southeast by
land held by the U.S. Bureau of Land Management. Other boundaries are the city of
Monticello and private property.
During the AEC era, the mill processed approximately one million tons of uranium ore.
Vanadium and uranium were the only substances extracted in the milling process. Other con-
stituents of the ore remained in the tailings and were not separated prior to disposal. During
the years of active mill operation, the mill tailings were normally moist, so erosion was
minimal. However, throughout the mill's operating period, area residents used these tailings
as fill material and as aggregate-in mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy (DOE)
initiated the Surplus Facilities Management Program (SFMP) in 1978 to ensure the safe
caretaking and decommissioning of government facilities that had been retired from service
but still had radioactive contamination. In 1980 the mill site at Monticello was accepted into
the SFMP, and the Monticello Remedial Action Project (MRAP) was established to restore
the government-owned mill site to safe levels of radioactivity, to dispose of or contain the
tailings in an environmentally safe manner, and to perform remedial actions on off-site
(vicinity) properties that had been contaminated by radioactive material resulting from mill
operations. The Monticello mill site and the tailings remain in the custody of the DOE Grand
Junction, Colorado, Projects Office. In 1983 remedial actions for vicinity properties were
separated from MRAP with establishment of the Monticello Vicinity Properties (MVP)
Project (U.S. DOE 1990b).
*The verification of remedial action was performed by members of the Environmental Assessment Group in the
Environmental Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE
contract DE-AC05-96OR22464 with Lockheed Martin Energy Research Corporation.
2
During 1995, RUST Geotech Inc. (Geotech), the remedial action contractor (RAC)
designated by DOE, performed remedial action on the vicinity property that is the subject of
this report, a single family residence located at 280 East 1st South Street, Monticello, Utah.
The remedial action plan required excavation of all exterior contamination. When the excava-
tion was completed, the property was resurveyed, including soil sampling, to ensure the
removal of all contamination, backfilled with uncontaminated material, and restored to a
condition comparable to that which existed prior to remedial action (Geotech 1996).
The DOE adopted a policy to assign an independent contractor to verify the data
supporting the adequacy of remedial action and to confirm the site's compliance with DOE
guidelines. The Environmental Technology Section (ETS) of Oak Ridge National Laboratory
(ORNL) has been assigned the responsibility of this task at the 280 East 1st South Street site.
This report describes the methods and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available documenta-
tion adequately and accurately describes the post-remedial-action radiological conditions of
the entire property that is to be certified and (2) that the remedial action reduced con-
tamination to below applicable DOE guidelines (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1996) indicates
the property was remediated as evaluated by DOE on the basis of Environmental Protection
Agency standards and the DOE guidelines (DOE 1990a). Excess residual radioactive materi-
als were present,, thus it was appropriate to designate this property for remedial action.
The pre-remedial-action survey performed by Geotech identified 409 yd3 of mill tailings
6 inches deep. During the actual removal process, a total of 714 yd3 of contaniinated earth
and uranium mill tailings, 4 to 30 inches deep, were removed from a
2,347 m2 area.
A post-excavation survey was performed by Geotech prior to backfilling the excavated
areas. This survey consisted of gamma scans with a scintillometer of the ground level of the
structure, a surface scan of the exterior, and soil sampling. Samples representative of the
bottom 15-cm (6-in.) soil layers often excavated verification areas were collected and blend-
ed to form representative composite soil samples. Two of the exterior verification areas (V9
and V10) were sampled using large area protocol. Samples were taken at the highest gamma
exposure rate in each 30- by 30-foot section.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation
levels have not been subtracted. Similarly, background concentrations have not been sub-
tracted from radionuclide concentrations in soil samples. Applicable DOE guidelines for pro-
tection against radiation are given in Table 1.
Gamma Measurements
Gamma exposure rate measurements taken by Geotech at the ground-level of the
residence ranged from 12 to 16 uR/h. Exterior surface gamma measurements taken from the
excavated areas prior to backfilling ranged from 14 to 25 uR/h.
Soil Sample Analysis
Prior to backfilling, Geotech collected soil samples representative of the excavated areas
from the bottom 15-cm (6-in.) soil layers. These samples were blended to form composite
soil samples representative of an average over the ten exterior verification areas. Geotech's
analysis of these samples showed ^Ra concentrations ranging from 2.0 to 5.6 pCi/g in the
composite sample. ORNL ETS obtained the samples and performed a confirmatory analysis
which showed M6Ra concentrations of 3.5 and 3.7 pCi/g. These values are below the EPA
standard value of 15 pCi/g for soil layers > 15 cm below the surface. Results of Geotech and
ORNL soil sample analyses are given in Table 2.
As a result of a meeting between the RAC and IVC on May 26, 1994, anomalous
readings, defined as > 30% above the average of the excavation, will be investigated to show
compliance to the DOE hot spot guideline. The RAC remediated this property after this pro-
cedure change. Two of the verification areas exceeded this average (V3 and V6); therefore,
one excavation control sample was taken in Area V6 at the highest gamma exposure (25
uR/h). This soil sample had a ^Ra concentration of 8.7 pCi/g. This value is well below the
minimum concentration of 30 pCi/g needed, when assuming the maximum area under the hot
spot guideline of 25 m2, for subsurface samples. Gamma ranges and/or soil sample results
demonstrate compliance to the DOE Hot Spot Guidelines for areas <25 m2 (Table 1).
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were determined
by the Alpha-track method. To monitor radon levels, Geotech placed three alpha-track detec-
tors on the ground floor of the residence located on this property for a period of approxi-
mately three months (from February 27, 1996 to May 28, 1996). The average annual work-
ing level (WL) of radon progeny concentration, as determined by the Tech./Ops-Landauer
Corporation, was 0.0099, which is well below the 0.03-WL guideline given in Table 1.
4
CONCLUSION
Results of Geotech soil sample analysis and confirmatory split soil sample analysis by
ORNL show that radionuclide concentrations are within applicable DOE guidelines. Based
on the results of the post-remedial-action data, which are confirmed by the verification assess-
ment data, these radiological measurements fall below the limits prescribed by DOE guide-
lines. It is concluded that the site successfully meets the DOE remedial action objectives.
5
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of 226Ra in soil
above background levels,
averaged over a 100-m2 area
5 pCi/g averaged over the
first 15 cm of soil below the
surface; 15 pCi/g when ave-
raged over 15-cm-thick soil
layers more than 15 cm
below the surface
Radionuclide con-
centrations in soil
for Hot Spot areas
Maximum Permissible con-
centration of Ra226 in soil
above background level, for
areas less than 25 m2
Ra226 concentrations, in any
surface or subsurface area
less than 25 m2, is below the
guideline by a factor of
(100/A)'\ where A is the
area of the elevated region
Exposure to 222Rn
progeny
Average annual radon proge-
ny concentration (including
background)
0.03 WL
(DOE 1990a)
6
Table 2. Results of ORNL analysis of Geotech soil samples from
280 East 1st South Street, Monticello, Utah (MS00194-RS)
226Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No." No^ (cm)
XI NCJ 544 >15 3.7 3.5
X3 NCL 792 >15 3.5 3.0
* An X-type sample is a split of the sample taken by the remedial action contractor.
* Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated areas
were taken by Geotech, and these samples were blended to form a composite soil
sample, which represents an average over one of the verification areas.
DOE ID No.: MS-00194-RS
Property Address: 280 East First South Street
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech of Energy (DOE,
Ra-226 is <. 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [X]f
Ra-226 is s 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2.
In-situ [ ] Lab [X]
Interior gamma is ^ 20 jt/R/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is <. 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21.
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
W [ ] [ 1
[V] [ ] [ ]
m [ I [ 1
If] [ ] [ ]
[ ] li\ [ ]
p/] [ 1 [ ]
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
tParts of two samples were from the top layer, and were lab-analvzed.
SFCERTIFED SFMS-00194
DOE ID No.: MS-00194-RS
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
7 /anda SyBusby
Manager, Monticello Programs
Rust Geotech
Date
DOE EVALUATION
[ Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Certification Official r/ Date
U.S. Department of Energy
f DEC 11 1996 ^
PROPERTY COMPLETION REPORT
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
DOE ID NO.: MS-00196-RS
ADDRESS: 265 SOUTH THIRD EAST STREET
MONTICELLO, UTAH 84535
MARCH 1996
Prepared for
U.S. Department of Energy
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
FOR
FOR
by
' Warufa S. Busby
Manager, Monticello Programs
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
TABLE OF CONTENTS
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.1.3 Radon Decay-Product Concentration (RDC) Measurement .... 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
i
DOE ID No.: MS-00196-RS
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Inclusion Survey Contractor. DOE reviewed
these evaluation results and determined that the property contained mill
tailings (residual radioactive material) exceeding EPA standards. The
Remedial Action Contractor was notified of the inclusion of this property
into the MVP Project and was authorized by DOE to conduct remedial
action as required to bring the property into conformance with EPA
standards and DOE hot spot criteria.
1
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
Property Address:
Property Owners:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
DOE ID No.: MS-00196-RS
MS-00196-RS
Location M-225; beginning 1430 feet south
of the NE corner of Section 36, T33S.,
R23E., Salt Lake Base Meridian; west
130 feet, south 169 feet, east 130 feet,
north 169 feet to the beginning, City of
Monticello, County of San Juan, State of
Utah
265 South Third East Street
Monticello, Utah 84535 "

Residential Simple (RS)
Oak Ridge National Laboratory
October 23, 1989
Rust Geotech
November 11, 1993
Diamond Back Services, Inc.
9861 Titan Park Circle
Littleton, Colorado
August 3, 1994
September 14, 1994
Interior: 0 cubic yards
Exterior: 372 cubic yards
1,695 square meters (mJ)
March 1996
2
DOE ID No.: MS-00196-RS
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of exterior residual radioactive
material (Appendix Figure 2.1). Once excavation was complete, the
affected areas were resurveyed for possible remaining residual radioactive
material and, upon attaining satisfactory results, were backfilled with
uncontaminated material. The property was restored to a physical
condition comparable to that which existed prior to remedial action
activities.
2.2 Previously Unidentified Contamination
The radiological assessment identified contamination, ranging from 6 to
12 inches deep, within the property. The quantity of contamination for
this property was not specified because it was assessed as part of Block
MS-09028-BK. The remedial action process included the removal of
approximately 372 cubic yards of residual radioactive material, ranging
from 3 to 15 inches deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID No.: MS-00196-RS
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by the Remedial Action
Contractor during May 1992, as described in the final REA dated
November 1993. Appendix Figure 2.1 shows the extent of
assessed contamination and identifies the areas recommended to
undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the excavation were
collected. These samples were blended to form composite
samples representing the verification areas (Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 13 to 30 microroentgens per
hour (//R/h), as indicated on Appendix Figure 2.1. Residual
radioactive material was left in place in Areas V-1, V-2, V-3, and
V-5 to avoid causing permanent damage to mature trees. The
results of analyses for radium-226 in 4 composite soil samples of
these areas ranged from 9.3 to 14.7 picocuries per gram (pCi/g).
The 100 m2 area averages of these areas ranged from 2.4 to
3.8 pCi/g (Appendix Table 3.1). Areas V-1, V-2, V-3, and V-5
also met the hot spot criteria, as indicated in Appendix Table 3.2.
The results of analyses for radium-226 in 20 remaining composite
soil samples ranged from 3.5 to 14.5 pCi/g (Appendix Table 3.3).
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on the DOE-approved abbreviated-measurement method the
RDCs ranged from 0.0036 to 0.0065 working level (WL), as
indicated in Appendix Table 3.4. Appendix Figure 2.1 shows the
measurement locations on the lowest habitable level of each
structure. The RDCs were as follows:
• 0.0065 WL in the basement of House 1
• 0.0047 WL on the ground floor of House 2
• 0.0036 WL on the ground floor of House 3
4
DOE ID No.: MS-00196-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at 265 South Third East Street, in
Monticello, Utah, is recommended for certification as required by DOE
guidelines, and the appropriate records should be documented.
Certification Data Summary
Applicability
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Standards
Shall not exceed 20 //R/h
above background.*
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Survey Results
Ranges were 11 to
12 //R/h for the basement
of House 1, 12 to
13 //R/h for the ground
floor of House 2, and
13 to 15 //R/h for the
ground floor of House 3.
Averages ranged from
0.0036 to 0.0065 WL,
based on the DOE-
approved abbreviated-
measurement method.
Land.
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
Soil sample results,
averaged over 100 m2
areas, ranged from 2.4 to
3.8 pCi/g.**
Soil sample results
ranged from 3.5 to
14.5 pCi/g.**
*The background exposure rate is approximately 15 //R/h.
The background radium-226 concentration is approximately 2.0 pCi/g.
**The hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-00196-RS
4.0 APPENDIX
Appendix Tables
Table 3.1 Calculations of Average Radium Concentrations
over 100 m2 Areas
Table 3.2 Hot Spot Calculation Results
Table 3.3 Post-Excavation Sample/Measurement Results
Table 3.4 Radon Decay-Product Concentration Measurement
Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
MRW:02-29-96
MS-00196.RS WP61
REV080195
6
Table 3.1
Calculations of Average Radium Concentrations over 100 m2 Areas
DOE ID No.: MS-00196-RS
Address: 265 South Third East Street, Monticello, Utah
Where:
'avg
1,076 =
'avg
(CpXAp) + [Crx (1,076-Ap)]
1,076
Radium-226 concentration in picocuries per gram averaged over a
100 m2 (1,076 ft2) area.
Radium-226 concentration in picocuries per gram of the residual
radioactive material left in place.
Area in square feet of the residual radioactive material left in
place.
Radium-226 concentration in picocuries per gram for the
remainder of the 100 m2 area, including excavated and
unexcavated areas.
Total area in square feet over which the EPA guideline is applied.
Area
Meas.
Method"
Depth
(inches)
p
(pCi/g)
P
(ft2) (pCi/g)
'-avg
(pCi/g)
EPA
Standard
(pCi/g)
V-1
V-2
V-3
V-5
OCS
OCS
OCS
OCS
03 - 06
04-06
03 - 06
03 - 06
14.7
9.3
12.2
10.4
154
113
113
50
2.0b
2.0b
2.0b
2.0b
3.8
2.8
3.1
2.4
5.0e
5.0C
5.0C
5.0C
Therefore, the averaged radium-226 concentrations do not exceed the EPA standard.
"OCS = Opposed Crystal System,
background radium-226 concentration.
The DOE-implemented EPA standard used for OCS measurements taken after
December 7, 1990, does not include the background radium concentration.
t
7
Table 3.2
Hot Spot Calculation Results
DOE ID No.: MS-00196-RS
Address: 265 South Third East Street, Monticello, Utah
Shg = [Sgx (100/A)34]
Where:
Shg = Hot Spot Limit of radium-226 concentration in picocuries per gram.
Sq = Authorized Limit of radium-226 concentration in picocuries per gram
(Sa = 5.0 pCi/g for surface soil and 15.0 pCi/g for subsurface
soils).
100 = Total area in square meters over which the Hot Spot Limit guideline
is applied.
A = Area in square meters of the hot spot.
A Sg Sh + Radium-226 in
Meas. Depth Background6 Hot Spot Area
Area Method* (inches) (m2) (pCi/g) (pCi/g) (pCi/g)
V-1 OCS 03-06 14.3 5.0 15.2 14.7
V-2 OCS 04-06 10.5 5.0 17.4 9.3
V-3 OCS 03-06 10.5 5.0 17.4 12.2
V-5 OCS 03-06 4.6 5.0 25.3 10.4
Therefore, the radium-226 concentrations in the hot spot areas do not exceed the
maximum allowable concentrations.
"OCS = Opposed Crystal System.
bMaximum allowable radium-226 concentration (the background radium-226
concentration for Monticello is 2.0 pCi/g).
8
Table 3.3
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00196-RS
Address: 265 South Third East Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (//R/h) Ticket No. Method" (pCi/g)
V-1 16-24 NCE 989 OCS 14.7
V-2 19-23 NCD 702 OCS 9.3
V-3 19-23 NCD 703 OCS 12.2
V-4 19-23 NCE 990 OCS 13.7
V-5 19-21 NCD 705 OCS 10.4
V-6 15-18 NCD 709 OCS 3.5
V-7 15-18 NCD 708 OCS 5.3
V-8 15-18 NCD 707 OCS 4.7
V-9 15-21 NCD 706 OCS 4.8
V-10 16-19 NCE 512 OCS 6.8
V-11 18-23 NCE 513 OCS 6.0
V-T2 17-23 NCE 514 OCS 7.9
V-13 15-19 . NCE 515 OCS 7.1
V-14 19-30 NCD 711 OCS 14.5
V-15 18-24 NCD 712 OCS 7.6
V-16 16-21 NCD 713 OCS 4.3
V-17 16.-24 NCE 518 OCS 10.7
V-18 18-24 NCE 519 OCS 7.9
V-19 18-24 NCG 437 OCS 9.8
V-20 17- 29 NCG 440 OCS 14.0
V-21 19-24 NCG 439 OCS 13.9
V-22 18- 24 NCB 923 OCS 9.0
V-23 17 - 23 NCB 924 OCS 5.6
V-24 18-21 NCB 925 OCS 6.6
See Appendix Figure 2.1 for the verification areas.
"OCS = Opposed Crystal System
9
Table 3.4
Radon Decay-Product Concentration Measurement Results
DOE ID No.: MS-00196-RS
Address: 265 South Third East Street, Monticello, Utah
Instrument Type: Landauer Radtrak Detector
Detector
Number Start Date End Date
Radon
Concentration
(pCi/L)
Working
Level
3974012
3974058
3973937
3964302
3964160
3964270
3964358
3964203
3964340
08-10-95
08-10-95
08-10-95
02-27-95
02-27-95
02-27-95
02-28-95
02-28-95
02-28-95
HOUSE 1
11-15-95
11-15-95
11-15-95
HOUSE 2
05-30-95
05-30-95
05-30-95
HOUSE 3
06-01-95
06-01-95
06-01-95
1.505 0.0075
1.050 0.0053
1.360 0.0068
Average: 0.0065
0.88 0.0044
1.13 0.0057
0.82 0.0041
Average: 0.0047
0.87 0.0044
0.53 0.0027
0.71 0.0036
Average: 0.0036
See Appendix Figure 2.1 for the measurement locations.
10
42
40
33
35
34
32
30
28
26
24
22
20
18
16
14
12
10
12
"T~
16 18 20 22 24 26 28 30 32 34
OL
I—
3
O
"777 777 777"
EAST THIRO SOUTH STREET
SCALE IN FEET
20 10 0 20 40
V:VAS\0JJ\00O3Vtu001«6v OVOs/Sf 08 21«m T50?S0
NORTH
36 38
r-GARAGE ::1
© 14-16 14-16
=1
0 V-24 0-^ RDC
V-9 18-2
© © 0 15-21 ONE STORY
STUCCO
HOUSE 1
W/BASEMENT
11-12 ©7+0
V-8
15-18
V-7 V-24
©UJ 15-18 18-21
ONE 14-15 V-10
STORY
Mr* FRAME 16-19
© HOUSE 3 0 © 0 13-15
0 v-6 V-2
RDC
© 15-ia 19-2 J
V-1 1
© 18-23
H V-5
15 0 v-22 0 19-21
V-12 18-24 © 17-23 V-3 V-13 V- 1
19-23 5-19 © 16-24
' 14-1
12.-V-21
SHED ONE STORY 19-2* STUCCO 13-16 HOUSE 2
3 12-13 V-15
I 21. RDC
3©: 18-24
0 V-l 6
V-20
18-21 01;:© •0 17-29
S..V.1.
—f
V-17 V-14
16-24 19-30
V-19 v-18
18-24 18-24
ADDRESSED
UNDER
MS-00195-CS
THIS DRAWING IS FOR THE SOLE USC Of THC U.S. OEPARTUENT
Of ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT UTILITY LOCATION PLAT. OR OTHER IMPROVEMENT SURVEY
PLAT ANO IS NOT TO BE RELIEO UPON FOR THE ESTABLISHMENT
OF FENCE. 8UIL0ING. OR OTHER FUTURE IMPROVEMENT LINES.
12 1 4 16 18 20 22 24 26 28 30 32 34 36 33
40
©
Lv.vj
12-15
12
v-i
16-17
42 46
"T
48
LECENO
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN /tR/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXPOSURE-RATE RANGE
RADON DECAY-PRODUCT CONCENTRATION
MEASUREMENT LOCATION
AREA WITH CONTAMINATION LEFT IN PLACE
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
40
U.S. OEPARTUENT OF ENERGY
B JUNCTION MOJCCTI Of net. COlO«A0O
"3^
265 SOUTH THIRD EAST STREE
MONTICELLO, UTAH
Rust 0«ttch MS-00196-RS
... |»~" 3-C00196-V1~ 1 , 1
42 44 46 48
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION .
OF RADIOLOGICAL REMEDIAL ACTION AT
265 SOUTH 3RD EAST STREET
MONTICELLO, UTAH (MS00196-RS)
M. J. Wilson-Nichols
July 1996
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 4
CONCLUSION 4
REFERENCES 8
iii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 5
2. Results of ORNL analysis of Geotech soil samples from 265 South 3rd East Street,
Monticello, Utah (MSOO196-RS) 6
3. ORNL verification soil calculations from 265 South 3rd East Street, Monticello,
Utah (MSOO 196-RS) 7
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site
Decommissioning Projects, U.S. Department of Energy. The author wishes to
acknowledge M. K. Jensen for analysis of soil samples and A. R. Jones and N. F.
Kirby for technical reviews.
vii
ABSTRACT
In 1980 the site of a vanadium and uranium mill at Monticello, Utah, was accepted
into the U.S. Department of Energy's (DOE's) Surplus Facilities Management Program,
with the objectives of restoring the government-owned mill site to safe levels of radio-
activity, disposing of or containing the tailings in an environmentally safe manner, and
performing remedial actions on off-site (vicinity) properties that had been contaminated
by radioactive material resulting from mill operations. During 1994, RUST Geotech, the
remedial action contractor designated by DOE, performed remedial action on the vicinity
property at 265 South 3rd East Street, Monticello, Utah. The Environmental Technology
Section (ETS) of Oak Ridge National Laboratory was assigned the responsibility of
verifying the data supporting the adequacy of remedial action and confirming the site's
compliance with DOE guidelines. The ETS found that the site successfully meets the
DOE remedial action objectives. Procedures used by the ETS are described in the
Environmental Technology Section Procedures Manual (ORNL 1993).
ix
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 265 SOUTH 3RD EAST STREET
MONTICELLO, UTAH (MS00196-RS)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the U.S. government through the
Defense Plant Corporation to provide vanadium during World War U. Various govern-
ment agencies operated the mill until 1947. In 1948 the Atomic Energy Commission
(AEC) obtained the mill and operated it under contract through 1959 to provide both
uranium and vanadium. Mill operations were terminated on January 1, 1960. In 1961 the
mill tailings piles were leveled and graded, covered with rock and soil, and seeded with na-
tive grasses. During 1974 and 1975, the ore stockpiles were removed from the site, and
the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city
of Monticello, in San Juan County, Utah. The site is bordered on the south and southeast
by land held by the U.S. Bureau of Land Management. Other boundaries are the city of
Monticello and private property.
During the AEC era, the mill processed approximately one million tons of uranium
ore. Vanadium and uranium were the only substances extracted in the milling process.
Other constituents of the ore remained in the tailings and were not separated prior to dis-
posal. During the years of active mill operation, the mill tailings were normally moist, so
erosion was minimal. However, throughout the mill's operating period, area residents
used these tailings as fill material and as aggregate in mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy
(DOE) initiated the Surplus Facilities Management Program (SFMP) in 1978 to ensure
the safe caretaking and decommissioning of government facilities that had been retired
from service but still had radioactive contamination. In 1980 the mill site at Monticello
was accepted into the SFMP, and the Monticello Remedial Action Project (MRAP) was
established to restore the government-owned mill site to safe levels of radioactivity, to dis-
pose of or contain the tailings in an environmentally safe manner, and to perform remedial
actions on off-site (vicinity) properties that had been contaminated by radioactive material
resulting from mill operations. The Monticello mill site and the tailings remain in the cus-
tody ofthe DOE Grand Junction, Colorado, Projects Office. In 1983 remedial actions for
vicinity properties were separated from MRAP with establishment of the Monticello
Vicinity Properties (MVP) Project (U.S. DOE 1990b).
*The verification of remedial action was performed by members of the Environmental Assessment Group in the
Environmental Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE
contract DE-AC05-96OR22464 with Lockheed Martin Energy Research Corporation.
2
During 1994, RUST Geotech Inc. (Geotech), the remedial action contractor (RAC)
designated by DOE, performed remedial action on the vicinity property that is the subject
of this report, a multi-family residence located at 265 South 3rd East Street, Monticello,
Utah. The remedial action plan required excavation of all exterior contamination. When
the excavation was completed, the property was resurveyed, including soil sampling, to
ensure the removal of all contamination, backfilled with uncontaminated material, and re-
stored to a condition comparable to that which existed prior to remedial action (Geotech
1996).
The DOE adopted a policy to assign an independent contractor to verify the data
supporting the adequacy of remedial action and to confirm the site's compliance with DOE
guidelines. The Environmental Technology Section (ETS) of Oak Ridge National Labor-
atory (ORNL) has been assigned the responsibility of this task at the 265 South 3rd East
Street site. This report describes the methods and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available docu-
mentation adequately and accurately describes the post-remedial-action radiological
conditions of the entire property that is to be certified and (2) that the remedial action
reduced contamination to below applicable DOE guidelines (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1996) in-
dicates the property was remediated as evaluated by DOE on the basis of Environmental
Protection Agency standards and the DOE guidelines (DOE 1990a). Excess residual
radioactive materials were present, thus it was appropriate to designate this property for
remedial action.
This property was assessed as part of Block MS09028, therefore, the quantity of
material assessed is not available. During the actual removal process, a total of 372 yd3
of contaminated earth and uranium mill tailings, 3 to 15 inches deep, was removed from
a 1695 m2 area.
A post-excavation survey was performed by Geotech prior to backfilling the exca-
vated areas. This survey consisted of gamma scans with a scintillometer of the ground
level ofthe structure, a surface scan of the exterior, and soil sampling. Samples repre-
sentative ofthe bottom 15-cm (6-in.) soil layers of 20 excavated verification areas were
collected and blended to form representative composite soil samples for each verification
area. Composite soil samples were also collected from the surface soil interval in four
areas where residual radioactive material was left in place around mature trees.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation
levels have not been subtracted. Similarly, background concentrations have not been sub-
tracted from radionuclide concentrations in soil samples. Applicable DOE guidelines for
protection against radiation are given in Table 1.
Gamma Measurements
Gamma exposure rate measurements taken by Geotech in the basement of House 1
ranged from 11 to 12 uR/h and at ground-level of House 2 and House 3 ranged from 12
to 15 pR/h. Exterior surface gamma measurements taken from the excavated areas prior
to backfilling ranged from 15 to 30 uR/h.
Soil Sample Analysis
Prior to backfilling, Geotech collected 20 soil samples representative of the excavated
areas from the bottom 15-cm (6-in.) soil layers. Four soil samples representative of the
surface soil interval were also collected. These samples were blended to form a composite
soil sample representative of an average over the 24 exterior verification areas. Geotech's
analysis of these samples showed ^Ra concentrations ranging from 3.5 to 14.7 pCi/g in
the composite samples. ORNL ETS obtained a percentage of these soil samples and per-
formed a confirmatory analysis which showed ~6Ra concentrations ranging from 3.5 to
18.5 pCi/g. These values are below the EPA standard value of 5 pCi/g for surface soil
layers and 15 pCi/g for soil layers > 15 cm below the surface averaged over 100 m2.
Results of Geotech and ORNL soil sample analyses are given in Table 2.
Composite soil samples collected from verification areas VI, V2, V3, and V5 with
residual radioactive material left in place, were averaged to show compliance to EPA and
DOE guidelines.
Verification area VI consists of residual radioactive material left in place around a
mature tree with an approximate area of 14 m2 and a depth from 7.5 to 15 cm. ORNL's
laboratory analysis of the split sample XI yielded a 226Ra concentration of 18.5 pCi/g.
When area-averaged the result is below the EPA standard of 5 pCi/g averaged over 100 m2,
however, the soil result is above the Hot Spot guideline of 15 pCi/g. The surface 7.5 cm
has been backfilled with clean soil that has a ^Ra concentration of approximately 2 pCi/g.
If the area were resampled to determine compliance to the Hot Spot guideline, the sample
would be 15 cm thick and consisting of 7.5 cm of clean backfill and 7.5 cm of material at
18.5 pCi/g. When average together this would give a result of 10.3 pCi/g, which is below
the Hot Spot guideline of 15 pCi/g. Therefore, based on this information and the RAC field
result below the Hot Spot guideline, ORNL believes this verification area is in compliance
with the DOE remedial action objectives. ORNL verification soil calculations are given in
Table 3.
4
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were deter-
mined by the Alpha-track method. To monitor radon levels, Geotech placed three alpha-
track detectors on the ground floor of each residence located on this property for a period
of approximately three months (from August 10, 1995 to November 15, 1995, for House
1; from February 27, 1995 to May 30, 1995, for House 2; and February 28, 1995 to June
1, 1995, for House 3). The average annual working level (WL) of radon progeny con-
centration, as determined by the Tech./Ops-Landauer Corporation, was 0.0065, 0.0047,
and 0.0036, respectively, which are well below the 0.03-WL guideline given in Table 1.
CONCLUSION
Results of Geotech soil sample analysis and confirmatory split soil sample analysis
by ORNL show that radionuclide concentrations are within applicable DOE guidelines.
Based upon the results of the post-remedial-action data, which are confirmed by the
verification assessment data, these radiological measurements fall below the limits pre-
scribed by DOE guidelines. It is concluded that the site successfully meets the DOE
remedial action objectives.
5
Table 1. Applicable guidelines for protection against radiation
Mode of exposure
Radionuclide con-
centrations in soil
Exposure conditions
Maximum permissible con-
centration of ^Ra in soil
above background levels,
averaged over a 100-m2 area
Guideline value
5 pCi/g averaged over the
first 15 cm of soil below the
surface; 15 pCi/g when ave-
raged over 15-cm-tHick soil
layers more than 15 cm
below the surface
Ra226 concentrations, in any
surface or subsurface area
less than 25 m2, is below the
guideline by a factor of
(lOO/A)*, where A is the
area of the elevated region
0.03 WL
Radionuclide
concentrations in soil
for Hot Spot areas
Maximum Permissible con-
centration of Ra226 in soil
above background level, for
areas less than 25 m2
Exposure to ^Rn
progeny
Average annual radon proge-
ny concentration (including
background)
(DOE 1990a)
6
Table 2. Results of ORNL analysis of Geotech soil samples
from 265 South 3rd East Street, Monticello Utah (MS00196-RS)
'Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No." No.6 (cm)
XI NCE989 7.5 to 15 18.5 -14.7
X10 NCE512 >15 7.7 6.8
X14 NCD711 >15 9.2 14.5
X23 NCB924 >15 3.5 5.6
" An X-type sample is a split of the sample taken by the remedial action contractor.
* Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated areas
were taken by Geotech, and these samples were blended to form a composite soil
sample, which represents an average over one of the verification areas.
7
Table 3. ORNL verification soil calculations from
265 South 3rd East Street, Monticello, Utah (MSOO 196-RS)
ORNL
sample
No.
Sample
depth
(cm)
226Ra
concentration,
pCi/g
Representative
area,
m2
Net estimated
area-weighted
average*
(pCi/g, CAW)
Hot Spot
guideline
(pCi/g)**
XI 7.5 to 15 18.5 14 1.2 15
Formula used:
-AW
AW
where
C
A
100
« CAD,
M (100X0.15)
= area-weighted ^'Ra concentration, pCi/g
= net ^Ra concentration, pCi/g (gross minus background)
= area of region, m2
= thickness of sample, m
= threshold area, m2
0.15 = threshold thickness, m
Hot Spot limit
SHg = Sg x (100ro2M)1/2 + BKG
where
S Hg the Hot Spot Limit, pCi/g
the Authorized Limit (5 pCi/g for surface soil or 15 pCi/g for subsurface
soil)
the area of the hot spot in m2.
8
REFERENCES
Geotech 1996. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MSOO 196-RS, Address: 265 South Third East Street,
Monticello, Utah 84535, Geotech, Grand Junction, Colorado, March 1996.
ORNL, 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
U. S. DOE 1990a. Verification and Certification Protocolfor the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination
and Decommissioning Program, Revision 3, November 1990. U.S. Department of
Energy, Washington, D.C.
U.S. DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision
and Record of Decision Summary. U.S. Department of Energy, Grand Junction Projects
Office, Grand Junction, Colorado.
DOE ID No.: MS-00196-RS
Property Address: 265 South Third East Street
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech of Energy (DOE)
Ra-226 is =s 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [X]
Ra-226 is < 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2.
In-situ [ ] Lab [X]
Interior gamma is < 20 pR/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is < 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21.
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
[>] [ ] [ ]
m I ] [ 1
\/H i ] t 1
[>] [ ] [ 1
[ 1 [ 1
|V] [ ] [ ]
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
SFCERTIFED SFMS-09028
DOE ID No.: MS-00196-RS
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Wanda S.^Busby Date
Manager, Monticello Programs
Rust Geotech
DOE EVALUATION
Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Certification Official
U.S. Department of Energy
Date
/
DOE ID No.: MS-00206-RS
Property Address: 349 South Second West Street
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech of Energy (DQE)
Ra-226 is < 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [ ]
Ra-226 is £ 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2.
In-situ [ ] Lab [X]
Interior gamma is <, 20 //R/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is < 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21.
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
M [ ] I J
[Yl [ 1 [ 1
MM I 1
M [ I [ I
t i m [ I
[V] [ ] [ ]
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
•Illlllll
SFCERTIFED 11
SFMS-00206
11111
DOE ID No.: MS-00206-RS
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Date Wanda S. Busby I
Manager, Monticello Programs
Rust Geotech
DOE EVALUATION
[*] Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
CejfificationTJfficial
U.S. Department of Energy
Date
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00206-RS
ADDRESS: 349 SOUTH SECOND WEST STREET
MONTICELLO, UTAH 84535
JUNE 1996
Prepared for
U.S. Department of Energy
by
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
Wanda S. Busby /
Manager, Monticello Programs
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.1.3 Radon Decay-Product Concentration (RDC) Measurement .... 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
i
DOE ID No.: MS-00206-RS
1.0 SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Inclusion Survey Contractor. DOE reviewed
these evaluation results and determined that the property contained mill
tailings (residual radioactive material) exceeding EPA standards. The
Remedial Action Contractor was notified of the inclusion of this property
into the MVP Project and was authorized by DOE to conduct remedial
action as required to bring the property into conformance with EPA
standards and DOE hot spot criteria.
1
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
Property Address:
Property Owner:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
DOE ID No.: MS-00206-RS
MS-00206-RS
Beginning 119.5 feet south of the NW
corner of Lot 3, Block 6, Monticello
Townsite Survey; east 77 feet, south
95 feet, west 77 feet, north 95 feet to
beginning, County of San Juan, State of
Utah
349 South Second West Street
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
November 26, 1990
Rust Geotech
November 11,1993
Diamond Back Services, Inc.
9861 Titan Park Circle
Littleton, Colorado
June 16, 1994
September 1, 1994
Interior: 0 cubic yards
Exterior: 11 cubic yards
23 square meters (m2)
June 1996
2
DOE ID No.: MS-00206-RS
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of exterior residual radioactive
material (Appendix Figure 2.1). Once excavation was complete, the
affected area was resurveyed for possible remaining residual radioactive
material and, upon attaining satisfactory results, was backfilled with
uncontaminated material. The property was restored to a physical
condition comparable to that which existed prior to remedial action
activities.
2.2 Previously Unidentified Contamination
The radiological assessment identified 14 cubic yards of contamination,
12 inches deep, within the property. The remedial action process
included the removal of approximately 11 cubic yards of residual
radioactive material, 14 inches deep. The differences in the extent of
assessed contamination and actual residual radioactive material removed
are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID No.: MS-00206-RS
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
Radiological surveys were conducted by the Remedial Action
Contractor during August 1991 and April 1992, as described in
the final REA dated November 1993. Appendix Figure 2.1 shows
the extent of assessed contamination and identifies the area
recommended to undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the excavation were
collected. These samples were blended to form a composite
sample representing the verification area (Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 12 to 40 microroentgens per
hour (//R/h), as indicated on Appendix Figure 2.1. Elevated
exposure rates in Area V-1 were associated with the property
adjoining the south inclusion boundary. The result of analysis for
radium-226 in one composite soil sample was 10.1 picocuries per
gram (pCi/g), as indicated in Appendix Table 3.1.
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on measurements representing an annual average, the RDC
was 0.0187 working level (WL), as indicated in Appendix
Table 3.2. Appendix Figure 2.1 shows the measurement location
in the basement (the lowest habitable level of the structure).
4
DOE ID No.: MS-00206-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at 349 South Second West Street, in
Monticello, Utah, is recommended for certification as required by DOE
guidelines, and the appropriate records should be documented.
Certification Data Summary
Applicability
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Standards
Shall not exceed 20 //R/h
above background.*
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Survey Results
Range for the basement
was 13 to 15 //R/h.
Annual average was
0.0187 WL.
Land.
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
< 5 pCi/g above
background.**
Soil sample result was
10.1 pCi/g.**
*The background exposure rate is approximately 13 //R/h.
The background radium-226 concentration is approximately 2.0 pCi/g.
**The hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-00206-RS
4.0 APPENDIX
Appendix Tables:
Table 3.1 Post-Excavation Sample/Measurement Results
Table 3.2 Radon Decay-Product Concentration Measurement
Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
SJW:05-28-96
MS-00206.RS WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00206-RS
Address: 349 South Second West Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range i/jR/h) Ticket No. Method" (pCi/g)
V-1 16-40 NCG 497 OCS 10.1
See Appendix Figure 2.1 for the verification area.
"OCS = Opposed Crystal System
7
Table 3.2
Radon Decay-Product Concentration Measurement Results
DOE ID No.: MS-00206-RS
Address: 349 South Second West Street, Monticello, Utah
Instrument Type: Landauer Radtrak Detector
Radon
Detector Concentration Working
Number Start Date End Date (pCi/L) Level
3839324
3853879
3853822
10-10-94
10-10-94
10-10-94
09-27-95
09-27-95
09-27-95
3.36
3.80
4.08
0.0168
0.0190
0.0204
Annual Average: 0.0187
See Appendix Figure 2.1 for the measurement location.
8
10 12 14 16 18 20 22 24 26 28 30 32 34 36 38 40
30
Y
10
LU
UJ or
i—
in
r—
co
o o
LU
CO
3
o
r 12-15
ONE STORY
HOUSE WITH
BASEMENT
13-15
L 12-15
7
SHED
12-14
SCALE IN FEET
1
12-15
V-1
It-40
A K1 1 4
20 10 0 20 40
^ M:\FAS\033\0003\RM00206V 05/29/96 2:55pm T50780
_J L_ I I L I L
4 9
NORTH
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT, UTILITY LOCATION PLAT, OR OTHER IMPROVEMENT SURVEY
PLAT AND IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE, BUILDING. OR OTHER FUTURE IMPROVEMENT LINES.
12 1 4 1 6 18 20 22 24 26 28
©
rrr.-q
L7.VJ
12-15
1 2
V-1
16-17
(RDC)
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN /xR/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST—REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE IXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE-RATE RANGE
RADON DECAY-PRODUCT CONCENTRATION
MEASUREMENT LOCATION
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
28
26
24
22
20
18
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERICR EXTENT OF CONTAMINATION
16
RESIDENCE-NO. OF OCCUPANTS
NON—RESIDENCE—UAN—HRS./WK.
INSTRUMENT NO.
SURVET OATE
SY CK. A.E. BY CK. A.E. APP
1 4
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE, COLORADO
1 349 SOUTH SECOND WEST ST.
MONTICELLO, UTAH
12
Rust Qeotech
AWMHTlilinliiHiiiCllMi
DATE APPROVAL OOE
DOEIONO. MS-00206-RS
owe.NO. 3-B00206-V1 sm 1 or 1 10
30 32 34 36 38 40
OAK RIDGE NATIONAL LABORATORY PHONE: (9?O) 24M200
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION FAX: [phone]
FOR THE U.S. DEPARTMENT OF ENERGY
POST OFFICE BOX 2567
GRAND JUNCTION, COLORADO 81502
JAN 3 I 1997
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by the U.S.
Department of Energy for Residual Radioactive Material at Formerly Utilized Sites Remedial
Action Program (FUSRAP) and Remote Surplus Facilities Management Program Sites (SFMP)
[Revision 2, March 1987]. This evaluation is based on an independent verification review of the
Remedial Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment of the
226Ra concentration in the soil, indoor radon daughter concentration, and indoor gamma exposure
rates at this property.
This property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
Location Number:
Location Address:
Property Owner:
Owner Address:
Tenant Name:
MS00206
349 South 2nd West Street
Monticello. Utah 84535

Same
Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
349 SOUTH 2ND WEST STREET
MONTICELLO, UTAH (MS00206)
A. R. Jones
January 1997
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81503
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 4
REFERENCES 7
iii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 5
2. Results of ORNL analysis of the RAC soil samples from 349 South 2nd West Street,
Monticello, Utah (MS00206) 6
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site Decommissioning
Projects, U.S. Department of Energy. The author wishes to acknowledge M. K. Jensen for analysis
of soil samples and technical review and S. M. Smith for technical review.
vii
ABSTRACT
In 1980, the site of a vanadium and uranium mill at Monticello, Utah, was accepted into the
U.S. Department of Energy (DOE) Surplus Facilities Management Program, with the objectives of
restoring the government-owned mill site to safe levels of radioactivity, disposing of or containing
the tailings in an environmentally safe manner, and performing remedial actions on off-site (vicinity)
properties that had been contaminated by radioactive material resulting from mill operations. During
1994, the Remedial Action Contractor (RAC) designated by DOE, performed remedial action on the
vicinity property at 349 South 2nd West Street, Monticello, Utah. The Environmental Technology
Section (ETS) of Oak Ridge National Laboratory was assigned the responsibility of verifying the
data supporting the adequacy of remedial action and confirming the site's compliance with DOE
guidelines. The ETS found that the site successfully meets the DOE remedial action objectives. All
questions noted in the initial review have been resolved. Procedures used by the ETS are described
in the Environmental Technology Section Procedures Manual (ORNL 1993).
be
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 349 SOUTH 2ND WEST STREET
MONTICELLO, UTAH (MS00206)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the United States (U.S.) government through
the Defense Plant Corporation to provide vanadium during World War II. Various government
agencies operated the mill until 1947. In 1948, the Atomic Energy Commission (AEC) obtained the
mill and operated it under contract through 1959 to provide both uranium and vanadium. Mill
operations were terminated on January 1, 1960. In 1961, the mill tailings piles were leveled and
graded, covered with rock and soil, and seeded with native grasses. During 1974 and 1975, the ore
stockpiles were removed from the site and the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city of
Monticello, in San Juan County, Utah. The site is bordered on the south and southeast by land held
by the U.S. Bureau of Land Management. Other boundaries are the city of Monticello and private
property.
During the AEC era, the mill processed approximately one million tons of uranium ore. Vana-
dium and uranium were the only substances extracted in the milling process. Other constituents of
the ore remained in the tailings and were not separated prior to disposal. During the years of active
mill operation, the mill tailings were normally moist, so erosion was minimal. However, throughout
the mill's operating period, area residents used these tailings as fill material and as aggregate in
mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy (DOE) initiated
the Surplus Facilities Management Program (SFMP) in 1978 to ensure the safe caretaking and de-
commissioning of government facilities that had been retired from service but still had radioactive
contamination. In 1980, the mill site at Monticello was accepted into the SFMP, and the Monticello
Remedial Action Project (MRAP) was established to restore the government-owned mill site to safe
levels of radioactivity, to dispose of or contain the tailings in an environmentally safe manner, and
to perform remedial actions on off-site (vicinity) properties that had been contaminated by radio-
active material resulting from mill operations. The Monticello mill site and the tailings remain in
the custody of the DOE Grand Junction, Colorado, Projects Office. In 1983, remedial actions for
vicinity properties were separated from MRAP with establishment ofthe Monticello Vicinity Proper-
ties (MVP) Project (US DOE 1990b).
*The verification of remedial action was performed by members ofthe Environmental Assessment Group in the Environmental
Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE contract DE-AC05-
960R22464 with Lockheed Martin Energy Research Corporation.
2
During 1994, the Remedial Action Contractor (RAC) designated by DOE, performed remedial
action on the vicinity property that is the subject of this report, a single family residence located at
349 South 2nd West Street, Monticello, Utah. The remedial action plan required excavation of all
exterior contamination. When the excavation was completed, the property was resurveyed, including
soil sampling, to ensure the removal of all contamination, backfilled with uncontaminated material,
and restored to a condition comparable to that which existed prior to remedial action (Geotech 1996).
DOE adopted a policy to assign an independent contractor to verify the data supporting the
adequacy of remedial action and to confirm the site's compliance with DOE guidelines. The Environ-
mental Technology Section (ETS) of Oak Ridge National Laboratory (ORNL) has been assigned the
responsibility of this task at the 349 South 2nd West Street site. This report describes the methods
and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available documentation
adequately and accurately describes the post-remedial-action radiological conditions of the entire
property that is to be certified and (2) that the remedial action reduced contamination to below
applicable DOE guidelines (US DOE 1990a).
Document Reviews
Review of the RAC property completion report (Geotech 1996) indicates the property was reme-
diated as evaluated by DOE on the basis of U.S. Environmental Protection Agency standards and the
DOE guidelines (US DOE 1990a). Excess residual radioactive materials were present, thus it was
appropriate to designate this property for remedial action.
The pre-remedial-action survey performed by the RAC identified 14 yd3 of mill tailings 12 inches
deep. During the actual removal process, a total of 11 yd3 of contaminated earth and uranium mill
tailings, 14 inches deep, were removed from a 23 nr area.
The RAC performed a post-excavation survey prior to backfilling the excavated area. This
survey consisted of gamma scans with a scintillometer of the ground level of the structure, a surface
scan ofthe exterior, and soil sampling. Samples representative of the bottom 15-cm (6-in.) soil layers
ofthe excavated verification area were collected and blended to form a representative composite soil
sample.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation levels have
not been subtracted. Similarly, background concentrations have not been subtracted from radionu-
clide concentrations in soil samples. Applicable DOE guidelines for protection against radiation are
given in Table 1.
Gamma Measurements
Gamma exposure rate measurements taken by the RAC at the ground-level of the residence
ranged from 13 to 15 uR/h. Exterior surface gamma measurements taken from the excavated areas
prior to backfilling ranged from 16 to 40 uR/h.
Soil Sample Analysis
Prior to backfilling, the RAC collected soil samples representative of the excavated areas from
the bottom 15-cm (6-in.) soil layers. These samples were blended to form a composite soil sample
representative of an average over the exterior verification area. The RAC's analysis of this sample
showed a 226Ra concentration of 10.1 pCi/g. ORNL ETS obtained this sample and performed a
confirmatory analysis which showed a mRa concentration of 11.0 pCi/g. These values are below the
DOE guideline value of 15 pCi/g for soil layers > 15 cm below the surface. Results of the RAC and
ORNL soil sample analyses are given in Table 2.
As a result of a meeting between the RAC and IVC on May 26, 1994, anomalous readings,
defined as > 30% above the average of the excavation, will be investigated to show compliance to
the DOE hot spot guideline. This property was remediated after the procedure change. The IVC
observed that 40 uR/h exceeds 30% of the excavation average of 19 uR/h. The IVC will allow a
correlation developed by the RAC to estimate 226Ra pCi/g concentrations based on gamma exposure
rates. The anomalous reading of 40 uR/h on this property using the RAC's correlation yields a ^Ra
concentration of 28.1 pCi/g. This value is below the minimum concentration of 30 pCi/g needed,
when assuming the maximum area under the hot spot guideline of 25 m2, for subsurface samples.
Results of the RAC and ORNL soil sample analyses are given in Table 2. Gamma ranges and/or soil
sample results demonstrate compliance to the DOE Hot Spot Guidelines for areas <25 m2 (Table 1).
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were determined by the
Alpha-track method. To monitor radon levels, the RAC placed three alpha-track detectors on the
ground floor ofthe residence located on this property for a period of approximately one year (from
October 10, 1994 to September 27, 1995). The average annual working level (WL) of radon
progeny concentration, as determined by the Tech./Ops-Landauer Corporation, was 0.0187, which
is well below the 0.03-WL guideline given in Table 1.
CONCLUSION
Results of RAC soil sample analysis and confirmatory split soil sample analysis by ORNL,
show that radionuclide concentrations are within applicable DOE guidelines. Based on the results
of the post-remedial-action data, which are confirmed by the verification assessment data, these
radiological measurements fall below the limits prescribed by DOE guidelines. All questions noted
in the initial review have been resolved as discussed in a meeting between Geotech and ORNL on
October 17, 1996. It is concluded that the site successfully meets the DOE remedial action objec-
tives.
5
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Radionuclide con-
centrations in soil
for Hot Spot areas
Exposure to 222Rn
progeny
Maximum permissible con-
centration of 226Ra in soil
above background levels,
averaged over a 100-m2
area
Maximum Permissible con-
centration of Ra226 in soil
above background level,
for areas less than 25 m2
Average annual radon
progeny concentration
(including background)
5 pCi/g averaged over the first 15 cm
of soil below the surface; 15 pCi/g
when averaged over 15-cm-thick soil
layers more than 15 cm below the
surface
Ra226 concentrations, in any surface
or subsurface area less than 25 m2,
is below the guideline by a factor of
(1007A)'/j, where A is the area of the
elevated region
0.03 WL
(US DOE 1990a)
6
Table 2. Results of ORNL analysis of the RAC soil samples
from 349 South 2nd West Street,
Monticello, Utah (MS00206)
226Ra concentration (pCi/g)
ORNL RAC
sample sample Depth ORNL RAC
No." No/ (cm)
XI NCG 497 >15 11 10.1
" An X-type sample is a split of the sample taken by the remedial action contractor.
* Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated areas were
taken by the RAC, and these samples were blended to form a composite soil sample, which
represents an average over one of the verification areas.
4
r * * "
7
REFERENCES
Geotech 1996. Property Completion Report for Monticello Vicinity Property Remedial Action for
DOE ID NO: MS00206, Address: 349 South Second West Street, Monticello, Utah 84535, RUST
Geotech, Grand Junction, Colorado, June 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment Group)
Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National Laboratory, Grand
Junction, Colorado.
US DOE 1990a. Verification and Certification Protocol for the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination and
Decommissioning Program. Revision 3, November 1990. U.S. Department of Energy, Washington,
D.C.
US DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision and Record
of Decision Summary. U.S. Department of Energy, Grand Junction Projects Office, Grand Junction,
Colorado.
DOE ID No.: MS-00217-MR
Property Address: 216 East First North Street
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech of Energy (DOE)
Ra-226 is < 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [ ]
Ra-226 is < 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2.
In-situ [ ] Lab [X]
Interior gamma is ^ 20 //R/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is < 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21,
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
[yi [ ] I 1
[yl [ 1 I 1
[y\ [ ] [ ]
[X] [ ] [ 1
[ ] [Y\ I ]
[yl [ ] [ 1
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
Ililllllllll llllllllll
SFCERTIFED SFMS-09033
DOE ID No.: MS-00217-MR
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
randa S. Busby 7anda S. Busby
Manager, Monticello Programs
Rust Geotech
Date
DOE EVALUATION
lY] Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Ce fificatidh Official
Department of Energy
Date
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00217-MR
ADDRESS: 216 EAST FIRST NORTH STREET
MONTICELLO, UTAH 84535
MARCH 1996
Prepared for
U.S. Department of Energy
by
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
/ VVahd/sT BusbV
Manager, Monticello Programs
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.1.3 Radon Decay-Product Concentration (RDC) Measurement .... 4
3.2 Recommendation for Certification 5
4.0 APPENDIX . 6
DOE ID No.: MS-00217-MR
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Inclusion Survey Contractor. DOE reviewed these
evaluation results and determined that the property contained mill tailings
(residual radioactive material) exceeding EPA standards and DOE hot spot
criteria. The Remedial Action Contractor was notified of the inclusion of
this property into the MVP Project and was authorized by DOE to conduct
remedial action as required to bring the property into conformance with
EPA standards and DOE hot spot criteria.
1
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
Property Address:
Property Owners:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
DOE ID No.: MS-00217-MR
MS-00217-MR
Location No. M-242; beginning at the NW
corner of Lot 3, Block G, Monticello
Townsite Survey; west 20 feet, south
135 feet, east 20 feet, south 40.5 feet,
east 107.5 feet, north 2.5 feet, east
5.5 feet, north 10.5 feet, west 5.5 feet,
north 162.5 feet, west 107.5 feet to the
point of beginning, County of San Juan,
State of Utah
216 East First North Street
Monticello, Utah 84535

Major Residential (MR)
Oak Ridge National Laboratory
January 25, 1990
Rust Geotech
September 14, 1994
Diamond Back Services, Inc.
9861 Titan Park Circle
Littleton, Colorado
July 11, 1995
August 21, 1995
Interior: 0 cubic yards
Exterior: 30 cubic yards
124 square meters (m2)
March 1996
2
DOE ID No.: MS-00217-MR
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of exterior residual radioactive
material (Appendix Figure 2.1). Interior assessed Area L (mortared brick)
was excluded from remedial action based on gamma exposure rates and
pre-remedial radon decay-product concentration measurements that did
not exceed EPA standards, as discussed in the REA. Once excavation was
complete, the affected areas were resurveyed for possible remaining
residual radioactive material and, upon attaining satisfactory results, were
backfilled with uncontaminated material. The property was restored to a
physical condition comparable to that which existed prior to remedial
action activities.
2.2 Previously Unidentified Contamination
The radiological assessment (excluding assessed Area L) identified
contamination, ranging from 6 to 12 inches deep, within the property.
The quantity of contamination for this property was not specified because
it was assessed as part of Block MS-09033-BK. The remedial action
process included the removal of approximately 30 cubic yards of residual
radioactive material, ranging from 6 to 24 inches deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID No.: MS-00217-MR
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by the Remedial Action
Contractor during July 1993, as described in the final REA dated
September 1994. Appendix Figure 2.1 shows the extent of
assessed contamination and identifies the areas recommended to
undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the excavation were
collected. These samples were blended to form composite
samples representing the verification areas (Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 13 to 25 microroentgens per
hour (//R/h), as indicated on Appendix Figure 2.1. The results of
analyses for radium-226 in two composite soil samples were
2.2 and 2.5 picocuries per gram (pCi/g), as indicated in Appendix
Table 3.1.
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on the DOE-approved abbreviated-measurement method, the
RDC was 0.0109 working level (WL), as indicated in
Appendix Table 3.2. Appendix Figure 2.1 shows the measurement
location in the basement (the lowest habitable level of the
structure). RDC measurements were taken before remediation of
the property.
4
DOE ID No.: MS-00217-MR
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at 216 East First North Street, in
Monticello, Utah, is recommended for certification as required by DOE
guidelines, and the appropriate records should be documented.
Certification Data Summary
Applicability
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Standards
Shall not exceed 20 /jR/h
above background.*
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Survey Results
Range for the basement
was 13 to 17 jL/R/h.
Average was 0.0109 WL,
based on the DOE-
approved abbreviated-
measurement method.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background1 in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
< 5 pCi/g above
background.**
Soil sample results were
2.2 and 2.5 pCi/g.**
*The background exposure rate is approximately 14 /vR/h.
The background radium-226 concentration is approximately 2.0 pCi/g.
**The hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-00217-MR
4.0 APPENDIX
Appendix Tables:
Table 3.1 Post-Excavation Sample/Measurement Results
Table 3.2 Radon Decay-Product Concentration Measurement
Results
Appendix Figure:
Figure 2.1 Interior and Exterior Extent of Contamination -
RADIOLOGICAL AS-BUILT
SJW:01 -09-96
MS-00217-MR WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00217-MR
Address: 216 East First North Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (//R/h) Ticket No. Method8 (pCi/g)
V-1 15-23 NCK 574 OCS 2.5
V-2 15-25 NCB 301 OCS 2.2
See Appendix Figure 2.1 for the verification areas.
aOCS = Opposed Crystal System
7
Table 3.2
Radon Decay-Product Concentration Measurement Results
DOE ID No.: MS-00217-MR
Address: 216 East First North Street, Monticello, Utah
Instrument Type: Landauer Radtrak Detector
Radon
Detector Tracks Per Concentration Working
Number Start Date End Date mm2 (pCi/L) Level
3964189 02-28-95 05-30-95
3964296 02-28-95 05-30-95
3964224 02-28-95 05-30-95
5.1 1.98 0.0099
6.3 2.43 0.0122
5.5 2.12 0.0106
Average: 0.0109
See Appendix Figure 2.1 for the measurement location.
8
42
40
38
36
34
32
30
28
26
24
22
20
18
16
14
12
10
12 16 18 20 22 24 26 28 30 32 34 36 38 40 42 44
T"
46 48 50
EAST FIRST NORTH STREET
in
HX12 15 13-17
V-2
15-25
18
V-l
15-23 RDC
\<6> 24!
I
ONE STORY
FRAME HOUSE
W/BASEMENT
13-17
SEE DETAIL A
13-17
13-17
v-2
15-25
18
V-2
15-25
18
18 6 X J
17-21
GROUND FLOOR
13-17
DETAIL A
NOT TO SCALE
©
<D
12-15
12
V-1
16-17
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN /iR/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE-RATE RANGE
RADON DECAY-PRODUCT CONCENTRATION
MEASUREMENT LOCATION
ASSESSED CONTAMINATION NOT FOUND AT TIME
REMEDIAL ACTION
ASSESSED AREA L (MORTARED BRICK) WAS
EXCLUDED FROM REMEDIAL ACTION
RADIOLOGICAL AS-BUILT
FIGURE 2.1
INTERIOR AND EXTERIOR EXTENT OF CONTAMINATION
L
SCALE IN FEET
20 10 0 20 40
UA'AS\033\0003\RU00217V 02/20/96 09:2Bom TS0780
NORTH
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVF.V
PLAT, UTILITY LOCATION PLAT. OR OTHER IMPROVEMENT SURVEY
PLAT ANO IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE. BUILDING. OR OTHER FUTURE IMPROVEMENT LINES.
12 14 16 18 20
J L
22
Mil •CVltiOm
MliPlKl-NA. v oceiwmrt
Cl. A.I. •&
U.S. DEPARTMENT OF ENERGY
CHAwO JUNCTION mOJCCTS Ofnct. COLORADO
'MM. tmi!
WMA
216 EAST FIRST NORTH ST.
MONTICELLO. UTAH
Rust O*ot«ch MS-00217-MR I
24 26 28 30 32 34 36 38 40 42 44 46
3-C00217-V1M 1 . 1
48 5'
OAK RIDGE NATIONAL LABORATORY PHONE: [phone]
FAX: [phone] MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
FOR THE U.S. DEPARTMENT OF ENERGY
POST OFFICE BOX 2567
GRANO JUNCTION, COLORADO 81502
M 2 8 ms
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by the
U.S. Department of Energy for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program (FUSRAP) and Remote Surplus Facilities Management Program
Sites (SFMP) [Revision 2, March 1987]. This evaluation is based on an independent
verification review of the Remedial Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment of
the 226Ra concentration in the soil at this property, indoor radon daughter concentration, and
indoor gamma exposure rates at this property.
Therefore, this property is recommended for certification by the U.S. Department of Energy.
Location Number: MS00217-MR
Location Address: 216 East 1st North Street
Monticello. Utah 84535
Property Owner:

Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
216 EAST 1ST NORTH STREET
MONTICELLO, UTAH (MS00217-MR)
M. J. Wilson-Nichols
June 1996
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 4
CONCLUSION 4
REFERENCES 7
iii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 5
2. Results of ORNL analysis of Geotech soil samples from 216 East 1 st North Street,
Monticello, Utah (MS00217-MR) 6
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site
Decommissioning Projects, U.S. Department of Energy. The author wishes to
acknowledge M. K. Jensen for analysis of soil samples and technical review and J. R.
Sauvage for technical review.
vii
ABSTRACT
In 1980 the site of a vanadium and uranium mill at Monticello, Utah, was accepted
into the U.S. Department of Energy's (DOE's) Surplus Facilities Management Program,
with the objectives of restoring the government-owned mill site to safe levels of radio-
activity, disposing of or containing the tailings in an environmentally safe manner, and
performing remedial actions on off-site (vicinity) properties that had been contaminated
by radioactive material resulting from mill operations. During 1995, RUST Geotech, the
remedial action contractor designated by DOE, performed remedial action on the vicinity
property at 216 East 1st North Street, Monticello, Utah. The Environmental Technology
Section (ETS) of Oak Ridge National Laboratory was assigned the responsibility of
verifying the data supporting the adequacy of remedial action and confirming the site's
compliance with DOE guidelines. The ETS found that the site successfully meets the
DOE remedial action objectives. Procedures used by the ETS are described in the
Environmental Technology Section Procedures Manual (ORNL 1993).
ix
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 216 EAST 1ST NORTH STREET
MONTICELLO, UTAH (MS00217-MR)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the U.S. government through the
Defense Plant Corporation to provide vanadium during World War II. Various govern-
ment agencies operated the mill until 1947. In 1948 the Atomic Energy Commission
(AEC) obtained the mill and operated it under contract through 1959 to provide both
uranium and vanadium. Mill operations were terminated on January 1,1960. In 1961 the
mill tailings piles were leveled and graded, covered with rock and soil, and seeded with
native grasses. During 1974 and 1975, the ore stockpiles were removed from the site, and
the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city
of Monticello, in San Juan County, Utah. The site is bordered on the south and southeast
by land held by the U.S. Bureau of Land Management. Other boundaries are the city of
Monticello and private property.
During the AEC era, the mill processed approximately one million tons of uranium
ore. Vanadium and uranium were the only substances extracted in the milling process.
Other constituents of the ore remained in the tailings and were not separated prior to dis-
posal. During the years of active mill operation, the mill tailings were normally moist, so
erosion was minimal. However, throughout the mill's operating period, area residents
used these tailings as fill material and as aggregate in mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy
(DOE) initiated the Surplus Facilities Management Program (SFMP) in 1978 to ensure
the safe caretaking and decommissioning of government facilities that had been retired
from service but still had radioactive contamination. In 1980 the mill site at Monticello
was accepted into the SFMP, and the Monticello Remedial Action Project (MRAP) was
established to restore the government-owned mill site to safe levels of radioactivity, to
dispose of or contain the tailings in an environmentally safe manner, and to perform
remedial actions on off-site (vicinity) properties that had been contaminated by
radioactive material resulting from mill operations. The Monticello mill site and the
tailings remain in the custody of the DOE Grand Junction, Colorado, Projects Office. In
1983 remedial actions for vicinity properties were separated from MRAP with
establishment ofthe Monticello Vicinity Properties (MVP) Project (U.S. DOE 1990b).
"The verification of remedial action was performed by members of the Environmental Assessment Group in the
Environmental Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE
contract DE-AC05-96OR22464 with Lockheed Martin Energy Research Corporation.
2
During 1995, RUST Geotech Inc. (Geotech), the remedial action contractor (RAC)
designated by DOE, performed remedial action on the vicinity property that is the subject
of this report, a single family residence located at 216 East 1st North Street, Monticello,
Utah. The remedial action plan required excavation of all exterior contamination. When
the excavation was completed, the property was resurveyed, including soil sampling, to
ensure the removal of all contamination, backfilled with uncontaminated material, and
restored to a condition comparable to that which existed prior to remedial action (Geotech
1996).
The DOE adopted a policy to assign an independent contractor to verify the data
supporting the adequacy of remedial action and to confirm the site's compliance with
DOE guidelines. The Environmental Technology Section (ETS) of Oak Ridge National
Laboratory (ORNL) has been assigned the responsibility of this task at the 216 East
1st North Street site. This report describes the methods and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available docu-
mentation adequately and accurately describes the post-remedial-action radiological
conditions of the entire property that is to be certified and (2) that the remedial action
reduced contamination to below applicable DOE guidelines (DOE 1990a).
Document Reviews
Review ofthe property completion report prepared by Geotech (Geotech 1996) in-
dicates the property was remediated as evaluated by DOE on the basis of Environmental
Protection Agency standards and the DOE guidelines (DOE 1990a). Excess residual
radioactive materials were present, thus it was appropriate to designate this property for
remedial action.
This property was assessed as part of Block 33, therefore, the quantity of material
assessed is not available. During the actual removal process, a total of 30 yd3 of con-
taminated earth and uranium mill tailings, 6 to 24 inches deep, was removed from a 124
m2 area. The ore cart located on the boundary between MS00234 and MS00217 was
removed during remedial action and not replaced.
A post-excavation survey was performed by Geotech prior to backfilling the exca-
vated areas. This survey consisted of gamma scans with a scintillometer of the ground
level of the structure, a surface scan of the exterior, and soil sampling. Samples
representative of the bottom 15-cm (6-in.) soil layers of two excavated verification areas
were collected and blended to form representative composite soil samples for each
verification area.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation
levels have not been subtracted. Similarly, background concentrations have not been sub-
tracted from radionuclide concentrations in soil samples. Applicable DOE guidelines for
protection against radiation are given in Table 1.
Gamma Measurements
Gamma exposure rate measurements taken by Geotech at the ground-level ofthe
residence ranged from 13 to 21 uR/h. Elevated gamma exposure rates of 17-21 uR/h on
the interior and 17-28 uR/h on the exterior of the house were due to contaminated mortar
in the brick found along the exterior walls. This area was excluded from remediation
based on gamma exposure rates and a pre-remedial radon decay-product concentration
that did not exceed EPA standards. Exterior surface gamma measurements taken from
the excavated areas prior to backfilling ranged from 13 to 25 uR/h.
Soil Sample Analysis
Prior to backfilling, Geotech collected soil samples representative ofthe excavated
areas from the bottom 15-cm (6-in.) soil layers. These samples were blended to form a
composite soil sample representative of an average over the two exterior verification
areas. Geotech's analysis of these samples showed 226Ra concentrations of 2.5 and
2.2 pCi/g in the composite samples. ORNL ETS obtained these samples and performed a
confirmatory analysis which showed 226Ra concentrations of 2.9 and 2.6 pCi/g. These
values are below the EPA standard value of 15 pCi/g for soil layers > 15 cm below the
surface. Gamma ranges and/or soil sample results demonstrate compliance to the DOE
Hot Spot Guidelines for areas <25 m2 (Table 1). Results of Geotech and ORNL soil
sample analyses are given in Table 2.
Anomalous readings, defined as > 30% above the average of the excavation, were
investigated in area VI. The high readings were associated with ore that had leached into
the ground underneath an ore cart previously located on the property. An excavation
control sample taken at this location had a 226Ra concentration of 2.7 pCi/g. In addition,
gamma readings in region H of 25 uR/h were also investigated and an excavation control
sample had a 226Ra concentration of 2.1 pCi/g. These values are well below the minimum
concentration of 30 pCi/g needed, when assuming the maximum area under the hot spot
guideline of 25 m2, for subsurface samples.
4
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were deter-
mined by the Alpha-track method. To monitor radon levels, Geotech placed three alpha-
track detectors on the ground floor of the residence located on this property for a period
of approximately three months (from February 28,1995 to May 30,1995). The average
annual working level (WL) of radon progeny concentration, as determined by the
Tech./Ops-Landauer Corporation, was 0.0109, which is well below the 0.03-WL
guideline given in Table 1.
CONCLUSION
Results of Geotech soil sample analysis and confirmatory split soil sample analysis
by ORNL show that radionuclide concentrations are within applicable DOE guidelines.
Based on the results of the post-remedial-action data, which are confirmed by the
verification assessment data, these radiological measurements fall below the limits
prescribed by DOE guidelines. It is concluded that the site successfully meets the DOE
remedial action objectives.
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of 226Ra in soil
above background levels,
averaged over a 100-m2 area
5 pCi/g averaged over the
first 15 cm of soil below the
surface; 15 pCi/g when ave-
raged over 15-cm-thick soil
layers more than 15 cm
below the surface
Radionuclide
concentrations in soil
for Hot Spot areas
Exposure to 222Rn
progeny
Maximum Permissible
concentration of Ra226 in soil
above background level, for
areas less than 25 m2
Average annual radon proge-
ny concentration (including
background)
Ra226 concentrations, in any
surface or subsurface area
less than 25 m2, is below the
guideline by a factor of
(lOO/A)*, where A is the
area of the elevated region
0.03 WL
(DOE 1990a)
6
Table 2. Results of ORNL analysis of Geotech soil samples
from 216 East 1st North Street, Monticello Utah (MS00217-MR)
226Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No.° No* (cm)
XI NCK 574 >15 2.8 2.5
X2 NCB 301 >15 2.6 2.2
° An X-type sample is a split of the sample taken by the remedial action contractor.
* Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated
areas were taken by Geotech, and these samples were blended to form a composite soil
sample, which represents an average over one of the verification areas.
7
REFERENCES
Geotech 1996. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00217-MR, Address: 216 East First North Street, Monticello,
Utah 84535, Geotech, Grand Junction, Colorado, March 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
U.S. DOE 1990a. Verification and Certification Protocol for the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination
and Decommissioning Program, Revision 3, November 1990. U.S. Department of
Energy, Washington, D.C.
U.S. DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision
and Record of Decision Summary. U.S. Department of Energy, Grand Junction Projects
Office, Grand Junction, Colorado.
DOE ID No.: MS-00221-RS
Property Address: 164 South First West Street
Vicinity Property Certification Summary and Recommendation
Summary Evaluation
Certification Criteria MACTEC-ERS
U.S. Department
of Energy (DOE)
Ra-226 is < 5 pCi/g above
background in top 15-cm-thick layer of
soil averaged over 100 m2
In situ [X] Lab [ ]
Ra-226 is ^ 15 pCi/g above
background in any 15-cm-thick layer
of soil more than 15 cm below the
surface averaged over 100 m2.
In situ [ ]Lab[X]
Interior gamma is < 20 uR/h above
background in any occupied or
habitable structure.
The radon decay-product
concentration in any occupied or
habitable structure is < 0.02 WL or, at
most, 0.03 WL.
Supplemental standards were applied
in accordance with EPA standard
40 CFR 192.21.
Hot spot criteria met as outlined by
DOE guidelines for FUSRAP (Rev.2,
March 1987)
Yes No Not Taken Yes No Not Taken
[X]a [ ]
[X] [ ]
[X] [ ]
[X] [ ]
[ ] [X]
[X] [ ]
[ ]
[ ]
[ ]
[ ]
[ ]
[ ]
[y] [ ]
[/] [ ]
[*1 [ ]
[ ] [ M
M [ ]
[ ]
[ ]
[ ]
[ ]
[ ]
[ ]
''The excavations were backfilled with materials that were measured at the source indicating that the Ra-226
concentrations are in the range of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
•UMIII1I liiiiilll
SFCERTIFED SFMS-00221
1 of 2
DOE ID No(s).: MS-00221-RS
MACTEC-ERS Recommendation
On the basis of the Property Completion Report evaluation, this property is recommended for
[X] Certification by DOE.
[ ] Certification by DOE with the concurrence ofthe U.S. Nuclear Regulatory Commission
because supplemental standards were applied according to 40 CFR 192.21.
Manager, Monticello Programs
MACTEC-ERS
DOE Evaluation
On the basis of the Property Completion Report recommendation, this property
[V] Should be certified by DOE.
[ ] Should be certified by DOE with the concurrence of the U. S. Nuclear Regulatory
Commission because supplemental standards were applied according to 40 CFR 192.21.
Date
U.S. Department of Energy
Work performed under DOE ContractNo. DE-AC13-96GJ87335, Task OrderNo.96-05.02.14
2 of 2
Monticello Vicinity Properties Project
Property Completion Report
for
Monticello
Vicinity Property Remedial Action
for
DOE DD No.: MS-00221-RS
Address: 164 South First West Street
Monticello, Utah 84535
November 1996
Prepared for
U.S. Department of Energy
Albuquerque Operations Office
Grand Junction Projects Office
Prepared by
MACTEC-Environmental Restoration Services, LLC (MACTEC-ERS)*
Grand Junction, Colorado
Michael C. Butherus
Manager, Monticello Programs
Work performed under DOE Contract No. DE-AC13-96GJ87335
Task Order No. 96-05.02.14
*MACTEC-ERS has been granted authorization to conduct remedial action by the U.S. Department of Energy.
Remedial action was performed in accordance with the U.S. Environmental Protection Agency "Standards for Cleanup
of Land and Buildings Contaminated with Residual Radioactive Materials from Inactive Uranium Processing Sites,"
40 CFR 192, Subpart B; and "Implementation," in 40 CFR 192, Subpart C, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
DOE ID No.: MS-00221-RS
Contents
Page
1.0 Surnmary 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Remedial Action Summary 2
2.0 Operations Summary 3
2.1 Remedial Action Plan 3
2.2 Assessed and Remediated Contamination 3
3.0 Verification Summary 4
3.1 Radiological Survey Data 4
3.1.1 Preremedial Action Survey 4
3.1.2 Postexcavation Survey 4
3.1.3 Radon Decay-Product Concentration Measurements 4
3.2 Recommendation for Certification 5
Table
Table 1. Certification Data Summary 5
Appendix
Appendix A. Radiological Conditions A-1
IX)l-./Gr;incl Junction Office MVP Property Completion Report
November IWh \'ugc ii
DOE ID No.: MS-O0221-RS
1.0 Summary
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce the potential hazard
to the public due to long-term exposure to low-level radioactivity associated with the offsite mill
tailings derived from the former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States Government through its agent,
the Defense Plant Corporation, to provide additional sources of vanadium needed during World
War II. Various government agencies operated the mill until 1947. The AEC obtained the mill in
1948 and operated it through 1959 under cost-type contracts to process both uranium and
vanadium ore. Mill operations were terminated on January 1,1960.
The mill processed approximately one million tons of ore during the AEC operations.
Throughout the operating period, mill tailings from the Monticello millsite were removed from
the site and used for construction-related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for Remedial Actions at Inactive
Uranium Processing Sites" (40 CFR Part 192) for all cleanup activities under the MVP Project.
These standards were prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and open lands. Cleanup
activities also were conducted to meet the hot spot criteria established by radiological protection
guidelines in the DOE Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management Program Sites
(Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot spot criteria and
determined to contain mill tailings (radioactive material) exceeding EPA standards and/or DOE
hot spot criteria. The Remedial Action Contractor* was notified of the inclusion of this property
into the MVP Project and was authorized by DOE to conduct remedial action as required to bring
the property into conformance with EPA standards and DOE hot spot criteria.
The Remedial Action Contractor, MACTEC-ERS, was awarded the U.S. Department of Energy Grand Junction
Office (DOE-GJO) Technical Assistance and Remediation contract and commenced work on September 5,1996.
The MACTEC-ERS team consists of International Technology Corporation, Science Application International
Corporation, Roy F. Weston, Inc., and Rust Federal Services, Inc. Rust Geotech was the DOE-GJO contractor from
October 1,1986, through September 4,1996, and implemented some of the tasks discussed in this report.
DOE/Grand Junction Office
November 1996
MVP Property Completion Report
Page 1
DOE ID No.: MS-00221-RS
1.3 Remedial Action Summary
DOE D3 No.:
Legal Description:
Property Address:
Property Owners:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological and Engineering Assessment (REA):
Construction Subcontractor:
Preconstruction Conference Record:
Notice of Final Completion Inspection:
Volume of Material Removed in Cubic Yards (yd3):
Area Cleaned Up in Square Meters (m2):
Property Completion Report Submitted:
MS-00221-RS
Beginning at the NE comer of Lot 1,
Block 16, Monticello Townsite
Survey; west 150 feet, south 70 feet,
east 150 feet, north 70 feet to the
beginning, County of San Juan, State
of Utah
164 South First West Street
Monticello, Utah 84535

Residential Simple (RS)
Not applicable: inclusion requested
by the Remedial Action Contractor
August 2, 1994
MACTEC-ERS
September 9, 1994
Crowley Construction, Inc.
September 6,1995
September 7,1995
Exterior: 3
Interior: < 1
7
November 1996
DOE/Grand Junction Office
November 1996
MVP Property Completion Report
Page 2
DOE ID No.: MS-00221-RS
2.0 Operations Summary
2.1 Remedial Action Plan
The remedial action plan specified removal of radioactive material. Once excavation was
completed, the affected areas were resurveyed for possible remaining radioactive material and,
upon attaining satisfactory results, were backfilled with uncontaminated material. The property
was restored to a physical condition comparable to that which existed before remedial action
activities.
2.2 Assessed and Remediated Contamination
The radiological assessment identified contamination, 6 inches (in.) deep, within the property
boundary. The quantity of contamination for this property was not specified because it was
assessed with MS-00222-RS. The remedial action process included removal of approximately
3 yd3 of residual radioactive material, ranging from 6 to 24 in. deep. The areas of assessed and
excavated contamination are shown on Figure A-1.
DOII/Ciraiul Junction Office
November I Wo
MVP Property Completion Report
Page 3
DOE ID No.: MS-00221-RS
3.0 Verification Summary
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Preremedial Action Survey
The Remedial Action Contractor conducted a radiological survey during January and March
1994, as described in the final REA. Figure A-1 shows the extent of assessed contamination and
identifies the areas recommended for remedial action.
3.1.2 Postexcavation Survey
A scintillometer was used to perform a surface gamma scan after the removal of radioactive
material and before backfilling. Following the gamma scan, soil samples representative of the
6-in.-thick soil layer at the bottom of the exterior excavation were collected. These samples,
representing the exterior verification area, were blended together and analyzed for radium-226.
The composite sample representing Area V-l included soil samples collected from
MS-00222-MR. The results of the gamma scans and soil sample analyses are presented in
Table A-1.
3.1.3 Radon Decay-Product Concentration Measurements
Radon decay-product concentration (RDC) measurements were taken on the lowest habitable
level of the house, as shown on Figure A-1. The measurement results are presented in
Table A-2.
DOE/Grand Junction Office
November 1996
MVP Property Completion Report
Page 4
DOE ID No.: MS-00221-RS
3.2 Recommendation for Certification
Radioactive materials have been removed from this property to the extent required by EPA
standards (40 CFR 192, Subparts B and C) and DOE hot spot criteria, as indicated in the
Certification Data Summary (Table 1). Therefore, the property located at 164 South First West
Street, in Monticello, Utah, is recommended for certification as required by DOE guidelines.
Table 1. Certification Data Summary
Applicability Standard Survey Results
Radium-226
Concentration in
Surface Soil
Radium-226
Concentration in
Subsurface Soil
Exposure Rate
Radon Decay-
Product
Concentration
Land
Shall not exceed 5 pCi/g above
background8 in the 15-cm-thick
surface layer, averaged over
100 m2.
Shall not exceed 15 pCi/g
above background8 in any
15-cm-thick soil layer more
than 15 cm below the surface,
averaged over 100 m2.
Habitable Structures
< 5 pCi/g above background on the
basis of gamma exposure rates that do
not exceed 30 percent above normal
background."
Soil sample result was 6.8 pCi/g.b
Shall not exceed 20 pR/h
above background^
Annual average shall not
exceed 0.02 WL, to the extent
practicable, and shall in no
case exceed 0.03 WL.
Ranges were 14 to 17 pR/h for the
remediated portion of the partial
basement, 15 to 17 pR/h for the
remainder of the partial basement,
and 13 to 15 pR/h for the ground floor.
Average was 0.0138 WL, on the basis
of the DOE-approved abbreviated-
measurement method.
Key: cm = centimeters; m2 = square meters; pCi/g = picocuries per gram; uR/h = microroentgens per hour
WL = working level
8The background radium-226 concentration for Monticello Vicinity Properties is approximately 2.0 pCi/g.
The hot spot criteria were met based on gamma scans and/or soil sample results.
The background exposure rate for this property is approximately 13 uR/h.
DOE/Grand Junction Office
November 1996
MVP Property Completion Report
Page 5
DOE ID No.: MS-00221-RS
Appendix A
Radiological Conditions
Table A-1. Postexcavation Survey Results
Table A-2. Radon Decay-Product Concentration Measurement Results
Figure A-1. Radiological As-Built
DOE ID No.: MS-00221-RS
Table A-1. Postexcavation Survey Results
Gamma Radium-226
Exposure Rate Soil Sample Measurement Concentration
Range (uR/h) Ticket No. Method (pCi/g)
Verification
Area*
V-1
V-2
17-27
14-17
EXTERIOR
NCL 730
INTERIOR
Not applicable
OCS 6.8
Key: uR/h = microroentgens per hour; pCi/g = picocuries per gram; OCS = opposed crystal system
V = verification area
"See Figure A-1 for location of verification areas.
DOE/Grand Junction Projects Office
November 1996
MVP Property Completion Report
Page A-2
DOE ID No.: MS-00221-RS
Table A-2. Radon Decay-Product Concentration Measurement Results*
Detector"
Number Start Date End Date
Radon
Concentration
(pCi/L) WL
4147344
4147087
4147176
02-27-96
02-27-96
02-27-96
06-03-96
06-03-96
06-03-96
3.05
2.67
2.55
Average:
0.0153
0.0134
0.0128
0.0138
Key: pCi/L = picocuries per liter; WL = working level
aSee Figure A-1 (or measurement location.
Terradex Radtrak Detector.
DOli/Grand Junction Projects Office
November
MVP Property Completion Report
Page A-3
10
> , • ' 30
12 14 16 18 20 22
T
24 26 28 30 32 34 36 38 40
30
28
26
24
22
20 -
18
16
14
12
2
7
24 13-16
v-f
ONE STORY
FRAME HOUSE
13-15
W/PARTIAL BASEMENT o SEE DETAIL A
13-16 3-16
L
V-2
(RDC)
PARTIAL BASEMENT
15-17
DETAIL A
NOT TO SCALE
M:\FAS\033\0003\RM00221V 01/16/97 09:53am S50730
— X
Ld
Ld
or
I-
00 \—
CO
to or
3
O
CO
®
<D
— .-q
Lv.vj
12-15
12
(RDC)
NORTH
SCALE IN FEET
20 10 0 20 40
LEGEND
ALL DEPTHS/HEIGHTS IN INCHES
ALL EXPOSURE RATES IN fiR/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
RADON DECAY-PRODUCT CONCENTRATION
MEASUREMENT LOCATION
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
POINT SOURCE (ORE SAMPLE)
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT. UTILITY LOCATION PLAT, OR OTHER IMPROVEMENT SURVEY
PLAT AND IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE, BUILDING, OR OTHER FUTURE IMPROVEMENT LINES.
10 J I L
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION OFFICE. COLORADO
•MJHIMAMH
164 SOUTH FIRST
WEST STREET
MONTICELLO, UTAH IUUNWL WIU
COMPLETION REPORTS
bit
MONTICELLO VICINITY PROPERTIES
FIGURE A-1
RADIOLOGICAL AS-BUILT
MS-00221-RS
MUVWdMOi-
10 12 1 4 16 18 20 22 24 26 28 30 32 34
3-B00221-V1
36
28
26
24
22
20
18
16
14
12
1 1
10
38 40
OAK RIDGE NATIONAL LABORATORY PHONE: (970) 24W5200
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION FAX: [phone]
FOR THE U.S. DEPARTMENT OF ENERGY
2587 BV. Red
GRAND JUNCTION, COLORADO 81503 HIM J |
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by the U.S.
Department of Energy for Residual Radioactive Material at Formerly Utilized Sites Remedial Action
Program (FUSRAP) and Remote Surplus Facilities Management Program Sites (SFMP) [Revision
2, March 1987]. This evaluation is based on an independent verification review of the Remedial
Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment of the 226Ra
concentration in the soil, indoor radon daughter concentration, and indoor and outdoor gamma
exposure rates at this property.
This property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
Location Number: MS00221-RS
Location Address: 164 South 1st West Street
Monticello. Utah 84535
Property Owner:

Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
164 SOUTH 1ST WEST STREET
MONTICELLO, UTAH (MS00221-RS)
M. K. Jensen
January 1997
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81503
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 3
REFERENCES 6
iii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 4
2. Results of ORNL analysis ofthe RAC soil samples from 164 South 1st West Street,
Monticello, Utah (MS00221-RS) 5
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site Decommissioning
Projects, U.S. Department of Energy. The author wishes to acknowledge A. R. Jones and P. D.
Roundtree for technical reviews.
vii
ABSTRACT
In 1980, the site of a vanadium and uranium mill at Monticello, Utah, was accepted into the
U.S. Department of Energy (DOE) Surplus Facilities Management Program, with the objectives of
restoring the government-owned mill site to safe levels of radioactivity, disposing of or containing
the tailings in an environmentally safe manner, and performing remedial actions on off-site (vicinity)
properties that had been contaminated by radioactive material resulting from mill operations. During
1995, the Remedial Action Contractor (RAC) designated by DOE, performed remedial action on the
vicinity property at 164 South 1st West Street, Monticello, Utah. The Environmental Technology
Section (ETS) of Oak Ridge National Laboratory was assigned the responsibility of verifying the
data supporting the adequacy of remedial action and confirming the site's compliance with DOE
guidelines. The ETS found that the site successfully meets the DOE remedial action objectives. All
deficiencies noted in the initial review have been resolved with the revised completion report
and additional documentation to the property folio. Procedures used by the ETS are described in the
Environmental Technology Section Procedures Manual (ORNL 1993).
ix
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 164 SOUTH 1ST WEST STREET
MONTICELLO, UTAH (MS00221-RS)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the United States (U.S.) government through
the Defense Plant Corporation to provide vanadium during World War II. Various government
agencies operated the mill until 1947. In 1948, the Atomic Energy Commission (AEC) obtained the
mill and operated it under contract through 1959 to provide both uranium and vanadium. Mill
operations were terminated on January 1, 1960. In 1961, the mill tailings piles were leveled and
graded, covered with rock and soil, and seeded with native grasses. During 1974 and 1975, the ore
stockpiles were removed from the site and the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city of
Monticello, in San Juan County, Utah. The site is bordered on the south and southeast by land held
by the U.S. Bureau of Land Management. Other boundaries are the city of Monticello and private
property.
During the AEC era, the mill processed approximately one million tons of uranium ore. Vana-
dium and uranium were the only substances extracted in the milling process. Other constituents of
the ore remained in the tailings and were not separated prior to disposal. During the years of active
mill operation, the mill tailings were normally moist, so erosion was minimal. However, throughout
the mill's operating period, area residents used these tailings as fill material and as aggregate in mortar
and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy (DOE) initiated
the Surplus Facilities Management Program (SFMP) in 1978 to ensure the safe caretaking and de-
commissioning of government facilities that had been retired from service but still had radioactive
contamination. In 1980, the mill site at Monticello was accepted into the SFMP, and the Monticello
Remedial Action Project (MRAP) was established to restore the government-owned mill site to safe
levels of radioactivity, to dispose of or contain the tailings in an environmentally safe manner, and to
perform remedial actions on off-site (vicinity) properties that had been contaminated by radioactive
material resulting from mill operations. The Monticello mill site and the tailings remain in the custody
ofthe DOE Grand Junction, Colorado, Projects Office. In 1983, remedial actions for vicinity
properties were separated from MRAP with establishment of the Monticello Vicinity Properties
(MVP) Project (US DOE 1990b).
*The verification of remedial action was performed by members ofthe Environmental Assessment Group in the Environmental
Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE contract DE-AC05-
960R22464 with Lockheed Martin Energy Research Corporation.
2
During 1995, the Remedial Action Contractor (RAC) designated by DOE, performed remedial
action on the vicinity property that is the subject of this report, a single family residence located at
164 South 1st West Street, Monticello, Utah. The remedial action plan required excavation of all
exterior contamination. When the excavation was completed, the property was resurveyed, including
soil sampling, to ensure the removal of all contamination, backfilled with uncontaminated material,
and restored to a condition comparable to that which existed prior to remedial action (MACTEC-
ERS 1996).
DOE adopted a policy to assign an independent contractor to verify the data supporting the
adequacy of remedial action and to confirm the site's compliance with DOE guidelines. The
Environmental Technology Section (ETS) of Oak Ridge National Laboratory (ORNL) has been
assigned the responsibility of this task at the 164 South 1 st West Street site. This report describes
the methods and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available documentation
adequately and accurately describes the post-remedial-action radiological conditions of the entire
property that is to be certified and (2) that the remedial action reduced contamination to below
applicable DOE guidelines (US DOE 1990a).
Document Reviews
Review ofthe RAC property completion report (MACTEC-ERS 1997) indicates the property
was remediated as evaluated by DOE on the basis of U.S. Environmental Protection Agency
standards and the DOE guidelines (US DOE 1990a). Excess residual radioactive materials were
present, thus it was appropriate to designate this property for remedial action.
This property was assessed with MS00222-RS, therefore, the quantity of material assessed is
not available. During the actual removal process, a total of 3 yd3 of contaminated earth and uranium
mill tailings, 6 to 24 inches deep, were removed from a 7 m2 area.
The RAC performed a post-excavation survey prior to backfilling the excavated areas. This
survey consisted of gamma scans with a scintillometer of the ground level of the structure, a surface
scan ofthe exterior, and soil sampling. Samples representative ofthe bottom 15-cm (6-in.) soil
layers of the excavated verification area were collected and blended to form a representative
composite soil sample. A piece of ore, approximately the size of a golf ball, was removed from the
sheetrock ceiling.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation levels have "
not been subtracted. Similarly, background concentrations have not been subtracted from radionu-
clide concentrations in soil samples. Applicable DOE guidelines for protection against radiation are
given in Table 1.
Gamma Measurements
Gamma exposure rate measurements taken by the RAC in the basement of the house ranged
from 15-16 uR/h, 14-17 uR/h in the area of removal. At the ground-level of the residence gamma
exposure rate measurements ranged from 13 to 15 uR/h. Exterior surface gamma measurements
taken from the excavated areas prior to backfilling ranged from 17 to 27 pR/h.
Soil Sample Analysis
Prior to backfilling, the RAC collected soil samples representative of the excavated areas from
the bottom 15-cm (6-in.) soil layers. These samples were blended to form a composite soil sample
representative of an average over the exterior verification area. The RAC's analysis of this sample
showed a 226Ra concentration of 6.8 pCi/g. ORNL ETS obtained this sample and performed a con-
firmatory analysis which showed a 226Ra concentration of 5.9 pCi/g. These values are below the
DOE guideline value of 15 pCi/g for soil layers > 15 cm below the surface. Gamma ranges and/or
soil sample results demonstrate compliance to the DOE Hot Spot Guidelines for areas <25 m2 (Table
1). Results of the RAC and ORNL soil sample analyses are given in Table 2.
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were determined by the
Alpha-track method. To monitor radon levels, the RAC placed three alpha-track detectors on the
ground floor of the residence located on this property for a period of approximately three months
(from February 27, 1996 to June 3, 1996). The average annual working level (WL) of radon
progeny concentration, as determined by the Tech./Ops-Landauer Corporation, was 0.0138, which
is below the 0.03-WL guideline given in Table 1.
CONCLUSION
Results of RAC soil sample analysis and confirmatory split soil sample analysis by ORNL,
show that radionuclide concentrations are within applicable DOE guidelines. Based on the results
of the post-remedial-action data, which are confirmed by the verification assessment data, these
radiological measurements fall below the limits prescribed by DOE guidelines. All deficiencies
noted in the initial review have been identified and corrected by the RAC as discussed in a meeting
between MACTEC-ERS and ORNL on January 15,1997. It is concluded that the site successfully
meets the DOE remedial action objectives.
4
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of ^Ra in soil
above background levels,
averaged over a 100-m2
area
5 pCi/g averaged over the first 15 cm
of soil below the surface; 15 pCi/g
when averaged over 15-cm-thick soil
layers more than 15 cm below the
surface
Radionuclide con-
centrations in soil
for Hot Spot areas
Exposure to 222Rn
progeny
Maximum Permissible con-
centration of Ra226 in soil
above background level,
for areas less than 25 m2
Average annual radon
progeny concentration
(including background)
Ra226 concentrations, in any surface
or subsurface area less than 25 m2,
is below the guideline by a factor of
(10G7A),/\ where A is the area of the
elevated region
0.03 WL
(US DOE 1990a)
5
Table 2. Results of ORNL analysis of the RAC soil samples from
164 South 1st West Street, Monticello, Utah (MS00221-RS)
226Ra concentration (pCi/g)
ORNL RAC
sample sample Depth ORNL RAC
No." No? (cm}
XI NCL 730 >15 5.9 6.8
" An X-type sample is a split of the sample taken by the remedial action contractor.
* Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated areas were
taken by the RAC, and these samples were blended to form a composite soil sample, which
represents an average over one of the verification areas.
REFERENCES
MACTEC-ERS 1996. Property Completion Report for Monticello Vicinity Property Remedial
ActionforDOEIDNO: MS00221-RS, Address: 164 SOUTH FIRST WEST STREET, Monticello,
Utah 84535, MACTEC-ERS, Grand Junction, Colorado, November 1996 .
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment Group)
Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National Laboratory, Grand
Junction, Colorado.
US DOE 1990a. Verification and Certification Protocol for the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination and
Decommissioning Program. Revision 3, November 1990. U.S. Department of Energy, Washington,
D.C.
US DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision and Record
of Decision Summary. U.S. Department of Energy, Grand Junction Projects Office, Grand Junction,
Colorado.
DOE ID Nos.: MS-00225-VL
Property Address: 196 South Main Street
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech of Energy (PQE)—
YES NO NOT TAKEN YES NO NOT TAKEN
Ra-226 is <. 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2. [X]* [ ] [ ] [)fl [ I [ 1
In-situ [X] Lab [ ]
Ra-226 is ^ 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2. [X] [ ] [ ] MM M
In-situ [ ] Lab [X]
Interior gamma is £ 20 //R/h
above background in any
occupied or habitable
structure. [ ] [ ] [X] [ ] [ ] [VI
(Vacant Lot)
The radon decay-product
concentration in any
occupied or habitable
structure is £ 0.02
working level or, at
most, 0.03 working level. [Ill [X] [ ] [ ] [Vi
(Vacant Lot)
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21. [ ] [X] [ ] [ ] [/] [ ]
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987). [X] [ ] [ ] Ul I 1 11
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
llllllllll •
SFCERTIFED
'i inn in i in
SFMS-00225
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
DOE ID NO.: MS-00225-VL
ADDRESS: 196 SOUTH MAIN STREET
MONTICELLO, UTAH 84535
FEBRUARY 1996
Prepared for
U.S. Department of Energy
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
/ Wah/a S. Busfjy
Manager, Monticello Programs
FOR
by
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
DOE ID No.: MS-00225-VL
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Inclusion Survey Contractor. DOE reviewed
these evaluation results and determined that the property contained mill
tailings (residual radioactive material) exceeding EPA standards. The
Remedial Action Contractor was notified of the inclusion of this property
into the MVP Project and was authorized by DOE to conduct remedial
action as required to bring the property into conformance with EPA
standards and DOE hot spot criteria.
1
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
Property Address:
Property Owner:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
DOE ID No.: MS-00225-VL
MS-00225-VL
Location M-132; beginning 105 feet north
of the SE corner of Block 17, Monticello
Townsite Survey, west 133 feet, north
54 feet, east 133 feet, south 54 feet to
beginning, County of San Juan, State
of Utah
196 South Main Street
Monticello, Utah 84535

Vacant Lot (VL)
Oak Ridge National Laboratory
July 25, 1990
Rust Geotech
March 4, 1993
Diamond Back Services, Inc.
9861 Titan Park Circle
Littleton, Colorado
May 24, 1994
July 13, 1994
Interior: 0 cubic yards
Exterior: 13 cubic yards
17 square meters (m2)
February 1996
2
DOE ID No.: MS-00225-VL
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of exterior residual radioactive
material (Appendix Figure 2.1). Once excavation was complete, the
affected areas were resurveyed for possible remaining residual radioactive
material and, upon attaining satisfactory results, were backfilled with
uncontaminated material. The property was restored to a physical
condition comparable to that which existed prior to remedial action
activities.
2.2 Previously Unidentified Contamination
The radiological assessment identified approximately 8 cubic yards of
contamination, ranging from 6 to 30 inches deep, within the property.
The remedial action process included the removal of approximately
13 cubic yards of residual radioactive material, ranging from 6 to
60 inches deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID No.: MS-00225-VL
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by the Remedial Action
Contractor during May and June 1992, as described in the final
REA dated March 1993. Appendix Figure 2.1 shows the extent of
assessed contamination and identifies the areas recommended to
undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the excavation were
collected. These samples were blended to form composite
samples representing the verification areas (Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 12 to 32 microroentgens per
hour OuR/h), as indicated on Appendix Figure 2.1. The results of
analyses for radium-226 in three composite soil samples ranged
from 3.0 to 12.1 picocuries per gram (pCi/g), as indicated in
Appendix Table 3.1.
4
DOE ID No.: MS-00225-VL
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at 196 South Main Street, in
Monticello, Utah, is recommended for certification as required by DOE
guidelines, and the appropriate records should be documented.
Certification Data Summary
Applicability
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Standards
Shall not exceed 20 //R/h
above background.
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Survey Results
Not applicable: vacant
lot.
Not applicable: vacant
lot.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background* in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background* in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
< 5 pCi/g above
background.
Soil sample results
ranged from 3.0 to
12.1 pCi/g.f
*The background radium-226 concentration is approximately 2.0 pCi/g.
The hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-00225-VL
4.0 APPENDIX
Appendix Table:
Table 3.1 Post-Excavation Sample/Measurement Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
SJW:09-14-95
MS-00225.VL WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: GJ-00225-VL
Address: 196 South Main Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (jjR/h) Ticket No. Method" (pCi/g)
V-1 17-32 NAY 193 OCS 12.1
V-2 15-18 NAY 194 OCS 3.3
V-3 17-32 NCB 527 OCS 3.0
See Appendix Figure 2.1 for the verification areas.
"OCS = Opposed Crystal System
7
10
30
12 1 4 16 18 20 22 24 26 28 30 32 34 36 38 40
30
28 28
26
24
22 -
20 -
18
V-2
15-18
r 12-16 V-3 12-16
17-32 12 30 60 N LU
LU
or
m 30
V-1 <
17-32
o X
12-16 3
o 32 32
12 6XF
i X
77 & H-
®
LV.VJ
12-15
12
V-1
16-17
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN /iR/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE-RATE RANGE
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
- 26
24
22
20
18
16
14
12
Y
10
SCALE IN FEET
20 10 0 20 40
M:\FAS\033\0003\RM00225V 09/15/95 09:35am T50780
*J I I I I I L
ft
NORTH
J I
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT, UTILITY LOCATION PLAT, OR OTHER IMPROVEMENT SURVEY
PLAT AND IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE, BUILDING, OR OTHER FUTURE IMPROVEMENT LINES.
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
RESIDENCE-NO. OF OCCUPANTS
NON-RESIOENCE-UAN-HRS./WK.
INSTRUMENT NO.
SURVEY OATE
VERIFICATION
BY CK. A.E. APP. NO. DATE BY CK. A.E. APP
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE. COLORADO
1 96 SOUTH MAIN STREET
MONTICELLO, UTAH
Rust Qeotech
AWUXl
APPROVAL OOE
OOEIDNO. MS-00225-VL
DWO.NO. 3-B00225-V1 5HI 1 nr 1
1 6
1 4
1 2
1 0
10 12 1 4 1 6 18 20 22 24 26 28 30 32 34 36 38 40
OAK RIDGE NATIONAL LABORATORY
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
FOR THE U.S. DEPARTMENT OF ENERGY
POST OFFICE BOX 2567
GRAND JUNCTION, COLORADO 81502
PHONE: [phone]
FAX: [phone]
MAY 3 I 1935
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by the
U.S. Department of Energy for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program (FUSRAP) and Remote Surplus Facilities Management Program
Sites (SFMP) [Revision 2, March 1987]. This evaluation is based on an independent
verification review of the Remedial Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment of
the 226Ra concentration in the soil.
Therefore, this property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
Location Number: MS00225-VL
Location Address: 196 South Main Street
Monticello. Utah 84535
Property Owner:

Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
196 SOUTH MAIN STREET
MONTICELLO, UTAH (MS00225-VL)
J. R. Sauvage
May 1996
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 4
REFERENCES 7
iii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 5
2. Results of ORNL analysis of Geotech soil samples from 196 South Main Street,
Monticello, Utah (MS00225-VL) 6
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site
Decommissioning Projects, U.S. Department of Energy. The author wishes to
acknowledge M. K. Jensen for analysis of soil samples and technical review and
N. F. Kirby for technical review.
vii
ABSTRACT
In 1980 the site of a vanadium and uranium mill at Monticello, Utah, was accepted
into the U.S. Department of Energy's (DOE's) Surplus Facilities Management Program,
with the objectives of restoring the government-owned mill site to safe levels of radio-
activity, disposing of or containing the tailings in an environmentally safe manner, and
performing remedial actions on off-site (vicinity) properties that had been contaminated
by radioactive material resulting from mill operations. During 1994, RUST Geotech, the
remedial action contractor designated by DOE, performed remedial action on the vicinity
property at 196 South Main Street, Monticello, Utah. The Environmental Technology
Section (ETS) of Oak Ridge National Laboratory was assigned the responsibility of
verifying the data supporting the adequacy of remedial action and confirming the site's
compliance with DOE guidelines. The ETS found that the site successfully meets the
DOE remedial action objectives. All deficiencies noted in the initial review have been
resolved with additional documentation to the property folio. Procedures used by the
ETS are described in the Environmental Technology Section Procedures Manual (ORNL
1993).
ix
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 196 SOUTH MAIN STREET
MONTICELLO, UTAH (MS00225-VL)*
INTRODUCTION
. The mill at Monticello, Utah, was built in 1942 by the U.S. government through the
Defense Plant Corporation to provide vanadium during World War II. Various govern-
ment agencies operated the mill until 1947. In 1948 the Atomic Energy Commission
(AEC) obtained the mill and operated it under contract through 1959 to provide both
uranium and vanadium. Mill operations were terminated on January 1,1960. In 1961 the
mill tailings piles were leveled and graded, covered with rock and soil, and seeded with
native grasses. During 1974 and 1975, the ore stockpiles were removed from the site, and
the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city
of Monticello, in San Juan County, Utah. The site is bordered on the south and southeast
by land held by the U.S. Bureau of Land Management. Other boundaries are the city of
Monticello and private property.
During the AEC era, the mill processed approximately one million tons of uranium
ore. Vanadium and uranium were the only substances extracted in the milling process.
Other constituents of the ore remained in the tailings and were not separated prior to dis-
posal. During the years of active mill operation, the mill tailings were normally moist, so
erosion was minimal. However, throughout the mill's operating period, area residents
used these tailings as fill material and as aggregate in mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy
(DOE) initiated the Surplus Facilities Management Program (SFMP) in 1978 to ensure
the safe caretaking and decommissioning of government facilities that had been retired
from service but still had radioactive contamination. In 1980 the mill site at Monticello
was accepted into the SFMP, and the Monticello Remedial Action Project (MRAP) was
established to restore the government-owned mill site to safe levels of radioactivity, to
dispose of or contain the tailings in an environmentally safe manner, and to perform
remedial actions on off-site (vicinity) properties that had been contaminated by
radioactive material resulting from mill operations. The Monticello mill site and the
tailings remain in the custody of the DOE Grand Junction, Colorado, Projects Office. In
1983 remedial actions for vicinity properties were separated from MRAP with
establishment ofthe Monticello Vicinity Properties (MVP) Project (U.S. DOE 1990b).
•The verification of remedial action was performed by members of the Environmental Assessment Group in the
Environmental Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE
contract DE-AC05-96OR22464 with Lockheed Martin Energy Research Corporation.
During 1994, RUST Geotech Inc. (Geotech), the remedial action contractor (RAC)
designated by DOE, performed remedial action on the vicinity property that is the subject
of this report, a vacant lot located at 196 South Main Street, Monticello, Utah. The
remedial action plan required excavation of all exterior contamination. When the
excavation was completed, the property was resurveyed, including soil sampling, to
ensure the removal of all contamination, backfilled with uncontaminated material, and
restored to a condition comparable to that which existed prior to remedial action (Geotech
1996).
The DOE adopted a policy to assign an independent contractor to verify the data
supporting the adequacy of remedial action and to confirm the site's compliance with
DOE guidelines. The Environmental Technology Section (ETS) of Oak Ridge National
Laboratory (ORNL) has been assigned the responsibility of this task at the 196 South
Main Street site. This report describes the methods and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available docu-
mentation adequately and accurately describes the post-remedial-action radiological
conditions of the entire property that is to be certified and (2) that the remedial action
reduced contamination to below applicable DOE guidelines (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1996) in-
dicates the property was remediated as evaluated by DOE on the basis of Environmental
Protection Agency standards and the DOE guidelines (DOE 1990a). Excess residual
radioactive materials were present, thus it was appropriate to designate this property for
remedial action.
The pre-remedial-action survey performed by Geotech identified 8 yd3 of mill
tailings 6 to 30 inches deep. During the actual removal process, a total of 13 yd3 of con-
taminated earth and uranium mill tailings, 6 to 60 inches deep, were removed from a
17 m2 area.
A post-excavation survey was performed by Geotech prior to backfilling the exca-
vated areas. This survey consisted of gamma scans with a scintillometer of the exterior
and soil sampling. Samples representative of the bottom 15-cm (6-in.) soil layers of three
excavated verification areas were collected and blended to form representative composite
soil samples for each verification area.
4
CONCLUSION
Results of Geotech soil sample analysis and confirmatory split soil sample analysis
by ORNL show that radionuclide concentrations are within applicable DOE guidelines.
Based on the results of the post-remedial-action data, which are confirmed by the
verification assessment data, these radiological measurements fall below the limits
prescribed by DOE guidelines. All deficiencies noted in the initial review have been
identified by the RAC as discussed in a meeting between Geotech and ORNL on May 17,
1996. It is concluded that the site successfully meets the DOE remedial action objectives.
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of 226Ra in soil
above background levels,
averaged over a 100-m2 area
5 pCi/g averaged over the
first 15 cm of soil below the
surface; 15 pCi/g when ave-
raged over 15-cm-thick soil
layers more than 15 cm
below the surface
Radionuclide
concentrations in soil
for Hot Spot areas
Exposure to 222Rn
progeny
Maximum Permissible
concentration of Ra226 in soil
above background level, for
areas less than 25 m2
Average annual radon proge-
ny concentration (including
background)
Ra226 concentrations, in any
surface or subsurface area
less than 25 m2, is below the
guideline by a factor of
(1007A)'/J, where A is the
area ofthe elevated region
0.03 WL
(DOE 1990a)
6
Table 2. Results of ORNL analysis of Geotech soil samples
from 196 South Main Street, Monticello Utah (MS00225-VL)
226Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No.° No/ (cm)
XI NAY 193 >15 16 12.1
X2 NAY 194 >15 2.3 3.3
X3 NCB 527 >15 3.3 3.0
" An X-type sample is a split of the sample taken by the remedial action contractor.
* Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated
areas were taken by Geotech, and these samples were blended to form a composite soil
sample, which represents an average over one of the verification areas.
REFERENCES
Geotech 1996. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00225-VL, Address: 196 South Main Street, Monticello,
Utah 84535, Geotech, Grand Junction, Colorado, February 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
U.S. DOE 1990a. Verification and Certification Protocol for the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination
and Decommissioning Program, Revision 3, November 1990. U.S. Department of
Energy, Washington, D.C.
U.S. DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision
and Record of Decision Summary. U.S. Department of Energy, Grand Junction Projects
Office, Grand Junction, Colorado.
DOE ID No.: MS-00227-MR
Property Address: 145 West Second South Street
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech of Energy (DOE)
YES NO NOT TAKEN YES NO NOT TAKEN
Ra-226 is < 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [ ]
Ra-226 is ^ 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2.
In-situ [ ] Lab [X]
Interior gamma is <; 20 /vR/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is < 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21.
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
[>] [ ] I ]
W [ 1 I 1
[*] [ ] [ ]
[M [ ] [ ]
[ ] [A [ }
[/] [ ] t ]
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
Ililllllllll IMMIMIMII
SFCERTIFED SFMS-09227
DOE ID No.: MS-00227-MR
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Wanda S^Busby
Manager Montic
iusby Date
Manager^ Monticello Programs
Rust Geotech
DOE EVALUATION
Df ] Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Certification Official 7 Date
U.S. Department of Energy
PROPERTY COMPLETION REPORT
DOE ID NO.: MS-00227-MR
ADDRESS: 145 WEST SECOND SOUTH STREET
MONTICELLO, UTAH 84535
APRIL 1996
Prepared for
U.S. Department of Energy
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
by
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
' Waiyla S. Busby
Manager, Monticello Programs
Ililllllllll Ililllllllll
SFOCPLRPTS SFMS-00227
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.1.3 Radon Decay-Product Concentration (RDC) Measurement .... 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
i
DOE ID No.: MS-00227-MR
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Inclusion Survey Contractor. DOE reviewed
these evaluation results and determined that the property contained mill
tailings (residual radioactive material) exceeding EPA standards. The
Remedial Action Contractor was notified of the inclusion of this property
into the MVP Project and was authorized by DOE to conduct remedial
action as required to bring the property into conformance with EPA
standards and DOE hot spot criteria.
1
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
Property Address:
Property Owner:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
DOE ID No.: MS-00227-MR
MS-00227-MR
Location No. M-122; beginning at the NW
corner of Lot 4, Block 15, Monticello
Townsite Survey; south 214.5 feet, east
75.5 feet, north 107.5 feet, east 32 feet,
north 107 feet, west 107.5 feet to
beginning, County of San Juan, State of
Utah
145 West Second South Street
Monticello, Utah 84535

Major Residential (MR)
Oak Ridge National Laboratory
January 14, 1992
Rust Geotech
September 9, 1994
Diamond Back Services, Inc.
9861 Titan Park Circle
Littleton, Colorado
July 11, 1995
November 6, 1995
Interior: 7 cubic yards
Exterior: 39 cubic yards
124 square meters (m2)
April 1996
2
DOE ID No.: MS-00227-MR
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of interior and exterior residual
radioactive material (Appendix Figure 2.1). Once excavation was
complete, the affected areas were resurveyed for possible remaining
residual radioactive material and, upon attaining satisfactory results, were
backfilled with uncontaminated material. The property was restored to a
physical condition comparable to that which existed prior to remedial
action activities.
2.2 Previously Unidentified Contamination
The radiological assessment identified 48 cubic yards of contamination,
ranging from 6 to 27 inches deep, within the property. The remedial
action process included the removal of approximately 46 cubic yards of
residual radioactive material, ranging from 6 to 24 inches deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
3.0 VERIFICATION SUMMARY
DOE ID No.: MS-00227-MR
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
Radiological surveys were conducted by the Remedial Action
Contractor during November 1993 and March 1994, as described
in the final REA dated September 1994. Appendix Figure 2.1
shows the extent of assessed contamination and identifies the
areas recommended to undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the exterior excavation
were collected. These samples were blended to form composite
samples representing the exterior verification areas (Appendix
Figure 2.1).
Interior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 15 to 95 microroentgens per
hour (//R/h) for the remediated portion of the crawl space.
Elevated exposure rates in Area V-4 were associated with
embedded point sources in the foundation. This material was left
in place to avoid structural damage to the foundation. This
material does not cause elevated exposure rates on the ground
floor as indicated by a post-restoration gamma scan of the ground
floor ranging from 13 to 16 //R/h (Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 10 to 21 //R/h (Appendix
Figure 2.1). The results of analyses for radium-226 in three
composite soil samples ranged from 1.9 to 5.3 picocuries per
gram (pCi/g), as indicated in Appendix Table 3.1.
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on the DOE-approved abbreviated-measurement method,
the RDC was 0.0051 working level (WL), as indicated in Appendix
Table 3.2. Appendix Figure 2.1 shows the measurement location
on the ground floor (the lowest habitable level of the structure).
RDC measurements were taken before remediation of the property.
4
DOE ID No.: MS-00227-MR
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at 145 West Second South Street, in
Monticello, Utah, is recommended for certification as required by DOE
guidelines, and the appropriate records should be documented.
Certification Data Summary
Applicability
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Standards
Shall not exceed 20 //R/h
above background.*
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Survey Results
Range for the remediated
portion of the crawl
space was 15 to
95 //R/h/ Range for the
ground floor was 13 to
16//R/h.
Average was 0.0051 WL,
based on the DOE-
approved abbreviated-
measurement method.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background** in
the 15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background** in
any 15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
< 5 pCi/g above
background.
Soil sample results
ranged frorn 1.9 to
5.3 pCi/g.
*The background exposure rate is approximately 15 //R/h.
Elevated exposure rates were due to a point sources (embedded in the foundation).
**The background radium-226 concentration is approximately 2.0 pCi/g.
n~he hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-00227-MR
4.0 APPENDIX
Appendix Tables:
Table 3.1 Post-Excavation Sample/Measurement Results
Table 3.2 Radon Decay-Product Concentration Measurement
Results
Appendix Figure:
Figure 2.1 Interior and Exterior Extent of Contamination -
RADIOLOGICAL AS-BUILT
SJW:03-14-96
MS-00227.MR WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00227-MR
Address: 145 West Second South Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (//R/h) Ticket No. Method" (pCi/g)
EXTERIOR
V-1 14- 20 NCN 660 OCS 5.3
V-2 16-20 NCN 723 OCS 1.9
V-3 16-21 NCN 724 OCS 2.4
INTERIOR
V-4 15-95 Not applicable
See Appendix Figure 2.1 for the verification areas.
"OCS = Opposed Crystal System
7
Table 3.2
Radon Decay-Product Concentration Measurement Results
DOE ID No.: MS-00227-MR
Address: 145 West Second South Street, Monticello, Utah
Instrument Type: Landauer Radtrak Detector
Detector
Number Start Date End Date
Radon
Concentration
(pCi/L)
Working
Level
3964259
3964323
3964256
02-28-95
02-28-95
02-28-95
05-31-95
05-31-95
05-31-95
0.90
1.10
1.04
0.0045
0.0055
0.0052
Average: 0.0051
See Appendix Figure 2.1 for the measurement location.
8
42
40
38
36
34
32
30
28
26
24
22
20
18
16
14
12
10
12 14
T—i—i—r
16 18 20 22 24 26 28 30 32 34 36 38 40 42 44 46 48
i—i—i—i—i—i—i—i—i—i—i—i—i—i—i—i—i—i—i—i—i—i—i—i—i—i—i—i i i i i r
WEST SECONO SOUTH STREET
-J-U. m
n 13-15
I
E3
ONE STORY
FRAME HOUSE
13-16
SEE DETAIL A
If Lrii
V-1
3 / 14-20 RDC
\<3 © _^ <D
G 24 16-20 V-3
16-21
27 18
J SHED
v-i 10-12
14-20
Tl"—@©LI3
13-15
CRAWL SPACE
15: V-4 15 12 15-95
L 20 10
SCALE IN FEET
20
©
V?:73
12-15
12
v-i
16-17
DETAIL A
NOT TO SCALE
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN /iR/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE—RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION AREA IDENTIFIER AND
EXCAVATION EXPOSURE-RATE RANGE
RADON DECAY—PRODUCT CONCENTRATION
MEASUREMENT LOCATION
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
RADIOLOGICAL AS-BUILT
FIGURE 2.1
INTERIOR AND EXTERIOR EXTENT OF CONTAMINATION
40 NORTH
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY ANO ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT. UTILITY LOCATION PLAT, OR OTHER IMPROVEMENT SURVEY
PLAT AND IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE. BUILDING. OR OTHER FUTURE IMPROVEMENT LINES.
M:\FAS\033\0O03\RUO0227V 03/22/06 10:iaom TS0730
J I I I I I L J L
U.S. DEPARTMENT OF ENERGY
CRAM JUMCTKW PROJECTS OFFtCC. C010RA00
145 WEST SECOND SOUTH ST.
MONTICELLO. UTAH
"••»• MS-00227-MR
"» » J-C00227-V1 ,
12 14 16 18 20 22 24 26 28 30 32 34 36 38 40 42 44 46 48 50
OAK RIDGE NATIONAL LABORATORY
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
FOR THE US. DEPARTMENT OF ENERGY
PHONE: [phone]
FAX [phone]
POST OFFICE BOX 2S67
GRAND JUNCTION, COLORADO 81502
JUL 3 ] \m
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by
the U.S. Department of Energy for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program (FUSRAP) and Remote Surplus Facilities Management Program
Sites (SFMP) [Revision 2, March 1987]. This evaluation is based on an independent verifi-
cation review of the Remedial Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment of
the ^Ra concentration in the soil, indoor radon daughter concentration, and indoor gamma
exposure rates at this property.
This property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
MS00227
145 West 2nd South Street
Monticello, Utah 84535

Ed and Connie Mills
Location Number:
Location Address:
Property Owner:
Owner Address:
Tenant Name:
Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
145 WEST 2ND SOUTH STREET
MONTICELLO, UTAH (MS00227-MR)
M. J. Wilson-Nichols
July 1996
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 3
REFERENCES 6
iii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 4
2. Results of ORNL analysis of Geotech soil samples from 145 West 2nd South Street,
Monticello, Utah (MS00227-MR) 5
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site Decom-
missioning Projects, U.S. Department of Energy. The author wishes to acknowledge M.
K. Jensen for analysis of soil samples and N. F. Kirby and A. R. Jones for technical
reviews.
vii
ABSTRACT
In 1980 the site of a vanadium and uranium mill at Monticello, Utah, was accepted
into the U.S. Department of Energy's (DOE's) Surplus Facilities Management Program,
with the objectives of restoring the government-owned mill site to safe levels of radio-
activity, disposing of or containing the tailings in an environmentally safe manner, and
performing remedial actions on off-site (vicinity) properties that had been contaminated
by radioactive material resulting from mill operations. During 1995, RUST Geotech, the
remedial action contractor designated by DOE, performed remedial action on the vicinity
property at 145 West 2nd South Street, Monticello, Utah. The Environmental Technol-
ogy Section (ETS) of Oak Ridge National Laboratory was assigned the responsibility of
verifying the data supporting the adequacy of remedial action and confirming the site's
compliance with DOE guidelines. The ETS found that the site successfully meets the
DOE remedial action objectives. Procedures used by the ETS are described in the
Environmental Technology Section Procedures Manual (ORNL 1993).
ix
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 145 WEST 2ND SOUTH STREET
MONTICELLO, UTAH (MS00227-MR)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the U.S. government through the
Defense Plant Corporation to provide vanadium during World War U. Various govern-
ment agencies operated the mill until 1947. In 1948 the Atomic Energy Commission
(AEC) obtained the mill and operated it under contract through 1959 to provide both
uranium and vanadium. Mill operations were terminated on January 1, 1960. In 1961 the
mill tailings piles were leveled and graded, covered with rock and soil, and seeded with na-
tive grasses. During 1974 and 1975, the ore stockpiles were removed from the site, and
the mill foundations were buried
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city
of Monticello, in San Juan County, Utah. The site is bordered on the south and southeast
by land held by the U.S. Bureau of Land Management. Other boundaries are the city of
Monticello and private property.
During the AEC era, the mill processed approximately one million tons of uranium
ore. Vanadium and uranium were the only substances extracted in the milling process.
Other constituents of the ore remained in the tailings and were not separated prior to dis-
posal. During the years of active mill operation, the mill tailings were normally moist, so
erosion was minimal. However, throughout the mill's operating period, area residents
used these tailings as fill material and as aggregate in mortar and concrete.
Under the authority ofthe Atomic Energy Act, the U.S. Department of Energy
(DOE) initiated the Surplus Facilities Management Program (SFMP) in 1978 to ensure
the safe caretaking and decommissioning of government facilities that had been retired
from service but still had radioactive contamination. In 1980 the mill site at Monticello
was accepted into the SFMP, and the Monticello Remedial Action Project (MRAP) was
established to restore the government-owned mill site to safe levels of radioactivity, to
dispose of or contain the tailings in an environmentally safe manner, and to perform reme-
dial actions on off-site (vicinity) properties that had been contaminated by radioactive ma-
terial resulting from mill operations. The Monticello mill site and the tailings remain in the
custody of the DOE Grand Junction, Colorado, Projects Office. In 1983 remedial actions
for vicinity properties were separated from MRAP with establishment of the Monticello
Vicinity Properties (MVP) Project (U.S. DOE 1990b).
*The verification of remedial action was performed by members of the Environmental Assessment Group in the
Environmental Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE
contract DE-AC0S-96OR22464 with Lockheed Martin Energy Research Corporation.
2
During 1995, RUST Geotech Inc. (Geotech), the remedial action contractor (RAC)
designated by DOE, performed remedial action on the vicinity property that is the subject
of this report, a single family residence located at 145 West 2nd South Street, Monticello,
Utah. The remedial action plan required excavation of all exterior contamination. When
the excavation was completed, the property was resurveyed, including soil sampling, to
ensure the removal of all contamination, backfilled with uncontaminated material, and re-
stored to a condition comparable to that which existed prior to remedial action (Geotech
1996).
The DOE adopted a policy to assign an independent contractor to verify the data
supporting the adequacy of remedial action and to confirm the site's compliance with DOE
guidelines. The Environmental Technology Section (ETS) of Oak Ridge National Labor-
atory (ORNL) has been assigned the responsibility of this task at the 145 West 2nd South
Street site. This report describes the methods and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available doc-
umentation adequately and accurately describes the post-remedial-action radiological
conditions of the entire property that is to be certified and (2) that the remedial action
reduced contamination to below applicable DOE guidelines (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1996) in-
dicates the property was remediated as evaluated by DOE on the basis of Environmental
Protection Agency standards and the DOE guidelines (DOE 1990a). Excess residual
radioactive materials were present, thus it was appropriate to designate this property for
remedial action.
The pre-remedial-action survey performed by Geotech identified 48 yd3 of mill tailings
6 to 27 inches deep. During the actual removal process, a total of 46 yd3 of contaminated
earth and uranium mill tailings, 6 to 24 inches deep, was removed from a 124 m2 area.
A post-excavation survey was performed by Geotech prior to backfilling the exca-
vated areas. This survey consisted of gamma scans with a scintillometer of the ground
level of the structure, a surface scan of the exterior, and soil sampling. Samples repre-
sentative of the bottom 15-cm (6-in.) soil layers of three excavated verification areas were
collected and blended to form representative composite soil samples for each verification
area.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation
levels have not been subtracted. Similarly, background concentrations have not been sub-
tracted from radionuclide concentrations in soil samples. Applicable DOE guidelines for
protection against radiation are given in Table 1.
Gamma Measurements
Gamma exposure rate measurements taken by Geotech at the ground-level of the
residence ranged from 13 to 16 uR/h. Gamma exposure rates in the excavated crawl
space ranged from IS to 95 uR/h. The anomalous gamma exposure rate of 95 uR/h was
on contact with a point source embedded in the foundation, which was left in place for
structural reasons. Exterior surface gamma measurements taken from the excavated areas
prior to backfilling ranged from 14 to 21 uR/h.
Soil Sample Analysis
Prior to backfilling, Geotech collected soil samples representative of the excavated
areas from the bottom 15-cm (6-in.) soil layers. These samples were blended to form a
composite soil sample representative of an average over the three exterior verification
areas. Geotech's analysis of these samples showed ^Ra concentrations ranging from 1.9
to 5.3 pCi/g in the composite sample. ORNL ETS obtained these soil samples and per-
formed a confirmatory analysis which showed ^Ra concentrations ranging from 1.5 to
4.0 pCi/g. These values are below the EPA standard value of 15 pCi/g for soil layers
> 15 cm below the surface. Gamma ranges and/or soil sample results demonstrate
compliance to the DOE Hot Spot Guidelines for areas <25 m2 (Table 1).
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were deter-
mined by the Alpha-track method. To monitor radon levels, Geotech placed three alpha-
track detectors on the ground floor of the residence located on this property for a period
of approximately three months (from February 28, 1995 to May 31, 1995). The average
annual working level (WL) of radon progeny concentration, as determined by the Tech./-
Ops-Landauer Corporation, was 0.0051, which is well below the 0.03-WL guideline given
in Table 1.
CONCLUSION
Results of Geotech soil sample analysis and confirmatory split soil sample analysis
by ORNL show that radionuclide concentrations are within applicable DOE guidelines.
Based upon the results ofthe post-remedial-action data, which are confirmed by the veri-
fication assessment data, these radiological measurements fall below the limits prescribed
by DOE guidelines. It is concluded that the site successfully meets the DOE remedial
action objectives.
Table 1. Applicable guidelines for protection against radiation
Mode of exposure
Radionuclide con-
centrations in soil
Exposure conditions
Maximum permissible con-
centration of ^Ra in soil
above background levels,
averaged over a 100-m2 area
Guideline value
5 pCi/g averaged over the
first IS cm of soil below the
surface; 15 pCi/g when ave-
raged over 15-cm-thick soil
layers more than 15 cm
below the surface
Ra226 concentrations, in any
surface or subsurface area
less than 25 m2, is below the
guideline by a factor of
(1007A)*, where A is the
area of the elevated region
0.03 WL
Radionuclide con-
centrations in soil
for Hot Spot areas
Maximum Permissible con-
centration of Ra226 in soil
above background level, for
areas less than 25 m2
Exposure to 222Rn
progeny
Average annual radon proge-
ny concentration (including
background)
(DOE 1990a)
5
Table 2. Results of ORNL analysis of Geotech soil samples
from 145 West 2nd South Street, Monticello, Utah (MS00227-MR)
""Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No." No^ (cm)
XI NCN660 >15 4.0 5.3
X2 NCN723 >15 1.5 1.9
X3 NCN724 >15 2.4 2.4
" An X-type sample is a split of the sample taken by the remedial action contractor.
* Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated areas
were taken by Geotech, and these samples were blended to form a composite soil
sample, which represents an average over one of the verification areas.
6
REFERENCES
Geotech 1996. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00227-MR, Address: 145 West Second South Street,
Monticello, Utah 84535, Geotech, Grand Junction, Colorado, April 1996.
ORNL, 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
U.S. DOE 1990a. Verification and Certification Protocol for the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination
and Decommissioning Program, Revision 3, November 1990. U.S. Department of
Energy, Washington, D.C.
U.S. DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision
and Record of Decision Summary. U.S. Department of Energy, Grand Junction Projects
Office, Grand Junction, Colorado.
DOE ID No.: MS-00233-MR
Property Address: 96 West Fourth South Street
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech of Energy (DOE)
Ra-226 is <, 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [X]
Ra-226 is ^ 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2.
In-situ [ ] Lab [X]
Interior gamma is <; 20 //R/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is < 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21.
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
[X] [ ] [ ]
[X] [ ] [ I
[*] [ ] [ ]
[ ] [V] [ ]
[Y] [ ] [ 1
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
iiiuiiiiii mnuim
SFCERTIFED SFMS-90233
DOE ID No.: MS-00233-MR
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
tenda S. Busby / /
lanager, Monticello Program
Wanda S. Busby / / Date
Manager, Monticello Programs
Rust Geotech
DOE EVALUATION
[X] Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
h^<4
Certification Official
U.S. Department of Energy
tt 04 n
Date
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
DOE ID NO.: MS-00233-MR
ADDRESS: 96 WEST FOURTH SOUTH STREET
MONTICELLO, UTAH 84535
JUNE 1996
Prepared for
U.S. Department of Energy
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
FOR
by
Wanda S. Busby/ /
Manager, Monticello Programs
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
TABLE OF CONTENTS
Section Page
1.0 SUMMARY . 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.1.3 Radon Decay-Product Concentration (RDC) Measurement .... 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
i
DOE ID No.: MS-00233-MR
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Inclusion Survey Contractor. DOE reviewed
these evaluation results and determined that the property contained mill
tailings (residual radioactive material) exceeding EPA standards and DOE
hot spot criteria. The Remedial Action Contractor was notified of the
inclusion of this property into the MVP Project and was authorized by DOE
to conduct remedial action as required to bring the property into
conformance with EPA standards and DOE hot spot criteria.
1
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
Property Address:
Property Owners:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
DOE ID No.: MS-00233-MR
MS-00233-MR
Beginning at the SW corner of Lot 2,
Block 7, Monticello Townsite Survey; east
126.5 feet, north 134.5 feet, west
16.5 feet, south 80 feet, west 110 feet,
south 54.5 feet to beginning, County of
San Juan, State of Utah
96 West Fourth South Street
Monticello, Utah 84535

Major Residential (MR)
Oak Ridge National Laboratory
January 25, 1990
Rust Geotech
September 13, 1994
Diamond Back Services, Inc.
9861 Titan Park Circle
Littleton, Colorado
May 2, 1995
June 12, 1995
Interior: 7.0 cubic yards
Exterior: 0.1 cubic yards
2 square meters (m2)
June 1996
2
DOE ID No.: MS-00233-MR
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of interior and exterior residual
radioactive material (Appendix Figure 2.1). Once excavation was
complete, the affected areas were resurveyed for possible remaining
residual radioactive material and, upon attaining satisfactory results, were
backfilled with uncontaminated material. The property was restored to a
physical condition comparable to that which existed prior to remedial
action activities.
2.2 Previously Unidentified Contamination
The radiological assessment identified contamination, ranging from
6 inches deep to 96 inches high, within the property. The quantity of
contamination for this property was not specified because it was assessed
as part of a larger property that was subsequently divided into two
smaller, separate properties. The remedial action process included the
removal of approximately 7.1 cubic yards of residual radioactive material,
ranging from 6 inches deep to 96 inches high.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID No.: MS-00233-MR
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
Radiological surveys were conducted by the Remedial Action
Contractor during October 1991 and May 1993, as described in
the final REA dated September 1994. Appendix Figure 2.1 shows
the extent of assessed contamination and identifies the areas
recommended to undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the exterior excavation
were collected. Individual soil samples were collected for
Areas V-3 and V-4. The remaining samples were blended to form
a composite sample representing the other verification area
(Appendix Figure 2.1).
Interior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 12 to 13 microroentgens per
hour (//R/h) for the partial basement, and 13 to 16 //R/h for the
remediated portion and remainder of the ground floor (Appendix
Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 13 to 20//R/h (Appendix
Figure 2.1). The results of analyses for radium-226 in two
individual soil samples and one composite soil sample ranged from
1.5 to 4.1 picocuries per gram (pCi/g), as indicated in Appendix
Table 3.1.
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on the DOE-approved abbreviated-measurement method,
the RDC was 0.0179 working level (WL), as indicated in Appendix
Table 3.2. Appendix Figure 2.1 shows the measurement location
in the partial basement (the lowest habitable level of the
structure).
4
DOE ID No.: MS-00233-MR
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at 96 West Fourth South Street, in
Monticello, Utah, is recommended for certification as required by DOE
guidelines, and the appropriate records should be documented.
Certification Data Summary
Applicability
Habitable Structures
Exposure Rate:
Standards
Shall not exceed 20 //R/h
above background.*
Survey Results
Ranges were 12 to
13 //R/h for the partial
basement, and 13 to
16 //R/h for the
remediated portion and
remainder of the ground
floor.
Radon Decay-Product
Concentration:
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Average was 0.0179 WL,
based on the DOE-
approved abbreviated-
measurement method.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
< 5 pCi/g.
Soil sample results
ranged from 1.5 to
4.1 pCi/g.**
*The background exposure rate is approximately 14//R/h.
The background radium-226 concentration is approximately 2.0 pCi/g.
* *The hot spot criteria were met based on gamma scans and/or soil sample results.
A part of samples V-3 and V-4 were from the 15-cm surface layer.
5
DOE ID No.: MS-00233-MR
4.0 APPENDIX
Appendix Tables:
Table 3.1 Post-Excavation Sample/Measurement Results
Table 3.2 Radon Decay-Product Concentration Measurement
Results
Appendix Figure:
Figure 2.1 Interior and Exterior Extent of Contamination -
RADIOLOGICAL AS-BUILT
SJW:04-30-96
MS-00233.MR WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00233-MR
Address: 96 West Fourth South Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range OuR/h) Ticket No. Method* (pCi/g)
EXTERIOR
V-1 16-18 NCJ 019 OCS 2.9
V-3 20 NCO 129 OCS 4.1
V-4 19 NCO 130 OCS 1.5
INTERIOR
V-2 13-16 Not applicable
See Appendix Figure 2.1 for the verification areas.
"OCS = Opposed Crystal System
7
Table 3.2
Radon Decay-Product Concentration Measurement Results
DOE ID No.: MS-00233-MR
Address: 96 West Fourth South Street, Monticello, Utah
Instrument Type: Landauer Radtrak Detector
Detector
Number Start Date End Date
Radon
Concentration
(pCi/L)
Working
Level
3973883
3973920
3973867
07-26-95
07-26-95
07-26-95
11-15-95
11-15-95
11-15-95
3.544 0.0177
3.741 0.0187
3.453 0.0173
Average: 0.0179
See Appendix Figure 2.1 for the measurement location.
8
10
30
12 1 4 16 20 22 24 26 28 32 34 36 38 40
30
28
26
24
22
20
Ld
LU
DC
t—
CO
1—
CO
LU
CO
Cd
o co
18
16
14
12
Y
v-z
13-16
GROUND FLOOR
13-16
D}[96]
HED|
>— 1 S I 1 3
V-3
2CVR/h
DETAIL A
NOT TO SCALE
13-18
13-18
ONE STORY
FRAME HOUSE
W/PARTIAL BASEMENT
12-13
SEE DETAIL A
JJJ
13-: 8
L...
V-1
16-18
RDC
s o . J e1
V-4
19uR/h
©
<£>
F7.n
12-15
1 2
v-1
16-17
(RDC)
[12]
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN /xR/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION AREA IDENTIFIER AND
EXCAVATION EXPOSURE-RATE RANGE
RADON DECAY-PRODUCT CONCENTRATION
MEASUREMENT LOCATION
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
HEIGHT IN INCHES OF ASSESSED CONTAMINATED
BRICK REMOVED AND REPLACED
NORTH
SCALE IN FEET
20 10 0 20 40
28
26
- 24
22
20
18
RADIOLOGICAL AS-BUILT
FIGURE 2.1
INTERIOR AND EXTERIOR EXTENT OF CONTAMINATION
16
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT. UTILITY LOCATION PLAT, OR OTHER IMPROVEMENT SURVEY
PLAT AND IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE, BUILDING OR OTHER FUTURE IMPROVEMENT LINES.
/// rrr
WEST FOURTH SOUTH STREET
10
M:\FAS\033\0003\RM00233V 05/22/96 07:22am T507B0
J I I I 1 I L
RESIDENCE-NO. OF OCCUPANTS
HON-RESIOENCC-UAN-HRS./WK.
INSTRUMENT NO.
SURVEY OATE
14
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE, COLORADO
CHECKED
96 WEST FOURTH SOUTH ST.
MONTICELLO, UTAH
12
Rust Qeotcch
APPROVAL OOE DATE
DOEIONO. MS-00233-MR
OWO.NO. 3-B00233-V1 2U, 10
10 12 1 4 1 6 18 20 22 24 26 28 30 32 34 36 38 40
OAK RIDGE NATIONAL LABORATORY
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
FOR THE US. DEPARTMENT OF ENERGY
PHONE: [phone]
FAX: [phone]
POST OFFICE BOX 2SS7
GRAND JUNCTION, COLORADO 81502 AUG 3 0 199S
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P.O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by the
U.S. Department of Energy for Residual Radioactive Material at Formerly Utilized Sites Remedial
Action Program (FUSRAP) and Remote Surplus Facilities Management Program Sites (SFMP)
[Revision 2, March 1987]. This evaluation is based on an independent verification review of the
Remedial Action Contractor's completion report and field verification.
This recommendation is based upon the Independent Verification Contractor's assessment of the
^Ra concentration in the soil, indoor radon daughter concentration, and indoor gamma exposure
rate at this property.
Therefore, this property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
Location Number: MS00233-MR
Location Address: 96 West 4th South Street
Monticello. Utah 84535
Property Owner:

Tenant Name: Same
Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE B INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
96 WEST 4TH SOUTH STREET
MONTICELLO, UTAH (MS00233-MR)
A. R. Jones
August 1996
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES v
LIST OF FIGURES v
ACKNOWLEDGMENTS vii
ABSTRACT viii
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
GEOTECH SURVEY RESULTS 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
ORNL SURVEY RESULTS 6
Gamma Measurements 6
Soil Sample Analysis 6
CONCLUSION 6
REFERENCES 8
ii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 4
2. Results of ORNL and Geotech analyses of soil samples from 96 West 4th South
Street Monticello, Utah (MS00233-MR) 5
LIST OF FIGURES
1. Property Map 7
v
ACKNOWLEDGMENTS
Research for this project was sponsored by the U.S. Department of Energy, Office of
Environmental Restoration, Southwestern Area Programs. The author wishes to acknow-
ledge M. K. Jensen for analysis of soil samples and G. A. Pierce and N. F. Kirby for technical
reviews.
vii
ABSTRACT
In 1980 the site of a vanadium and uranium mill at Monticello, Utah, was accepted into
the U.S. Department of Energy's (DOE's) Surplus Facilities Management Program, with the
objectives of restoring the government-owned mill site to safe levels of radioactivity, dis-
posing of or containing the tailings in an environmentally safe manner, and performing reme-
dial actions on off-site (vicinity) properties that had been contaminated by radioactive material
resulting from mill operations. During 1995 and 1996, RUST Geotech Inc., the remedial ac-
tion contractor designated by DOE, performed remedial action on the vicinity property at 96
West 4th South Street, Monticello, Utah. The Environmental Technology Section (ETS) of
Oak Ridge National Laboratory was assigned the responsibility of verifying the data support-
ing the adequacy of remedial action and confirming the site's compliance with DOE guide-
lines. The ETS found that the site successfully meets the DOE remedial action objectives.
Procedures used by ETS are described in the Environmental Technology Section Procedures
Manual (ORNL 1993).
viii
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 96 WEST 4TH SOUTH STREET
MONTICELLO, UTAH (MS00233-MR)'
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the U.S. government through the
Defense Plant Corporation to provide vanadium during World War U. Various government
agencies operated the mill until 1947. In 1948 the Atomic Energy Commission (AEC)
obtained the mill and operated it under contract through 1959 to provide both uranium and
vanadium. Mill operations were terminated on January 1,1960. In 1961 the mill tailings piles
were leveled and graded, covered with rock and soil, and seeded with native grasses. During
1974 and 1975, the ore stockpiles were removed from the site, and the mill foundations were
buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city of
Monticello, in San Juan County, Utah. The site is bordered on the south and southeast by
land held by the U.S. Bureau of Land Management. Other boundaries are the city of Monti-
cello and private property.
During the AEC era, the mill processed approximately one million tons of uranium ore.
Vanadium and uranium were the only substances extracted in the milling process. Other con-
stituents ofthe ore remained in the tailings and were not separated prior to disposal. During
the years of active mill operation, the mill tailings were normally moist, so erosion was mini-
mal. However, throughout the mill's operating period, area residents used these tailings as
fill material and as aggregate in mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy (DOE)
initiated the Surplus Facilities Management Program (SFMP) in 1978 to ensure the safe
caretaking and decommissioning of government facilities that had been retired from service
but still had radioactive contamination. In 1980 the mill site at Monticello was accepted into
the SFMP, and the Monticello Remedial Action Project (MRAP) was established to restore
the government-owned mill site to safe levels of radioactivity, to dispose of or contain the
tailings in an environmentally safe manner, and to perform remedial actions on off-site (vicin-
ity) properties that had been contaminated by radioactive material resulting from mill
operations. The Monticello mill site and the tailings remain in the custody of the DOE Grand
Junction, Colorado, Projects Office. In 1983 remedial actions for vicinity properties were
separated from MRAP with establishment of the Monticello Vicinity Properties (MVP)
Project (U.S. DOE 1990b).
The verification of remedial action was performed by members of the Environmental
Technology Section ofthe Health Sciences Research Division at Oak Ridge National Laboratory
under DOE contract DE-AC05-96OR22464 with Lockheed Martin Energy Research Corp.
2
During 1995 and 1996, RUST Geotech Inc. (Geotech), the remedial action contractor
(RAC) designated by DOE, performed remedial action on the vicinity property that is the
subject of this report, a private residence located at 96 West 4th South Street, Monticello,
Utah. The remedial action plan required removal of all interior contamination and excavation
of all exterior contamination, backfilling with uncontaminated material, and restoration to a
condition comparable to that which existed prior to remedial action (Geotech 1996). When
the excavation stage was completed, the property was resurveyed, including soil sampling,
by Geotech and by an independent contractor to verify the data supporting the adequacy of
remedial action and to confirm the site's compliance with DOE guidelines. The Environmen-
tal Technology Section (ETS) of Oak Ridge National Laboratory (ORNL) has been desig-
nated the Independent Verification Contractor for the 96 West 4th South Street site. This re-
port describes the methods and results of the verification surveys.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available documenta-
tion adequately and accurately describes the post-remedial-action radiological conditions of
the entire property that is to be certified and (2) that the remedial action reduced contami-
nation to below applicable DOE guidelines (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1996) indicates
the property was remediated as evaluated by DOE on the basis of Environmental Protection
Agency standards (DOE 1990a) and that excess residual radioactive materials were present.
Thus it was appropriate to designate this property for remedial action.
The pre-remedial-action survey performed by Geotech identified mill tailings 6 inches
deep to 96 inches high. The quantity of contamination was not determined for this property
as it was assessed with MS01073. However, during the actual removal process, a total of 7.1
yd3 of contaminated earth and uranium mill tailings, 6 inches deep to 96 inches high, were
removed from a 2 m2 area.
A post-excavation survey was performed by Geotech of the interior areas of removal, and
prior to backfilling of the excavated areas. This survey consisted of gamma scans with a scin-
tillometer, ground-level and basement scans of the building, a surface scan of the exterior, and
soil sampling. Samples representative of the bottom 15-cm (6-in.) soil layers of one exca-
vated area was collected and blended to form a representative composite soil sample for the
verification area VI. Soil results for the interior verification area V2 are not applicable to
evaluate DOE guidelines and are not reported.
The RAC was requested by their reports subsection to return to the property to gather addi-
tional gamma exposure data on the partial basement and the exterior of the property. A
subsequent survey on May 8, 1996, detected two isolated ore deposits. Individual samples
representative of the bottom 15-cm soil layers of the two excavated areas were collected for
verification areas V3 and V4 (May 14, 1996).
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation
levels have not been subtracted. Similarly, background concentrations have not been sub-
tracted from radionuclide concentrations in soil samples. Applicable DOE guidelines for
protection against radiation are given in Table 1.
GEOTECH SURVEY RESULTS
Gamma Measurements
Gamma exposure rate measurements taken by Geotech over the ground-level of the
residence including the remediated area ranged from 13 to 16 //R/h. Exterior surface gamma
measurements taken from the excavated areas prior to backfilling ranged from 16 to 20 uR/h.
Soil Sample Analysis
Prior to backfilling, Geotech collected soil samples representative of excavated area VI
from the bottom 15-cm (6-in.) soil layers. These samples were blended to form a composite
soil sample representative of an average over the exterior verification area. Geotech's analysis
of this sample showed a ^Ra concentration of 2.9 pCi/g. ORNL ETS obtained this sample
and performed a confirmatory analysis which showed a 226Ra concentration of 2.0 pCi/g.
Geotech also collected two individual soil samples that included material from the surface soil
layer. Geotech's analysis of these samples showed ^Ra concentrations of 4.1 and 1.5 pCi/g.
These values are below the EPA standard value of 5 pCi/g for surface soil layers and 15 pCi/g
for soil layers >15 cm below the surface (Table 1). Gamma ranges and/or soil sample results
demonstrate compliance to the DOE Hot Spot Guideline for areas < 25 m2 (Table 1).
Results of Geotech and ORNL soil sample analyses are given in Table 2.
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were determined
by the alpha-track method. To monitor radon levels, Geotech placed three Alpha-track detec-
tors on the basement level ofthe residence located on this property for a period of approxi-
mately three months during a DOE approved prompt window (from July 26, 1995 to
November 15,1995). The IVC was present during placement and retrieval of the detectors
to verify the RDC measurements. The average annual working level (WL) of radon progeny
concentration, as determined by the Tech./Ops-Landauer Corporation, was 0.0179, which is
below the 0.03-WL guideline given in Table 1. The procedures and methods used to obtain
the annual average WL are deemed adequate and the results accurate by the IVC.
4
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of ^Ra in soil
above background levels,
averaged over a 100-m2 area
5 pCi/g averaged over the
first 15 cm of soil below the
surface; 15 pCi/g when
averaged over 15-cm-thick
soil layers more than 15 cm
below the surface.
Radionuclide con-
centrations in soil
for Hot Spot areas
Exposure to 222Rn
progeny
Maximum permissible con-
centration of ^Ra in soil
above background level, for
areas less than 25 m2.
Average annual radon proge-
ny concentration (including
background).
Ra concentration, in any
surface or subsurface area
less than 25 m2, is below the
guideline of (lOO/A)*,
where A is the area of the
elevated region.
0.03 WL
(DOE 1990a)
5
Table 2. Results of ORNL and Geotech analyses of soil samples
from 96 West 4th South Street, Monticello, Utah (MS00233-MR)
—Ra concentration (pCi/g)
ORNL Geotech
sample
No.*
sample Depth
(cm) No." Confirmatory* ORNL'' Geotech
V1H 1.6
XI NCJ 019 >15 2.0 2.9
* An X-type sample is a split of the sample taken by the remedial action contractor.
6 Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated
areas were taken by RUST Geotech Inc., and these samples were blended to form
composite soil samples, which represent an average over verification areas.
c ORNL performed analysis on aliquots of the composite samples taken by Geotech
(confirmatory).
d Composite samples collected by ORNL from approximately the same excavated
locations sampled by Geotech.
6
ORNL SURVEY RESULTS
Gamma Measurements
Measurements taken by ORNL over the ground surface in the excavated areas prior to
backfilling ranged from 14 to 16 uR/h. Gamma exposure rate measurements in the area of
interior removal ranged from 12 to 16 uR/h (Figure 1).
Soil Sample Analysis
ORNL sampled excavated area VI prior to backfilling, collecting an individual sample
representative of the highest gamma exposure rate from the bottom 15 cm (6 inch) soil layer.
ORNL's analysis of this sample showed 226Ra concentrations of 1.6 pCi/g. This value is below
the DOE guideline value of 15 pCi/g for soil layers >15 cm below the surface (Table 1).
ORNL was not notified or present during the excavation and verification of areas V3 and V4.
Results of ORNL sample analyses are given in Table 2.
CONCLUSION
The results of all Geotech and ORNL soil sample analyses show that radionuclide
concentrations are within applicable DOE guidelines. Based upon the results of the post-
remedial-action data, which are confirmed by the verification assessment data, these radio-
logical measurements fall below the limits prescribed by DOE guidelines. It is concluded that
the site successfully meets the DOE remedial action objectives.
7
This page (7) is for the property map.
LU
or
I—
CO
I—
CO
LU
r-
to
3
o
CO
L.
n
£DC)
SHED
ONE STORY
FRAME HOUSE
W/PART. BSMT
—t J
to
WEST 4TH SOUTH STREET
EXPLANATION
Concrete
Assessed
contamination
Assessed area
not found
Excavated
area
Remaining
contamination
RDC
Measurement
Area identifier &
Composite sample
Identifier of
j B1 | averaged area &
Biased sample
Vll 14-16 fiR/h
V2~l 12-16 fiR/h
N.
A
JL
i
FEET
IS CO
3 6
METERS
30
9
Figure 1. Property Map
MS00233
0000 WEST 4TH SOUTH STREET
MONTICELLO, UTAH
8
REFERENCES
Geotech 1996, Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00233-MR, Address: 96 West Fourth South Street, Monticello,
Utah 84535, Geotech, Grand Junction, Colorado, June, 1996.
ORNL, 1993. Environmental Technology Section Procedures Manual. ORNL 6645/R2 Oak
Ridge National Laboratory, Grand Junction, Colorado.
TJ. S. DOE 1990a. Verification and Certification Protocolfor the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination and
Decommissioning Program, Revision 3, November 1990. U.S. Department of Energy,
Washington, D.C.
U.S. DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision and
Record of Decision Summary. U.S. Department of Energy, Grand Junction Projects Office,
Grand Junction, Colorado.
DOE ID No.: MS-00234-VL
Property Address: 195 East First North Street
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
Ra-226 is <; 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [ ]
Ra-226 is <; 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2.
In-situ [ ] Lab [X]
Interior gamma is <; 20 //R/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is £ 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21.
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
Rust Gfiotech
YES NO NOT TAKEN
[XI* [ ] [ ]
[X] [ ] [ ]
[ ] [ ] [X]
(Vacant Lot)
U.S. Department
of Energy (DOE)
YES NO NOT TAKEN
[/] I ] I 1
[>] [ ]
k [ ] [ 1
[ ] [X] [ ]
[X] [ J [ ]
[ ]
[ ] I ] [X] [ ] [ ] l/l
(Vacant Lot)
[ 1 W [ 1
m I 1 I 1
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
•nmiiiiH ••uni
SFCERTIFED SFMS-09033
DOE ID No.: MS-00234-VL
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Date tenda S. Busby
Manager, Monticello Programs
Rust Geotech
DOE EVALUATION
[X] Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Certification 'Official 7
U.S. Department of Energy
Date
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00234-VL
ADDRESS: 195 EAST FIRST NORTH STREET
MONTICELLO, UTAH 84535
FEBRUARY 1996
Prepared for
U.S. Department of Energy
by
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
w Wand4 S. Busby
Manager, Monticello Programs
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
DOE ID No.: MS-00234-VL
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Remedial Action Contractor. DOE reviewed these
evaluation results and determined that the property contained mill tailings
(residual radioactive material) exceeding EPA standards. The Remedial
Action Contractor was notified of the inclusion of this property into the
MVP Project and was authorized by DOE to conduct remedial action as
required to bring the property into conformance with EPA standards and
DOE hot spot criteria.
1
2.0 OPERATIONS SUMMARY
DOE ID No.: MS-00234-VL
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of exterior residual radioactive
material (Appendix Figure 2.1). Once excavation was complete, the
affected areas were resurveyed for possible remaining residual radioactive
material and, upon attaining satisfactory results, were backfilled with
uncontaminated material. The property was restored to a physical
condition comparable to that which existed prior to remedial action
activities.
2.2 Previously Unidentified Contamination
The radiological assessment identified contamination, 6 inches deep,
within the property. The quantity of contamination for this property was
not specified because it was assessed as part of Block MS-09033-BK.
The remedial action process included the removal of approximately
50 cubic yards of residual radioactive material, ranging from 8 to
10 inches deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID No.: MS-00234-VL
VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
Radiological surveys were conducted by the Remedial Action
Contractor during September 1992 and June 1993, as described
in the final REA dated September 1994. Appendix Figure 2.1
shows the extent of assessed contamination and identifies the
areas recommended to undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the excavation were
collected. These samples were blended to form composite
samples representing the verification areas (Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 13 to 20 microroentgens per
hour U/R/h), as indicated on Appendix Figure 2.1. The results of
analyses for radium-226 in three composite soil samples ranged
from 1.9 to 4.3 picocuries per gram (pCi/g), as indicated in
Appendix Table 3.1.
DOE ID No.: MS-00234-VL
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at 195 East First North Street, in
Monticello, Utah, is recommended for certification as required by DOE
guidelines, and the appropriate records should be documented.
Certification Data Summary
Applicability
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Standards
Shall not exceed 20 //R/h
above background.
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Survey Results
Not applicable:
vacant lot.
Not applicable:
vacant lot.
Land.
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background* in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background* in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
< 5 pCi/g above
background.
Soil sample results
ranged from 1.9 to
4.3 pCi/g.T
•The background radium-226 concentration is approximately 2.0 pCi/g.
The hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-00234-VL
4.0 APPENDIX
Appendix Table:
Table 3.1 Post-Excavation Sample/Measurement Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
SJW:11-30-95
MS-00234.VL WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00234-VL
Address: 195 East First North Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (//R/h) Ticket No. Method" (pCi/g)
V-1 14-17 NCH 058 OCS 1.9
V-2 14-20 NCH 059 OCS 3.0
V-3 14-20 NCH 060 OCS 4.3
See Appendix Figure 2.1 for the verification areas.
"OCS = Opposed Crystal System
7
1
42
40
38
36
34
32
30
28
26
24
22
20
18
16
14
12
10
1 2 16
~i—r
18 20 22
i—r
24 26 28 30 32 34 36 38 40 42 46 48 51
i r
EAST FIRST NORTH STREET
/// UJ_ ///
13-16
v-
14-17 V-2
14-20
Sj (6) V-3
14-20
13-16
V-3
14-20 I
0
C7.\vl
rv.vj
12-15
12
v-i
16-17
13-16
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN fiH/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST—REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE-RATE RANGE
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
SCALE IN FEET
20 10 0 20 40
U:\rAS\033\0OO3\RU00234v 01/09/96 09:30om T507S0
J L
NORTH
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. OEPARTUENT
OF ENERGY ANO ITS CONTRACTORS. IT IS NOT A LAND SURVEf
PLAT, UTILITY LOCATION PLAT, OR OTHER IMPROVEMENT SUR/EY
PLAT ANO IS NOT TO BE RELIEO UPON FOR THE ESTABLISHMENT
OF FENCE. BUILOINC, OR OTHER FUTURE IMPROVEMENT LINES.
MW-ICllMKCf-IMIt-HIIVM.
U.S. DEPARTMENT OF ENERGY
WHO JUNCTION MOJCCTS OFFICC, COLORADO
195 EAST FIRST NORTH ST.
MONTICELLO. UTAH
Ku»t 0«oUch "«•"• MS-002J4-VL
m ~ 3-C00234-V1 ,
12 14 16 18 20 22 24 26 28 30 32 34 36 38 40 42 44 46 48 5i
OAK RIDGE NATIONAL LABORATORY PHONE: (»70) 24M200
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION FAX: (870) 24M220
FOR THE U.S. DEPARTMENT OF ENERGY
POST OFFICE BOX 2507
GRAND JUNCTION, COLORADO 81502 gj^V g j
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by the
U.S. Department of Energy for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program (FUSRAP) and Remote Surplus Facilities Management Program
Sites (SFMP) [Revision 2, March 1987]. This evaluation is based on an independent
verification review of the Remedial Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment of
the 226Ra concentration in the soil at this property.
Therefore, this property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
Location Number: MS00234-VL
Location Address: 195 East 1st North Street
Monticello, Utah 84535
Property Owner:

Tenant Name: N/A
Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
195 EAST 1ST NORTH STREET
MONTICELLO, UTAH (MS00234-VL)
M. J. Wilson-Nichols
May 1996
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
CONCLUSION 3
REFERENCES 6
iii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 4
2. Results of ORNL analysis of Geotech soil samples from 195 East 1st North Street,
Monticello, Utah (MS00234-VL) 5
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site Decom-
missioning Projects, U.S. Department of Energy. The author wishes to acknowledge
M. K. Jensen for analysis of soil samples and N. F. Kirby and G. A. Pierce for technical
reviews.
vii
ABSTRACT
In 1980 the site of a vanadium and uranium mill at Monticello, Utah, was accepted
into the U.S. Department of Energy's (DOE's) Surplus Facilities Management Program,
with the objectives of restoring the government-owned mill site to safe levels of radio-
activity, disposing of or containing the tailings in an environmentally safe manner, and
performing remedial actions on off-site (vicinity) properties that had been contaminated
by radioactive material resulting from mill operations. During 1995, RUST Geotech, the
remedial action contractor designated by DOE, performed remedial action on the vicinity
property at 195 East 1st North Street, Monticello, Utah. The Environmental Technology
Section (ETS) of Oak Ridge National Laboratory was assigned the responsibility of veri-
fying the data supporting the adequacy of remedial action and confirming the site's com-
pliance with DOE guidelines. The ETS found that the site successfully meets the DOE
remedial action objectives. All deficiencies noted in the initial review have been resolved
in the revised completion report. Procedures used by the ETS are described in the Envi-
ronmental Technology Section Procedures Manual (ORNL 1993).
ix
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 195 EAST 1ST NORTH STREET
MONTICELLO, UTAH (MS00234-VL)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the U.S. government through the
Defense Plant Corporation to provide vanadium during World War TJ. Various govern-
ment agencies operated the mill until 1947. In 1948 the Atomic Energy Commission
(AEC) obtained the mill and operated it under contract through 1959 to provide both
uranium and vanadium. Mill operations were terminated on January 1, 1960. In 1961 the
mill tailings piles were leveled and graded, covered with rock and soil, and seeded with
native grasses. During 1974 and 1975, the ore stockpiles were removed from the site, and
the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city
of Monticello, in San Juan County, Utah. The site is bordered on the south and southeast
by land held by the U.S. Bureau of Land Management. Other boundaries are the city of
Monticello and private property.
During the AEC era, the mill processed approximately one million tons of uranium
ore. Vanadium and uranium were the only substances extracted in the milling process.
Other constituents of the ore remained in the tailings and were not separated prior to
disposal. During the years of active mill operation, the mill tailings were normally moist,
so erosion was minimal. However, throughout the mill's operating period, area residents
used these tailings as fill material and as aggregate in mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy
(DOE) initiated the Surplus Facilities Management Program (SFMP) in 1978 to ensure
the safe caretaking and decommissioning of government facilities that had been retired
from service but still had radioactive contamination. In 1980 the mill site at Monticello
was accepted into the SFMP, and the Monticello Remedial Action Project (MRAP) was
established to restore the government-owned mill site to safe levels of radioactivity, to
dispose of or contain the tailings in an environmentally safe manner, and to perform re-
medial actions on off-site (vicinity) properties that had been contaminated by radioactive
material resulting from mill operations. The Monticello mill site and the tailings remain
in the custody of the DOE Grand Junction, Colorado, Projects Office. In 1983 remedial
actions for vicinity properties were separated from MRAP with establishment of the
Monticello Vicinity Properties (MVP) Project (U.S. DOE 1990b).
•The verification of remedial action was performed by members of the Environmental Assessment Group in the
Environmental Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE
contract DE-AC05-96OR22464 with Lockheed Martin Energy Research Corporation.
2
During 1995, RUST Geotech Inc. (Geotech), the remedial action contractor (RAC)
designated by DOE, performed remedial action on the vicinity property that is the subject
of this report, a vacant lot located at 195 East 1st North Street, Monticello, Utah. The
remedial action plan required excavation of all exterior contamination. When the excava-
tion was completed, the property was resurveyed, including soil sampling, to ensure the
removal of all contamination, backfilled with uncontaminated material, and restored to a
condition comparable to that which existed prior to remedial action (Geotech 1996).
The DOE adopted a policy to assign an independent contractor to verify the data
supporting the adequacy of remedial action and to confirm the site's compliance with DOE
guidelines. The Environmental Technology Section (ETS) of Oak Ridge National Labora-
tory (ORNL) has been assigned the responsibility of this task at the 195 East 1st North
Street site. This report describes the methods and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available doc-
umentation adequately and accurately describes the post-remedial-action radiological
conditions of the entire property that is to be certified and (2) that the remedial action
reduced contamination to below applicable DOE guidelines (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1996) in-
dicates the property was remediated as evaluated by DOE on the basis of Environmental
Protection Agency standards and the DOE guidelines (DOE 1990a). Excess residual
radioactive materials were present, thus it was appropriate to designate this property for
remedial action.
This property was assessed as part of Block 33, therefore, the quantity of material
assessed is not available. During the actual removal process, a total of 50 yd3 of contami-
nated earth and uranium mill tailings, 8 to 10 inches deep, was removed from a 187 m2
area.
The ore cart located on the boundary between MS00234 and MS00217 was removed
during remedial action and not replaced.
A post-excavation survey was performed by Geotech prior to backfilling the excavat-
ed areas. This survey consisted of gamma scans with a scintillometer and soil sampling.
Samples representative of the bottom 15-cm (6-in.) soil layers of three excavated verifica-
tion areas were collected and blended to form representative composite soil samples for
each verification area.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation
levels have not been subtracted. Similarly, background concentrations have not been
subtracted from radionuclide concentrations in soil samples. Applicable DOE guidelines
for protection against radiation are given in Table 1.
Gamma Measurements
Exterior surface gamma measurements taken from the excavated areas prior to
backfilling ranged from 14 to 20 uR/h.
Soil Sample Analysis
Prior to backfilling, Geotech collected soil samples representative of the excavated
areas from the bottom 15-cm (6-in.) soil layers. These samples were blended to form a
composite soil sample representative of an average over the three exterior verification
areas. Geotech's analysis of these samples showed ^Ra concentrations to range from
1.9 to 4.3 pCi/g in the composite sample. ORNL ETS obtained these samples and per-
formed a confirmatory analysis which showed ^Ra concentrations from 2.4 to 4.2 pCi/g.
These values are below the EPA standard value of 15 pCi/g for soil layers > 15 cm below
the surface. Gamma ranges and/or soil sample results demonstrate compliance to the
DOE Hot Spot Guidelines for areas <25 m2 (Table 1).
As a result of a meeting between the RAC and IVC on May 26, 1994, anomalous
readings, defined as > 30% above the average of the excavation, will be investigated to
show compliance to the DOE hot spot guideline. The RAC remediated this property after
this procedure change. The IVC observed that 20 uR/h exceeds 30% of the excavation
average of 18 uR/h. The IVC will allow a correlation developed by the RAC to estimate
226Ra pCi/g concentrations based on gamma exposure rates. The anomalous reading of 20
pR/h on this property using the RAC's correlation yields a 226Ra concentration of 4 pCi/g.
This value is well below the minimum concentration of 30 pCi/g needed, when assuming
the maximum area under the hot spot guideline of 25 m2, for subsurface samples. Results
of Geotech and ORNL soil sample analyses are given in Table 2.
CONCLUSION
Results of Geotech soil sample analysis and confirmatory split soil sample analysis
by ORNL show that radionuclide concentrations are within applicable DOE guidelines.
Based upon the results of the post-remedial-action data, which are confirmed by the
verification assessment data, these radiological measurements fall below the limits
prescribed by DOE guidelines. All deficiencies noted in the initial review have been
identified by the RAC as discussed in a meeting between Geotech and ORNL on April 15,
1996, and in the revised completion report. It is concluded that the site successfully meets
the DOE remedial action objectives.
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Radionuclide
concentrations in soil
for Hot Spot areas
Exposure to 222Rn
progeny
Maximum permissible con-
centration of 226Ra in soil
above background levels,
averaged over a 100-m2 area
Maximum Permissible con
centration of Ra226 in soil
above background level, for
areas less than 25 m2
Average annual radon proge-
ny concentration (including
background)
5 pCi/g averaged over the
first 15 cm of soil below the
surface; 15 pCi/g when ave-
raged over 15-cm-thick soil
layers more than 15 cm
below the surface
Ra226 concentrations, in any
surface or subsurface area
less than 25 m2, is below the
guideline by a factor of
(100/A)'/2, where A is the
area of the elevated region
0.03 WL
(DOE 1990a)
5
Table 2. Results of ORNL analysis of Geotech soU samples
from 195 East 1st North Street, MonticeUo Utah (MS00234-VL)
^Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No.' Nof (cm}
XI NCH058 >15 2.4 1.9
X2 NCH059 >15 3.7 3.0
X3 NCH060 >15 4.2 4.3
" An X-type sample is a split of the sample taken by the remedial action contractor.
b Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated areas
were taken by Geotech, and these samples were blended to form a composite soil
sample, which represents an average over one of the verification areas.
REFERENCES
Geotech 1996. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00234-VL, Address: 195 East 1st North Street, Monticello,
Utah 84535, Geotech, Grand Junction, Colorado, February 1996.
ORNL, 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
U.S. DOE 1990a. Verification and Certification Protocolfor the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination
and Decommissioning Program, Revision 3, November 1990. U.S. Department of
Energy, Washington, D.C.
U. S. DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision
and Record of Decision Summary. U.S. Department of Energy, Grand Junction Projects
Office, Grand Junction, Colorado.
DOE ID No.: MS-00250-RS
Property Address: 349 East Center Street
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Gfiotech of Energy (DQE)
Ra-226 is ^ 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [X]
Ra-226 is ^ 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2.
In-situ [ ] Lab [X]
Interior gamma is < 20 //R/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is < 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21.
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
[yf] [ ] I ]
p] [ ] [ ]
M I ] I ]
[ ] [ ] [X] [ ] [ ] [VI
(Missing windows)
[ ] [X] [ ]
[X] [ ] [ ]
[ ] [Y] [ ]
[VI [ ] [ ]
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
milium liiiiiiin SFCERTIFED SFMS-09031
DOE ID No.: MS-00250-RS
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Wanda S. Busby Date
Manager, Monticello Programs
Rust Geotech
DOE EVALUATION
[V] Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Certification utficiai
U.S. Department of Energy
Date
1
PROPERTY COMPLETION REPORT
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
DOE ID NO.: MS-00250-RS
ADDRESS: 349 EAST CENTER STREET
MONTICELLO, UTAH 84535
FEBRUARY 1996
Prepared for
U.S. Department of Energy
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
Wa'atfa S. BxistSy
Manager, Monticello Programs
FOR
FOR
by
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
- r r
TABLE OF CONTENTS
Section Ease
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.1.3 Radon Decay-Product Concentration (RDC) Measurement .... 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
i
DOE ID No.: MS-00250-RS
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE.
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Remedial Action Contractor. DOE reviewed these
evaluation results and determined that the property contained mill tailings
(residual radioactive material) exceeding EPA standards and DOE hot spot
criteria. The Remedial Action Contractor was notified of the inclusion of
this property into the MVP Project and was authorized by DOE to conduct
remedial action as required to bring the property into conformance with
EPA standards and DOE hot spot criteria.
1
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
Property Address:
Property Owners:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
DOE ID No.: MS-00250-RS
MS-00250-RS
Location No. M-230; beginning 14.8 feet
north and 73.9 feet east of the SW corner
of Section 30, T33S., R24E., Salt Lake
Base Meridian; east 76 feet, north
210.5 feet, west 76 feet, south 210.5 feet
to beginning, City of Monticello, County of
San Juan, State of Utah
349 East Center Street
Monticello, Utah 84535

Residential Simple (RS)
Not applicable: inclusion requested by the
Remedial Action Contractor
July 1, 1992
Rust Geotech
March 4, 1993
Diamond Back Services, Inc.
9861 Titan Park Circle
Littleton, Colorado
July 7, 1994
September 7, 1994
Interior: 0 cubic yards
Exterior: 86 cubic yards
372 square meters (m2)
February 1996
2
DOE ID No.: MS-00250-RS
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of exterior residual radioactive
material (Appendix Figure 2.1). Once excavation was complete, the
affected areas were resurveyed for possible remaining residual radioactive
material and, upon attaining satisfactory results, were backfilled with
uncontaminated material. The property was restored to a physical
condition comparable to that which existed prior to remedial action
activities.
2.2 Previously Unidentified Contamination
The radiological assessment identified contamination, ranging from 6 to
18 inches deep, within the property. The quantity of contamination for
this property was not specified because it was assessed as part of Block
MS-09031-BK. The remedial action process included the removal of
approximately 86 cubic yards of residual radioactive material, ranging
from 6 to 36 inches deep^
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
3.0 VERIFICATION SUMMARY
DOE ID No.: MS-00250-RS
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by the Remedial Action
Contractor during August and December 1991, as described in the
final REA dated March 1993. Appendix Figure 2.1 shows the
extent of assessed contamination and identifies the areas
recommended to undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the excavation were
collected. These samples were blended to form composite
samples representing the verification areas (Appendix Figure 2.1).
Additionally, a soil sample was collected in an unremediated area
where gamma exposure-rate measurements exceeded
17 microroentgens per hour {pR/h), which is 30 percent greater
than background (13//R/h).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 12 to 29 jjR/h, as indicated on
Appendix Figure 2.1. The results of analyses for radium-226 in six
composite soil samples ranged from 1.7 to 3.9 picocuries per
gram (pCi/g), as indicated in Appendix Table 3.1. The composite
sample representing Area V-6 included soil samples collected from
MS-00251-CS (Area V-1). The soil sample for radium-226 in the
unremediated area with elevated exposure rates was 4.1 pCi/g
(Appendix Table 3.2).
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
RDC measurements were not taken in the house due to excessive
ventilation caused by missing windows.
4
DOE ID No.: MS-00250-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at 349 East Center Street, in
Monticello, Utah, is recommended for certification as required by DOE
guidelines, and the appropriate records should be documented.
Certification Data Summary
Applicability
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Standards
Shall not exceed 20 //R/h
above background.*
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Survey Results
Range for the ground
floor was 13 to 19 //R/h.
Not taken due to
excessive ventilation.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
Soil sample result was
4.1 pCi/g.**
Soil sample results
ranged from 1.7 to
3.9pCi/g.*»
*The background exposure rate is approximately 13 //R/h.
The background radium-226 concentration is approximately 2.0 pCi/g.
**The hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-00250-RS
4.0 APPENDIX
Appendix Table:
Table 3.1 Post-Excavation Sample/Measurement Results
Table 3.2 Radium Measurement Results for an Unremediated Area with
Elevated Gamma Exposure Rates
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
JEK: 11-06-95
MS-00250.RS WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00250-RS
Address: 349 East Center Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (//R/h) Ticket No. Method" (pCi/g)
V-1 14-16 NCE 982 OCS 2.2
V-2 14-18 NCE 983 OCS 3.8
V-3 15-18 NCE 984 OCS 3.0
V-4 15-18 NCE 985 OCS 3.9
V-5 15-18 NCE 986 OCS 1.8
V-6 14-18 NCE 987 OCS 1.7
See Appendix Figure 2.1 for the verification areas.
aOCS = Opposed Crystal System
7
Table 3.2
Radium Measurement Results for an Unremediated Area
with Elevated Gamma Exposure Rates
DOE ID No.: MS-00250-RS
Address: 349 East Center Street, Monticello, Utah
Assessed Meas. Depth Radium-226
Area Method" (inches) (pCi/g)
H OCS 00-06 4.1
"OCS = Opposed Crystal System
8
42
40
38
36
34
32
30
28
26
24
22
20
18
16
14
12
10
12 14 16 18 20 22 24 26 28 30 32 34 36 38 40 42 44 46 48 50
r 12-16
12-16
CD
29*iR/h
®8> !
LiD
V-6
Si
14-18
ONE STORY
FRAME HOUSE
13-19 —
V-5
15-18
V-5 12-16
J 15-18
0
r?.v?i
LY.VJ
12-15
12
v-i
16-17
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN jtR/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE-RATE RANGE
SCALE IN FEET
20 10 0 20 40
M:\FAS\03J\00OJ\RM0O25OV 11/J7/9J 12:49pm 150710
12 14 16 18
EAST CENTER STREET (U.S. HIGHWAY 666)
NORTH
20
THIS ORAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT. UTILITY LOCATION PLAT, OR OTHER IMPROVEMENT SURVEY
PLAT ANO IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE. BUILDING. OR OTHER FUTURE IMPROVEMENT LINES.
22 24 26 28 30
J L
32 34
J l_
36 38
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
tciiMKC-no. or oecuMHri
MM-MIMMCC-MMJ-m /**.
U.S. DEPARTMENT OF ENERGY
CMHO JWCTIOII WlOJCcn Of MCI. COLOMBO
•rr
i. UNA.
349 EAST CENTER STREET
MONTICELLO. UTAH
I mi \ mam ivi
Rust tt*otoch MS-0O250-RS
•» •"• 3-C00250-V1 „ 1 .
40 42 44 46 48 5i
OAK RIDGE NATIONAL LABORATORY PHONE: (970) 24M200
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION FAX: (970)24M220
FOR THE US. DEPARTMENT OF ENERGY
POST OFFICE BOX 2587
GRAND JUNCTION. COLORADO 81502 HAY 3 I 199S
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81S02
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by the
U.S. Department of Energy for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program (FUSRAP) and Remote Surplus Facilities Management Program
Sites (SFMP) [Revision 2, March 1987]. This evaluation is based on an independent
verification review of the Remedial Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment of
the 226Ra concentration in the soil and indoor gamma exposure rates at this property.
Therefore, this property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
Location Number: MS00250-RS
Location Address: 349 East Center Street
Monticello, Utah 84535
Property Owner:

Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
349 EAST CENTER STREET
MONTICELLO, UTAH (MS00250-RS)
A. R. Jones
May 1996
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 4
REFERENCES 7
iii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 5
2. Results of ORNL analysis of Geotech soil samples from 349 East Center Street,
Monticello, Utah (MS00250-RS) 6
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site
Decommissioning Projects, U.S. Department of Energy. The author wishes to
acknowledge M. K. Jensen for analysis of soil samples and technical review and J. R.
Sauvage for technical review.
vii
ABSTRACT
In 1980 the site of a vanadium and uranium mill at Monticello, Utah, was accepted
into the U.S. Department of Energy's (DOE's) Surplus Facilities Management Program,
with the objectives of restoring the government-owned mill site to safe levels of radio-
activity, disposing of or containing the tailings in an environmentally safe manner, and
performing remedial actions on off-site (vicinity) properties that had been contaminated
by radioactive material resulting from mill operations. During 1994, RUST Geotech, the
remedial action contractor designated by DOE, performed remedial action on the vicinity
property at 349 East Center Street, Monticello, Utah. The Environmental Technology
Section (ETS) of Oak Ridge National Laboratory was assigned the responsibility of
verifying the data supporting the adequacy of remedial action and confirming the site's
compliance with DOE guidelines. The ETS found that the site successfully meets the
DOE remedial action objectives. All deficiencies noted in the initial review have been
resolved in the revised property completion report. Procedures used by the ETS are
described in the Environmental Technology Section Procedures Manual (ORNL 1993).
ix
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 349 EAST CENTER STREET
MONTICELLO, UTAH (MS00250-RS)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the U.S. government through the
Defense Plant Corporation to provide vanadium during World War II. Various govern-
ment agencies operated the mill until 1947. In 1948 the Atomic Energy Commission
(AEC) obtained the mill and operated it under contract through 1959 to provide both
uranium and vanadium. Mill operations were terminated on January 1, 1960. In 1961 the
mill tailings piles were leveled and graded, covered with rock and soil, and seeded with
native grasses. During 1974 and 1975, the ore stockpiles were removed from the site, and
the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city
of Monticello, in San Juan County, Utah. The site is bordered on the south and southeast
by land held by the U.S. Bureau of Land Management. Other boundaries are the city of
Monticello and private property.
During the AEC era, the mill processed approximately one million tons of uranium
ore. Vanadium and uranium were the only substances extracted in the milling process.
Other constituents of the ore remained in the tailings and were not separated prior to dis-
posal. During the years of active mill operation, the mill tailings were normally moist, so
erosion was minimal. However, throughout the mill's operating period, area residents
used these tailings as fill material and as aggregate in mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy
(DOE) initiated the Surplus Facilities Management Program (SFMP) in 1978 to ensure
the safe caretaking and decommissioning of government facilities that had been retired
from service but still had radioactive contamination. In 1980 the mill site at Monticello
was accepted into the SFMP, and the Monticello Remedial Action Project (MRAP) was
established to restore the government-owned mill site to safe levels of radioactivity, to
dispose of or contain the tailings in an environmentally safe manner, and to perform
remedial actions on off-site (vicinity) properties that had been contaminated by
radioactive material resulting from mill operations. The Monticello mill site and the
tailings remain in the custody of the DOE Grand Junction, Colorado, Projects Office. In
1983 remedial actions for vicinity properties were separated from MRAP with
establishment ofthe Monticello Vicinity Properties (MVP) Project (U.S. DOE 1990b).
•The verification of remedial action was performed by members of the Environmental Assessment Group in the
Environmental Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE
contract DE-AC05-96OR22464 with Lockheed Martin Energy Research Corporation.
2
During 1994, RUST Geotech Inc. (Geotech), the remedial action contractor (RAC)
designated by DOE, performed remedial action on the vicinity property that is the subject
of this report, an abandoned house located at 349 East Center Street, Monticello, Utah.
The remedial action plan required excavation of all exterior contamination. When the
excavation was completed, the property was resurveyed, including soil sampling, to
ensure the removal of all contamination* backfilled with uncontaminated material, and
restored to a condition comparable to that which existed prior to remedial action (Geotech
1996).
The DOE adopted a policy to assign an independent contractor to verify the data
supporting the adequacy of remedial action and to confirm the site's compliance with
DOE guidelines. The Environmental Technology Section (ETS) of Oak Ridge National
Laboratory (ORNL) has been assigned the responsibility of this task at the 349 East
Center Street site. This report describes the methods and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available docu-
mentation adequately and accurately describes the post-remedial-action radiological
conditions of the entire property that is to be certified and (2) that the remedial action
reduced contamination to below applicable DOE guidelines (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1996) in-
dicates the property was remediated as evaluated by DOE on the basis of Environmental
Protection Agency standards and the DOE guidelines (DOE 1990a). Excess residual
radioactive materials were present, thus it was appropriate to designate this property for
remedial action.
This property was assessed as part of Block 31, therefore, the quantity of material
assessed is not available. During the actual removal process, a total of 86 yd3 of contami-
nated earth and uranium mill tailings, 6 to 36 inches deep, was removed from a 372 m2
area.
A post-excavation survey was performed by Geotech prior to backfilling the exca-
vated areas. This survey consisted of gamma scans with a scintillometer of the ground
level ofthe structure, a surface scan of the exterior, and soil sampling. Samples repre-
sentative ofthe bottom 15-cm (6-in.) soil layers of six excavated verification areas were
collected and blended to form representative composite soil samples for each verification
area.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation
levels have not been subtracted. Similarly, background concentrations have not been sub-
tracted from radionuclide concentrations in soil samples. Applicable DOE guidelines for
protection against radiation are given in Table 1.
Gamma Measurements
Gamma exposure rate measurements taken by Geotech at the ground-level of the
residence ranged from 13 to 19 uR/h. Exterior surface gamma measurements taken from
the excavated areas prior to backfilling ranged from 14 to 18 pR/h.
Soil Sample Analysis
Prior to backfilling, Geotech collected soil samples representative of the excavated
areas from the bottom 15-cm (6-in.) soil layers. These samples were blended to form a
composite soil sample representative of an average over six exterior verification areas
(the composite sample for Area V-6 contained soil samples collected from MS00251-CS
Area VI). Geotech's analysis of these samples showed 226Ra concentrations ranging from
1.7 to 3.9 pCi/g in the composite sample. ORNL ETS obtained a percentage of these soil
samples and performed a confirmatory analysis which showed 226Ra concentrations
ranging from 3.0 to 4.1 pCi/g.
This property was revisited as contaminated clothesline poles were not mentioned as
part of the remediation. The poles had been removed from the property although it is
unclear when this removal occurred (the structure had also been removed from the
property since the remediation). A gamma scan revealed elevated readings of 29 pR/h at
the west clothesline pole (Region H), and background readings at the east clothesline pole
(Region I). Soil samples taken at each location had 226Ra concentrations of 4.1 and 3.5
pCi/g, respectively.
All of the above values are below the EPA standard value of 15 pCi/g for soil layers
>15 cm below the surface. Gamma ranges and/or soil sample results demonstrate compli-
ance to the DOE Hot Spot Guidelines for areas <25 m2 (Table 1). Results of Geotech and
ORNL soil sample analyses are give in Table 2.
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were not
taken, the structure was removed after remedial action was performed.
4
CONCLUSION
Results of Geotech soil sample analysis and confirmatory split soil sample analysis
by ORNL show that radionuclide concentrations are within applicable DOE guidelines.
Based on the results of the post-remedial-action data, which are confirmed by the veri-
fication assessment data, these radiological measurements fall below the limits prescribed
by DOE guidelines. All deficiencies noted in the initial review have been identified by
the RAC and corrected in the revised completion report as discussed in a meeting be-
tween Geotech and ORNL on April 15,1996. It is concluded that the site successfully
meets the DOE remedial action objectives.
5
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of 226Ra in soil
above background levels,
averaged over a 100-m2 area
5 pCi/g averaged over the
first 15 cm of soil below the
surface; 15 pCi/g when ave-
raged over 15-cm-thick soil
layers more than 15 cm
below the surface
Radionuclide
concentrations in soil
for Hot Spot areas
Exposure to 222Rn
progeny
Maximum Permissible
concentration of Ra226 in soil
above background level, for
areas less than 25 m2
Average annual radon proge-
ny concentration (including
background)
Ra226 concentrations, in any
surface or subsurface area
less than 25 m2, is below the
guideline by a factor of
(100/A)'/J, where A is the
area of the elevated region
0.03 WL
(DOE 1990a)
6
Table 2. Results of ORNL analysis of Geotech soil samples from
349 East Center Street, Monticello Utah (MS00250-RS)
226Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No." No* (cm)
X3 NCE 984 >15 3.3 3.0
X5 NCE 986 >15 4.1 1.8
X6 NCE 987 >15 3.0 1.7
a An X-type sample is a split ofthe sample taken by the remedial action contractor.
* Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated
areas were taken by Geotech, and these samples were blended to form a composite soil
sample, which represents an average over one of the verification areas.
7
REFERENCES
Geotech 1996. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00250-RS, Address: 349 East Center Street, Monticello,
Utah 84535, Geotech, Grand Junction, Colorado, February 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
U.S. DOE 1990a. Verification and Certification Protocol for the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination
and Decommissioning Program, Revision 3, November 1990. U.S. Department of
Energy, Washington, D.C.
U.S. DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision
and Record of Decision Summary. U.S. Department of Energy, Grand Junction Projects
Office, Grand Junction, Colorado.
T
DOE ID No.: MS-00251-CS
Property Address: 365 East Center Street
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech of Energy (DOE)
Ra-226 is s 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [ ]
Ra-226 is ^ 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2.
In-situ [ ] Lab [X]
Interior gamma is £ 20 //R/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is £ 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21.
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
YES NO NOT TAKEN
lA I ] [ 1
[X] [ ] [ ] [)d [ 1 [ 1
[ ] [ ] [X] [ ] I 1
(Uninhabitable Structure)
[ ] [ 1 [X] [ ] [ ]
(Uninhabitable Structure)
I ] [X] [ ]
I*
[X] [ ] [ ]
I 1 [tf [ ]
[MM [ ]
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
lillliilM P11I1INI
SFCERTIFED
SFMS-09031
DOE ID No.: MS-00251-CS
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the. U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
U21 tend a S^Susby
Manager, Monticello Programs
Rust Geotech
Date
DOE EVALUATION
M Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Certification Official/
U.S. Department of Energy
/3 GJ,
Date
PROPERTY COMPLETION REPORT
DOE ID NO.: MS-00251-CS
ADDRESS: 365 EAST CENTER STREET
MONTICELLO, UTAH 84535
FEBRUARY 1996
Prepared for
U.S. Department of Energy
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
by
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.1.3 Radon Decay-Product Concentration (RDC) Measurement .... 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
i
DOE ID No.: MS-00251-CS
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Remedial Action Contractor. DOE reviewed these
evaluation results and determined that the property contained mill tailings
(residual radioactive material) exceeding EPA standards. The Remedial
Action Contractor was notified of the inclusion of this property into the
MVP Project and was authorized by DOE to conduct remedial action as
required to bring the property into conformance with EPA standards and
DOE hot spot criteria.
1
DOE ID No.: MS-00251-CS
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
Property Address:
Property Owners:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
MS-00251-CS
Location No. M-234; beginning 14.8 feet
north and 149.9 feet east of the SW corner
of Section 30, T33S., R24E., Salt Lake
Base Meridian; east 100 feet, north
210.5 feet, west 100 feet, south
210.5 feet to beginning, City of Monticello,
County of San Juan, State of Utah
365 East Center Street
Monticello, Utah 84535

Commercial Structure (CS)
Not applicable: inclusion requested by the
Remedial Action Contractor
July 1, 1992
Rust Geotech
March 4, 1993
Diamond Back Services, Inc.
9861 Titan Park Circle
Littleton, Colorado
July 7, 1994
September 7, 1994
Interior: 0 cubic yards
Exterior: 40 cubic yards
95 square meters (m2)
February 1996
2
DOE ID No.: MS-00251-CS
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of exterior residual radioactive
material (Appendix Figure 2.1). Once excavation was complete, the
affected areas were resurveyed for possible remaining residual radioactive
material and, upon attaining satisfactory results, were backfilled with
uncontaminated material. The property was restored to a physical
condition comparable to that which existed prior to remedial action
activities.
2.2 Previously Unidentified Contamination
The radiological assessment identified contamination, 6 to 18 inches deep,
within the property. The quantity of contamination for this property was
not specified because it was assessed as part of Block MS-09031-BK.
The remedial action process included the removal of approximately
40 cubic yards of residual radioactive material, ranging from 6 to
36 inches deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID No.: MS-00251-CS
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by the Remedial Action
Contractor during August and December 1991, as described in the
final REA dated March 1993. Appendix Figure 2.1 shows the
extent of assessed contamination and identifies the areas
recommended to undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the excavation were
collected. These samples were blended to form a composite
sample representing the verification area (Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 13 to 18 microroentgens per
hour O/R/h), as indicated on Appendix Figure 2.1. The result of
analysis for radium-226 in one composite soil sample was
1.7 picocuries per gram (pCi/g), as indicated in Appendix
Table 3.1. The composite sample representing Area V-1 included
soil samples collected from MS-00250-RS (Area V-6).
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
RDC measurements were not taken in the uninhabitable structure;
this structure was verified according to exterior standards.
4
DOE ID No.: MS-00251-CS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at 365 East Center Street, in
Monticello, Utah, is recommended for certification as required by DOE
guidelines, and the appropriate records should be documented.
Certification Data Summary
Applicability
Hahitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Standards
Shall not exceed 20 //R/h
above background.
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Survey Results
Not applicable:
uninhabitable building.
Not applicable:
uninhabitable building.
land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background* in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background* in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
< 5 pCi/g above
background.
Soil sample result was
1.7 pCi/g.f
*The background radium-226 concentration is approximately 2.0 pCi/g.
The hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-00251-CS
<**
4.0 APPENDIX
Appendix Table:
Table 3.1 Post-Excavation Sample/Measurement Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
JEK: 11-06-95
MS-00251.CS WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00251-CS
Address: 365 East Center Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (//R/h) Ticket No. Method* (pCi/g)
V-1 14-18 NCE 987 OCS 1.7
See Appendix Figure 2.1 for the verification area.
"OCS = Opposed Crystal System
7
42
40
38
36
34
32
30
28
26
24
22
20
18
16
14
12
10
12 1 6 18 20 22 24 26 28 30 32 34 36 38 40 42 46 5
r 14-16
V-1
14-18
0
36
KUN IN HABITABLE
x ONE STORY
BLOCK BUILDING
13-14
14-16
L I
®
©
12-15
12
V-1
16-17
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN uR/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST -REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE-RATE RANGE
1—- X
SCALE IN FEET
20 10 0 20 40
\FAS\03J\OOOJ\RUOC-231V n/c-8/95 0»:46gm T5078O
12 1 4 16 18
EAST CENTER STREET (U.S. HIGHWAY 666)
NORTH
20 22 24 26
J L_
28
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT. UTILITY LOCATION PLAT, OR OTHER IMPROVEMENT SURVEY
PLAT AND IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE. BUILDING, OR OTHER FUTURE IMPROVEMENT LINES.
30 32 34 36 38
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
niWKt'W. of OCCUMHTI
40
U.S. DEPARTMENT OF ENERGY
CRANO JUNCTION PROJECTS OFFICE. COLORADO
365 EAST CENTER STREET
MONTICELLO, UTAH
I HI j A* »!<>»(. Oil
Rust Q«ot«ch •»••» MS-O0251-CS
42 44 46
3-C00251-VI ,
48 5C
OAK RIDGE NATIONAL LABORATORY
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
FOR THE U.S. DEPARTMENT OF ENERGY
POST OFFICE BOX 2987
GRAND JUNCTION. COLORADO 61502
PHONE: <B70)24M200
FAX: (970) 24M220
31 m
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by the
U.S. Department of Energy for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program (FUSRAP) and Remote Surplus Facilities Management Program
Sites (SFMP) [Revision 2, March 1987]. This evaluation is based on an independent
verification review of the Remedial Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment of
the 226Ra concentration in the soil.
Therefore, this property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
MS00251-CS
365 East Center Street
Monticello, Utah 84535

Location Number:
Location Address:
Property Owner:
Owner Address:
Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
365 EAST CENTER STREET
MONTICELLO, UTAH (MS00251-CS)
M. K. Jensen
May 1996
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 3
REFERENCES 6
iii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 4
2. Results of ORNL analysis of Geotech soil samples from 365 East Center Street,
Monticello, Utah (MS00251-CS) 5
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site
Decommissioning Projects, U.S. Department of Energy. The author wishes to
acknowledge M. J. Wilson-Nichols and A. R. Jones for technical reviews.
vii
ABSTRACT
In 1980 the site of a vanadium and uranium mill at Monticello, Utah, was accepted
into the U.S. Department of Energy's (DOE's) Surplus Facilities Management Program,
with the objectives of restoring the government-owned mill site to safe levels of radio-
activity, disposing of or containing the tailings in an environmentally safe manner, and
performing remedial actions on off-site (vicinity) properties that had been contaminated
by radioactive material resulting from mill operations. During 1994, RUST Geotech, the
remedial action contractor designated by DOE, performed remedial action on the vicinity
property at 365 East Center Street, Monticello, Utah. The Environmental Technology
Section (ETS) of Oak Ridge National Laboratory was assigned the responsibility of
verifying the data supporting the adequacy of remedial action and confirming the site's
compliance with DOE guidelines. The ETS found that the site successfully meets the
DOE remedial action objectives. Procedures used by the ETS are described in the
Environmental Technology Section Procedures Manual (ORNL 1993).
ix
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 365 EAST CENTER STREET
MONTICELLO, UTAH (MS00251-CS)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the U.S. government through the
Defense Plant Corporation to provide vanadium during World War U. Various govern-
ment agencies operated the mill until 1947. In 1948 the Atomic Energy Commission
(AEC) obtained the mill and operated it under contract through 1959 to provide both
uranium and vanadium. Mill operations were terminated on January 1,1960. In 1961 the
mill tailings piles were leveled and graded, covered with rock and soil, and seeded with
native grasses. During 1974 and 1975, the ore stockpiles were removed from the site, and
the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city
of Monticello, in San Juan County, Utah. The site is bordered on the south and southeast
by land held by the U.S. Bureau of Land Management. Other boundaries are the city of
Monticello and private property.
During the AEC era, the mill processed approximately one million tons of uranium
ore. Vanadium and uranium were the only substances extracted in the milling process.
Other constituents of the ore remained in the tailings and were not separated prior to
disposal. During the years of active mill operation, the mill tailings were normally moist,
so erosion was minimal. However, throughout the mill's operating period, area residents
used these tailings as fill material and as aggregate in mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy
(DOE) initiated the Surplus Facilities Management Program (SFMP) in 1978 to ensure the
safe caretaking and decommissioning of government facilities that had been retired from
service but still had radioactive contamination. In 1980 the mill site at Monticello was
accepted into the SFMP, and the Monticello Remedial Action Project (MRAP) was esta-
blished to restore the government-owned mill site to safe levels of radioactivity, to dispose
of or contain the tailings in an environmentally safe manner, and to perform remedial ac-
tions on off-site (vicinity) properties that had been contaniinated by radioactive material
resulting from mill operations. The Monticello mill site and the tailings remain in the cus-
tody ofthe DOE Grand Junction, Colorado, Projects Office. In 1983 remedial actions for
vicinity properties were separated from MRAP with establishment of the Monticello
Vicinity Properties (MVP) Project (U.S. DOE 1990b).
*The verification of remedial action was performed by members of the Environmental Assessment Group in the
Environmental Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE
contract DE-AC05-96OR22464 with Lockheed Martin Energy Research Corporation.
2
During 1994, RUST Geotech Inc. (Geotech), the remedial action contractor (RAC)
designated by DOE, performed remedial action on the vicinity property that is the subject
of this report, a car wash located at 365 East Center Street, Monticello, Utah. The reme-
dial action plan required excavation of all exterior contamination. When the excavation
was completed, the property was resurveyed, including soil sampling, to ensure the re-
moval of all contamination, backfilled with uncontaminated material, and restored to a
condition comparable to that which existed prior to remedial action (Geotech 1996).
The DOE adopted a policy to assign an independent contractor to verify the data
supporting the adequacy of remedial action and to confirm the site's compliance with DOE
guidelines. The Environmental Technology Section (ETS) of Oak Ridge National Labora-
tory (ORNL) has been assigned the responsibility of this task at the 365 East Center Street
site. This report describes the methods and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available doc-
umentation adequately and accurately describes the post-remedial-action radiological
conditions of the entire property that is to be certified and (2) that the remedial action
reduced contamination to below applicable DOE guidelines (DOE 1990a).
Document Reviews
Review ofthe property completion report prepared by Geotech (Geotech 1996)
indicates the property was remediated as evaluated by DOE on the basis of Environmental
Protection Agency standards and the DOE guidelines (DOE 1990a). Excess residual
radioactive materials were present, thus it was appropriate to designate this property for
remedial action.
This property was assessed as part of Block 31, therefore, the quantity of material
assessed is not available. During the actual removal process, a total of 40 yd3 of contam-
inated earth and uranium mill tailings, 6 to 36 inches deep, were removed from a 95 m2
area.
A post-excavation survey was performed by Geotech prior to backfilling the exca-
vated areas. This survey consisted of gamma scans with a scintillometer of the ground
level ofthe structure, a surface scan of the exterior, and soil sampling. Samples repre-
sentative ofthe bottom 15-cm (6-in.) soil layers of one excavated verification area were
collected and blended to form a representative composite soil sample.
3
VERIFICATION OF REMEDIAL ACTION
Ail measurements presented in this report are gross readings. Background radiation
levels have not been subtracted. Similarly, background concentrations have not been sub-
tracted from radionuclide concentrations in soil samples. Applicable DOE guidelines for
protection against radiation are given in Table 1.
Gamma Measurements
Gamma exposure rate measurements taken by Geotech at the ground-level of the
building ranged from 13 to 14 uR/h. Exterior surface gamma measurements taken from
the excavated areas prior to backfilling ranged from 14 to 18 uR/h.
Soil Sample Analysis
Prior to backfilling, Geotech collected soil samples representative of the excavated
areas from the bottom 15-cm (6-in.) soil layers. These samples were blended to form a
composite soil sample representative of an average over the exterior verification area.
Geotech's analysis of this sample showed a 226Ra concentration of 1.7 pCi/g. ORNL ETS
obtained this sample and performed a confirmatory analysis which showed a 226Ra concen-
tration of 3.0 pCi/g. These values are below the EPA standard value of 15 pCi/g for soil
layers > 15 cm below the surface. Gamma ranges and/or soil sample results demonstrate
compliance to the DOE Hot Spot Guidelines for areas <25 m2 (Table 1). Results of
Geotech and ORNL soil sample analyses are given in Table 2.
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were not
determined as the structure is a car wash containing no enclosed rooms.
CONCLUSION
Results of Geotech soil sample analysis and confirmatory split soil sample analysis by
ORNL show that radionuclide concentrations are within applicable DOE guidelines.
Based on the results of the post-remedial-action data, which are confirmed by the verifi-
cation assessment data, these radiological measurements fall below the limits prescribed by
DOE guidelines. It is concluded that the site successfully meets the DOE remedial action
objectives.
4
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of ^Ra in soil
above background levels,
averaged over a 100-m2 area
5 pCi/g averaged over the
first 15 cm of soil below the
surface; 15 pCi/g when ave-
raged over 15-cm-thick soil
layers more than 15 cm
below the surface
Radionuclide
concentrations in soil
for Hot Spot areas
Exposure to 222Rn
progeny
Maximum Permissible
concentration of Ra226 in soil
above background level, for
areas less than 25 m2
Average annual radon proge-
ny concentration (including
background)
Ra226 concentrations, in any
surface or subsurface area
less than 25 m2, is below the
guideline by a factor of
(lOO/A)*, where A is the
area of the elevated region
0.03 WL
(DOE 1990a)
5
Table 2. Results of ORNL analysis of Geotech soil samples
from 365 East Center Street, Monticello Utah (MS00251-CS)
226Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No." Nof (cm)
XI NCE 987 >15 3.0 1.7
" An X-type sample is a split of the sample taken by the remedial action contractor.
* Soil samples representative of the bottom 15-cm (6-in.) soil layers ofthe excavated areas
were taken by Geotech, and these samples were blended to form a composite soil
sample, which represents an average over one of the verification areas.
6
REFERENCES
Geotech 1995. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00251-CS, Address: 365 East Center Street, Monticello,
Utah 84535, Geotech, Grand Junction, Colorado, February 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
U.S. DOE 1990a. Verification and Certification Protocol for the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination
and Decommissioning Program, Revision 3, November 1990. U.S. Department of
Energy, Washington, D.C.
U.S. DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision
and Record of Decision Summary. U.S. Department of Energy, Grand Junction Projects
Office, Grand Junction, Colorado.
DOE ID No.: MS-00261-MO
Property Address: 197 East Center Street
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech of Energy (DOE)
Ra-226 is <. 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [ ]
Ra-226 is <. 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2.
In-situ [ ] Lab IX]
Interior gamma is * 20 //R/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is <, 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21.
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
bf] [ ] [ ]
[Ml) I )
[>\ I ] [ 1
[ ] [ 1
[>4 [ ] t 1
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the ranoe
of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
•iiiiiinni iiniiiiiiii
SFCERTIFED SFMS-00261
DOE ID No.: MS-00261-MO
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Wanda S./Busby Date
Manager, Monticello Programs
Rust Geotech
DOE EVALUATION
\X] Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
4
Certification Official Date
U.S. Department of Energy
PROPERTY COMPLETION REPORT
DOE ID NO.: MS-00261-MO
ADDRESS: 197 EAST CENTER STREET
MONTICELLO, UTAH 84535
MARCH 1996
Prepared for
U.S. Department of Energy
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
by
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
Manager, Monticello Programs
•llllllllll Ililllllllll
SFOCPLRPTS SFMS-00261
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.1.3 Radon Decay-Product Concentration (RDC) Measurement .... 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
i
DOE ID No.: MS-00261-MO
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill. .
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Inclusion Survey Contractor. DOE reviewed
these evaluation results and determined that the property contained mill
tailings (residual radioactive material) exceeding DOE hot spot criteria.
The Remedial Action Contractor was notified of the inclusion of this
property into the MVP Project and was authorized by DOE to conduct
remedial action as required to bring the property into conformance with
EPA standards and DOE hot spot criteria.
1
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
Property Address:
Property Owner:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
DOE ID No.: MS-00261-MO
MS-00261-MO
Location No. M-237; beginning 184.6 feet
west of the SE corner of Lot 2, Block G,
Monticello Townsite Survey, north
214.5 feet, west 180.9 feet, south
214.5 feet, east 180.9 feet to the point of
beginning, County of San Juan, State of
Utah
197 East Center Street
Monticello, Utah 84535

Motel (MO)
Oak Ridge National Laboratory
February 2, 1993
Rust Geotech
November 28, 1994
Diamond Back Services, Inc.
9861 Titan Park Circle
Littleton, Colorado
August 22, 1995
September 26, 1995
Interior: 0 cubic yards
Exterior: 5 cubic yards
14 square meters (m2)
March 1996
2
DOE ID No.: MS-00261-MO
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of exterior residual radioactive
material (Appendix Figure 2.1). Interior assessed Area D (concrete stem
wall) was excluded from remedial action based on gamma exposure rates
and pre-remedial radon decay-product concentration measurements that
did not exceed EPA standards, as discussed in the REA. Once excavation
was complete, the affected areas were resurveyed for possible remaining
residual radioactive material and, upon attaining satisfactory results, were
backfilled with uncontaminated material. The property was restored to a
physical condition comparable to that which existed prior to remedial
action activities.
2.2 Previously Unidentified Contamination
The radiological assessment (excluding assessed Area D) identified
6 cubic yards of contamination, ranging from 12 inches deep to 48 inches
high, within the property. The remedial action process included the
removal of approximately 5 cubic yards of residual radioactive material,
ranging from 12 inches deep to 48 inches high.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID No.: MS-00261-MO
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
Radiological surveys were conducted by the Remedial Action
Contractor during July and August 1993, as described in the final
REA dated November 1994. Appendix Figure 2.1 shows the
extent of assessed contamination and identifies the areas
recommended to undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the excavation were
collected. These samples were blended to form a composite
sample representing the verification area (Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 12 to 21 microroentgens per
hour (/yR/h), as indicated on Appendix Figure 2.1. The result of
analysis for radium-226 in one composite soil sample was
4.9 picocuries per gram (pCi/g), as indicated in Appendix
Table 3.1.
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on measurements representing an annual average, the RDC
was 0.0047 working level (WL), as indicated in Appendix
Table 3.2. Appendix Figure 2.1 shows the measurement location
on the ground floor (the lowest habitable level of the structure).
RDC measurements were taken by Oak Ridge National Laboratory
before remediation of the property.
4
DOE ID No.: MS-00261-MO
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at 197 East Center Street, in
Monticello, Utah, is recommended for certification as required by DOE
guidelines, and the appropriate records should be documented.
Certification Data Summary
Applicability
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Standards
Shall not exceed 20 //R/h
above background.*
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Survey Results
Range for the ground
floor was 12 to 21 //R/h.
Annual average was
0.0047 WL.
Laod
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
< 5 pCi/g above
background.**
Soil sample result was
4.9 pCi/g.**
*The background exposure rate is approximately 13 //R/h.
The background radium-226 concentration is approximately 2.0 pCi/g.
**The hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-00261-MO
4.0 APPENDIX
Appendix Tables:
Table 3.1 Post-Excavation Sample/Measurement Results
Table 3.2 Radon Decay-Product Concentration Measurement
Results
Appendix Figure:
Figure 2.1 Interior and Exterior Extent of Contamination -
RADIOLOGICAL AS-BUILT
WKR:02-12-96
MS-00261.MO WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00261-MO
Address: 197 East Center Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (//R/h) Ticket No. Method" (pCi/g)
V-1 14-21 NCL 806 OCS 4.9
See Appendix Figure 2.1 for the verification area.
"OCS = Opposed Crystal System
7
Table 3.2
Radon Decay-Product Concentration Measurement Results
DOE ID No.: MS-00261-MO
Address: 197 East Center Street, Monticello, Utah
Instrument Type: Landauer Radtrak Detector
Detector
Number Start Date End Date
Radon
Concentration
(pCi/L)
Working
Level
3275830
3275841
3275849
07-11-91
07-11-91
07-11-91
07-21-92
07-21-92
07-21-92
1.00
0.90
0.90
0.0050
0.0045
0.0045
Annual Average: 0.0047
See Appendix Figure 2.1 for the measurement location.
8
42
40
38
36
34
32
30
28
26
24
22
20
18
16
14
12
10
12 14
T
16 18
17-21
20 22 24 26
i r
28 30 32 34 36 38
T
40
12.-13
"T
ONE STORY
BRICK BUILDING
12-16
12-13
12
v-1
14-21
V-1
14-21
13-16
Cj[48]
©
<D
LV.VJ
12-15
12
v-i
16-17
12-13
[12]
777
EAST CENTER STREET
42 44 46 48 5C
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN ^R/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE—RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE-RATE RANGE
RADON DECAY-PRODUCT CONCENTRATION
MEASUREMENT LOCATION
HEIGHT IN INCHES OF ASSESSED CONTAMINATED
RETAINING WALLS REMOVED AND REPLACED
ASSESSED AREA D (CONCRETE STEM WALL)
WAS EXCLUDED FROM REMEDIAL ACTION
RADIOLOGICAL AS-BUILT
FIGURE 2.1
INTERIOR AND EXTERIOR EXTENT OF CONTAMINATION
SCALE IN FEET
20 10 0 20 40
M.\FAS\0JJ\000JVM002»1V 03/0e/»o 07:310m 150780
' ' I I I I L_
NORTH
J I
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT, UTILITY LOCATION PLAT, OR OTHER IMPROVEMENT SURVEY
PLAT AND IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE. BUILDING. OR OTHER FUTURE IMPROVEMENT LINES.
J L J L
t-m. or OCCUMMII U.S. DEPARTMENT OF ENERGY
MAMD JUNCTION MOJCCTS «Tt«. CQUHWOO
197 EAST CENTER STREET
MONTICELLO, UTAH
MS-00261-MO
— » 3-C00261-V1 „ 1 „ 1
12 14 16 18 20 22 24 26 28 30 32 34 36 38 40 42 44 46 48 51
OAK RIDGE NATIONAL LABORATORY
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
FOR THE U.S. DEPARTMENT OF ENERGY
PHONE: (970) 248-«200
FAX: (970) 24&-«220
POST OFFICE BOX 2SS7
GRAND JUNCTION, COLORADO 81502
JUL 3 1 1996
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by the
U.S. Department of Energy for Residual Radioactive Material at Formerly Utilized Sites Remedial
Action Program (FUSRAP) and Remote Surplus Facilities Management Program Sites (SFMP)
[Revision 2, March 1987]. This evaluation is based on an independent verification review of the
Remedial Action Contractor's completion report and a field verification.
This recommendation is based upon the Independent Verification Contractor's assessment of the
^Ra concentration in the soiL indoor radon daughter concentration, and indoor gamma exposure
rate at this property.
Therefore, this property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/TVC Project Manager
Environmental Assessment Group
Location Number: MS00261-MO
Location Address: 197 East Center Street
Monticello. Utah 84535
Property Owner:

HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE B INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
197 EAST CENTER STREET
MONTICELLO, UTAH (MS00261-MO)
M. K. Jensen
July 1996
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES v
LIST OF FIGURES v
ACKNOWLEDGMENTS vii
ABSTRACT viii
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
GEOTECH SURVEY RESULTS 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
ORNL SURVEY RESULTS 5
Gamma Measurements 5
Soil Sample Analysis 5
CONCLUSION 5
REFERENCES 9
ii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 4
2. Results of ORNL and Geotech analyses of soil samples from 197 East Center Street,
Monticello, Utah (MS00261-MO) 6
3. Results of ORNL high outdoor gamma soil samples from 197 East Center Street,
Monticello, Utah (MS00261-MO) 6
LIST OF FIGURES
1. Property Map 8
v
ACKNOWLEDGMENTS
Research for this project was sponsored by the U.S. Department of Energy, Office
of Environmental Restoration, Southwestern Area Programs. The author wishes to
acknowledge A. R. Jones and J. R. Sauvage for technical reviews.
vii
ABSTRACT
In 1980 the site of a vanadium and uranium mill at Monticello, Utah, was accepted
into the U.S. Department of Energy's (DOE's) Surplus Facilities Management Program,
with the objectives of restoring the government-owned mill site to safe levels of radioac-
tivity, disposing of or containing the tailings in an environmentally safe manner, and per-
forming remedial actions on off-site (vicinity) properties that had been contaminated by
radioactive material resulting from mill operations. During 1995, RUST Geotech Inc., the
remedial action contractor designated by DOE, performed remedial action on the vicinity
property at 197 East Center Street, Monticello, Utah. The Environmental Technology
Section (ETS) of Oak Ridge National Laboratory was assigned the responsibility of veri-
fying the data supporting the adequacy of remedial action and confirming the site's compli-
ance with DOE guidelines. The ETS found that the site successfully meets the DOE re-
medial action objectives. Procedures used by ETS are described in the Environmental
Technology Section Procedures Manual (ORNL 1993).
viii
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 197 EAST CENTER STREET
MONTICELLO, UTAH (MS00261-MO)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the U.S. government through the
Defense Plant Corporation to provide vanadium during World War II. Various govern-
ment agencies operated the mill until 1947. In 1948 the Atomic Energy Commission
(AEC) obtained the mill and operated it under contract through 1959 to provide both
uranium and vanadium. Mill operations were terminated on January 1,1960. In 1961 the
mill tailings piles were leveled and graded, covered with rock and soil, and seeded with
native grasses. During 1974 and 1975, the ore stockpiles were removed from the site, and
the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city
of Monticello, in San Juan County, Utah. The site is bordered on the south and southeast
by land held by the U.S. Bureau of Land Management. Other boundaries are the city of
Monticello and private property.
During the AEC era, the mill processed approximately one million tons of uranium
ore. Vanadium and uranium were the only substances extracted in the milling process.
Other constituents of the ore remained in the tailings and were not separated prior to dis-
posal. During the years of active mill operation, the mill tailings were normally moist, so
erosion was minimal. However, throughout the mill's operating period, area residents
used these tailings as fill material and as aggregate in mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy
(DOE) initiated the Surplus Facilities Management Program (SFMP) in 1978 to ensure
the safe caretaking and decommissioning of government facilities that had been retired
from service but still had radioactive contamination. In 1980 the mill site at Monticello
was accepted into the SFMP, and the Monticello Remedial Action Project (MRAP) was
established to restore the government-owned mill site to safe levels of radioactivity, to
dispose of or contain the tailings in an environmentally safe manner, and to perform re-
medial actions on off-site (vicinity) properties that had been contaminated by radioactive
material resulting from mill operations. The Monticello mill site and the tailings remain
in the custody of the DOE Grand Junction, Colorado, Projects Office. In 1983 remedial
actions for vicinity properties were separated from MRAP with establishment ofthe
Monticello Vicinity Properties (MVP) Project (U.S. DOE 1990b).
The verification of remedial action was performed by members of the Environmental
Technology Section of the Health Sciences Research Division at Oak Ridge National
Laboratory under DOE contract DE-AC05-96OR22464 with Lockheed Martin Energy
Research Corp.
2
During 1995, RUST Geotech Inc. (Geotech), the remedial action contractor (RAC)
designated by DOE, performed remedial action on the vicinity property that is the subject
of this report, a motel located at 197 East Center Street, Monticello, Utah. The remedial
action plan required excavation of all exterior contamination, backfilling with uncontami-
nated material, and restoration to a condition comparable to that which existed prior to
remedial action (Geotech 1996). When the excavation stage was completed, the property
was resurveyed, including soil sampling, by Geotech and by an independent contractor to
verify the data supporting the adequacy of remedial action and to confirm the site's com-
pliance with DOE guidelines. The Environmental Technology Section (ETS) of Oak
Ridge National Laboratory (ORNL) has been designated the Independent Verification
Contractor for the 197 East Center Street site. This report describes the methods and
results of the verification surveys.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available doc-
umentation adequately and accurately describes the post-remedial-action radiological
conditions of the entire property that is to be certified and (2) that the remedial action
reduced contamination to below applicable DOE guidelines (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1996)
indicates the property was remediated as evaluated by DOE on the basis of Environmental
Protection Agency standards (DOE 1990a) and that excess residual radioactive materials
were present. Thus it was appropriate to designate this property for remedial action
The pre-remedial-action survey performed by Geotech identified 6 yd3 of mill tailings
12 inches deep to 48 inches high. During the actual removal process, a total of 5 yd3 of
contaniinated earth and uranium mill tailings, 12 inches deep to 48 inches high, were
removed from a 14 m2 area.
A post-excavation survey was performed by Geotech prior to backfilling the exca-
vated areas. This survey consisted of gamma scans with a scintillometer of the ground-
level ofthe building, a surface scan of the exterior, and soil sampling. Samples represen-
tative ofthe bottom 15-cm (6-in.) soil layers of the one excavated area were collected and
blended to form a representative composite soil sample. The RAC is unable to locate or
inadvertently disposed of the sample requested for ORNL confirmatory analysis.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation
levels have not been subtracted. Similarly, background concentrations have not been
subtracted from radionuclide concentrations in soil samples. Applicable DOE guidelines
for protection against radiation are given in Table 1.
GEOTECH SURVEY RESULTS
Gamma Measurements
Gamma exposure rate measurements taken by Geotech over the ground-level of the
building ranged from 12 to 21^R/h. Elevated gamma rate measurements were due to a
contaminated concrete stem wall, which was excluded from remedial action based on
radon measurements. Exterior surface gamma measurements taken from the excavated
areas prior to backfilling ranged from 14 to 21 pR/h.
Soil Sample Analysis
Prior to backfilling, Geotech collected soil samples representative of the excavated
areas from the bottom 15-cm (6-in.) soil layers. These samples were blended to form a
composite soil sample representative of an average over the the exterior verification area.
Geotech's analysis of this sample showed a 226Ra concentration of 4.9 pCi/g. ORNL ETS
was unable to obtain the sample for confirmatory analysis. This value is below the EPA
standard value of 15 pCi/g for soil layers >15 cm below the surface (Table 1). Gamma
ranges and/or soil sample results demonstrate compliance to the DOE Hot Spot Guideline
for areas < 25 m2 (Table 1).
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were deter-
mined by the alpha-track method. RDC measurements were taken by ORNL during the
inclusion survey of this property. To monitor radon levels, ORNL placed three Alpha-
track detectors on the ground floor of the building located on this property for a period of
approximately one year (from July 11, 1991 to July 21, 1992). The average annual work-
ing level (WL) of radon progeny concentration, as determined by the Tech./Ops-Landauer
Corporation, was 0.0047, which is well below the 0.03-WL guideline given in Table 1.
The procedures and methods used to obtain the annual average WL are deemed adequate
and the results accurate by the IVC.
4
i Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of ^Ra in soil
above background levels,
averaged over a 100-m2 area
5 pCi/g averaged over the
first 15 cm of soil below the
surface; 15 pCi/g when
averaged over 15-cm-thick
soil layers more than 15 cm
below the surface.
Radionuclide con-
centrations in soil
for Hot Spot areas
Exposure to ^Rn
progeny
Maximum permissible con-
centration of 226Ra in soil
above background level, for
areas less than 25m2.
Average annual radon proge-
ny concentration (including
background).
Ra concentration, in any
surface or subsurface area
less than 25 m2, is below the
guideline of (100/A),/J,
where A is the area of the
elevated region.
0.03 WL
(DOE 1990a)
5
ORNL SURVEY RESULTS
Gamma Measurements
Measurements taken by ORNL over the ground surface in the excavated areas prior
to backfilling ranged from 13 to 22 uR/h (Figure 1).
Soil Sample Analysis
ORNL sampled the excavated areas prior to backfilling, collecting aliquots repre-
sentative of those areas from the bottom 15-cm (6-in.) soil layers. These samples were
blended to form a composite soil sample representative of an average over the exterior
verification area. ORNL's analysis of this composite sample showed a ^Ra concentration
of 4.2 pCi/g. These values are below the DOE guideline value of 15 pCi/g for soil layers
>15 cm below the surface (Table 1). Results of ORNL sample analyses are given in Table
2. In addition, ORNL collected samples from the highest gamma exposure in each of the
three excavation areas. These samples had 226Ra concentrations ranging from 2.1 to 45
pCi/g. Results showing compliance to the DOE Hot Spot guideline are given in Table 3.
CONCLUSION
The results of all Geotech and ORNL soil sample analyses show that radionuclide
concentrations are within applicable DOE guidelines. Based upon the results of the post-
remedial-action data, which are confirmed by the verification assessment data, these radio-
logical measurements fall below the limits prescribed by DOE guidelines. It is concluded
that the site successfully meets the DOE remedial action objectives.
6
Table 2. Results of ORNL and Geotech analyses of soil samples
from 197 East Center Street, Monticello, Utah (MS00261-MO)
^Ra concentration (pCi/g)
ORNL sample no. Geotech sample no. ORNL Geotech
MS00261V1" NCL 806* >15 4.2 4.9
" Soil samples representative of the bottom 15-cm (6 in.) soil layers of the excavated area
were taken and blended form composite samples, which represent an average over
verification areas. Composite samples collected by ORNL from approximately the same
excavated locations sampled by Geotech.
6 Composite soil samples collected by RUST Geotech, Inc.
Table 3. Results of ORNL high outdoor gamma soil samples from
197 East Center Street, Monticello, Utah (MS00261-MO)
ORNL sample no. Depth Area 726Ra concentration Hot Spot
(cm) (m2) (pCi/g) guideline
MS00261V1AH" >15 2 2.1 106
MS00261V1BH" >15 2 45 106
MS00261V1CH" >15 8 20 53
" Individual soil samples collected by ORNL at the highest gamma exposure in each of the
excavation areas.
SEE
DETAIL
A
131 FT.
SINGLE-STORY
BRICK MOTEL
Jl
^SEE
OETAIli
;B-
f.'..
t
CM
EAST CENTER STREET
EXPLANATION
Concrete
Assessed
contamination
Assessed area
not found
YA Excavated
22 area
Remaining
contamination
RDC
Measurement
Area identifier &
Composite sample
Identifier of
averaged area &
Biased sample
rccT
M eO 30 40
NETtm
MS00261
197 EAST CENTER STREET
MONTICELLO, UTAH
Figure 1. Property Map (Sheet 1 of 2)
i- •
3 V1 AH
A
A
A
ED .J.
; < A
6 V1BH' 7^
vTj 13-22/uiR/h
V1CH
V1
" -1
2
*'* ^ «i
DETAIL B
DETAIL A
EXPLANATION
Concrete
Assessed
contamination
Assessed area
not found
Excavated
area
Remaining
contamination
RDC
Measurement
Area identifier Sc
Composite sample
Identifier of
averaged area &
Biased sample
O Individual soil
V1AH sample from high
outdoor gamma
N
A
FEET
ICTCRS
DETAIL
MS00261
197 EAST CENTER STREET
MONTICELLO, UTAH
Figure 1. Property Map (Sheet 2 of 2)
9
REFERENCES
Geotech 1996, Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00261-MO, Address: 197 East Center Street, Monticello,
Utah 84535, Geotech, Grand Junction, Colorado, March, 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessments
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
U. S. DOE 1990a. Verification and Certification Protocol for the Office of Environ-
mental Restoration, Formerly Utilized Sites Remedial Action Programs and Decon-
tamination and Decommissioning Program, Revision 3, November 1990. U.S.
Department of Energy, Washington, D.C.
U.S. DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision
and Record of Decision Summary. U.S. Department of Energy, Grand Junction Projects
Office, Grand Junction, Colorado.
DOE ID No.: MS-00266-CS
Property Address: 80 North First East Street
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech nf Energy (DOE)
Ra-226 is <, 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [ ]
Ra-226 is < 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2.
In-situ [ ] Lab [X]
Interior gamma is £ 20 //R/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is < 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21.
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
I*] [ 1 I 1
MM [ 1
[A I ] I ]
[ ] [>1 [ I
m [ ] [ ]
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
iiiiiiiM mmi
SFCERTIFED SFMS-00266
DOE ID No.: MS-00266-CS
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
t ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
A/Vanda syBusby ' Date
Manager Monticello Programs
Rust Geotech
DOE EVALUATION
IX] Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Date Certification Official'
U.S. Department of Energy
PROPERTY COMPLETION REPORT
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
DOE ID NO.: MS-00266-CS
ADDRESS: 80 NORTH FIRST EAST STREET
MONTICELLO, UTAH 84535
APRIL 1996
Prepared for
U.S. Department of Energy
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
FOR
FOR
by
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.1.3 Radon Decay-Product Concentration (RDC) Measurement .... 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
DOE ID No.: MS-00266-CS
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Inclusion Survey Contractor. DOE reviewed
these evaluation results and determined that the property contained mill
tailings (residual radioactive material) exceeding EPA standards and DOE
hot spot criteria. The Remedial Action Contractor was notified of the
inclusion of this property into the MVP Project and was authorized by DOE
to conduct remedial action as required to bring the property into
conformance with EPA standards and DOE hot spot criteria.
1
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
Property Address:
Property Owners:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
DOE ID No.: MS-00266-CS
MS-00266-CS
Beginning 202 feet north of the SW corner
of Block H, Monticello Townsite Survey;
north 90 feet, east 120 feet, south 90 feet,
west 120 feet to beginning, County of San
Juan, State of Utah
80 North First East Street
Monticello, Utah 84535

Commercial Structure (CS)
Oak Ridge National Laboratory
November 6, 1992
Rust Geotech
September 12, 1994
Diamond Back Services, Inc.
9861 Titan Park Circle
Littleton, Colorado
July 13, 1995
August 3, 1995
Interior: 0 cubic yards
Exterior: 7 cubic yards
25 square meters (m2)
April 1996
2
DOE ID No.: MS-00266-CS
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of exterior residual radioactive
material (Appendix Figure 2.1). Interior assessed Areas B and C
(contaminated mortared exterior brick wall and block chimney) were
excluded from remedial action based on gamma exposure rates and pre-
remedial radon decay-product concentration measurements that did not
exceed EPA standards, as discussed in the REA. Once excavation was
complete, the affected areas were resurveyed for possible remaining
residual radioactive material and, upon attaining satisfactory results, were
backfilled with uncontaminated material. The property was restored to a
physical condition comparable to that which existed prior to remedial
action activities.
2.2 Previously Unidentified Contamination
The radiological assessment (excluding assessed Areas B and C) identified
2 cubic yards of contamination, 6 inches deep, within the property. The
remedial action process included the removal of approximately 7 cubic
yards of residual radioactive material, ranging from 6 to 9 inches deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID No.: MS-00266-CS
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by the Remedial Action
Contractor during August 1993, as described in the final REA
dated September 1994. Appendix Figure 2.1 shows the extent of
assessed contamination and identifies the area recommended to
undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the excavation were
collected. These samples were blended to form a composite
sample representing the verification area (Appendix Figure 2.1).
Additionally, in-situ measurements were taken in unremediated
areas where gamma exposure-rate measurements exceeded
18 microroentgens per hour (//R/h), which is 30 percent greater
than background (14//R/h).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 12 to 25 //R/h (Appendix
Figure 2.1). The result of analysis for radium-226 in one
composite soil sample was 1.2 picocuries per gram (pCi/g), as
indicated in Appendix Table 3.1. The in-situ measurement results
for radium-226 in two unremediated areas with elevated exposure
rates were 2.3 and 4.0 pCi/g (Appendix Table 3.2).
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on the DOE-approved abbreviated-measurement method,
the RDC was 0.0020 working level (WL), as indicated in Appendix
Table 3.3. Appendix Figure 2.1 shows the measurement location
on the ground floor (the lowest habitable level of the structure).
RDC measurements were taken before remediation of the property.
4
DOE ID No.: MS-00266-CS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at 80 North First East Street, in
Monticello, Utah, is recommended for certification as required by DOE
guidelines, and the appropriate records should be documented.
Certification Data Summary
Applicability Standards Survey Results
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 20 //R/h
above background.*
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Shall not exceed 5 pCi/g
above background in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
Range for the ground
floor was 12 to 28 //R/h.
Average was 0.0020 WL,
based on the DOE-
approved abbreviated-
measurement method.
In-situ measurement
results were 2.3 and
4.0 pCi/g.**
Soil sample result was
1.2 pCi/g.**
*The background exposure rate is approximately 14//R/h.
The background radium-226 concentration is approximately 2.0 pCi/g.
**The hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-00266-CS
' 4.0 APPENDIX
Appendix Tables:
Table 3.1 Post-Excavation Sample/Measurement Results
Table 3.2 Radium Measurement Results for Unremediated Areas
with Elevated Gamma Exposure Rates
Table 3.3 Radon Decay-Product Concentration Measurement
Results
Appendix Figure:
Figure 2.1 Interior and Exterior Extent of Contamination -
RADIOLOGICAL AS-BUILT
JEK:04-08-96
MS-00266.CS WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00266-CS
Address: 80 North First East Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (//R/h) Ticket No. Method" (pCi/g)
V-1 16-17 NCC 127 OCS 1.2
See Appendix Figure 2.1 for the verification area.
"OCS = Opposed Crystal System
7
Table 3.2
Radium Measurement Results for Unremediated Areas
with Elevated Gamma Exposure Rates
DOE ID No.: MS-00266-CS
Address: 80 North First East Street, Monticello, Utah
Meas.
Loc. Grid Meas. Depth Radium-226
Coord. Method0 (inches) (pCi/g)
151280 DS 00 2.3
263257 DS [ 24 ] 4.0
"DS = Delta Scanner
[ 24 ] = Height in inches above ground.
8
Table 3.3
Radon Decay-Product Concentration Measurement Results
DOE ID No.: MS-00266-CS
Address: 80 North First East Street, Monticello, Utah
Instrument Type: Landauer Radtrak Detector
Detector
Number Start Date End Date
Radon
Concentration
(pCi/L)
"Working
Level
3964341
3964273
3964299
02-28-95
02-28-95
02-28-95
05-30-95
05-30-95
05-30-95
0.33
0.44
0.40
0.0017
0.0022
0.0020
Average: 0.0020
See Appendix Figure 2.1 for the measurement location.
9
10
30
1 2 1 4 1 6 18 20 22 24 26 28 3f 32 34 38 40
30
28
26
24
22 -
20
18 -
16
14
12
LU
Ld
CC
I— N
I—
CO <
LU
CO
- N
Li_ N
cc
o
i~rr
12-13
1 7-25
ONE STORY METAL BUILDING
SEE DETAIL A
13-14
13-15
13-15
V-1
6-7
BRICK PILE
17-21
17-28
12-15
GROUND FLOOR
12-15
DETAIL A
NOT TO SCALE
Y
SCALE IN FEET
20 10 0 20 40
M:\FAS\033\0003\RM00266V 04/12/96 12:11 pm T50780
NORTH
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT. UTILITY LOCATION PLAT, OR OTHER IMPROVEMENT SURVEY
PLAT AND IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE, BUILDING, OR OTHER FUTURE IMPROVEMENT LINES.
10 J I I L
12
V-1
16-17
(RDC)
-X-
28
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN /zR/h
(J) ASSESSED AREA IDENTIFIER
(&) AVERAGE DEPTH OF ASSESSED CONTAMINATION
[v/'v] AREA OF ASSESSED CONTAMINATION
12-15 POST-REMEDIAL ACTION EXPOSURE-RATE RANGE
— BOUNDARY OF EXCAVATION
26
24
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE-RATE RANGE
RADON DECAY-PRODUCT CONCENTRATION
MEASUREMENT LOCATION
ASSESSED AREAS B (CONTAMINATED MORTARED
BRICK WALL) AND C (CONTAMINATED MORTARED
BLOCK CHIMNEY) WERE EXCLUDED FROM REMEDIAL
ACTION
22
RADIOLOGICAL AS-BUILT
FIGURE 2.1
INTERIOR AND EXTERIOR EXTENT OF CONTAMINATION
RESIOENCE-NO. OF OCCUPANTS
NON—RESIDENCE—UAN-HRS./WK.
INSTRUMENT NO.
SURVEY OATE
DT CK. A.E. APP.
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE, COLORADO
4%
80 NORTH FIRST EAST STREET
MONTICELLO, UTAH
Rust Qeotech
AWAl
APPROVAL OOE
0OE.0N0. MS-00266-CS
OW.NO. 3-B00266-V1 SMt 1 0f 1
20
18
— 16
1 4
1 2
10
10 12 1 4 1 6 18 20 22 24 26 28 30 32 34 36 38 40
OAK RIDGE NATIONAL LABORATORY
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
FOR THE U.S. DEPARTMENT OF ENERGY
PHONE: [phone]
FAX: [phone]
POST OFFICE BOX 2567
GRAND JUNCTION, COLORADO 81502
JM. 3 I 1996
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by
the U.S. Department of Energy for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program (FUSRAP) and Remote Surplus Facilities Management Program
Sites (SFMP) [Revision 2, March 1987]. This evaluation is based on an independent verifi-
cation review of the Remedial Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment of
the ^Ra concentration in the soil, indoor radon daughter concentration, and indoor gamma
exposure rates at this property.
This property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
Location Number:
Location Address:
Property Owner:
Owner Address:
MS00266-CS
80 North 1st East Street
Monticello. Utah 84535

Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
80 NORTH 1ST EAST STREET
MONTICELLO, UTAH (MS00266-CS)
M. K. Jensen
June 1996
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 4
REFERENCES 7
iii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 5
2. Results of ORNL analysis of Geotech soil samples from 80 North 1st East Street,
Monticello, Utah (MS00266-CS) 6
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site
Decommissioning Projects, U.S. Department of Energy. The author wishes to
acknowledge M. J. Wilson-Nichols and A. R. Jones for technical reviews.
vii
ABSTRACT
In 1980 the site of a vanadium and uranium mill at Monticello, Utah, was accepted
into the U.S. Department of Energy's (DOE's) Surplus Facilities Management Program,
with the objectives of restoring the government-owned mill site to safe levels of radio-
activity, disposing of or containing the tailings in an environmentally safe manner, and
performing remedial actions on off-site (vicinity) properties that had been contaminated
by radioactive material resulting from mill operations. During 1995, RUST Geotech, the
remedial action contractor designated by DOE, performed remedial action on the vicinity
property at 80 North 1st East Street, Monticello, Utah. The Environmental Technology
Section (ETS) of Oak Ridge National Laboratory was assigned the responsibility of
verifying the data supporting the adequacy of remedial action and confirming the site's
compliance with DOE guidelines. The ETS found that the site successfully meets the
DOE remedial action objectives. Procedures used by the ETS are described in the
Environmental Technology Section Procedures Manual (ORNL 1993).
ix
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 80 NORTH 1ST EAST STREET
MONTICELLO, UTAH (MS00266-CS)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the U.S. government through the
Defense Plant Corporation to provide vanadium during World War II. Various govern-
ment agencies operated the mill until 1947. In 1948 the Atomic Energy Commission
(AEC) obtained the mill and operated it under contract through 1959 to provide both
uranium and vanadium. Mill operations were terminated on January 1,1960. In 1961 the
mill tailings piles were leveled and graded, covered with rock and soil, and seeded with
native grasses. During 1974 and 1975, the ore stockpiles were removed from the site, and
the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city
of Monticello, in San Juan County, Utah. The site is bordered on the south and southeast
by land held by the U.S. Bureau of Land Management. Other boundaries are the city of
Monticello and private property.
During the AEC era, the mill processed approximately one million tons of uranium
ore. Vanadium and uranium were the only substances extracted in the milling process.
Other constituents of the ore remained in the tailings and were not separated prior to dis-
posal. During the years of active mill operation, the mill tailings were normally moist, so
erosion was minimal. However, throughout the mill's operating period, area residents
used these tailings as fill material and as aggregate in mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy
(DOE) initiated the Surplus Facilities Management Program (SFMP) in 1978 to ensure
the safe caretaking and decommissioning of government facilities that had been retired
from service but still had radioactive contamination. In 1980 the mill site at Monticello
was accepted into the SFMP, and the Monticello Remedial Action Project (MRAP) was
established to restore the government-owned mill site to safe levels of radioactivity, to
dispose of or contain the tailings in an environmentally safe manner, and to perform
remedial actions on off-site (vicinity) properties that had been contaminated by
radioactive material resulting from mill operations. The Monticello mill site and the
tailings remain in the custody of the DOE Grand Junction, Colorado, Projects Office. In
1983 remedial actions for vicinity properties were separated from MRAP with
establishment ofthe Monticello Vicinity Properties (MVP) Project (U.S. DOE 1990b).
•The verification of remedial action was performed by members of the Environmental Assessment Group in the
Environmental Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE
contract DE-AC05-96OR22464 with Lockheed Martin Energy Research Corporation.
2
During 1995, RUST Geotech Inc. (Geotech), the remedial action contractor (RAC)
designated by DOE, performed remedial action on the vicinity property that is the subject
of this report, a day care center located at 80 North 1st East Street, Monticello, Utah. The
remedial action plan required excavation of all exterior contamination. When the
excavation was completed, the property was resurveyed, including soil sampling, to
ensure the removal of all contamination, backfilled with uncontaminated material, and
restored to a condition comparable to that which existed prior to remedial action (Geotech
1996).
The DOE adopted a policy to assign an independent contractor to verify the data
supporting the adequacy of remedial action and to confirm the site's compliance with
DOE guidelines. The Environmental Technology Section (ETS) of Oak Ridge National
Laboratory (ORNL) has been assigned the responsibility of this task at the 80 North
1st East Street site. This report describes the methods and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available doc-
umentation adequately and accurately describes the post-remedial-action radiological
conditions of the entire property that is to be certified and (2) that the remedial action
reduced contamination to below applicable DOE guidelines (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1996) in-
dicates the property was remediated as evaluated by DOE on the basis of Environmental
Protection Agency standards and the DOE guidelines (DOE 1990a). Excess residual
radioactive materials were present, thus it was appropriate to designate this property for
remedial action.
The pre-remedial-action survey performed by Geotech identified 2 yd3 of mill
tailings 6 inches deep. During the actual removal process, a total of 7 yd3 of contaminat-
ed earth and uranium mill tailings, 6 to 9 inches deep, were removed from a 25 m2 area.
A post-excavation survey was performed by Geotech prior to backfilling the exca-
vated areas. This survey consisted of gamma scans with a scintillometer of the ground
level ofthe structure, a surface scan of the exterior, and soil sampling. Samples
representative of the bottom 15-cm (6-in.) soil layers of one excavated verification area
were collected and blended to form a representative composite soil sample.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation
levels have not been subtracted. Similarly, background concentrations have not been sub-
tracted from radionuclide concentrations in soil samples. Applicable DOE guidelines for
protection against radiation are given in Table 1.
Gamma Measurements
Gamma exposure rate measurements taken by Geotech at the ground-level ofthe
business ranged from 12 to 28 uR/h. Elevated gamma exposure rates were due to
contaminated mortar in the brick veneer on the exterior of the building and block
chimney inside the building. Gamma exposure rates and radon measurements precluded
any structural remediation. Elevated gamma exposure rates of 17-25 pR/h were noted on
contact with the brick veneer on the outside of the building. In addition, a brick pile east
of the structure had gamma exposure rates of 17-21 uR/h. In situ delta measurements
were taken in the surface soil under the brick pile and next to the house adjacent to the
brick veneer to show compliance to surface soil criteria. Exterior surface gamma
measurements taken from the excavated areas prior to backfilling ranged from 16 to 17
uR/h.
Soil Sample Analysis
Prior to backfilling, Geotech collected soil samples representative of the excavated
areas from the bottom 15-cm (6-in.) soil layers. These samples were blended to form a
composite soil sample representative of an average over the exterior verification area.
Geotech's analysis of this sample showed a 226Ra concentration of 1.2 pCi/g. ORNL ETS
obtained this sample and performed a confirmatory analysis which showed a 226Ra
concentration of 1.3 pCi/g. These values are below the EPA standard value of 15 pCi/g
for soil layers > 15 cm below the surface. Gamma ranges and/or soil sample results
demonstrate compliance to the DOE Hot Spot Guidelines for areas <25 m2 (Table 1).
Results of Geotech and ORNL soil sample analyses are given in Table 2.
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were deter-
mined by the Alpha-track method. To monitor radon levels, Geotech placed three alpha-
track detectors on the ground floor of the residence located on this property for a period
of approximately three months (from February 28,1995 to May 30,1995). The average
annual working level (WL) of radon progeny concentration, as determined by the
TechVOps-Landauer Corporation, was 0.0020, which is well below the 0.03-WL
guideline given in Table 1.
4
CONCLUSION
Results of Geotech soil sample analysis and confirmatory split soil sample analysis
by ORNL show that radionuclide concentrations are within applicable DOE guidelines.
Based on the results ofthe post-remedial-action data, which are confirmed by the
verification assessment data, these radiological measurements fall below the limits
prescribed by DOE guidelines. It is concluded that the site successfully meets the DOE
remedial action objectives.
5
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of 226Ra in soil
above background levels,
averaged over a 100-m2 area
5 pCi/g averaged over the
first 15 cm of soil below the
surface; 15 pCi/g when ave-
raged over 15-cm-thick soil
layers more than 15 cm
below the surface
Radionuclide
concentrations in soil
for Hot Spot areas
Maximum Permissible con-
centration of Ra226 in soil
above background level, for
areas less than 25 m2
Ra226 concentrations, in any
surface or subsurface area
less than 25 m2, is below the
guideline by a factor of
(1007A)'/J, where A is the
area of the elevated region
Exposure to 222Rn
progeny
Average annual radon proge-
ny concentration (including
background)
0.03 WL
(DOE 1990a)
6
Table 2. Results of ORNL analysis of Geotech soil samples
from 80 North 1st East Street, Monticello Utah (MS00266-CS)
226Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No.0 No/ (cm)
XI NCC 127 >15 1.3 1.2
a An X-type sample is a split of the sample taken by the remedial action contractor.
* Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated
areas were taken by Geotech, and these samples were blended to form a composite soil
sample, which represents an average over one of the verification areas.
7
REFERENCES
Geotech 1996. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00266-CS, Address: 80 North First East Street, Monticello,
Utah 84535, Geotech, Grand Junction, Colorado, April 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
U.S. DOE 1990a. Verification and Certification Protocolfor the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination
and Decommissioning Program, Revision 3, November 1990. U.S. Department of
Energy, Washington, D.C.
U.S. DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision
and Record of Decision Summary. U.S. Department of Energy, Grand Junction Projects
Office, Grand Junction, Colorado.
DOE ID No.: MS-00281-RS
Property Address: 96 North Third West Street
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech of Energy (DQE)
Ra-226 is < 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [XV
Ra-226 is <, 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2.
In-situ [ ] Lab [X]
Interior gamma is < 20 //R/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is <, 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21.
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
[H [ ] I 1.
MM [ ]
[V] [ ] [ ]
M [ ] M
[ i iy\ i ]
ty] [ ] [ 1
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of oamma
exposure rates that do not exceed 30 percent above normal background.
^art of one sample was taken from the surface soil layer, and was lab-analyzed.
Ililllllllll
SFCERTIFED •II
SFMS-00281
DOE ID No.: MS-00281-RS
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
7" /anda S-JSusby
Manager/Monticello Programs
Rust Geotech
<T/z*/9l
Date
DOE EVALUATION
[X] Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Off ial Certificai
U.S. Department of Energy
Date
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00281-RS
ADDRESS: 96 NORTH THIRD WEST STREET
MONTICELLO, UTAH 84535
MAY 1996
Prepared for
U.S. Department of Energy
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
by
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
' WandX S. Bus6y
Manager, Monticello Programs
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.1.3 Radon Decay-Product Concentration (RDC) Measurement .... 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
i
DOE ID No.: MS-00281-RS
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Inclusion Survey Contractor. DOE reviewed
these evaluation results and determined that the property contained mill
tailings (residual radioactive material) exceeding EPA standards and DOE
hot spot criteria. The Remedial Action Contractor was notified of the
inclusion of this property into the MVP Project and was authorized by DOE
to conduct remedial action as required to bring the property into
conformance with EPA standards and DOE hot spot criteria.
1
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
Property Address:
Property Owners:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
DOE ID No.: MS-00281-RS
MS-00281-RS
Beginning 321.75 feet north of the SW
corner of Block L, Monticello Townsite
Survey; west 36 feet, north 107.25 feet,
east 36 feet, south 107.25 feet to
beginning; and beginning at the NW corner
of Lot 3, said Block L, south 107.25 feet,
east 64 feet, north 107.25 feet, west
64 feet to beginning, County of San Juan,
State of Utah
96 North Third West Street
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
July 25, 1990
Rust Geotech
April 7, 1994
Diamond Back Services, Inc.
9861 Titan Park Circle
Littleton, Colorado
July 12, 1995
August 16, 1995
Interior: 0 cubic yards
Exterior: 14 cubic yards
37 square meters (m2)
May 1996
2
DOE ID No.: MS-00281-RS
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of exterior residual radioactive
material (Appendix Figure 2.1). Once excavation was complete, the
affected areas were resurveyed for possible remaining residual radioactive
material and, upon attaining satisfactory results, were backfilled with
uncontaminated material. The property was restored to a physical
condition comparable to that which existed prior to remedial action
activities.
2.2 Previously Unidentified Contamination
The radiological assessment identified 24 cubic yards of contamination,
ranging from 42 inches deep to 60 inches high, within the property. The
remedial action process included the removal of approximately 14 cubic
yards of residual radioactive material, ranging from 42 inches deep to
60 inches high.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID No.: MS-00281-RS
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by the Remedial Action
Contractor during August 1990, as described in the final REA
dated April 1994. Appendix Figure 2.1 shows the extent of
assessed contamination and identifies the areas recommended to
undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the excavation were
collected. These samples were blended to form composite
samples representing the verification areas (Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 12 to 25 microroentgens per
hour Ot/R/h), as indicated on Appendix Figure 2.1. Elevated
exposure rates of up to 25 //R/h adjacent to the south and
southwest walls of the house were associated with material in the
foundation. This material was not removed because it did not
cause the interior gamma exposure rates to exceed EPA standards.
The results of analyses for radium-226 in two composite soil
samples were 1.0 and 1.3 picocuries per gram (pCi/g), as
indicated in Appendix Table 3.1.
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on the DOE-approved abbreviated-measurement method,
the RDC was 0.0059 working level (WL), as indicated in Appendix
Table 3.2. Appendix Figure 2.1 shows the measurement location
in the basement (the lowest habitable level of the structure). RDC
measurements were taken before remediation of the property.
4
DOE ID No.: MS-00281-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at 96 North Third West Street, in
Monticello, Utah, is recommended for certification as required by DOE
guidelines, and the appropriate records should be documented.
Certification Data Summary
Applicability
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Standards
Shall not exceed 20 //R/h
above background.*
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Survey Results
Ranges were 12 to
15 //R/h for the
basement, and 13 to
18 //R/h for the attached
garage.
Average was 0.0059 WL,
based on the DOE-
approved abbreviated-
measurement method.
Land.
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
< 5 pCi/g abovt
background.**
Soil sample results were
1.0 and 1.3 pCi/g.**
*The background exposure rate is approximately 15 //R/h.
The background radium-226 concentration is approximately 2.0 pCi/g.
**The hot spot criteria were met based on gamma scans and/or soil sample results.
A part of sample V-2 was from the 15-cm surface layer.
5
DOE ID No.: MS-00281-RS
4.0 APPENDIX
Appendix Tables:
Table 3.1 Post-Excavation Sample/Measurement Results
Table 3.2 Radon Decay-Product Concentration Measurement
Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
JEK:04-11-96
MS-00281.RS WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00281-RS
Address: 96 North Third West Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range U/R/h) Ticket No. Method" (pCi/g)
V-1 13-18 NCL 638 OCS 1.0
V-2 13- 20 NCH 081 OCS 1.3
See Appendix Figure 2.1 for the verification areas.
"OCS = Opposed Crystal System
7
Table 3.2
Radon Decay-Product Concentration Measurement Results
DOE ID No.: MS-00281-RS
Address: 96 North Third West Street, Monticello, Utah
Instrument Type: Landauer Radtrak Detector
Radon
Detector Concentration Working
Number Start Date End Date (pCi/L) Level
3964257 02-28-95 06-06-95 0.98 0.0049
3964221 02-28-95 06-06-95 1.26 0.0063
3964154 02-28-95 06-06-95 1.28 0.0064
Average: 0.0059
See Appendix Figure 2.1 for the measurement location.
8
10
30
28
26
24
22 -
20
18
16
1 4
12
Y
10
12
Ld
Ld rr
r— co
Ld
Q
or
or o
1 4 1 6 20 22 24 26 28
WEST FIRST NORTH STREET
6 X A
1 r HED/ SH V-1 SHED/ SHED
12-15 12-14 U 13-18
I 1
iCELLAR , 16-17
12-15
12-15
ONE STORY
LOG HOUSE
W/BASEMENT
V-1
12-15 13-18
RDC
42 42 rT7,
V-2
13-20
42 42
GARAGE
13-18 60
V-1
13-18
\ SHED
12-14
17-25 18 12 v-2
13-20
SCALE IN FEET
20 10 0 20 40
M:\FAS\033\0003\RM00281V 04/16/96 3:44pm T50780
NORTH
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT, UTILITY LOCATION PLAT, OR OTHER IMPROVEMENT SURVEY
PLAT AND IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE. BUILDING. OR OTHER FUTURE IMPROVEMENT LINES.
©
pr.-^
LV.VJ
12-15
12
V-1
16-17
[12]
32 34 ^6 38
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN ^R/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE-RATE RANGE
RADON DECAY-PRODUCT CONCENTRATION
MEASUREMENT LOCATION
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
HEIGHT IN INCHES OF ASSESSED CONTAMINATED
CINDER BLOCK WALL REMOVED AND REPLACED
40
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
RESIDENCE-NO. OF OCCUPANTS
NON-RESIDF.NCE-MAN-HRS./WK.
INSTRUMENT NO.
SURVEY OATE
A.E. APP. NO. BY CK. A.E. APP.
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE. COLORADO
'7-7-96 NORTH THIRD WEST STREET
MONTICELLO, UTAH
Rust Qeotech
AWBTiiliHtlitan^)
APPROVAL DOE
ooc io NO. MS-00281-RS
o«c.MO. 3-BQ0281 -VI SHT 1 or 1
30
28
26
24
22
20
18
1 6
1 4
12
10
10 1 2 1 4 1 6 18 20 22 24 26 28 30 32 34 36 38 40
OAK RIDGE NATIONAL LABORATORY PHONE: pro) 24»«200
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION FAX: [phone]
FOR THE U.S. DEPARTMENT OF ENERGY
POST OFFICE BOX 2567
GRAND JUNCTION, COLORADO 81502 ^yg ^ Q 1996
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81S02
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by
the U.S. Department of Energy for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program (FUSRAP) and Remote Surplus Facilities Management Program
Sites (SFMP) [Revision 2, March 1987], This evaluation is based on an independent verifi-
cation review of the Remedial Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment of
the ^Ra concentration in the soil, indoor radon daughter concentration, and indoor gamma
exposure rates at this property.
This property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
Location Number: MS00281-RS
Location Address: 96 North 3rd West Street
Monticello, Utah 84535
Property Owner:

Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
96 NORTH 3RD WEST STREET
MONTICELLO, UTAH (MS00281-RS)
M. J. Wilson-Nichols
August 1996
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 3
REFERENCES 6
iii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 4
2. Results of ORNL analysis of Geotech soil samples from 96 North 3rd West Street,
Monticello, Utah (MS00281 -RS) 5
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site
Decommissioning Projects, U.S. Department of Energy. The author wishes to
acknowledge M. K. Jensen for analysis of soil samples and technical review and
N. F. Kirby for technical review.
vii
ABSTRACT
In 1980 the site of a vanadium and uranium mill at Monticello, Utah, was accepted
into the U.S. Department of Energy's (DOE's) Surplus Facilities Management Program,
with the objectives of restoring the government-owned mill site to safe levels of radio-
activity, disposing of or containing the tailings in an environmentally safe manner, and
performing remedial actions on off-site (vicinity) properties that had been contaminated
by radioactive material resulting from mill operations. During 1995, RUST Geotech, the
remedial action contractor designated by DOE, performed remedial action on the vicinity
property at 96 North 3rd West Street, Monticello, Utah. The Environmental Technology
Section (ETS) of Oak Ridge National Laboratory was assigned the responsibility of veri-
fying the data supporting the adequacy of remedial action and confirming the site's com-
pliance with DOE guidelines. The ETS found that the site successfully meets the DOE
remedial action objectives. Procedures used by the ETS are described in the Environmen-
tal Technology Section Procedures Manual (ORNL 1993).
ix
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 96 NORTH 3RD WEST STREET
MONTICELLO, UTAH (MS00281-RS)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the U.S. government through the
Defense Plant Corporation to provide vanadium during World War II. Various govern-
ment agencies operated the mill until 1947. In 1948 the Atomic Energy Commission
(AEC) obtained the mill and operated it under contract through 1959 to provide both
uranium and vanadium. Mill operations were terminated on January 1, 1960. In 1961 the
mill tailings piles were leveled and graded, covered with rock and soil, and seeded with na-
tive grasses. During 1974 and 1975, the ore stockpiles were removed from the site, and
the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city
of Monticello, in San Juan County, Utah. The site is bordered on the south and southeast
by land held by the U.S. Bureau of Land Management. Other boundaries are the city of
Monticello and private property.
During the AEC era, the mill processed approximately one million tons of uranium
ore. Vanadium and uranium were the only substances extracted in the milling process.
Other constituents of the ore remained in the tailings and were not separated prior to dis-
posal. During the years of active mill operation, the mill tailings were normally moist, so
erosion was minimal. However, throughout the mill's operating period, area residents
used these tailings as fill material and as aggregate in mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy
(DOE) initiated the Surplus Facilities Management Program (SFMP) in 1978 to ensure
the safe caretaking and decommissioning of government facilities that had been retired
from service but still had radioactive contamination. In 1980 the mill site at Monticello
was accepted into the SFMP, and the Monticello Remedial Action Project (MRAP) was
established to restore the government-owned mill site to safe levels of radioactivity, to
dispose of or contain the tailings in an environmentally safe manner, and to perform reme-
dial actions on off-site (vicinity) properties that had been contaminated by radioactive ma-
terial resulting from mill operations. The Monticello mill site and the tailings remain in the
custody of the DOE Grand Junction, Colorado, Projects Office. In 1983 remedial actions
for vicinity properties were separated from MRAP with establishment of the Monticello
Vicinity Properties (MVP) Project (U.S. DOE 1990b).
*The verification of remedial action was performed by members ofthe Environmental Assessment Group in the
Environmental Technology Section ofthe Health Sciences Research Division at Oak Ridge National Laboratory under DOE contract
DE-AC05-96OR22464 with Lockheed Martin Energy Research Corporation.
2
During 1995, RUST Geotech Inc. (Geotech), the remedial action contractor (RAC)
designated by DOE, performed remedial action on the vicinity property that is the subject
of this report, a single family residence located at 96 North 3rd West Street, Monticello,
Utah. The remedial action plan required excavation of all exterior contamination. When
the excavation was completed, the property was resurveyed, including soil sampling, to
ensure the removal of all contamination, backfilled with uncontaminated material, and re-
stored to a condition comparable to that which existed prior to remedial action (Geotech
1996).
The DOE adopted a policy to assign an independent contractor to verify the data
supporting the adequacy of remedial action and to confirm the site's compliance with DOE
guidelines. The Environmental Technology Section (ETS) of Oak Ridge National Labor-
atory (ORNL) has been assigned the responsibility of this task at the 96 North 3rd West
Street site. This report describes the methods and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available doc-
umentation adequately and accurately describes the post-remedial-action radiological
conditions of the entire property that is to be certified and (2) that the remedial action
reduced contamination to below applicable DOE guidelines (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1996) in-
dicates the property was remediated as evaluated by DOE on the basis of Environmental
Protection Agency standards and the DOE guidelines (DOE 1990a). Excess residual
radioactive materials were present, thus it was appropriate to designate this property for
remedial action.
The pre-remedial-action survey performed by Geotech identified 24 yd3 of mill tailings
42 inches deep to 60 inches high. During the actual removal process, a total of 14 yd3 of
contaminated earth and uranium mill tailings, 42 inches deep to 60 inches high, were
removed from a 37 m2 area.
A post-excavation survey was performed by Geotech prior to backfilling the exca-
vated areas. This survey consisted of gamma scans with a scintillometer of the ground
level of the structure, a surface scan of the exterior, and soil sampling. Samples repre-
sentative of the bottom 15-cm (6-in.) soil layers of two excavated verification areas were
collected and blended to form representative composite soil samples.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation
levels have not been subtracted. Similarly, background concentrations have not been sub-
tracted from radionuclide concentrations in soil samples. Applicable DOE guidelines for
protection against radiation are given in Table 1.
Gamma Measurements
Gamma exposure rate measurements taken by Geotech of the residence ranged from
12 to 15 uR/h in the basement and 13-18 uR/h in the attached garage. The slightly ele-
vated readings in the garage were due to contamination left in place in the footings on two
sides of the garage. In addition, in-situ delta measurements were taken in areas F, G, and
H and along the contaminated footings of the garage. This material was not removed be-
cause it did not exceed EPA interior gamma exposure standards. Gamma measurements
taken on the exterior of the garage along the footings ranged from 17 to 25 uR/h. Exter-
ior surface gamma measurements taken from the excavated areas prior to backfilling
ranged from 12 to 20 uR/h.
Soil Sample Analysis
Prior to backfilling, Geotech collected soil samples representative ofthe excavated
areas from the bottom 15-cm (6-in.) soil layers. These samples were blended to form
composite soil samples representative of an average over the two exterior verification
areas. Geotech's analysis of these samples showed ^Ra concentrations ranging from
1.0 to 1.3 pCi/g in the composite sample. ORNL ETS obtained these samples and per-
formed a confirmatory analysis which showed 226Ra concentrations ranging from 1.2 to
1.6 pCi/g. These values are below the EPA standard value of 15 pCi/g for soil layers
>15 cm below the surface. Results of Geotech and ORNL soil sample analyses are given
in Table 2. Gamma ranges and/or soil sample results demonstrate compliance to the DOE
Hot Spot Guidelines for areas <25 m2 (Table 1).
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were deter-
mined by the Alpha-track method. To monitor radon levels, Geotech placed three alpha-
track detectors on the ground floor of the residence located on this property for a period
of approximately three months (from February 28, 1995 to June 6, 1995). The average
annual working level (WL) of radon progeny concentration, as determined by the Tech./-
Ops-Landauer Corporation, was 0.0059, which is well below the 0.03-WL guideline given
in Table 1.
CONCLUSION
Results of Geotech soil sample analysis and confirmatory split soil sample analysis
by ORNL show that radionuclide concentrations are within applicable DOE guidelines.
Based on the results of the post-remedial-action data, which are confirmed by the veri-
fication assessment data, these radiological measurements fall below the limits prescribed
by DOE guidelines. It is concluded that the site successfully meets the DOE remedial
action objectives.
4
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Radionuclide con-
centrations in soil
for Hot Spot areas
Exposure to 222Rn
progeny
Maximum permissible con-
centration of ^Ra in soil
above background levels,
averaged over a 100-m2 area
Maximum Permissible con-
centration of Ra226 in soil
above background level, for
areas less than 25 m2
Average annual radon proge-
ny concentration (including
background)
5 pCi/g averaged over the
first 15 cm of soil below the
surface; 15 pCi/g when ave-
raged over 15-cm-thick soil
layers more than 15 cm
below the surface
Ra226 concentrations, in any
surface or subsurface area
less than 25 m2, is below the
guideline by a factor of
(100/A)*, where A is the
area of the elevated region
0.03 WL
(DOE 1990a)
5
Table 2. Results of ORNL analysis of Geotech soil samples
from 96 North 3rd West Street, Monticello, Utah (MS00281-RS)
^Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No* Noi fern)
XI NCL 638 >15 1.6 1.0
X2 NCH 081 >15 1.2 1.3
" An X-type sample is a split of the sample taken by the remedial action contractor.
* Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated areas
were taken by Geotech, and these samples were blended to form a composite soil
sample, which represents an average over one of the verification areas.
6
REFERENCES
Geotech 1996. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00281-RS, Address: 96 North Third West Street,
Monticello, Utah 84535, Geotech, Grand Junction, Colorado, May 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
U.S. DOE 1990a. Verification and Certification Protocolfor the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination
and Decommissioning Program, Revision 3, November 1990. U.S. Department of
Energy, Washington, D.C.
U.S. DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision
and Record of Decision Summary. U.S. Department of Energy, Grand Junction Projects
Office, Grand Junction, Colorado.
DOE ID No.: MS-00315-RS
Property Address: 248 Uranium Drive
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech of Energy (PQE)
Ra-226 is <. 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [ ]
Ra-226 is < 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2.
In-situ [ ] Lab [X]
Interior gamma is <. 20 //R/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is < 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21.
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
1% I ] t ]
[V4 [ ] [ ]
[y] I ] I 1
[ ] [XJ I ]
[VT t ] [ ]
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
Iiunui an unt utu tntu uttt tm uttt itui tsti HI ttti Ililllllllll Hill
SFCERTIFED SFMS-00315
DOE ID No.: MS-00315-RS
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
/anda S. Busby Date
Manager, Monticello Programs
Rust Geotech
DOE EVALUATION
[X] Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Certification Official Date
U.S. Department of Energy
PROPERTY COMPLETION REPORT
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
DOE ID NO.: MS-00315-RS
ADDRESS: 248 URANIUM DRIVE
MONTICELLO, UTAH 84535
AUGUST 1996
Prepared for
U.S. Department of Energy
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
' WandyS. Busby'
Manager, Monticello Programs
FOR
FOR
by
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.1.3 Radon Decay-Product Concentration (RDC) Measurement .... 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
i
DOE ID No.: MS-00315-RS
1.0 SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Inclusion Survey Contractor. DOE reviewed
these evaluation results and determined that the property contained mill
tailings (residual radioactive material) exceeding EPA standards and DOE
hot spot criteria. The Remedial Action Contractor was notified of the
inclusion of this property into the MVP Project and was authorized by DOE
to conduct remedial action as required to bring the property into
conformance with EPA standards and DOE hot spot criteria.
1
DOE ID No.: MS-00315-RS
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
Property Address:
Property Owners:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
MS-00315-RS
Beginning at a point which is north
89 degrees 21 minutes west 348.5 feet
from the center of Section 36, T33S.,
R23E., Salt Lake Base Meridian; north
89 degrees 21 minutes west 56.5 feet,
north 00 degrees 42 minutes east
165.0 feet, south 89 degrees 21 minutes
east 56.5 feet, south 00 degrees
42 minutes west 165.0 feet to beginning,
City of Monticello, County of San Juan,
State of Utah
248 Uranium Drive
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
December 11, 1990
Rust Geotech
Not applicable: streamlined remediation
procedures were followed
Sonderegger Inc.
P.O. Box 713
Monticello, Utah
August 4, 1994
August 15, 1994
Interior: 0 cubic yards
Exterior: 3.1 cubic yards
8.3 square meters (m2)
August 1996
2
DOE ID No.: MS-00315-RS
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
Streamlined remediation procedures were followed for this property. The
remedial action plan involved removal of exterior residual radioactive
material (Appendix Figure 2.1). Once excavation was complete, the
affected areas were resurveyed for possible remaining residual radioactive
material and, upon attaining satisfactory results, were backfilled with
uncontaminated material. The property was restored to a physical
condition comparable to that which existed prior to remedial action
activities.
2.2 Previously Unidentified Contamination
The radiological assessment identified contamination ranging from 6 to
12 inches deep, within the property. The quantity of contamination for
this property was not specified. The remedial action process included the
removal of 3.1 cubic yards of residual radioactive material, ranging from 6
to 18 inches deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID No.: MS-00315-RS
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by the Remedial Action
Contractor during May 1992. Appendix Figure 2.1 shows the
extent of assessed contamination and identifies the areas
recommended to undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the excavation were
collected. These samples were blended to form composite
samples representing the verification areas (Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 12 to 20 microroentgens per
hour {jjR/h), as indicated on Appendix Figure 2.1. The results of
analyses for radium-226 in 5 composite soil samples ranged from
1.8 to 4.0 picocuries per gram (pCi/g), as indicated in Appendix
Table 3.1.
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on measurements representing an annual average, the RDC
was 0.0056 working level (WL), as indicated in Appendix
Table 3.2. Appendix Figure 2.1 shows the measurement location
on the ground floor (the lowest habitable level of the structure).
4
DOE ID No.: MS-00315-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at 248 Uranium Drive, in Monticello,
Utah, is recommended for certification as required by DOE guidelines,
and the appropriate records should be documented.
Certification Data Summary
Applicability
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Standards
Shall not exceed 20 //R/h
above background.*
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Survey Results
Range for the ground
floor was 12 to 14//R/h.
Annual average was
0.0056 WL.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
< 5 pCi/g above
background.**
Soil sample results
ranged from 1.8 to
4.0 pCi/g.**
*The background exposure rate is approximately 13 //R/h.
The background radium-226 concentration is approximately 2.0 pCi/g.
**The hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-00315-RS
4.0 APPENDIX
Appendix Tables:
Table 3.1 Post-Excavation Sample/Measurement Results
Table 3.2 Radon Decay-Product Concentration Measurement
Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
JEK:7/12/96
MS-00315.RS WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00315-RS
Address: 248 Uranium Drive, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (//R/h) Ticket No. Method" (pCi/g)
V-1 14-15 NAR 077 OCS 2.4
V-2 13-15 NAR 078 OCS 2.2
V-3 14-15 NAR 079 OCS 1.8
V-4 15-20 NAR 080 OCS 4.0
V-5 15-18 NAR 081 OCS 2.4
See Appendix Figure 2.1 for the verification areas.
"OCS = Opposed Crystal System
7
Table 3.2
Radon Decay-Product Concentration Measurement Results
DOE ID Np.: MS-00315-RS
Address: 248 Uranium Drive, Monticello, Utah
Instrument Type: Landauer Radtrak Detector
Radon
Detector Concentration Working
Number Start Date End Date (pCi/L) Level
3851661
3851679
3851602
10-27-94
10-27-94
10-27-94
09-28-95
09-28-95
09-28-95
1.21
1.17
0.97
0.0061
0.0059
0.0049
Annual Average: 0.0056
See Appendix Figure 2.1 for the measurement location.
8
10
30
12 14 1 6 18 20 22 24 26 28 30 32 34 36 38 40
30
28
26
24
22 -
20
18
16
14
12
Y
10
12-15
T
GARAGE
12-13
I
v-4
v-3 18 15-20
14-15
12
6 X D
V-2
13-15
I
V-1
14-15
ONE STORY
FRAME HOUSE
12-14
^AXI 2)
12
V-5
15-181
"777
URANIUM DRIVE
•777-
SCALE IN FEET
30 15 0 30 60
M:\FAS\033\0003\RM00315V 08/07/96 10:24om T50780
NORTH
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT. UTILITY LOCATION PLAT, OR OTHER IMPROVEMENT SURVEY
PLAT AND IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE. BUILDING, OR OTHER FUTURE IMPROVEMENT LINES.
®
<D
LY.VJ
12-15
1 2
V-1
16-17
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN /iR/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE-RATE RANGE
RADON DECAY-PRODUCT CONCENTRATION
MEASUREMENT LOCATION
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
28
26
24
22
20
18
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
16
RCSIDCNCE-NO. OF OCCUPANTS
NON-RESIDENCE-UAN-HRS./WK.
INSTRUMENT NO.
SURVEY OATE
VERIFICATION
A.E. APP. NO.
14
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE, COLORADO
TFT 2tf
248 URANIUM DRIVE
MONTICELLO, UTAH
12
Rust Oeotech
AWUX1
APPROVAL OOE
o0110"0- MS-00315-RS
owe.NO. 3-C00315-V1 ,HT 1 „r 1
10
10 12 14 1 6 18 20 22 24 26 28 30 32 34 36 38 40
OAK RIDGE NATIONAL LABORATORY PHONE: [phone]
FAX: [phone] MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
FOR THE U.S. DEPARTMENT OF ENERGY
2597 BV. Road
GRAND JUNCTION. COLORADO 81503
WU I 5 1997
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by the U.S.
Department of Energy for Residual Radioactive Material at Formerly Utilized Sites Remedial
Action Program (FUSRAP) and Remote Surplus Facilities Management Program Sites (SFMP)
[Revision 2, March 1987]. This evaluation is based on an independent verification review of the
Remedial Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment of the
226Ra concentration in the soil, indoor radon daughter concentration, and indoor gamma exposure
rates at this property.
This property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
Location Number:
Location Address:
MS00315-RS
248 Uranium Drive
Monticello. Utah 84535

A. K. Gentry
Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERD7ICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
248 URANIUM DRIVE
MONTICELLO, UTAH (MS00315-RS)
S. M. Smith
March 1997
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81503
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 4
REFERENCES 7
iii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 5
2. Results of ORNL analysis of the RAC soil samples from 248 Uranium Drive,
Monticello, Utah (MS00315-RS) 6
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site Decommissioning
Projects, U.S. Department of Energy. The author wishes to acknowledge M. K. Jensen for analysis
of soil samples and technical review and A. D. Laase for technical review.
vii
ABSTRACT
In 1980, the site of a vanadium and uranium mill at Monticello, Utah, was accepted into the
U.S. Department of Energy (DOE) Surplus Facilities Management Program, with the objectives of
restoring the government-owned mill site to safe levels of radioactivity, disposing of or containing
the tailings in an environmentally safe manner, and performing remedial actions on off-site (vicinity)
properties that had been contaminated by radioactive material resulting from mill operations. During
1994, the Remedial Action Contractor (RAC) designated by DOE, performed remedial action on the
vicinity property at 248 Uranium Drive, Monticello, Utah. The Environmental Technology Section
(ETS) of Oak Ridge National Laboratory was assigned the responsibility of verifying the data
supporting the adequacy of remedial action and confirming the site's compliance with DOE
guidelines. The ETS found that the site successfully meets the DOE remedial action objectives.
Procedures used by the ETS are described in the Environmental Technology Section Procedures
Manual (ORNL 1993).
ix
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 248 URANIUM DRIVE
MONTICELLO, UTAH (MS00315-RS)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the United States (U.S.) government through
the Defense Plant Corporation to provide vanadium during World War II. Various government
agencies operated the mill until 1947. In 1948, the Atomic Energy Commission (AEC) obtained the
mill and operated it under contract through 1959 to provide both uranium and vanadium. Mill
operations were terminated on January 1, 1960. In 1961, the mill tailings piles were leveled and
graded, covered with rock and soil, and seeded with native grasses. During 1974 and 1975, the ore
stockpiles were removed from the site and the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city of
Monticello, in San Juan County, Utah. The site is bordered on the south and southeast by land held
by the U.S. Bureau of Land Management. Other boundaries are the city of Monticello and private
property.
During the AEC era, the mill processed approximately one million tons of uranium ore. Vana-
dium and uranium were the only substances extracted in the milling process. Other constituents of
the ore remained in the tailings and were not separated prior to disposal. During the years of active
mill operation, the mill tailings were normally moist, so erosion was minimal. However, throughout
the mill's operating period, area residents used these tailings as fill material and as aggregate in
mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy (DOE) initiated
the Surplus Facilities Management Program (SFMP) in 1978 to ensure the safe caretaking and de-
commissioning of government facilities that had been retired from service but still had radioactive
contamination. In 1980, the mill site at Monticello was accepted into the SFMP, and the Monticello
Remedial Action Project (MRAP) was established to restore the government-owned mill site to safe
levels of radioactivity, to dispose of or contain the tailings in an environmentally safe manner, and
to perform remedial actions on off-site (vicinity) properties that had been contaminated by radio-
active material resulting from mill operations. The Monticello mill site and the tailings remain in
the custody of the DOE Grand Junction, Colorado, Projects Office. In 1983, remedial actions for
vicinity properties were separated from MRAP with establishment of the Monticello Vicinity Proper-
ties (MVP) Project (US DOE 1990b).
*The verification of remedial action was performed by members of the Environmental Assessment Group in the Environmental
Technology Section ofthe Health Sciences Research Division at Oak Ridge National Laboratory under DOE contract DE-AC05-
960R22464 with Lockheed Martin Energy Research Corporation.
2
During 1994, the Remedial Action Contractor (RAC) designated by DOE, performed remedial
action on the vicinity property that is the subject of this report, a single family residence located at
248 Uranium Drive, Monticello, Utah. The remedial action plan required excavation of all exterior
contamination. When the excavation was completed, the property was resurveyed, including soil
sampling, to ensure the removal of all contamination, backfilled with uncontaminated material, and
restored to a condition comparable to that which existed prior to remedial action (Geotech 1996).
DOE adopted a policy to assign an independent contractor to verify the data supporting the
adequacy of remedial action and to confirm the site's compliance with DOE guidelines. The Environ-
mental Technology Section (ETS) of Oak Ridge National Laboratory (ORNL) has been assigned the
responsibility of this task at the 248 Uranium Drive site. This report describes the methods and
results of that verification.
PROCEDURES
Objectives
The objectives ofthe verification activities were to confirm (1) that available documentation
adequately and accurately describes the post-remedial-action radiological conditions of the entire
property that is to be certified and (2) that the remedial action reduced contamination to below
applicable DOE guidelines (US DOE 1990a).
Document Reviews
Review ofthe RAC property completion report (Geotech 1996) indicates the property was reme-
diated as evaluated by DOE on the basis of U.S. Environmental Protection Agency standards and the
DOE guidelines (US DOE 1990a). Excess residual radioactive materials were present, thus it was
appropriate to designate this property for remedial action using streamlined remedial action
procedures.
The pre-remedial-action survey performed by the RAC identified contamination 6 to 12 inches
deep. During the actual removal process, a total of 3 .1 yd3 of contaminated earth and mill tailings,
6 to 18 inches deep were removed from a 8.3 m2 area.
The RAC performed a post-excavation survey prior to backfilling the excavated areas. This
survey consisted of gamma scans with a scintillometer of the ground level of the structure, a surface
scan ofthe exterior, and soil sampling. Samples representative of the bottom 15-cm (6-in.) soil layers
of five excavated verification areas were collected and blended to form representative composite soil
samples for each verification area.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation levels have
not been subtracted. Similarly, background concentrations have not been subtracted from radionu-
clide concentrations in soil samples. Applicable DOE guidelines for protection against radiation are
given in Table 1.
Gamma Measurements
Gamma exposure rate measurements taken by the RAC at the ground-level of the residence
ranged from 12 to 14 pR/h. Exterior surface gamma measurements taken from the excavated areas
prior to backfilling ranged from 13 to 20 pR/h.
Soil Sample Analysis
Prior to backfilling, the RAC collected soil samples representative of the excavated areas from
the bottom 15-cm (6-in.) soil layers. These samples were blended to form composite soil samples
representative of an average over the five exterior verification areas. The RAC's analysis of these
samples showed 226Ra concentrations ranging from 1.8 to 4.0 pCi/g in the composite sample. ORNL
ETS obtained a percentage of these samples and performed a confirmatory analysis which showed
226Ra concentrations ranging from 1.8 to 2.0 pCi/g. These values are below the DOE guideline value
of 15 pCi/g for soil layers > 15 cm below the surface. Results of the RAC and ORNL soil sample
analyses are given in Table 2.
As a result of a meeting between the RAC and IVC on May 26, 1994, anomalous readings,
defined as >30% above the average of the excavation, will be investigated to show compliance to
the DOE Hot Spot Guideline. The RAC remediated this property after this procedure change. The
IVC observed that 20 uR/h for area V4 exceeds 30% of the excavation average of 16 pR/h. The IVC
will allow a correlation developed by the RAC to estimate 226Ra pCi/g concentrations based on
gamma exposure rates. The anomalous reading of 20 uR/h on this property using the RAC's correla-
tion yields a 226Ra concentration of 3.0 pCi/g. This value is well below the minimum concentration
of 30 pCi/g needed, when assuming the maximum area under the hot spot guideline of 25 m2, for
subsurface samples. Gamma ranges and/or soil sample results demonstrate compliance to the DOE
Hot Spot Guideline for areas <25 m2 (Table 1).
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were determined by the
Alpha-track method. To monitor radon levels, the RAC placed three alpha-track detectors on the
ground floor of the residence located on this property for a period of approximately one year (from
October 27, 1994 to September 28, 1995). The average annual working level (WL) of radon
progeny concentration, as determined by the Tech./Ops-Landauer Corporation, was 0.0056, which
is well below the 0.03-WL guideline given in Table 1.
4
CONCLUSION
Results of RAC soil sample analysis and confirmatory split soil sample analysis by ORNL, show
that radionuclide concentrations are within applicable DOE guidelines. Based on the results of the
post-remedial-action data, which are confirmed by the verification assessment data, these radiological
measurements fall below the limits prescribed by DOE guidelines. It is concluded that the site
successfully meets the DOE remedial action objectives.
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of 226Ra in soil
above background levels,
averaged over a 100-m2
area
5 pCi/g averaged over the first 15 cm
of soil below the surface; 15 pCi/g
when averaged over 15-cm-thick soil
layers more than 15 cm below the
surface
Radionuclide con-
centrations in soil
for Hot Spot areas
Exposure to 222Rn
progeny
Maximum Permissible con-
centration of Ra226 in soil
above background level,
for areas less than 25 m2
Average annual radon
progeny concentration
(including background)
Ra226 concentrations, in any surface
or subsurface area less than 25 m2,
is below the guideline by a factor of
(1007A)'/2, where A is the area ofthe
elevated region
0.03 WL
(US DOE 1990a)
6
Table 2. Results of ORNL analysis of the RAC soil samples from
248 Uranium Drive, Monticello, Utah (MS00315-RS)
226Ra concentration (pCi/g)
ORNL RAC
sample sample Depth ORNL RAC
No.a No^ (cm)
XI NAR 077 >15 1.8 2.4
X5 NAR 081 >15 2.0 2.4
" An X-type sample is a split of the sample taken by the remedial action contractor.
* Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated areas were
taken by the RAC, and these samples were blended to form a composite soil sample, which
represents an average over one of the verification areas.
7
REFERENCES
Geotech 1996. Property Completion Report for Monticello Vicinity Property Remedial Action for
DOE ID NO: MS00315-RS, Address: 248 Uranium Drive, Monticello, Utah 84535, RUST
Geotech, Grand Junction, Colorado, August 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment Group)
Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National Laboratory, Grand
Junction, Colorado.
US DOE 1990a. Verification and Certification Protocol for the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination and
Decommissioning Program. Revision 3, November 1990. U.S. Department of Energy, Washington,
D.C.
US DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision and Record
of Decision Summary. U.S. Department of Energy, Grand Junction Projects Office, Grand Junction,
Colorado.
DOE ID No.: MS-00328-MR
Property Address: 417 South First West Street
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech of Energy (DQE)
Ra-226 is z 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab I ]
Ra-226 is s 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2.
In-situ [ ] Lab [X]
Interior gamma is < 20 //R/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is < 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21.
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
W [ ] [ 1
[V] [ ] [ ]
[VI [ ] [ ]
[Mil [ ]
[] [X t ]
L*] [ ] [ ]
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
•Illlllll Ililllllllll
SFCERTIFED SFMS-00328
DOE ID No.: MS-00328-MR
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
tenda S. Busby ^ Date
Manager, Monticello Programs
Rust Geotech
DOE EVALUATION
\A Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Certification Official / Date
U.S. Department of Energy
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00328-MR
ADDRESS: 417 SOUTH FIRST WEST STREET
MONTICELLO, UTAH 84535
JULY 1996
Prepared for
U.S. Department of Energy
by
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
Wand^S. Busb/'
Manager, Monticello Programs
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.1.3 Radon Decay-Product Concentration (RDC) Measurement .... 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
i
DOE ID No.: MS-00328-MR
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Inclusion Survey Contractor. DOE reviewed
these evaluation results and determined that the property contained mill
tailings (residual radioactive material) exceeding DOE hot spot criteria.
The Remedial Action Contractor was notified of the inclusion of this
property into the MVP Project and was authorized by DOE to conduct
remedial action as required to bring the property into conformance with
EPA standards and DOE hot spot criteria.
1
DOE ID No.: MS-00328-MR
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
Property Address:
Property Owners:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
MS-00328-MR
Beginning 107.25 feet south of the NW
corner of Lot 3, Block 4, Monticello
Townsite Survey; south 107.25 feet, east
107.25 feet, north 107.25 feet, west
107.25 feet to beginning, County of San
Juan, State of Utah
417 South First West Street
Monticello, Utah 84535

Major Residential (MR)
Oak Ridge National Laboratory
February 21, 1991
Rust Geotech
February 8, 1995
Diamond Back Services, Inc.
9861 Titan Park Circle
Littleton, Colorado
August 22, 1995
September 25, 1995
Interior:
Exterior:
0 cubic yards
28 cubic yards
54 square meters (m2)
July 1996
2
DOE ID No.: MS-00328-MR
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of exterior residual radioactive
material (Appendix Figure 2.1). Interior assessed Area H (brick and
mortar) was excluded from remedial action based on gamma exposure
rates and pre-remedial radon decay-product concentration measurements
that did not exceed EPA standards, as discussed in the REA. Once
excavation was complete, the affected areas were resurveyed for possible
remaining residual radioactive material and, upon attaining satisfactory
results, were backfilled with uncontaminated material. The property was
restored to a physical condition comparable to that which existed prior to
remedial action activities.
2.2 Previously Unidentified Contamination
The radiological assessment (excluding assessed Area H) identified
28 cubic yards of contamination, ranging from 6 inches deep to 36 inches
high, within the property. The remedial action process included the
removal of approximately 28 cubic yards of residual radioactive material,
ranging from 12 inches deep to 36 inches high.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID No.: MS-00328-MR
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
Radiological surveys were conducted by the Remedial Action
Contractor during December 1991, January 1992, and August
1994 as described in the final REA dated February 1995.
Appendix Figure 2.1 shows the extent of assessed contamination
and identifies the areas recommended to undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the excavation were
collected. These samples were blended to form composite
samples representing the verification areas (Appendix Figure 2.1).
Additionally, in-situ measurements were taken for portions of V-1
and V-2.
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 12 to 19 microroentgens per
hour (juR/h), as indicated on Appendix Figure 2.1. The results of
analyses for radium-226 in 2 composite soil samples were 1.8 and
1.9 picocuries per gram (pCi/g), as indicated in Appendix
Table 3.1. In portions of Areas V-1 and V-2, contaminated
mortar, rock, and concrete were removed revealing
uncontaminated foundations. In-situ measurement results for
radium-226 in these areas ranged from 1.1 to 2.4 pCi/g (Appendix
Table 3.1).
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on measurements representing an annual average, the RDC
was 0.0046 working level (WL), as indicated in Appendix
Table 3.2. RDC measurements were taken before remediation of
the property. Appendix Figure 2.1 shows the measurement
location in the basement (the lowest habitable level of the
structure).
4
DOE ID No.: MS-00328-MR
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at 417 South First West Street, in
Monticello, Utah, is recommended for certification as required by DOE
guidelines, and the appropriate records should be documented.
Certification Data Summary
Applicability
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Standards
Shall not exceed 20 //R/h
above background.*
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Survey Results
Range for the basement
was 11 to 32 //R/h.
Annual average was
0.0046 WL.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
In-situ measurements
ranged from 1.1 to
2.4 pCi/g.**
Soil sample results were
1.8 and 1.9 pCi/g.**
*The background exposure rate is approximately 12 //R/h.
The background radium-226 concentration is approximately 2.0 pCi/g.
**The hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-00328-MR
4.0 APPENDIX
Appendix Tables:
Table 3.1 Post-Excavation Sample/Measurement Results
Table 3.2 Radon Decay-Product Concentration Measurement
Results
Appendix Figure:
Figure 2.1 Interior and Exterior Extent of Contamination -
RADIOLOGICAL AS-BUILT
SJW:05-28-96
MS-00328.MR WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00328-MR
Address: 417 South First West Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range Gc/R/h) Ticket No. Method" (pCi/g)
V-1 13-18 NCL 720 OCS 1.8
V-1 13-18 DS 2.0
V-2 15-19 NCL 721 OCS 1.9
V-2 15-19 DS 1.1
V-2 15-19 DS 1.1
V-2 15-19 DS 2.4
See Appendix Figure 2.1 for the verification areas.
"OCS = Opposed Crystal System; DS = Delta Scanner
7
Table 3.2
Radon Decay-Product Concentration Measurement Results
DOE ID No.: MS-00328-MR
Address: 417 South First West Street, Monticello, Utah
Instrument Type: Landauer Radtrak Detector
Detector
Number Start Date End Date"
Radon
Concentration
(pCi/L)
Working
Level
3729875
3729924
3729900
07-20-93
07-20-93
07-20-93
06-13-94
06-13-94
06-13-94
0.94
0.87
0.95
0.0047
0.0044
0.0048
Annual Average: 0.0046
See Appendix Figure 2.1 for the measurement location.
' The detectors placed at this property were retrieved 7 days early. The results are
valid since the remaining measurement days would require a reading 167 times
higher than the average for the previous measurement period to exceed an annual
average of 0.02 working level.
8
10
' 30
12 14 16
~i—i—r
18 20 22 24 26 28 30 32 34 36 38 40
30
28
26
24
22
20 -
18
16
i—T
UJ
UJ or
i—
to
CO
UJ
to cc
3
o
00
[6]
18
r 6
V-1
12-15 13-18
18
V-1
13-18
z
D
SPLIT LEVEL
BRICK HOUSE
11-16
W/BASEMENT
SEE DETAIL A
ATTACHED
GARAGE
14
[6]
L.
14-15
36
V-2
15-19
14-15
J
12
Y
SCALE IN FEET
20 10 0 20 40
M:\FAS\033\0003\RM00328V 06/18/96 09:04am T50780
RDC
17-32
BASEMENT
11-14
DETAIL A
NOT TO SCALE
NORTH
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT. UTILITY LOCATION PLAT, OR OTHER IMPROVEMENT SURVEY
PLAT AND IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE. BUILDING. OR OTHER FUTURE IMPROVEMENT LINES.
10
®
®
rv.-TTi
Lv.vj
12-15
12
v-1
16-17
(RDC)
[12]
-X-
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN /zR/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST —REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE-RATE RANGE
RADON DECAY-PRODUCT CONCENTRATION
MEASUREMENT LOCATION
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
HEIGHT IN INCHES OF ASSESSED CONTAMINATED
FLAGSTONE, ROCK AND CONCRETE CURB
REMOVED AND REPLACED
ASSESSED AREA H (BRICK AND MORTAR)
WAS EXCLUDED FROM REMEDIAL ACTION
RADIOLOGICAL AS-BUILT
FIGURE 2.1
INTERIOR AND EXTERIOR EXTENT OF CONTAMINATION
RCSI0CNCC-N0. or OCCUPANTS
NON-RESID£NCE-UAH-HRS./«K.
INSTRUMENT NO.
SURVEY OMC
VERIFICATION
CK. A.C. APP.
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE. COLORADO
DRAVN
CHEOKEO^foJ
PROJ. ENCTl.
SUBMITTED
417 SOUTH FIRST WEST STREET
MONTICELLO, UTAH
Rust Qeotech
tWHtMpjCw
APPROVAL OOE OATE
00t"",° MS00328-MR
owc.No. 3-BQQ328-V1 ,HT 1 of 1
28
26
24
22
20
18
1 6
1 4
1 2
10
10 12 1 4 1 6 18 20 22 24 26 28 30 32 34 36 38 40
OAK RIDGE NATIONAL LABORATORY
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
FOR THE U.S. DEPARTMENT OF ENERGY
PHONE: [phone]
FAX: [phone]
2597 BK Road
GRAND JUNCTION. COLORADO 81503
MAR 2 5 mi
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by the U.S.
Department of Energy for Residual Radioactive Material at Formerly Utilized Sites Remedial
Action Program (FUSRAP) and Remote Surplus Facilities Management Program Sites (SFMP)
[Revision 2, March 1987]. This evaluation is based on an independent verification review of the
Remedial Action Contractor's completion report and independent field verification.
This recommendation is based upon the Independent Verification Contractor's assessment of the
226Ra concentration in the soil, indoor radon daughter concentration, and indoor gamma exposure
rates at this property.
This property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
MS00328-MR
417 South 1st West Street
Monticello. Utah 84535

Location Number:
Location Address:
Property Owner:
Owner Address:
Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE B INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
417 SOUTH 1ST WEST STREET
MONTICELLO, UTAH (MS00328-MR)
M. K. Jensen
March 1997
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81503
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES v
LIST OF FIGURES v
ACKNOWLEDGMENTS vii
ABSTRACT viii
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
RAC SURVEY RESULTS 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
ORNL SURVEY RESULTS 6
Gamma Measurements 6
Soil Sample Analysis 6
CONCLUSION 6
REFERENCES 8
ii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 4
2. Results of ORNL and the RAC analyses of soil samples from 417 South 1st West Street,
Monticello, Utah (MS00328-MR) 5
LIST OF FIGURES
1. Property Map 7
v
ACKNOWLEDGMENTS
Research for this project was sponsored by the U.S. Department of Energy, Office of Environ-
mental Restoration, Southwestern Area Programs. The author wishes to acknowledge A. R. Jones
and T. L. Meyer for technical reviews.
vii
ABSTRACT
In 1980, the site of a vanadium and uranium mill at Monticello, Utah, was accepted into the
U.S. Department of Energy (DOE) Surplus Facilities Management Program, with the objectives of
restoring the government-owned mill site to safe levels of radioactivity, disposing of or containing
the tailings in an environmentally safe manner, and performing remedial actions on off-site (vicinity)
properties that had been contaminated by radioactive material resulting from mill operations. During
1995, the Remedial Action Contractor (RAC) designated by DOE, performed remedial action on the
vicinity property at 417 South 1st West Street, Monticello, Utah. The Environmental Technology
Section (ETS) of Oak Ridge National Laboratory was assigned the responsibility of verifying the
data supporting the adequacy of remedial action and confirming the site's compliance with DOE
guidelines. ETS performed an independent field verification at this site. The ETS found that the site
successfully meets the DOE remedial action objectives. Procedures used by ETS are described in
the Environmental Technology Section Procedures Manual (ORNL 1993).
viii
1
RESULTS OF THE TYPE B INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 417 SOUTH 1ST WEST STREET
MONTICELLO, UTAH (MS00328-MR)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the United States (U.S.) government through
the Defense Plant Corporation to provide vanadium during World War U. Various government
agencies operated the mill until 1947. In 1948, the Atomic Energy Commission (AEC) obtained the
mill and operated it under contract through 1959 to provide both uranium and vanadium. Mill
operations were terminated on January 1, 1960. In 1961, the mill tailings piles were leveled and
graded, covered with rock and soil, and seeded with native grasses. During 1974 and 1975, the ore
stockpiles were removed from the site and the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city of
Monticello, in San Juan County, Utah. The site is bordered on the south and southeast by land held
by the U.S. Bureau of Land Management. Other boundaries are the city of Monticello and private
property.
During the AEC era, the mill processed approximately one million tons of uranium ore.
Vanadium and uranium were the only substances extracted in the milling process. Other constituents
of the ore remained in the tailings and were not separated prior to disposal. During the years of
active mill operation, the mill tailings were normally moist, so erosion was minimal. However,
throughout the mill's operating period, area residents used these tailings as fill material and as
aggregate in mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy (DOE) initiated
the Surplus Facilities Management Program (SFMP) in 1978 to ensure the safe caretaking and
decommissioning of government facilities that had been retired from service but still had radioactive
contamination. In 1980, the mill site at Monticello was accepted into the SFMP, and the Monticello
Remedial Action Project (MRAP) was established to restore the government-owned mill site to safe
levels of radioactivity, to dispose of or contain the tailings in an environmentally safe manner, and
to perform remedial actions on off-site (vicinity) properties that had been contaminated by
radioactive material resulting from mill operations. The Monticello mill site and the tailings remain
in the custody of the DOE Grand Junction, Colorado, Projects Office. In 1983, remedial actions for
vicinity properties were separated from MRAP with establishment of the Monticello Vicinity
Properties (MVP) Project (US DOE 1990b).
* The verification of remedial action was performed by members of the Environmental Technology Section of the Health Sciences Research
Division at Oak Ridge National Laboratory under DOE contract DE-AC05-96OR22464 with Lockheed Martin Energy Research Corp.
2
During 1995, the Remedial Action Contractor (RAC) designated by DOE, performed remedial
action on the vicinity property that is the subject of this report, a private residence located at 417
South 1st West Street, Monticello, Utah. The remedial action plan required excavation of all exterior
contamination, backfilling with uncontaminated material, and restoration to a condition comparable
to that which existed prior to remedial action (Geotech 1996). When the excavation stage was
completed the property was resurveyed, including soil sampling, by the RAC and by an independent
contractor to verify the data supporting the adequacy of remedial action and to confirm the site's
compliance with DOE guidelines.
The Environmental Technology Section (ETS) of Oak Ridge National Laboratory (ORNL) has
been designated the Independent Verification Contractor for the 417 South 1st West Street site.
ORNL conducts independent Type B verifications on 10% of the Monticello vicinity properties.
MS00328 was selected for Type B verification. This report describes the methods and results of the
verification surveys.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available documentation
adequately and accurately describes the post-remedial-action radiological conditions of the entire
property that is to be certified and (2) that the remedial action reduced contamination to below
applicable DOE guidelines (US DOE 1990a).
Document Reviews
Review of the RAC property completion report (Geotech 1996) indicates the property was
remediated as evaluated by DOE on the basis of U.S. Environmental Protection Agency standards
(US DOE 1990a) and that excess residual radioactive materials were present. Thus it was
appropriate to designate this property for remedial action.
The pre-remedial-action survey performed by Geotech identified 28 yd3 of mill tailings 6 inches
deep to 36 inches high. During the actual removal process, a total of 28 yd3 of contaminated earth
and radioactive material, 12 inches deep to 36 inches high, were removed from a 54 m2 area.
The RAC performed a post-excavation survey prior to backfilling of the excavated areas. This
survey consisted of gamma scans with a scintillometer of the ground-level and basement of the
building, a surface scan of the exterior, and soil sampling. Samples representative of the bottom 15-
cm (6-in.) soil layers of two excavated areas were collected and blended to form representative
composite soil samples for each verification area. In addition, in-situ delta measurements were
performed where soil samples could not be taken to estimate 226Ra-in-soil concentrations.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation levels have
not been subtracted. Similarly, background concentrations have not been subtracted from radionu-
clide concentrations in soil samples. Applicable DOE guidelines for protection against radiation are
given in Table 1.
RAC SURVEY RESULTS
Gamma Measurements
Gamma exposure rate measurements taken by the RAC over the ground-level of the residence
ranged from 11 to 16 /uR/h. Readings in the basement ranged from 11 to 32 pR/h. Elevated readings
in the basement were due to assessed area H contaminated mortar in the fireplace, which was ex-
cluded from remedial action. Exterior surface gamma measurements taken from the excavated areas
prior to backfilling ranged from 13 to 19 pR/h.
Soil Sample Analysis
Prior to backfilling, the RAC collected soil samples representative of the excavated areas from
the bottom 15-cm (6-in.) soil layers. These samples were blended to form composite soil samples
representative of an average over the two exterior verification areas. The RAC's analysis of these
samples showed 226Ra concentrations ranging from 1.8 to 1.9 pCi/g in the composite sample. ORNL
ETS obtained one of these samples and performed a confirmatory analysis which showed a 226Ra
concentration of 2.2 pCi/g. These values are below the DOE guideline of 15 pCi/g for soil layers
>15 cm below the surface (Table 1). Gamma ranges and/or soil sample results demonstrate
compliance to the DOE Hot Spot Guideline for areas < 25 m2 (Table 1). Results of the RAC and
ORNL soil sample analyses are given in Table 2.
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were determined by the
alpha-track method. To monitor radon levels, the RAC placed three Alpha-track detectors in the
basement ofthe residence located on this property prior to remediation for a period of approximately
one year (from July 20, 1993 to June 13, 1994). The IVC was not present during placement or
retrieval of the detectors. The average annual working level (WL) of radon progeny concentration,
as determined by the Tech./Ops-Landauer Corporation, was 0.0046, which is well below the 0.03-
WL guideline given in Table 1. As is noted in the completion report, the detectors were retrieved
seven days early. The JVC agrees with the RAC that due to the low WL value, the additional seven
days of exposure would not cause a significant change in the results and the WL would not exceed
the guideline value. The procedures and methods used to obtain the annual average WL are deemed
adequate and the results accurate by the IVC.
4
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of 226Ra in soil
above background levels,
averaged over a 100-m2 area
5 pCi/g averaged over the first 15 cm
of soil below the surface; 15 pCi/g
when averaged over 15-cm-thick soil
layers more than 15 cm below the
surface.
Radionuclide con-
centrations in soil
for Hot Spot areas
Exposure to 222Rn
progeny
Maximum permissible con-
centration of 226Ra in soil
above background level,
for areas less than 25m2.
Average annual radon proge-
ny concentration (including
background).
Ra226 concentration, in any surface or
subsurface area less than 25 m2, is
below the guideline of (100/A)'/2, where
A is the area of the elevated region.
0.03 WL
(US DOE 1990a)
5
Table 2. Results of ORNL and Geotech analyses of soil samples
from 417 South 1st West Street, Monticello, Utah (MS00328-MR)
^Ra concentration (pCi/$)
ORNL RAC
sample sample Depth
No. No.a (cm) Confirmatory ORNL Geotech
XI*
VIC
vmd
V2CC
vmd
NCL 720
NCL 720
NCL 721
>15
>15
>15
>15
>15
2.2
2.1
2.3
1.8
2.2
1.8
1.8
1.9
a Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated areas were
taken by the RAC. These samples were blended to form composite soil samples which
represent an average over the verification area.
h An X-type sample is a split of the sample taken by the RAC. ORNL performed a confirmatory
analysis of these samples.
c Composite samples collected by ORNL from approximately the same locations sampled by the
RAC.
d Individual samples collected by ORNL from the highest outdoor gamma exposure rate from the
verification area.
6
ORNL SURVEY RESULTS
Gamma Measurements
Measurements taken by ORNL over the ground surface in the excavated areas prior to
backfilling ranged from 13 to 17 uR/h (Figure 1).
Soil Sample Analysis
ORNL sampled the excavated areas prior to backfilling, collecting aliquots representative of
those areas from the bottom 15-cm (6-in.) soil layers. These samples were blended to form two
composite soil samples representative of an average over the exterior verification areas. ORNL's
analysis of these composite samples showed 226Ra concentrations of 2.1 and 1.8 pCi/g. These values
are below the DOE guideline values of 15 pCi/g for soil layers >15 cm below the surface (Table 1).
In addition, ORNL collected an individual soil sample at the high outdoor gamma in each of the
verification areas to show compliance to the Hot Spot Guideline. The analysis of these samples
showed 226Ra concentrations of 2.3 and 2.2 pCi/g. Results of ORNL sample analyses are given in
Table 2.
CONCLUSION
The results of RAC and ORNL soil sample analyses show that radionuclide concentrations are
within applicable DOE guidelines. Based upon the results of the post-remedial-action data, which
are confirmed by the verification assessment data, these radiological measurements fall below the
limits prescribed by DOE guidelines. It is concluded that the site successfully meets the DOE
remedial action objectives.
or
f— co
i— co
UJ
(—
CO
o
00
n r
V1 RDC
x „TW0 STORY
BRICK HOUSE
W/BASEMENT V2
x o X
X
V1 GARAGE
J L
107 FT.
N.
EXPLANATION
Concrete
Assessed
contamination
Excavated
22 orea
£DCJ
"vT
H
RDC
measurement
Area identifier &
Composite sample
Location of
HOG sample
| VI | 13-17 fiR/b
V2 | 13-17/iR/h
4
Jl
FEET
METERS
MS00328
417 SOUTH 1ST WEST STREET
MONTICELLO, UTAH
Figure 1. Property Map
8
REFERENCES
Geotech 1996, Property Completion Report for Monticello Vicinity Property Remedial Action for
DOE ID NO: MS00328-MR, Address: 417 South First West Street, Monticello, Utah 84535, Rust
Geotech, Grand Junction, Colorado, July 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment Group)
Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National Laboratory, Grand
Junction, Colorado.
US DOE 1990a. Verification and Certification Protocol for the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination and
Decommissioning Program. Revision 3, November 1990. U.S. Department of Energy, Washington,
D.C.
US DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision and Record
of Decision Summary. U.S. Department of Energy, Grand Junction Projects Office, Grand Junction,
Colorado.
DOE ID No.: MS-00338-MR
Property Address: 396 South First West Street
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech of Energy (DQE)
Ra-226 is <; 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [ ]
Ra-226 is < 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2.
In-situ [ ] Lab [ ]
Interior gamma is <, 20 /yR/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is < 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21.
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[ ] [ ] [X]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
[V] [ 1 [ ]
[ ] [ ] [y\
[V] [ ] I ]
M [ 1 [ 1
[ ] [XI t ]
[yl [ ] [ 1
COMMENTS: *Surface areas were verified on the basis of gamma exposure
rates that do not exceed 30 percent above normal background.
•Miiiiiiiin
SFCERTIFED llllllllll
SFMS-00338
DOE ID No.: MS-00338-MR
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
randa S. Busby ( / Date
Manager, Monticello Programs
Rust Geotech
DOE EVALUATION
[*] Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
CertificatiorrOTfi'cial
U.S. Department of Energy
Date
9cL
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
DOE ID NO.: MS-00338-MR
ADDRESS: 396 SOUTH FIRST WEST STREET
MONTICELLO, UTAH 84535
JUNE 1996
Prepared for
U.S. Department of Energy
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
FOR
by
Wanda S. Busby /
Manager, Monticello Programs
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
TABLE OF CONTENTS
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.1.3 Radon Decay-Product Concentration (RDC) Measurement .... 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
i
DOE ID No.: MS-00338-MR
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Inclusion Survey Contractor. DOE reviewed
these evaluation results and determined that the property contained mill
tailings (residual radioactive material) exceeding EPA standards. The
Remedial Action Contractor was notified of the inclusion of this property
into the MVP Project and was authorized by DOE to conduct remedial
action as required to bring the property into conformance with EPA
standards and DOE hot spot criteria.
1
DOE ID No.: MS-00338-MR
.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
Property Address:
Property Owners:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
MS-00338-MR
Lot 1, Block 6, Monticello Townsite Survey,
County of San Juan, State of Utah
396 South First West Street
Monticello, Utah 84535

Major Residential (MR)
Oak Ridge National Laboratory
November 6, 1992
Rust Geotech
September 12, 1994
Diamond Back Services, Inc.
9861 Titan Park Circle
Littleton, Colorado
May 1, 1995
August 7, 1995
Interior: 8 cubic yards
Exterior: 0 cubic yards
3 square meters (m2)
June 1996
DOE ID No.: MS-00338-MR
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of interior residual radioactive
material (Appendix Figure 2.1). Once removal was complete, the affected
area was resurveyed for possible remaining residual radioactive material
and, upon attaining satisfactory results, was reconstructed with
uncontaminated material. The property was restored to a physical
condition comparable to that which existed prior to remedial action
activities.
2.2 Previously Unidentified Contamination
The radiological assessment identified 8 cubic yards of contamination,
96 inches high, within the property. The remedial action process included
the removal of approximately 8 cubic yards of residual radioactive
material, 96 inches high.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID No.: MS-00338-MR
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by the Remedial Action
Contractor during April and August 1992, as described in the final
REA dated September 1994. Appendix Figure 2.1 shows the
extent of assessed contamination and identifies the area
recommended to undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to
reconstruction.
Interior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 15 to 17 microroentgens per
hour (//R/h) for the remediated portion of the ground floor, 11 to
16 //R/h for the rest of the ground floor, and 11 to 12 /;R/h for the
partial basement (Appendix Figure 2.1).
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on measurements representing an annual average, the RDC
was 0.0199 working level (WL), as indicated in Appendix
Table 3.1. Appendix Figure 2.1 shows the measurement location
in the partial basement (the lowest habitable level of the
structure). RDC measurements were started prior to remediation
of the property.
4
DOE ID No.: MS-00338-MR
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at 396 South First West Street, in
Monticello, Utah, is recommended for certification as required by DOE
guidelines, and the appropriate records should be documented.
Certification Data Summary
Applicability
Hahitable Structures
Exposure Rate:
Standards
Shall not exceed 20 //R/h
above background.*
Survey Results
Ranges were 15 to
17 //R/h for the
remediated portion of the
ground floor, 11 to
16 //R/h for the rest of
the ground floor, and 11
to 12 //R/h for the partial
basement.
Radon Decay-Product
Concentration:
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Annual average was
0.0199 WL.
Land
Radium-226 Concentration
in Surface Soil:
Shall not exceed
5 picocuries per gram
(pCi/g) above background
in the 15-cm surface
layer, averaged over
100 m2.
< 5 pCi/g above
background.
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 15 pCi/g
above background in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
< 15 pCi/g above
background.
*The background exposure rate is approximately 13 //R/h.
The hot spot criteria were met based on gamma scans.
5
DOE ID No.: MS-00338-MR
4.0 APPENDIX
Appendix Table:
Table 3.1 Radon Decay-Product Concentration Measurement
Results
Appendix Figure:
Figure 2.1 Interior Extent of Contamination - RADIOLOGICAL
AS-BUILT
RKJ:06-07-96
MS-00338.MR WP61
REV080195
6
Table 3.1
Radon Decay-Product Concentration Measurement Results
DOE ID No.: MS-00338-MR
Address: 396 South First West Street, Monticello, Utah
Instrument Type: Landauer Radtrak Detector
Radon
Detector Concentration Working
Number Start Date End Date (pCi/L) Level
3851567
3851417
3851458
10-10-94
10-10-94
10-10-94
09-27-95
09-27-95
09-27-95
4.05
3.84
4.04
0.0203
0.0192
0.0202
Annual Average: 0.0199
See Appendix Figure 2.1 for the measurement location.
7
42
40
38
36
34
32
30
28
26
24
22
20
18
16
14
12
10
12 1 6 18 20 22 24 26 28 30 32 36 38 40 44 46 48 5i
12-15 L3 SHED
2-15
GARAGE
12-15
ONE STORY
BRICK HOUSE
W/PARTIAL
BASEMENT
SEE DETAIL A
-a SHED
12-15
12-15
GROUND 12-15 SHED.
12-15 FLOOR
11-16
SILO
GARAGE
11-13 _. J
V- 1
15-17
GROUND FLOOR-
14-16
to
UJ
S
l/l ar
=5
o
[96](A
LV.VJ
12-15
v-1
6-17
(RDC)
[12]
BASEMENT
11-12
'RDC)
DETAIL A
NOT TO SCALE
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN /iR/h
ASSESSED AREA IDENTIFIER
AREA OF ASSESSED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
VERIFICATION AREA IDENTIFIER AND
EXPOSURE-RATE RANGE
RADON DECAY-PRODUCT CONCENTRATION
MEASUREMENT LOCATION
HEIGHT IN INCHES OF ASSESSED CONTAMINATED
BRICK WALLS REMOVED AND REPLACED
WEST FOURTH SOUTH STREET
RADIOLOGICAL AS-BUILT
FIGURE 2.1
INTERIOR EXTENT OF CONTAMINATION
L 30 15
SCALE IN FEET
30 60
X U.\FAS\03J\000J\RU00J38V 06/18/96 12:36pm T50760
_J I I I I I L
NORTH
I I L
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT, UTILITY LOCATION PLAT. OR OTHER IMPROVEMENT SURVEY
PLAT AND IS NOT TO 8E RELIED UPON FOR THE ESTABLISHMENT
OF FENCE. BUILDING. OR OTHER FUTURE IMPROVEMENT LINES.
J L
nitocMCf-HO areccu*M>n U.S. DEPARTMENT OF ENERGY
C4AND JUNCTION MOJtCtS OfTICl. COLORADO
396 SOUTH FIRST WEST STREET
MONTICELLO, UTAH
MS-00338-UR
» 3-C00338-VI ...1
12 14 16 IB 20 22 24 26 28 30 32 34 36 38 40 42 44 46 48 50
OAK RIDGE NATIONAL LABORATORY
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
FOR THE U.S. DEPARTMENT OF ENERGY
PHONE: [phone]
FAX: [phone]
POST OFFICE BOX 2567
GRAND JUNCTION, COLORADO 81502 MS 3 0 1935
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by the U.S.
Department of Energy for Residual Radioactive Material at Formerly Utilized Sites Remedial Action
Program (FUSRAP) and Remote Surplus Facilities Management Program Sites (SFMP) [Revision
2, March 1987]. This evaluation is based on an independent verification review of the Remedial
Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment of the
indoor radon daughter concentration and indoor gamma exposure rates at this property.
This property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
Location Number:
Location Address:
Property Owner:
Owner Address:
Tenant Name:
MS00338-MR
396 South First West Street
Monticello. Utah 84535

Same
Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
396 SOUTH FIRST WEST STREET
MONTICELLO, UTAH (MS00338-MR)
N. F. Kirby
August 1996
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Radon Measurement Results 3
CONCLUSION 3
REFERENCES 5
iii
LIST OF TABLES
Applicable guidelines for protection against radiation
IV
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site
Decommissioning Projects, U.S. Department of Energy. The author wishes to
acknowledge A. R. Jones and M. K. Jensen for technical reviews.
Vll
ABSTRACT
In 1980 the site of a vanadium and uranium mill at Monticello, Utah, was accepted
into the U.S. Department of Energy's (DOE's) Surplus Facilities Management Program,
with the objectives of restoring the government-owned mill site to safe levels of radio-
activity, disposing of or containing the tailings in an environmentally safe manner, and
performing remedial actions on off-site (vicinity) properties that had been contaminated
by radioactive material resulting from mill operations. During 1995, RUST Geotech, the
remedial action contractor designated by DOE, performed remedial action on the vicinity
property at 396 South First West Street, Monticello, Utah. The Environmental Technol-
ogy Section (ETS) of Oak Ridge National Laboratory was assigned the responsibility of
verifying the data supporting the adequacy of remedial action and confirming the site's
compliance with DOE guidelines. The ETS found that the site successfully meets the
DOE remedial action objectives. Procedures used by the ETS are described in the Envi-
ronmental Technology Section Procedures Manual (ORNL 1993).
ix
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 396 SOUTH FrRST WEST STREET
MONTICELLO, UTAH (MS00338-MR)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the U.S. government through the
Defense Plant Corporation to provide vanadium during World War II. Various govern-
ment agencies operated the mill until 1947. In 1948 the Atomic Energy Commission
(AEC) obtained the mill and operated it under contract through 1959 to provide both
uranium and vanadium. Mill operations were terminated on January 1, 1960. In 1961 the
mill tailings piles were leveled and graded, covered with rock and soil, and seeded with na-
tive grasses. During 1974 and 1975, the ore stockpiles were removed from the site, and
the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city
of Monticello, in San Juan County, Utah. The site is bordered on the south and southeast
by land held by the U.S. Bureau of Land Management. Other boundaries are the city of
Monticello and private property.
During the AEC era, the mill processed approximately one million tons of uranium
ore. Vanadium and uranium were the only substances extracted in the milling process.
Other constituents of the ore remained in the tailings and were not separated prior to dis-
posal. During the years of active mill operation, the mill tailings were normally moist, so
erosion was minimal. However, throughout the mill's operating period, area residents
used these tailings as fill material and as aggregate in mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy
(DOE) initiated the Surplus Facilities Management Program (SFMP) in 1978 to ensure
the safe caretaking and decommissioning of government facilities that had been retired
from service but still had radioactive contamination. In 1980 the mill site at Monticello
was accepted into the SFMP, and the Monticello Remedial Action Project (MRAP) was
established to restore the government-owned mill site to safe levels of radioactivity, to
dispose of or contain the tailings in an environmentally safe manner, and to perform reme-
dial actions on off-site (vicinity) properties that had been contaminated by radioactive ma-
terial resulting from mill operations. The Monticello mill site and the tailings remain in the
custody of the DOE Grand Junction, Colorado, Projects Office. In 1983 remedial actions
for vicinity properties were separated from MRAP with establishment of the Monticello
Vicinity Properties (MVP) Project (U.S. DOE 1990b).
*Tlie verification of remedial action was performed by members ofthe Environmental Assessment Group in the
Environmental Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE contract
DE-AC05-96OR22464 with Lockheed Martin Energy Research Corporation.
2
During 1995, RUST Geotech Inc. (Geotech), the remedial action contractor (RAC)
designated by DOE, performed remedial action on the vicinity property that is the subject
of this report, a single family residence located at 396 South First West Street, Monticello,
Utah. The remedial action plan required removal of all interior contamination. When the
remediation was completed, the property was resurveyed to ensure the removal of all con-
tamination and restored to a condition comparable to that which existed prior to remedial
action (Geotech 1996).
The DOE adopted a policy to assign an independent contractor to verify the data
supporting the adequacy of remedial action and to confirm the site's compliance with DOE
guidelines. The Environmental Technology Section (ETS) of Oak Ridge National Labor-
atory (ORNL) has been assigned the responsibility of this task at the 396 South First West
Street site. This report describes the methods and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available doc-
umentation adequately and accurately describes the post-remedial-action radiological
conditions of the entire property that is to be certified and (2) that the remedial action
reduced contamination to below applicable DOE guidelines (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1996) in-
dicates the property was remediated as evaluated by DOE on the basis of Environmental
Protection Agency standards and the DOE guidelines (DOE 1990a). Excess residual
radioactive materials were present, thus it was appropriate to designate this property for
remedial action.
The pre-remedial-action survey performed by Geotech identified 8 yd3 of mill tailings
96 inches high. During the actual removal process, a total of 8 yd3 of contaminated brick
and mortar containing uranium mill tailings, 96 inches high, were removed from a 3 m2
area.
A post-excavation survey was performed by Geotech prior to reconstruction. This
survey consisted of gamma scans with a scintillometer of the remediated verification area,
the remainder of the ground level of the structure, and the basement.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation
levels have not been subtracted. Applicable DOE guidelines for protection against
radiation are given in Table 1.
Gamma Measurements
Gamma exposure rate measurements taken by Geotech from the remediated portion
of the ground-level of the residence ranged from 15 to 17 uR/h, the remainder of the
ground floor ranged from 11 to 16 |iR/h. The basement had a gamma exposure range
of 11 to 12 uR/h. Exterior surface gamma measurements ranged from 12 to 15 uR/h.
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were deter-
mined by the Alpha-track method. To monitor radon levels, Geotech placed three alpha-
track detectors on the ground floor of the residence located on this property for a period
of approximately one year (from October 10, 1994 to September 27, 1995). These moni-
tors were in place during remedial action on this property. Results of Geotech's gamma
exposure rate measurement and RDC results show radionuclide concentrations are within
applicable DOE guidelines. The average annual working level (WL) of radon progeny
concentration, as determined by the Tech./Ops-Landauer Corporation, was 0.0199, which
is below the 0.03-WL guideline given in Table 1.
CONCLUSION
Based on the results of the post-remedial-action data, which are confirmed by the
verification assessment data, these radiological measurements fall below the limits pre-
scribed by DOE guidelines, lt is concluded that the site successfully meets the DOE
remedial action objectives.
4
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of 226Ra in soil
above background levels,
averaged over a 100-m2 area
5 pCi/g averaged over the
first 15 cm of soil below the
surface; 15 pCi/g when ave-
raged over 15-cm-thick soil
layers more than 15 cm
below the surface
Radionuclide con-
centrations in soil
for Hot Spot areas
Exposure to 222Rn
progeny
Maximum Permissible con-
centration of Ra226 in soil
above background level, for
areas less than 25 m2
Average annual radon proge-
ny concentration (including
background)
Ra concentrations, in any
surface or subsurface area
less than 25 m2, is below the
guideline by a factor of
(100/A)'7', where A is the
area of the elevated region
0.03 WL
(DOE 1990a)
5
REFERENCES
Geotech 1996. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00338-MR, Address: 396 South First West Street,
Monticello, Utah 84535, Geotech, Grand Junction, Colorado, June 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual. ORNL6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
U.S. DOE 1990a. Verification and Certification Protocol for the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination
and Decommissioning Program, Revision 3, November 1990. U.S. Department of
Energy, Washington, D.C.
U.S. DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision
and Record of Decision Summary. U.S. Department of Energy, Grand Junction Projects
Office, Grand Junction, Colorado.
DOE ID No.: MS-00360-RS
Property Address: 132 East Third South Street
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech of Energy (DOE)
Ra-226 is <: 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [ ]
Ra-226 is ^ 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2.
In-situ [ ] Lab [X]
Interior gamma is s 20 //R/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is <. 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ 1 [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
[A [ 1 [ 1
[A I ] [ I
[Xl [ ] [ ]
[tf [ ] [ ]
[ ] [ 1
ly\ [ ] [ ]
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
II
SFCERTIFED Ililllllllll
SFMS-08359 ft
DOE ID No.: MS-00360-RS
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
A/anda S. Busby / / Wanda S. Busby ' / Date
Manager, Monticello Programs
Rust Geotech
DOE EVALUATION
[*] Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Ceflfification Official Date
U.S. Department of Energy
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
DOE ID NO.: MS-00360-RS
ADDRESS: 132 EAST THIRD SOUTH STREET
MONTICELLO, UTAH 84535
JUNE 1996
Prepared for
U.S. Department of Energy
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
FOR
by
Wanda S. Busby / /
Manager, Monticello Programs
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.1.3 Radon Decay-Product Concentration (RDC) Measurement .... 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
i
DOE ID No.: MS-00360-RS
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Remedial Action Contractor. DOE reviewed these
evaluation results and determined that the property contained mill tailings
(residual radioactive material) exceeding EPA standards. The Remedial
Action Contractor was notified of the inclusion of this property into the
MVP Project and was authorized by DOE to conduct remedial action as
required to bring the property into conformance with EPA standards and
DOE hot spot criteria.
1
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
Property Address:
Property Owner:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
DOE ID No.: MS-00360-RS
MS-00360-RS
Beginning 44.24 feet west of the NE corner
of Lot 3, Block 9, Monticello Townsite
Survey, Plat A, west 63 feet, south
107.25 feet, east 63 feet, north
107.25 feet to the beginning, County of
San Juan, State of Utah
132 East Third South Street
Monticello, Utah 84535

Residential Simple (RS)
Not applicable: inclusion requested by the
Remedial Action Contractor
November 29, 1993
Rust Geotech
September 9, 1994
Diamond Back Services, Inc.
9861 Titan Park Circle
Littleton, Colorado
June 26, 1995
September 6, 1995
Interior: 0 cubic yards
Exterior: 121 cubic yards
327 square meters (m2)
June 1996
2
DOE ID No.: MS-00360-RS
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of exterior residual radioactive
material (Appendix Figure 2.1). Once excavation was complete, the
affected areas were resurveyed for possible remaining residual radioactive
material and, upon attaining satisfactory results, were backfilled with
uncontaminated material. The property was restored to a physical
condition comparable to that which existed prior to remedial action
activities.
2.2 Previously Unidentified Contamination
The radiological assessment identified contamination, 6 inches deep,
within the property. The quantity of contamination for this property was
not specified because it was assessed as part of Group 19. The remedial
action process included the removal of approximately 121 cubic yards of
residual radioactive material, ranging from 6 to 24 inches deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID No.: MS-00360-RS
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by the Remedial Action
Contractor during May 1993, as described in the final REA dated
September 1994. Appendix Figure 2.1 shows the extent of
assessed contamination and identifies the areas recommended to
undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the excavation were
collected. These samples were blended to form composite
samples representing the verification areas (Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 13 to 19 microroentgens per
hour (//R/h), as indicated on Appendix Figure 2.1. The results of
analyses for radium-226 in four composite soil samples ranged
from 1.9 to 4.5 picocuries per gram (pCi/g), as indicated in
Appendix Table 3.1.
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on the DOE-approved abbreviated-measurement method,
the RDC was 0.0103 working level (WL), as indicated in Appendix
Table 3.2. Appendix Figure 2.1 shows the measurement location
on the ground floor (the lowest habitable level of the structure).
The RDC measurements were completed before remediation of the
property.
4
DOE ID No.: MS-00360-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at 132 East Third South Street, in
Monticello, Utah, is recommended for certification as required by DOE
guidelines, and the appropriate records should be documented.
Certification Data Summary
Applicability
Habitahle Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Standards
Shall not exceed 20 //R/h
above background.*
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Survey Results
Range for the ground
floor was 12 to 13 //R/h.
Average was 0.0103 WL,
based on the DOE-
approved abbreviated-
measurement method.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
< 5 pCi/g above
background.**
Soil sample results
ranged from 1.9 to
4.5 pCi/g.**
*The background exposure rate is approximately 15 //R/h.
The background radium-226 concentration is approximately 2.0 pCi/g.
* *The hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-00360-RS
4.0 APPENDIX
Appendix Tables:
Table 3.1 Post-Excavation Sample/Measurement Results .
Table 3.2 Radon Decay-Product Concentration Measurement
Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
MRW:05-24-96
MS-00360.RS WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00360-RS
Address: 132 East Third South Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (jwR/h) Ticket No. Method" (pCi/g)
V-1 14-18 NCH 069 OCS 4.5
V-2 14-18 NCH070 OCS 1.9
V-3 14-19 NCH 071 OCS 3.6
V-4 15-18 NCH 072 OCS 4.5
See Appendix Figure 2.1 for the verification areas.
•OCS = Opposed Crystal System
7
Table 3.2
Radon Decay-Product Concentration Measurement Results
DOE ID No.: MS-00360-RS
Address: 132 East Third South Street, Monticello, Utah
Instrument Type: Landauer Radtrak Detector
Detector
Number Start Date End Date
Radon
Concentration
(pCi/L)
Working
Level
3973924
3973892
3973907
03-08-95
03-08-95
03-08-95
06-07-95
06-07-95
06-07-95
1.86
2.42
1.90
0.0093
0.0121
0.0095
Average: 0.0103
See Appendix Figure 2.1 for the measurement location.
8
1
30
0
28
26
24
22 -
20 -
18
16
1 4
12
Y
10
x 1
12 1 4 16 18
i—r
20
T"
EAST THIRD SOUTH STREET
LLL ///
22 24 26 28
T
X
SCALE IN FEET
20 10 0 20 40
M:\FAS\033\0003\RM00360V 05/30/96 10:21om T50780
J I I I I I I
NORTH
V--;
V-4
15-18
r::.
V-1 13-15
14-18
RDC
1 2
L ONE STORY
FRAME HOUSE
12-13 v-4
15-18
4-19
13-15 fit
FRAME
SHED
14-1* 24
• • o
V-2
14-18
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT, UTILITY LOCATION PLAT, OR OTHER IMPROVEMENT SURVEY
PLAT AND IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE, BUILDING, OR OTHER FUTURE IMPROVEMENT LINES.
30
i—T
nv.vTI
12-15
12
V-1
16-17
(RDC)
32 34 36 38
n—T
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN fxR/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE-RATE RANGE
RADON DECAY-PRODUCT CONCENTRATION
MEASUREMENT LOCATION
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
40
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
PESIMNCE-NO. OT OCCUPANTS
HOH-RESIOCNCC-MAN-MRS./WK.
INSTRUMENT HO.
SURVEY DATC
VERIFICATION
ar CK. A.C. APP.
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE. COLORADO
ORAWU-^ 132 EAST THIRD SOUTH STREET
MONTICELLO, UTAH
Rust Qeotech
AHMTnl nlitfn mmm
"DATF" APPROVAL DOE -FATT
DOCIONO. MS-00360-RS
D.C.NQ. 3-BQQ360-V1 SHI 1 nr 1
30
28
26
24
22
20
18
16
14
12
10
0 12 1 4 1 6 18 20 22 24 26 28 30 32 34 36 38 40
OAK RIDGE NATIONAL LABORATORY PHONE: [phone]
FAX: [phone] MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
FOR THE U.S. DEPARTMENT OF ENERGY
POST OFFICE BOX 2567
GRAND JUNCTION, COLORADO 61502
NOV 2 7 1996
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by the U.S.
Department of Energy for Residual Radioactive Material at Formerly Utilized Sites Remedial
Action Program (FUSRAP) and Remote Surplus Facilities Management Program Sites (SFMP)
[Revision 2, March 1987]. This evaluation is based on an independent verification review of the
Remedial Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment of the
226Ra concentration in the soil, indoor radon daughter concentration, and indoor gamma exposure
rates at this property.
This property is recommended for certification by the U.S. Department of Energy.
Location Number: MS0036O-RS
Location Address: 132 East 3rd South Street
Monticello. Utah 84535
Property Owner:

Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
132 EAST 3RD SOUTH STREET
MONTICELLO, UTAH (MS00360-RS)
M. K. Jensen
November 1996
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 3
REFERENCES 6
iii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 4
2. Results of ORNL analysis of RAC soil samples from 132 East 3rd South Street, Monticello,
Utah (MS00360-RS) : 5
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site Decommissioning
Projects, U.S. Department of Energy. The author wishes to acknowledge A. R. Jones and S. M.
Smith for technical reviews.
vii
ABSTRACT
In 1980, the site of a vanadium and uranium mill at Monticello, Utah, was accepted into the
U.S. Department of Energy (DOE) Surplus Facilities Management Program, with the objectives of
restoring the government-owned mill site to safe levels of radioactivity, disposing of or containing
the tailings in an environmentally safe manner, and performing remedial actions on off-site (vicinity)
properties that had been contaniinated by radioactive material resulting from mill operations. During
1995, the Remedial Action Contractor (RAC), designated by DOE, performed remedial action on
the vicinity property at 132 East 3rd South Street, Monticello, Utah. The Environmental Technology
Section (ETS) of Oak Ridge National Laboratory was assigned the responsibility of verifying the
data supporting the adequacy of remedial action and confimiing the site's compliance with DOE
guidelines. The ETS found that the site successfully meets the DOE remedial action objectives.
Procedures used by the ETS are described in the Environmental Technology Section Procedures
Manual (ORNL 1993).
ix
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 132 EAST 3RD SOUTH STREET
MONTICELLO, UTAH (MS00360-RS)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the United States (U.S.) government through
the Defense Plant Corporation to provide vanadium during World War II. Various government
agencies operated the mill until 1947. In 1948, the Atomic Energy Commission (AEC) obtained the
mill and operated it under contract through 1959 to provide both uranium and vanadium. Mill
operations were terminated on January 1, 1960. In 1961, the mill tailings piles were leveled and
graded, covered with rock and soil, and seeded with native grasses. During 1974 and 1975, the ore
stockpiles were removed from the site and the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city of
Monticello, in San Juan County, Utah. The site is bordered on the south and southeast by land held
by the U.S. Bureau of Land Management. Other boundaries are the city of Monticello and private
property.
During the AEC era, the mill processed approximately one million tons of uranium ore. Vana-
dium and uranium were the only substances extracted in the milling process. Other constituents of
the ore remained in the tailings and were not separated prior to disposal. During the years of active
mill operation, the mill tailings were normally moist, so erosion was minimal. However, throughout
the mill's operating period, area residents used these tailings as fill material and as aggregate in
mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy (DOE) initiated
the Surplus Facilities Management Program (SFMP) in 1978 to ensure the safe caretaking and de-
commissioning of government facilities that had been retired from service but still had radioactive
contamination. In 1980, the mill site at Monticello was accepted into the SFMP, and the Monticello
Remedial Action Project (MRAP) was established to restore the government-owned mill site to safe
levels of radioactivity, to dispose of or contain the tailings in an environmentally safe manner, and
to perform remedial actions on off-site (vicinity) properties that had been contaminated by
radioactive material resulting from mill operations. The Monticello mill site and the tailings remain
in the custody of the DOE Grand Junction, Colorado, Projects Office. In 1983, remedial actions for
vicinity properties were separated from MRAP with establishment of the Monticello Vicinity
Properties (MVP) Project (US DOE 1990b).
"The verification of remedial action was performed by meembers of the Environmental Assessment Group in the Environmental Technology
Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE contract DE-AC05-96OR22464 with Lockheed Martin
Energy Research Corporation.
2
During 1995, the Remedial Action Contractor (RAC) designated by DOE, performed remedial
action on the vicinity property that is the subject of this report, a single family residence located at
132 East 3rd South Street, Monticello, Utah. The remedial action plan required excavation of all
exterior contamination. When the excavation was completed the property was resurveyed, including
soil sampling, to ensure the removal of all contamination, backfilled with uncontaminated material,
and restored to a condition comparable to that which existed prior to remedial action (Geotech 1996).
The DOE adopted a policy to assign an independent contractor to verify the data supporting the
adequacy of remedial action and to confirm the site's compliance with DOE guidelines. The
Environmental Technology Section (ETS) of Oak Ridge National Laboratory (ORNL) has been
assigned the responsibility of this task at the 132 East 3rd South Street site. This report describes
the methods and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available documentation
adequately and accurately describes the post-remedial-action radiological conditions of the entire
property that is to be certified and (2) that the remedial action reduced contamination to below
applicable DOE guidelines (US DOE 1990a).
Document Reviews
Review of the RAC property completion report (Geotech 1996) indicates the property was
remediated as evaluated by DOE on the basis of U.S. Environmental Protection Agency standards
and the DOE guidelines (US DOE 1990a). Excess residual radioactive materials were present, thus
it was appropriate to designate this property for remedial action.
This property was assessed as part of Group 19, therefore, the quantity of material assessed is
not available. During the actual removal process a total of 121 yd3 of contaminated earth and
uranium mill tailings, 6 to 24 inches deep, were removed from a 327 m2 area.
The RAC performend a post-excavation survey prior to backfilling the excavated areas. This
survey consisted of gamma scans with a scintillometer of the ground level of the structure, a surface
scan ofthe exterior, and soil sampling. Samples representative of the bottom 15-cm (6-in.) soil
layers of four excavated verification areas were collected and blended to form representative
composite soil samples for each verification area.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation levels have
not been subtracted. Similarly, background concentrations have not been subtracted from radionu-
clide concentrations in soil samples. Applicable DOE guidelines for protection against radiation are
given in Table 1.
Gamma Measurements
Gamma exposure rate measurements taken by the RAC at the ground-level of the residence
ranged from 12 to 13 uR/h. Exterior surface gamma measurements taken from the excavated areas
prior to backfilling ranged from 14 to 19 pR/h.
Soil Sample Analysis
Prior to backfilling, the RAC collected soil samples representative of the excavated areas from
the bottom 15-cm (6-in.) soil layers. These samples were blended to form composite soil samples
representative of an average over the four exterior verification areas. The RAC's analysis of these
samples showed 226Ra concentrations ranging from 1.9 to 4.5 pCi/g in the composite sample. ORNL
ETS obtained these samples and performed a confirmatory analysis which showed 226Ra
concentrations ranging from 2.4 to 4.5 pCi/g. These values are below the DOE guideline value of
15 pCi/g for soil layers >15 cm below the surface. Gamma ranges and/or soil sample results
demonstrate compliance to the DOE Hot Spot Guidelines for areas <25 m2 (Table 1). Results of the
RAC and ORNL soil sample analyses are given in Table 2.
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were determined by the
Alpha-track method before remediation of the property. To monitor radon levels, the RAC placed
three alpha-track detectors on the ground floor of the residence located on this property for a period
of approximately three months (from March 8,1995 to June 7,1995). The average annual working
level (WL) of radon progeny concentration, as determined by the TechVOps-Landauer Corporation,
was 0.0103, which is below the 0.03-WL guideline given in Table 1.
CONCLUSION
Results ofthe RAC soil sample analysis and confirmatory split soil sample analysis by ORNL
show that radionuclide concentrations are within applicable DOE guidelines. Based on the results
of the post-remedial-action data, which are confirmed by the verification assessment data, these
radiological measurements fall below the limits prescribed by DOE guidelines. It is concluded that
the site successfully meets the DOE remedial action objectives.
4
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Radionuclide con-
centrations in soil
for Hot Spot areas
Exposure to 222Rn
progeny
Maximum permissible
concentration of ^Ra in
soil above background
levels, averaged over a
100-m2 area
Maximum Permissible
concentration of Ra226 in
soil above background
level, for areas less than
25 m2
Average annual radon
progeny concentration
(including background)
5 pCi/g averaged over the first 15 cm
of soil below the surface; 15 pCi/g
when averaged over 15-cm-thick soil
layers more than 15 cm below the
surface
Ra226 concentrations, in any surface or
subsurface area less than 25 m2, is
below the guideline by a factor of
(lOO/A)*, where A is the area ofthe
elevated region
0.03 WL
(DOE 1990a)
5
Table 2. Results of ORNL analysis of RAC soil samples from
132 East 3rd South Street, Monticello, Utah (MS00360-RS)
226Ra concentration (pCi/g)
ORNL RAC
sample sample Depth ORNL RAC
No.° No/ (cm)
XI NCH 069 >15 4.5 • 4.5
X2 NCH 070 >15 2.4 1.9
X3 NCH 071 >15 2.9 3.6
X4 NCH 072 >15 3.5 4.5
° An X-type sample is a split of the sample taken by the remedial action contractor.
* Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated areas were
taken by the RAC, and these samples were blended to form a composite soil sample, which
represents an average over one of the verification areas.
6
REFERENCES
Geotech 1996. Property Completion Report for Monticello Vicinity Property Remedial Action for
DOE ID NO: MS00360-RS, Address: 132 East Third South Street, Monticello, Utah 84535, Rust
Geotech, Grand Junction, Colorado, June 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment Group)
Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National Laboratory, Grand
Junction, Colorado.
US DOE 1990a. Verification and Certification Protocol for the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination and
Decommissioning Program. Revision 3, November 1990. U.S. Department of Energy, Washington,
D.C.
US DOE 1990b. Monticello Mill Tailings Site Declaration for the Record ofDecision and Record
of Decision Summary. U.S. Department of Energy, Grand Junction Projects Office, Grand Junction,
Colorado.
DOE ID No.: MS-00396-RS
Property Address: 196 West Third South Street
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech of Energy (DOE)
Ra-226 is < 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [ ]
Ra-226 is <; 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2.
In-situ [ ] Lab [X]
Interior gamma is < 20 //R/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is < 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21,
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
[>l [ ] t 1
M I ) i ]
M [ ] [ ]
[ ] IX [ )
[X] [ ] [ ]
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
•llllllllll llllllllll
SFCERTIFED SFMS-09015
DOE ID No.: MS-00396-RS
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
/anda S/Busby Date
Manager, Monticello Programs
Rust Geotech
DOE EVALUATION
\y\ Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Certification Official Date
U.S. Department of Energy
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00396-RS
ADDRESS: 196 WEST THIRD SOUTH STREET
MONTICELLO, UTAH 84535
APRIL 1996
Prepared for
U.S. Department of Energy
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
by
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
TABLE OF CONTENTS
Section Page
1.0 SUMMARY . . . 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.1.3 Radon Decay-Product Concentration (RDC) Measurement .... 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
DOE ID No.: MS-00396-RS
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Inclusion Survey Contractor. DOE reviewed
these evaluation results and determined that the property contained mill
tailings (residual radioactive material) exceeding DOE hot spot criteria.
The Remedial Action Contractor was notified of the inclusion of this
property into the MVP Project and was authorized by DOE to conduct
remedial action as required to bring the property into conformance with
EPA standards and DOE hot spot criteria.
1
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
Property Address:
Property Owner:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
DOE ID No.: MS-00396-RS
MS-00396-RS
Location No. M-116; Beginning at the SW
corner of Lot 2, Block 15, Monticello
Townsite Survey; north 75 feet, east
110 feet, south 75 feet, west 110 feet to
the point of beginning, County of San Juan,
State of Utah
196 West Third South Street
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
April 3, 1990
Rust Geotech
October 21, 1991
Crowley Construction, Inc.
East Route 63 HC Box 66
Monticello, Utah
July 28, 1992
August 26, 1992
Interior: 0 cubic yards
Exterior: 0.4 cubic yards
2.2 square meters (m2)
April 1996
2
DOE ID No.: MS-00396-RS
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of exterior residual radioactive
material (Appendix Figure 2.1). Once excavation was complete, the
affected area was resurveyed for possible remaining residual radioactive
material and, upon attaining satisfactory results, was backfilled with
uncontaminated material. The property was restored to a physical
condition comparable to that which existed prior to remedial action
activities.
2.2 Previously Unidentified Contamination
The radiological assessment identified contamination, 6 inches deep,
within the property. The quantity of contamination for this property was
not specified because it was assessed as part of Block MS-09015-BK.
The remedial action process included the removal of approximately
0.4 cubic yards of residual radioactive material, 6 inches deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID No.: MS-00396-RS
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by the Remedial Action
Contractor during August 1991, as described in the final REA
dated October 1991. Appendix Figure 2.1 shows the extent of
assessed contamination and identifies the area recommended to
undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the excavation were
collected.
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 11 to 15 microroentgens per
hour OwR/h), as indicated on Appendix Figure 2.1. The result of
analysis for radium-226 in one composite soil sample was
1.7 picocuries per gram (pCi/g), as indicated in Appendix
Table 3.1.
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on measurements representing an annual average, the RDC
was 0.0042 working level (WL), as indicated in Appendix
Table 3.2. Appendix Figure 2.1 shows the measurement location
on the ground floor (the lowest habitable level of the structure).
4
DOE ID No.: MS-00396-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at 196 West Third South Street, in
Monticello, Utah, is recommended for certification as required by DOE
guidelines, and the appropriate records should be documented.
Certification Data Summary
Applicability
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Standards
Shall not exceed 20 //R/h
above background.*
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Survey Results
Range for the ground
floor was 12 to 13 jt/R/h.
Annual average was
0.0042 WL.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
< 5 pCi/g above
background.**
Soil sample result was
1.7 pCi/g.**
*The background exposure rate is approximately 13 yR/h.
The background radium-226 concentration is approximately 2.0 pCi/g.
**The hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-00396-RS
4.0 APPENDIX
Appendix Table:
Table 3.1 Post-Excavation Sample/Measurement Results
Table 3.2 Radon Decay-Product Concentration Measurement
Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
SJW:03-14-96
MS-00396-RS WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00396-RS
Address: 196 West Third South Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range Ot/R/h) Ticket No. Method" (pCi/g)
V-1 13-15 NAT 849 OCS 1.7
See Appendix Figure 2.1 for the verification area.
"OCS = Opposed Crystal System
7
Table 3.2
Radon Decay-Product Concentration Measurement Results
DOE ID No.: MS-00396-RS
Address: 196 West Third South Street, Monticello, Utah
Instrument Type: Landauer Radtrak Detector
Detector
Number Start Date End Date
Radon
Concentration
(pCi/L)
Working
Level
3892325
3892284
3892232
08-17-94
08-17-94
08-17-94
07-24-95
07-24-95
07-24-95
0.75
0.83
0.90
0.0038
0.0042
0.0045
Average: 0.0042
See Appendix Figure 2.1 for the measurement location.
8
10
30
28
26
24
22
20
18
1 6
1 4
12
Y
10
12
LU
LU
CC
h-
co
i— co
LU
o o
LU
CO
o
CO
14 16 18 20 22 24 26 28
V-1
13-15
=7*
•
11-14
Q O (RDC)
ONE STORY
FRAME HOUSE
12-13
O
-14
777 TT7 777"
WEST THIRD SOUTH STREET
X
SCALE IN FEET
20 10 0 20 40
M:\FAS\033\0003\RM00396V 04/10/96 1:09pmT50780
I I
o
NORTH
I I I
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT. UTILITY LOCATION PLAT. OR OTHER IMPROVEMENT SURVEY
PLAT AND IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE, BUILDING, OR OTHER FUTURE IMPROVEMENT LINES.
30
©
<D
rv.vTi
LV.YJ
12-15
12
V-1
16-17
32 34 36 38
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN /iR/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE-RATE RANGE
RADON DECAY-PRODUCT CONCENTRATION
MEASUREMENT LOCATION
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
40
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
PESIOENCE-NO. OF OCCUPANTS
NON-KCSIOCNCC-UAN-HRS./WK.
tNSTRUUENT NO.
SURVEY OATE
CK. A.E. APP. NO. OATC
mi DRAWN
CHECKED
SUSUtTTEO
U.S. DEPARTMENT OF ENERGY
GRANO JUNCTION PROJECTS OFFICE. COLORADO
196 WEST THIRD SOUTH STREET
. MONTICELLO. UTAH
Rust Qeotech
»wmTini<u»nc«wr
OATC APPROVAL DOC
oocoNo. MS-00396-RS
O»C.NO. 3-B00396-V1 SHT 1 or 1
30
28
26
24
22
20
18
- 16
1 4
12
10
10 12 1 4 1 6 18 20 22 24 26 28 30 32 34 36 38 40
OAK RIDGE NATIONAL LABORATORY
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
FOR THE U.S. DEPARTMENT OF ENERGY
PHONE: [phone]
FAX: [phone]
POST OFFICE BOX 2567
GRAND JUNCTION, COLORADO 815Q2
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by
the U.S. Department of Energy for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program (FUSRAP) and Remote Surplus Facilities Management Program
Sites (SFMP) [Revision 2, March 1987]. This evaluation is based on an independent verifi-
cation review of the Remedial Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment of
the 226Ra concentration in the soil, indoor radon daughter concentration, and indoor gamma
exposure rates at this property.
This property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
Location Number: MS00396-RS
Location Address: 196 West 3rd South Street
Monticello, Utah 84535
Property Owner:

Tenant Name: Same
Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
196 WEST 3RD SOUTH STREET
MONTICELLO, UTAH (MS00396-RS)
S. M. Smith
June 1996
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEIXJMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 3
REFERENCES 6
iii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 4
2. Results of ORNL analysis of Geotech soil samples from 196 West 3rd South Street,
Monticello, Utah (MS00396-RS) 5
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site
Decommissioning Projects, U.S. Department of Energy. The author wishes to
acknowledge M. K. Jensen for analysis of soil samples and A. R. Jones for technical
reviews.
vii
ABSTRACT
In 1980 the site of a vanadium and uranium mill at Monticello, Utah, was accepted
into the U.S. Department of Energy's (DOE's) Surplus Facilities Management Program,
with the objectives of restoring the government-owned mill site to safe levels of radio-
activity, disposing of or containing the tailings in an environmentally safe manner, and
performing remedial actions on off-site (vicinity) properties that had been contaniinated
by radioactive material resulting from mill operations. During 1992, RUST Geotech, the
remedial action contractor designated by DOE, performed remedial action on the vicinity
property at 196 West 3rd South Street, Monticello, Utah. The Environmental Technology
Section (ETS) of Oak Ridge National Laboratory was assigned the responsibility of veri-
fying the data supporting the adequacy of remedial action and confirming the site's compli-
ance with DOE guidelines. The ETS found that the site successfully meets the DOE re-
medial action objectives. Procedures used by the ETS are described in the Environmental
Technology Section Procedures Manual (ORNL 1993).
ix
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 196 WEST 3RD SOUTH STREET
MONTICELLO, UTAH (MS00396-RS)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the U.S. government through the
Defense Plant Corporation to provide vanadium during World War II. Various govern-
ment agencies operated the mill until 1947. In 1948 the Atomic Energy Commission
(AEC) obtained the mill and operated it under contract through 1959 to provide both
uranium and vanadium. Mill operations were terminated on January 1, 1960. In 1961 the
mill tailings piles were leveled and graded, covered with rock and soil, and seeded with na-
tive grasses. During 1974 and 1975, the ore stockpiles were removed from the site, and
the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city
of Monticello, in San Juan County, Utah. The site is bordered on the south and southeast
by land held by the U.S. Bureau of Land Management. Other boundaries are the city of
Monticello and private property.
During the AEC era, the mill processed approximately one million tons of uranium
ore. Vanadium and uranium were the only substances extracted in the milling process.
Other constituents of the ore remained in the tailings and were not separated prior to dis-
posal. During the years of active mill operation, the mill tailings were normally moist so
erosion was minimal. However, throughout the mill's operating period, area residents
used these tailings as fill material and as aggregate in mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy
(DOE) initiated the Surplus Facilities Management Program (SFMP) in 1978 to ensure
the safe caretaking and decommissioning of government facilities that had been retired
from service but still had radioactive contamination. In 1980 the mill site at Monticello
was accepted into the SFMP, and the Monticello Remedial Action Project (MRAP) was
established to restore the government-owned mill site to safe levels of radioactivity, to
dispose of or contain the tailings in an environmentally safe manner, and to perform reme-
dial actions on off-site (vicinity) properties that had been contaminated by radioactive ma-
terial resulting from mill operations. The Monticello mill site and the tailings remain in the
custody of the DOE Grand Junction, Colorado, Projects Office. In 1983 remedial actions
for vicinity properties were separated from MRAP with establishment of the Monticello
Vicinity Properties (MVP) Project (U.S. DOE 1990b).
*The verification of remedial action was performed by members of the Environmental Assessment Group in the
Environmental Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE
contract DE-AC05-96OR22464 with Lockheed Martin Energy Research Corporation.
During 1992, RUST Geotech Inc. (Geotech), the remedial action contractor (RAC)
designated by DOE, performed remedial action on the vicinity property that is the subject
of this report, a private residence located at 196 West 3rd South Street, Monticello, Utah.
The remedial action plan required excavation of all exterior contamination. When the
excavation was completed, the property was resurveyed, including soil sampling, to ensure
the removal of all contamination, backfilled with uncontaminated material, and restored to
a condition comparable to that which existed prior to remedial action (Geotech 1994).
The DOE adopted a policy to assign an independent contractor to verify the data
supporting the adequacy of remedial action and to confirm the site's compliance with DOE
guidelines. The Environmental Technology Section (ETS) of Oak Ridge National Labor-
atory (ORNL) has been assigned the responsibility of this task at the 196 West 3rd South
Street site. This report describes the methods and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available doc-
umentation adequately and accurately describes the post-remedial-action radiological
conditions of the entire property that is to be certified and (2) that the remedial action
reduced contamination to below applicable DOE guidelines (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1996) in-
dicates the property was remediated as evaluated by DOE on the basis of Environmental
Protection Agency standards and the DOE guidelines (DOE 1990a). Excess residual
radioactive materials were present, thus it was appropriate to designate this property for
remedial action.
This property was assessed as part of Block MS-09015-BK, therefore, the quantity of
material assessed is not available. During the actual removal process, a total of 0.4 yd3 of
contaminated earth and uranium mill tailings, 6 inches deep, was removed from a 2.2 m2
area.
A post-excavation survey was performed by Geotech prior to backfilling the exca-
vated areas. This survey consisted of gamma scans with a scintillometer of the ground
level ofthe structure, a surface scan of the exterior, and soil sampling. Samples repre-
sentative of the bottom 15-cm (6-in.) soil layers of the excavated verification area were
collected and blended to form a representative composite soil sample for the verification
area.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation
levels have not been subtracted. Similarly, background concentrations have not been sub-
tracted from radionuclide concentrations in soil samples. Applicable DOE guidelines for
protection against radiation are given in Table 1.
Gamma Measurements
Gamma exposure rate measurements taken by Geotech at the ground-level of the resi-
dence ranged from 12 to 13 uR/h. Exterior surface gamma measurements taken from the
excavated area prior to backfilling ranged from 13 to 15 uR/h.
Soil Sample Analysis
Prior to backfilling, Geotech collected soil samples representative of the excavated
area from the bottom 15-cm (6-in.) soil layers. These samples were blended to form a
composite soil sample representative of an average over the exterior verification area.
Geotech's analysis of this sample showed a 226Ra concentration of 1.7 pCi/g. ORNL ETS
obtained this sample and performed a confirmatory analysis which showed a 226Ra con-
centration of 1.5 pCi/g. These values are below the EPA standard value of 15 pCi/g for
soil layers > 15 cm below the surface. Gamma ranges and/or soil sample results demon-
strate compliance to the DOE Hot Spot Guidelines for areas <25 m2 (Table 1).
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were deter-
mined by the Alpha-track method. To monitor radon levels, Geotech placed three alpha-
track detectors on the ground floor of the residence located on this property for a period
of approximately one year (from August 17, 1994 to July 24, 1995). The average annual
working level (WL) of radon progeny concentration, as determined by the Tech./Ops-
Landauer Corporation, was 0.0042, which is well below the 0.03 WL guideline given in
Table 1.
CONCLUSION
Results of Geotech soil sample analysis and confirmatory split soil sample analysis
by ORNL show that radionuclide concentrations are within applicable DOE guidelines.
Based upon the results of the post-remedial-action data, which are confirmed by the
verification assessment data, these radiological measurements fall below the limits pre-
scribed by DOE guidelines. It is concluded that the site successfully meets the DOE
remedial action objectives.
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of ^Ra in soil
above background levels,
averaged over a 100-m2 area
5 pCi/g averaged over the
first 15 cm of soil below the
surface; IS pCi/g when ave-
raged over 15-cm-thick soil
layers more than 15 cm
below the surface
Radionuclide
concentrations in soil
for Hot Spot areas
Exposure to 222Rn
progeny
Maximum Permissible con-
centration of Ra226 in soil
above background level, for
areas less than 25 m2
Average annual radon proge-
ny concentration (including
background)
Ra concentrations, in any
surface or subsurface area
less than 25 m2, is below the
guideline by a factor of
(100/A)14, where A is the
area of the elevated region
0.03 WL
(DOE 1990a)
5
Table 2. Results of ORNL analysis of Geotech soil samples
from 196 West 3rd South Street, Monticello Utah (MS00396-RS)
^Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No." Nof (cm)
XI NAT 849 15 1.5 1.7
" An X-type sample is a split of the sample taken by the remedial action contractor.
6 Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated areas
were taken by Geotech, and these samples were blended to form a composite soil
sample, which represents an average over one of the verification areas.
6
REFERENCES
Geotech 1996. Property Completion Report for Monticello Vicinity Property Reme-
dial Action for DOE ID NO: MS00396-RS, Address: 196 West Third South Street,
Monticello, Utah 84535, Geotech, Grand Junction, Colorado, April 1996.
ORNL, 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
U.S. DOE 1990a. Verification and Certification Protocolfor the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination
and Decommissioning Program, Revision 3, November 1990. U.S. Department of
Energy, Washington, D.C.
U.S. DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision
and Record of Decision Summary. U.S. Department of Energy, Grand Junction Projects
Office, Grand Junction, Colorado.
DOE ID No(s).: MS-00413-RS
Property Address(es): 181 South First West Street
Vicinity Property Certification Summary and Recommendation
Summary Evaluation
Certification Criteria MACTEC-ERS
U.S. Department
of Energy (DOE)
Ra-226 is <; 5 pCi/g above background
in top 15-cm-thick layer of soil
averaged over 100 m2
In situ [X] Lab [X]
Ra-226 is ^ 15 pCi/g above
background in any 15-cm-thick layer of
soil more than 15 cm below the
surface averaged over 100 m2.
In situ [ ]Lab[X]
Interior gamma is <; 20 uR/h above
background in any occupied or
habitable structure.
The radon decay-product
concentration in any occupied or
habitable structure is <; 0.02 WL or, at
most, 0.03 WL.
Supplemental standards were applied
in accordance with EPA standard
40 CFR 192.21.
Hot spot criteria met as outlined by
DOE guidelines for FUSRAP (Rev.2,
March 1987)
Yes No Not Taken Yes No Not Taken
[xr [ ]
[X] [ ]
[X] [ ]
[ i [ i
[ ] [X]
pq [ ]
[ i
[ i
[ ]
[X]b
[ i
[ i
W [ ] t i
[M [ i
[ i [ i
[ i i*r
[ i
[ i
"Surface areas were verified on the basis of gamma exposure rates that do not exceed 30 percent above normal
background.
'Trailer house with no permanent foundation.
•miiiu
SFCERTIFED
•llllllllll
SFMS-00413
lof2
DOE ID No(s).: MS-00413-RS
MACTEC-ERS Recommendation
On the basis ofthe MACTEC-ERS evaluation, this property is recommended for
[X] Certification by DOE.
[ ] Certification by DOE with the concurrence of the U.S. Nuclear Regulatory Commission
because supplemental standards were applied according to 40 CFR 192.21.
Date / /
2
Michael C. Butherus
Manager, Monticello Programs
MACTEC-ERS
DOE Evaluation
On the basis of the MACTEC-ERS recommendation, this property
[A] Should be certified by DOE.
[ ] Should be certified by DOE with the concurrence of the U. S. Nuclear Regulatory
Commission because supplemental standards were applied according to 40 CFR 192.21.
Certification Official Date
U.S. Department of Energy
Work performed under DOE Contract No. DE-AC13-95GJ87335, Task Order No. WPP 96-05.02.14.001
2 Of 2
Monticello Vicinity Properties Project
Property Completion Report
for
Monticello
Vicinity Property Remedial Action
for
DOE D3 No(s).: MS-00413-RS
Address(es): 181 South First West Street
Monticello, Utah 84535
October 1996
Prepared for
U.S. Department of Energy
Albuquerque Operations Office
Grand Junction Projects Office
Prepared by
MACTEC-ERS*
Grand Junction, Colorado
7* Michael C. Butherus
Manager, Monticello Programs
Work performed under DOE Contract No. DE-AC13-95GJ87335
Task Order No. 96-05.02.14.001
*MACTEC-ERS has been granted authorization to conduct remedial action by the U.S. Department of Energy.
Remedial action was done in accordance with the U.S. Environmental Protection Agency "Standards for Cleanup of
Land and Buildings Contaminated with Residual Radioactive Materials from Inactive Uranium Processing Sites,"
40 CFR 192, Subpart B; and "Implementation," in 40 CFR 192, Subpart C, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
DOE ID No.: MS-00413-RS
Contents
Page
1.0 Summary 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Remedial Action Summary 2
2.0 Operations Summary 3
2.1 Remedial Action Plan 3
2.2 Assessed and Remediated Contamination 3
3.0 Verification Summary 4
3.1 Radiological Survey Data 4
3.1.1 Preremedial Action Survey 4
3.1.2 Postexcavation Survey 4
3.1.3 Radon Decay-Product Concentration Measurements 4
3.2 Recommendation for Certification 5
Table
Table 1. Certification Data Summary 5
Appendix
Appendix A. Radiological Conditions A-1
DOE/Grand Junction Projects Office MVP Property Completion Report
October 1996 Pageii
DOE ID No.: MS-00413-RS
1.0 Summary
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce potential hazards to
the public resulting from long-term exposure to low-level radioactivity associated with the off-site
mill tailings derived from the former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States Government through its agent,
the Defense Plant Corporation, to provide additional sources of vanadium needed during World
War II. Various government agencies operated the mill until 1947. The AEC obtained the mill in
1948 and operated it through 1959 under cost-type contracts to process uranium and vanadium
ore. Mill operations were terminated on January 1, 1960.
The mill processed approximately one million tons of ore during AEC operations. Throughout the
operating period, mill tailings were removed from the Monticello millsite and used for
construction-related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for Remedial Actions at Inactive
Uranium Processing Sites" (40 CFR Part 192) for all cleanup activities under the MVP Project.
These standards were prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and open lands. Cleanup
activities also were conducted to meet the hot-spot criteria established by radiological protection
guidelines in the DOE Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management Program Sites
(Revision 2, March 1987).
This vicinity property was evaluated on the basis of EPA standards and DOE hot-spot criteria and
determined to contain mill tailings (radioactive material) exceeding EPA standards and/or DOE
hot-spot criteria. The Remedial Action Contractor was notified of the inclusion of this property
into the MVP Project and was authorized by DOE to conduct remedial action as required to bring
the property into conformance with EPA standards and DOE hot-spot criteria.
DOE/Grand Junction Projects Office
October 1996
MVP Property Completion Report
Paget
DOE ID No.: MS-00413-RS
1.3 Remedial Action Summary
DOE D3 No(s).:
Legal Description:
Property Address(es):
Property Owner(s):
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological and Engineering Assessment (REA):
Construction Subcontractor:
Preconstruction Conference Record:
Notice of Final Completion Inspection:
Volume of Material Removed in Cubic Yards (yd3):
Area Cleaned Up in Square Meters (m1):
Property Completion Report Submitted:
MS-00413-RS
Beginning 126.5 feet north of the SW
corner of Lot 2, Block 17, Monticello
Townsite Survey; north 50 feet, east
114.16 feet, south 50 feet, west
114.16 feet to beginning, County of
San Juan, State of Utah
181 South First West Street
Monticello, Utah 84535

Residential Simple (RS)
Rust Geotech
November 2, 1993
MACTEC-ERS
June 23, 1994
Diamond Back Services, Inc.
July 20, 1995
August 16, 1995
Exterior: 0
Interior: 0
0
October 1996
DOE/Grand Junction Projects Office
October 1996
MVP Property Completion Report
Page 2
DOE ID No.: MS-00413-RS
2.0 Operations Summary
2.1 Remedial Action Plan
The remedial action plan specified removal of radioactive material. No radioactive material was
identified at the time of remedial action. The property was restored to a physical condition
comparable to that which existed before remedial action activities.
2.2 Assessed and Remediated Contamination
The radiological assessment identified contamination, 12 inches (in.) deep, within the property
boundary. The quantity of contamination for this property was not specified because it was
assessed as part of Group 21. Verification personnel did not locate any radioactive material on the
property at the scheduled time for removal. The area of assessed contamination is shown in
Figure A-1.
DOE/Grand Junction Projects Office
October 1996
MVP Property Completion Report
Page 3
DOE ID No.: MS-00413-RS
3.0 Verification Summary
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Preremedial Action Survey
The Remedial Action Contractor conducted a radiological survey during May 1993, as described
in the final REA. Figure A-1 shows the extent of assessed contamination and identifies the area(s)
recommended for remedial action.
3.1.2 Postremedial Action Survey
A scintillometer was used to perform a surface gamma scan during remedial action activities.
Following the gamma scan, soil samples were collected in the area of assessed contamination. The
results of the gamma scan and analysis for radium-226 provided the basis for the determination
that no contamination was present on the property.
3.1.3 Radon Decay-Product Concentration Measurements
Radon decay-product concentration (RDC) measurements were not taken in the trailer due to
excessive ventilation caused by no permanent foundation.
DOE/Grand Junction Projects Office
October 1996
MVP Property Completion Report
Page 4
DOE ID No.: MS-00413-RS
3.2 Recommendation for Certification
Radiological conditions on this property conform to EPA standards (40 CFR 192, Subparts B
and C) and DOE hot-spot criteria, as presented in the Certification Data Summary (Table 1).
Therefore, the property located at 181 South First West Street, in Monticello, Utah, is
recommended for certification as required by DOE guidelines.
Table 1. Certification Data Summary
Applicability Standard Survey Results
Radium-226
Concentration in
Surface Soil
Radium-226
Concentration in
Subsurface Soil
Exposure Rate
Land
Shall not exceed 5 pCi/g above
background3 in the 15-cm-thick
surface layer, averaged over
100 m2.
Shall not exceed 15 pCi/g
above background8 in any
15-cm-thick soil layer more than
15 cm below the surface,
averaged over 100 m2.
< 5 pCi/g above background on the
basis of gamma exposure rates that do
not exceed 30 percent above normal
background.6
< 15 pCi/g above background on the
basis of gamma exposure rates that do
not exceed 30 percent above normal
background."
Habitable Structures
Shall not exceed 20 uR/h above
background.0
Range for the ground floor was 12 to
14 pR/h.
Radon Decay-
Product
Concentration
Annual average shall not
exceed 0.02 WL, to the extent
practicable, and shall in no
case exceed 0.03 WL.
Not taken in the trailer house due to
excessive ventilation caused by no
permanent foundation.
Key: cm = centimeters; m1 = square meters; pCi/g = picocuries per gram; pR/h = microroentgens per hour;
WL = working level
"The background radium-226 concentration for Monticello Vicinity Properties is approximately 2.0 pCi/g.
The hot-spot criteria were met based on gamma scans and/or soil sample results.
The background exposure rate for this property is approximately 14 uR/h.
DOE/Grand Junction Projects Office
October 1996
MVP Property Completion Report
Page 5
DOE ID No.: MS-00413-RS
Appendix A
Radiological Conditions
Figure A-1. Radiological As-Built
10
30
12 14 1 6 18 20 22 24 26 28 30 32 34 36 38 40
30
28 28
26
24
22
20 -
18
LU
LU cc
i—
CO
t—
CO
LU
CO
CC
LL.
X
I—
ZD
O
CO
r 13-16
14-16
r TRAILER HOUSE
12-14 13-16
-H-
©
12-15
LEGEND
ALL DEPTHS/HEIGHTS IN INCHES
ALL EXPOSURE RATES IN fj.R/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
EXPOSURE-RATE RANGE
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
26
24
22
20
18
16 1 6
14
12
Y
NORTH
SCALE IN FEET
10
20 10 0
M:\FAS\033\0003\RM00413V 10/10/96 2:45pm SS0730
- X
I I 1 I I I
20
10 12 14 16
40
J L
18 20
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT. UTILITY LOCATION PLAT, OR OTHER IMPROVEMENT SURVEY
PLAT AND IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE. BUILDING, OR OTHER FUTURE IMPROVEMENT LINES.
22 24 26 28
rmm 181 SOUTH FIRST
WEST STREET
MONTICELLO, UTAH
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE. COLORADO
COMPLETION REPORTS MONTICELLO VICINITY PROPERTIES
FIGURE A-1
RADIOLOGICAL AS-BUILT
MS-00413-RS
30 32 34
3-B00415-V1
36
1 1
38
14
12
10
40
OAK RIDGE NATIONAL LABORATORY PHONE: [phone]
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION FAX: [phone]
FOR THE U.S. DEPARTMENT OF ENERGY
2597 BV. Road
GRANO JUNCTION, COLORADO 81503
rM 3 l W
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by the U.S.
Department of Energy for Residual Radioactive Material at Formerly Utilized Sites Remedial Action
Program (FUSRAP) and Remote Surplus Facilities Management Program Sites (SFMP) [Revision
2, March 1987]. This evaluation is based on an independent verification review of the Remedial
Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment of the ^Ra
concentration in the soil, and indoor and outdoor gamma exposure rates at this property.
This property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
MS00413-RS •
181 South 1st West Street
Monticello. Utah 84535 '

"
Location Number:
Location Address:
Property Owner:
Owner Address.
Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
181 SOUTH 1ST WEST STREET
MONTICELLO, UTAH (MS00413-RS)
M. K. Jensen
January 1997
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81503
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 3
REFERENCES 5
iii
LIST OF TABLES
Applicable guidelines for protection against radiation
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site Decommissioning
Projects, U.S. Department of Energy. The author wishes to acknowledge M. J. Wilson-Nichols and
G. A. Pierce for technical reviews.
vii
ABSTRACT
In 1980, the site of a vanadium and uranium mill at Monticello, Utah, was accepted into the U.S.
Department of Energy (DOE) Surplus Facilities Management Program, with the objectives of
restoring the government-owned mill site to safe levels of radioactivity, disposing of or containing
the tailings in an environmentally safe manner, and performing remedial actions on off-site (vicinity)
properties that had been contaminated by radioactive material resulting from mill operations. During
1995, the Remedial Action Contractor (RAC) designated by DOE, attempted to perform remedial
action on the vicinity property at 181 South 1st West Street, Monticello, Utah, however, no
contamination was located on the property. The Environmental Technology Section (ETS) of Oak
Ridge National Laboratory was assigned the responsibility of verifying the data supporting the
adequacy of remedial action and confirming the site's compliance with DOE guidelines. The ETS
found that the site successfully meets the DOE remedial action objectives. Procedures used by the
ETS are described in the Environmental Technology Section Procedures Manual (ORNL 1993).
ix
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 181 SOUTH 1ST WEST STREET
MONTICELLO, UTAH (MS00413-RS)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the United States (U.S.) government through
the Defense Plant Corporation to provide vanadium during World War II. Various government
agencies operated the mill until 1947. In 1948, the Atomic Energy Commission (AEC) obtained the
mill and operated it under contract through 1959 to provide both uranium and vanadium. Mill
operations were terminated on January 1, 1960. In 1961, the mill tailings piles were leveled and
graded, covered with rock and soil, and seeded with native grasses. During 1974 and 1975, the ore
stockpiles were removed from the site and the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city of
Monticello, in San Juan County, Utah. The site is bordered on the south and southeast by land held
by the U.S. Bureau of Land Management. Other boundaries are the city of Monticello and private
property.
During the AEC era, the mill processed approximately one million tons of uranium ore. Vana-
dium and uranium were the only substances extracted in the milling process. Other constituents of
the ore remained in the tailings and were not separated prior to disposal. During the years of active
mill operation, the mill tailings were normally moist, so erosion was minimal. However, throughout
the mill's operating period, area residents used these tailings as fill material and as aggregate in mortar
and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy (DOE) initiated
the Surplus Facilities Management Program (SFMP) in 1978 to ensure the safe caretaking and de-
commissioning of government facilities that had been retired from service but still had radioactive
contamination. In 1980, the mill site at Monticello was accepted into the SFMP, and the Monticello
Remedial Action Project (MRAP) was established to restore the government-owned mill site to safe
levels of radioactivity, to dispose of or contain the tailings in an environmentally safe manner, and to
perform remedial actions on off-site (vicinity) properties that had been contaminated by radioactive
material resulting from mill operations. The Monticello mill site and the tailings remain in the custody
of the DOE Grand Junction, Colorado, Projects Office. In 1983, remedial actions for vicinity
properties were separated from MRAP with establishment of the Monticello Vicinity Properties
(MVP) Project (US DOE 1990b).
*The verification of remedial action was performed by members ofthe Environmental Assessment Group in the Environmental
Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE contract DE-AC05-
960R22464 with Lockheed Martin Energy Research Corporation.
2
During 1995, the Remedial Action Contractor (RAC) designated by DOE, attempted to perform
remedial action on the vicinity property that is the subject of this report, a single family residence
located at 181 South 1st West Street, Monticello, Utah. The remedial action plan required
excavation of all exterior contamination, however, no gamma measurements above the background
range were located on the property. The property was resurveyed and soil samples were taken to
ensure that no contamination remained on the property (MACTECH-ERS 1996 ).
DOE adopted a policy to assign an independent contractor to verify the data supporting the
adequacy of remedial action and to confirm the site's compliance with DOE guidelines. The Environ-
mental Technology Section (ETS) of Oak Ridge National Laboratory (ORNL) has been assigned the
responsibility of this task at the 181 South 1st West Street site. This report describes the methods
and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available documentation
adequately and accurately describes the post-remedial-action radiological conditions of the entire
property that is to be certified and (2) that the remedial action reduced contamination to below
applicable DOE guidelines (US DOE 1990a).
Document Reviews
Review of the RAC property completion report (MACTEC-ERS 1996) indicates the property
does not require remedial action based on U.S. Environmental Protection Agency standards and the
DOE guidelines (US DOE 1990a).
This property was assessed as part of Group 21, therefore, the quantity of material assessed is
not available. During the actual removal process, verification personnel did not locate any material
exceeding background gamma exposure rates.
The RAC performed a post-excavation survey consisting of gamma scans with a scintillometer
of the ground level of the structure, a surface scan of the exterior, and soil sampling. The RAC is
unable to locate or inadvertently disposed of the samples requested for ORNL confirmatory analysis.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation levels have
not been subtracted. Similarly, background concentrations have not been subtracted from radionu-
clide concentrations in soil samples. Applicable DOE guidelines for protection against radiation are
given in Table 1.
Gamma Measurements
Gamma exposure rate measurements taken by the RAC at the ground-level of the residence
ranged from 12 to 14 uR/h. Exterior surface gamma measurements ranged from 13 to 16 uR/h and
14 to 16 uR/h in the area of assessed contamination.
Soil Sample Analysis
The RAC collected soil samples at the area of assessed contamination from the surface and
subsurface soil layers. The RAC's analysis of these samples showed ^Ra concentrations of 2.5 pCi/g
in the surface layer and 2.1 pCi/g in the subsurface layer. ORNL ETS was unable to obtain samples
for confirmatory analysis. These values are below the DOE guideline value of 5 pCi/g for surface and
15 pCi/g for subsurface soil layers. Gamma ranges and/or soil sample results demonstrate compliance
to the DOE Hot Spot Guidelines for areas <25 m2 (Table 1).
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were not taken as the only
structure was a trailer with no permanent foundation.
CONCLUSION
Results of RAC soil sample analysis show that radionuclide concentrations are within applicable
DOE guidelines. Based on the results of the post-remedial-action data, which are confirmed by the
verification assessment data, these radiological measurements fall below the limits prescribed by DOE
guidelines. It is concluded that the site successfully meets the DOE remedial action objectives.
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of 226Ra in soil
above background levels,
averaged over a 100-m2
area
5 pCi/g averaged over the first 15 cm
of soil below the surface; 15 pCi/g
when averaged over 15-cm-thick soil
layers more than 15 cm below the
surface
Radionuclide con-
centrations in soil
for Hot Spot areas
Exposure to n2Rn
progeny
Maximum Permissible con-
centration of Ra226 in soil
above background level,
for areas less than 25 nr
Average annual radon
progeny concentration
(including background)
Ra226 concentrations, in any surface
or subsurface area less than 25 m2,
is below the guideline by a factor of
(100/A)'4, where A is the area of the
elevated region
0.03 WL
(US DOE 1990a)
5
REFERENCES
MACTEC-ERS 1996. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00413-RS, Address: 181 South First West Street, Monticello, Utah
84535, MACTEC-ERS, Grand Junction, Colorado, October 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment Group)
Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National Laboratory, Grand
Junction, Colorado.
US DOE 1990a. Verification and Certification Protocol for the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination and
Decommissioning Program. Revision 3, November 1990. U.S. Department of Energy,
Washington, D.C.
US DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision and
Record of Decision Summary. U.S. Department of Energy, Grand Junction Projects Office,
Grand Junction, Colorado.
DOE ID No.: MS-00437-RS
Property Address: 132 South Third East Street
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech Of Energy (DOE)
Ra-226 is <; 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [ ]
Ra-226 is <; 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2.
In-situ [ ] Lab [X]
Interior gamma is £ 20 //R/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is £ 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21.
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
M [ ] [ ]
PO [ ] [ 1
[X] [ ] [ ]
[VI f ] [ ]
[ ] [A I }
[)(][) [ 1
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
ll
SFCERTIFED llllllllll
SFMS-00437
DOE ID No.: MS-00437-RS
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Wanda S. Busby / 7 Date
Manager, Monticello Programs
Rust Geotech
DOE EVALUATION
Lx] Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
4. Certification Official 7 Date
U.S. Department of Energy
PROPERTY COMPLETION REPORT
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
DOE ID NO.: MS-00437-RS
ADDRESS: 132 SOUTH THIRD EAST STREET
MONTICELLO, UTAH 84535
JUNE 1996
Prepared for
U.S. Department of Energy
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
FOR
FOR
by
Wanda S. Busby /
Manager, Monticello Programs
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
•llllllllll minimi SFOCPLRPTS SFMS-80437
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action _ 1
1.2 Criteria for Remedial Action " 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.1.3 Radon Decay-Product Concentration (RDC) Measurement .... 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
i
DOE ID No.: MS-00437-RS
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Remedial Action Contractor. DOE reviewed these
evaluation results and determined that the property contained mill tailings
(residual radioactive material) exceeding EPA standards. The Remedial
Action Contractor was notified of the inclusion of this property into the
MVP Project and was authorized by DOE to conduct remedial action as
required to bring the property into conformance with EPA standards and
DOE hot spot criteria.
1
DOE ID No.: MS-00437-RS
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
Property Address:
Property Owner:
Property Category:
Inclusion Survey Contractor:
inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
MS-0O437-RS
Beginning at the NE corner of Lot 4,
Block 20, Monticello Townsite Survey;
west 65 feet, south 120 feet, east 65 feet,
north 120 feet to beginning, County of San
Juan, State of Utah
132 South Third East Street
Monticello, Utah 84535

Residential Simple (RS)
Not applicable: inclusion requested by the
Remedial Action Contractor
January 31, 1992
Rust Geotech
September 13, 1994
Diamond Back Services, Inc.
9861 Titan Park Circle
Littleton, Colorado
August 3, 1995
September 14, 1995
Interior: 0 cubic yards
Exterior: 178 cubic yards
892 square meters (m2)
June 1996
2
DOE ID No.: MS-00437-RS
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of exterior residual radioactive
material (Appendix Figure 2.1). Once excavation was complete, the
affected area was resurveyed for possible remaining residual radioactive
material and, upon attaining satisfactory results, was backfilled with
uncontaminated material. The property was restored to a physical
condition comparable to that which existed prior to remedial action
activities.
2.2 Previously Unidentified Contamination
The radiological assessment identified 185 cubic yards of contamination,
ranging from 6 to 12 inches deep, within the property. The remedial
action process included the removal of approximately 178 cubic yards of
residual radioactive material, ranging from 6 to 12 inches deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID No.: MS-00437-RS
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by the Remedial Action
Contractor during August 1990 and July 1994, as described in the
final REA dated September 1994. Appendix Figure 2.1 shows the
extent of assessed contamination and identifies the area
recommended to undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the excavation were
collected. These samples were blended to form composite
samples representing the verification areas (Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 15 to 23 microroentgens per
hour (//R/h), as indicated on Appendix Figure 2.1. The results of
analyses for radium-226 in 12 composite soil samples ranged from
2.7 to 6.8 picocuries per gram (pCi/g), as indicated in Appendix
Table 3.1.
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on measurements representing an annual average, the RDC
was 0.0088 working level (WL), as indicated in Appendix
Table 3.2. Appendix Figure 2.1 shows the measurement location
on the ground floor (the lowest habitable level of the structure).
4
DOE ID No.: MS-00437-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at 132 South Third East Street, in
Monticello, Utah, is recommended for certification as required by DOE
guidelines, and the appropriate records should be documented.
Certification Data Summary
Applicability Standards Survey Results
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Shall not exceed 20 //R/h
above background.*
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Range for the ground
floor was 13 to 14//R/h.
Annual average was
0.0088 WL.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
< 5 pCi/g above
background.**
Soil sample results
ranged from 2.7 to
6.8 pCi/g.**
*The background exposure rate is approximately 15 A/R/h.
The background radium-226 concentration is approximately 2.0 pCi/g.
* *The hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-00437-RS
4.0 APPENDIX
Appendix Tables:
Table 3.1 Post-Excavation Sample/Measurement Results
Table 3.2 Radon Decay-Product Concentration Measurement
Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
SJW:06-03-96
MS-00437.RS WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00437-RS
Address: 132 South Third First Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range OuR/h) Ticket No. Method" (pCi/g)
V-1
V-2
V-3
V-4
V-5
V-6
V-7
V-8
V-9
V-10
V-11
V-12
16
16
16
16
16
16
16
16
16
15
16
16
21
23
20
21
21
18
23
21
22
18
18
20
NCJ 542
NCJ 543
NCL 651
NCL 652
NCL 653
NCL 654
NCL 655
NCL 656
NCL 657
NCL 658
NCL 659
NCL 660
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
6.8
3.4
4.4
2.7
6.1
2.8
4.4
4.5
4.7
4.5
2.9
4.1
See Appendix Figure 2.1 for the verification areas.
"OCS = Opposed Crystal System
7
Table 3.2
Radon Decay-Product Concentration Measurement Results
DOE ID No.: MS-00437-RS
Address: 132 South Third East Street, Monticello, Utah
Instrument Type: Landauer Radtrak Detector
Detector
Number Start Date End Date
Radon
Concentration
(pCi/L)
Working
Level
3964184
3964315
3964262
03-06-95
03-06-95
03-06-95
02-27-96
02-27-96
02-27-96
1.71
1.75
1.80
0.0086
0.0088
0.0090
Annual Average: 0.0088
See Appendix Figure 2.1 for the measurement location.
8
10
30
28
26
24
22
20
18
16
1 4
12
Y
10
12 1 4 16 1P 20 22 24 26 28 30 32
///. EAST FIRST SOUTH STREET
— LLL
V-2 V-1
16-23 16-21
V-10
15-18 N3
1 r
r 15-17
V-1 1 V-12
16-18 16-20
DS
12 V-9 1 2
16-22
V-8 12 12 .X1 2>.\ 16-21
V-6
V-7 16-18
16-23
12 ONE STORY
STUCCO HOUSE
13-14
RDC
V-5 V-3
16-21 16-20
V-4
® HED 1 |v!
16-21
i r
u
LJ cr
i—
CO
CO
<
LU
Q
oc
Z3
o co
NORTH
SCALE IN FEET
20 20 10 0
M:\FAS\033\0003\RM00437V 06/17/96 3:14pm T50780
I I I I I L
40
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT. UTILITY LOCATION PLAT, OR OTHER IMPROVEMENT SURVEY
PLAT AND IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE, BUILDING, OR OTHER FUTURE IMPROVEMENT LINES.
®
r?.-?7i
LV.YJ
12-15
12
V-1
16-17
(RDC)
34 36
1—i—i—r
38
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN /xR/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE-RATE RANGE
RADON DECAY-PRODUCT CONCENTRATION
MEASUREMENT LOCATION
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
40
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
RESIOENCE-HO. OF OCCUPANTS
NON-RESIOENCE-MAN-HRS./WK.
INSTRUMENT NO.
SURVEY OATE
VERIFICATION
A.E. APP. NO. OATE CK. AC. APP.
U.S. DEPARTMENT OF ENERGY
GRANO JUNCTION PROJECTS OFFICE. COLORADO
DESIGNER
DRAWN.
PROJ. CNCRT 25
132 SOUTH THIRD EAST STREET
MONTICELLO, UTAH
Rust Qeotech
DATf I APPROVAL OOE "0A7T
OOEIONO. MS-00437-RS
OWC.NO. 3-BQQ437-V1SHT1 0f
30
28
26
24
22
20
18
- 16
14
12
10
10 12 1 4 16 18 20 22 24 26 28 30 32 34 36 38 40
OAK RIDGE NATIONAL LABORATORY PHONE: <970) 24W52O0
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION FAX: [phone]
FOR THE U.S. DEPARTMENT OF ENERGY
POST OFFICE BOX 2567
GRAND JUNCTION, COLORADO 81502 SEP 2 u 1996
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by the U.S.
Department of Energy for Residual Radioactive Material at Formerly Utilized Sites Remedial Action
Program (FUSRAP) and Remote Surplus Facilities Management Program Sites (SFMP) [Revision
2, March 1987]. This evaluation is based on an independent verification review of the Remedial
Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment ofthe 226Ra
concentration in the soil, indoor radon daughter concentration, and indoor gamma exposure rates at
this property.
This property is recommended for certification by the U.S. Department of Energy.
Sincerely,
j
Gret'cnen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
Location Number: MS00437-RS
Location Address: 132 South 3rd East Street
Monticello. Utah 84535
Property Owner:

Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
132 SOUTH 3RD EAST STREET
MONTICELLO, UTAH (MS00437-RS)
M. K. Jensen
September 1996
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 4
REFERENCES 7
iii
•*
LIST OF TABLES
1. Applicable guidelines for protection against radiation 5
2. Results of ORNL analysis of Geotech soil samples from 132 South 3rd East Street,
Monticello, Utah (MS00437-RS) 6
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site
Decommissioning Projects, U.S. Department of Energy. The author wishes to acknowledge
A. R. Jones and J. R. Sauvage for technical reviews.
vii
ABSTRACT
In 1980 the site of a vanadium and uranium mill at Monticello, Utah, was accepted into
the U.S. Department of Energy's (DOE's) Surplus Facilities Management Program, with the
objectives of restoring the government-owned mill site to safe levels of radioactivity, dis-
posing of or containing the tailings in an environmentally safe manner, and performing reme-
dial actions on off-site (vicinity) properties that had been contaminated by radioactive material
resulting from mill operations. During 1995, RUST Geotech, the remedial action contractor
designated by DOE, performed remedial action on the vicinity property at 132 South 3rd East
Street, Monticello, Utah. The Environmental Technology Section (ETS) of Oak Ridge
National Laboratory was assigned the responsibility of verifying the data supporting the
adequacy of remedial action and confirming the site's compliance with DOE guidelines. The
ETS found that the site successfully meets the DOE remedial action objectives. Procedures
used by the ETS are described in the Environmental Technology Section Procedures Manual
(ORNL 1993).
ix
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 132 SOUTH 3RD EAST STREET
MONTICELLO, UTAH (MS00437-RS)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the U.S. government through the
Defense Plant Corporation to provide vanadium during World War II. Various government
agencies operated the mill until 1947. In 1948 the Atomic Energy Commission (AEC) ob-
tained the mill and operated it under contract through 1959 to provide both uranium and
vanadium. Mill operations were terminated on January 1,1960. In 1961 the mill tailings piles
were leveled and graded, covered with rock and soil, and seeded with native grasses. During
1974 and 1975, the ore stockpiles were removed from the site, and the mill foundations were
buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city of
Monticello, in San Juan County, Utah. The site is bordered on the south and southeast by
land held by the U.S. Bureau of Land Management. Other boundaries are the city of Monti-
cello and private property.
During the AEC era, the mill processed approximately one million tons of uranium ore.
Vanadium and uranium were the only substances extracted in the milling process. Other con-
stituents of the ore remained in the tailings and were not separated prior to disposal. During
the years of active mill operation, the mill tailings were normally moist, so erosion was
minimal. However, throughout the mill's operating period, area residents used these tailings
as fill material and as aggregate in mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy (DOE)
initiated the Surplus Facilities Management Program (SFMP) in 1978 to ensure the safe care-
taking and decommissioning of government facilities that had been retired from service but
still had radioactive contamination. In 1980 the mill site at Monticello was accepted into the
SFMP, and the Monticello Remedial Action Project (MRAP) was established to restore the
government-owned mill site to safe levels of radioactivity, to dispose of or contain the tailings
in an environmentally safe manner, and to perform remedial actions on off-site (vicinity)
properties that had been contaminated by radioactive material resulting from mill operations.
The Monticello mill site and the tailings remain in the custody of the DOE Grand Junction,
Colorado, Projects Office. In 1983 remedial actions for vicinity properties were separated
from MRAP with establishment of the Monticello Vicinity Properties (MVP) Project (U.S.
DOE 1990b).
•The verification of remedial action was performed by members of the Environmental Assessment Group in the
Environmental Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE
contract DE-AC05-96OR22464 with Lockheed Martin Energy Research Corporation.
2
During 1995, RUST Geotech Inc. (Geotech), the remedial action contractor (RAC)
designated by DOE, performed remedial action on the vicinity property that is the subject of
this report, a private residence located at 132 South 3rd East Street, Monticello, Utah. The
remedial action plan required excavation of all exterior contamination. When the excavation
was completed, the property was resurveyed, including soil sampling, to ensure the removal
of all contamination, backfilled with uncontaminated material, and restored to a condition
comparable to that which existed prior to remedial action (Geotech 1996).
The DOE adopted a policy to assign an independent contractor to verify the data
supporting the adequacy of remedial action and to confirm the site's compliance with DOE
guidelines. The Environmental Technology Section (ETS) of Oak Ridge National Laboratory
(ORNL) has been assigned the responsibility of this task at the 132 South 3rd East Street site.
This report describes the methods and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available documenta-
tion adequately and accurately describes the post-remedial-action radiological conditions of
the entire property that is to be certified and (2) that the remedial action reduced contamina-
tion to below applicable DOE guidelines (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1996) indicates
the property was remediated as evaluated by DOE on the basis of Environmental Protection
Agency standards and the DOE guidelines (DOE 1990a). Excess residual radioactive materi-
als were present, thus it was appropriate to designate this property for remedial action.
The pre-remedial-action survey performed by Geotech identified 185 yd3 of mill tailings
6 to 12 inches deep. During the actual removal process, a total of 178 yd3 of contaminated
earth and uranium mill tailings, 6 to 12 inches deep, were removed from a 892 m2 area.
A post-excavation survey was performed by Geotech prior to backfilling the excavated
areas. This survey consisted of gamma scans with a scintillometer of the ground level of the
structure, a surface scan of the exterior, and soil sampling. Samples representative of the
bottom 15-cm (6-in.) soil layers of twelve excavated verification areas were collected and
blended to form representative composite soil samples.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation
levels have not been subtracted. Similarly, background concentrations have not been sub-
tracted from radionuclide concentrations in soil samples. Applicable DOE guidelines for
protection against radiation are given in Table 1.
Gamma Measurements
Gamma exposure rate measurements taken by Geotech at the ground-level of the
residence ranged from 13 to 14 uR/h. Exterior surface gamma measurements taken from the
excavated areas prior to backfilling ranged from 15 to 23 uR/h.
Soil Sample Analysis
Prior to backfilling, Geotech collected soil samples representative of the excavated areas
from the bottom 15-cm (6-in.) soil layers. These samples were blended to form composite
soil samples representative of an average over the twelve exterior verification areas. Geo-
tech's analysis of these samples showed 226Ra concentrations ranging from 2.7 to 6.8 pCi/g
in the composite sample. ORNL ETS obtained a percentage of these samples and performed
a confirmatory analysis which showed ^Ra concentrations ranging from 4.0 to 7.5 pCi/g.
These values are below the EPA standard value of 15 pCi/g for soil layers > 15 cm below the
surface. Results of Geotech and ORNL soil sample analyses are given in Table 2.
As a result of a meeting between the RAC and IVC on May 26, 1994, anomalous
readings, defined as > 30% above the average of the excavation, will be investigated to show
compliance to the DOE hot spot guideline. They remediated this property after this proce-
dure change. The IVC observed that areas VI, V2, V5, and V9 exceeds 30% of the excava-
tion average. The IVC will allow a correlation developed by the RAC to estimate ^Ra pCi/g
concentrations based on gamma exposure rates. The highest anomalous reading of 23 uR/h
on this property using the RAC's correlation yields a ^Ra concentration of 5.0 pCi/g. This
value is well below the minimum concentration of 30 pCi/g needed, when assuming the maxi-
mum area under the hot spot guideline of 25 m2, for subsurface samples. Gamma ranges
and/or soil sample results demonstrate compliance to the DOE Hot Spot Guidelines for areas
<25 m2.
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were determined
by the Alpha-track method. To monitor radon levels, Geotech placed three alpha-track
detectors on the ground floor of the residence located on this property for a period of
approximately one year (from March 6, 1995 to February 27, 1996). The average annual
working level (WL) of radon progeny concentration, as determined by the TechVOps-
Landauer Corporation, was 0.0088, which is well below the 0.03-WL guideline given in Table
1.
4
CONCLUSION
Results of Geotech soil sample analysis and confirmatory split soil sample analysis by
ORNL show that radionuclide concentrations are within applicable DOE guidelines. Based
on the results ofthe post-remedial-action data, which are confirmed by the verification assess-
ment data, these radiological measurements fall below the limits prescribed by DOE guide-
lines. It is concluded that the site successfully meets the DOE remedial action objectives.
5
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Radionuclide con-
centrations in soil
for Hot Spot areas
Exposure to 222Rn
progeny
Maximum permissible con-
centration of ^Ra in soil
above background levels,
averaged over a 100-m2 area
Maximum Permissible con-
centration of Ra226 in soil
above background level, for
areas less than 25 m2
Average annual radon progeny
concentration (including
background)
5 pCi/g averaged over the
first 15 cm of soil below the
surface; 15 pCi/g when ave-
raged over 15-cm-thick soil
layers more than 15 cm
below the surface
Ra226 concentrations, in any
surface or subsurface area
less than 25 m2, is below the
guideline by a factor of
(lOO/A)* where A is the area
of the elevated region
0.03 WL
(DOE 1990a)
6
Table 2. Results of ORNL analysis of Geotech soil samples from
132 South 3rd East Street, Monticello, Utah (MS00437-RS)
^Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No." No*. (cm)
X2 NCJ 543 >15 4.0 3.4
X5 NCL 653 >15 7.5 6.1
X9 NCL 657 >15 4.8 4.7
X12 NCL 660 >15 4.8 4.1
" An X-type sample is a split of the sample taken by the remedial action contractor.
4 Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated areas
were taken by Geotech, and these samples were blended to form a composite soil sample,
which represents an average over one of the verification areas.
7
REFERENCES
Geotech 1996. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00437-RS, Address: 132 South Third East Street, Monticello,
Utah 84535, Geotech, Grand Junction, Colorado, June 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment Group)
Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National Laboratory,
Grand Junction, Colorado.
U.S. DOE 1990a. Verification and Certification Protocolfor the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination and
Decommissioning Program, Revision 3, November 1990. U.S. Department of Energy,
Washington, D.C.
U.S. DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision and
Record of Decision Summary. U.S. Department of Energy, Grand Junction Projects Office,
Grand Junction, Colorado.
DOE ID No.: MS-00439-RS
Property Address: 249 East First South Street
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech of Energy (DQE)
Ra-226 is < 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [ ]
Ra-226 is < 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2.
In-situ [ ] Lab [X]
Interior gamma is < 20 j/R/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is <; 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21.
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] t ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
[Y] [ ] [ I
[X] [ ] [ ]
{/[ [ ] [ ]
[*l [ ] [ ]
[yi [ ] [ ]
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
Ililllllllll 11111111111
SFCERTIFED SFMS-00439
DOE ID No.: MS-00439-RS
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Wanda S. f5usby / Date
r, M Manager, Tvlonticello Programs
Rust Geotech
DOE EVALUATION
1X1 Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Certification Official
U.S. Department of Energy
Date
PROPERTY COMPLETION REPORT
DOE ID NO.: MS-00439-RS
ADDRESS: 249 EAST FIRST SOUTH STREET
MONTICELLO, UTAH 84535
JULY 1996
Prepared for
U.S. Department of Energy
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
by
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.1.3 Radon Decay-Product Concentration (RDC) Measurement .... 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
i
DOE ID No.: MS-00439-RS
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Inclusion Survey Contractor. DOE reviewed
these evaluation results and determined that the property contained mill
tailings (residual radioactive material) exceeding DOE hot spot criteria.
The Remedial Action Contractor was notified of the inclusion of this
property into the MVP Project and was authorized by DOE to conduct
remedial action as required to bring the property into conformance with
EPA standards and DOE hot spot criteria.
1
DOE ID No.: MS-00439-RS
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
Property Address:
Property Owner:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
MS-00439-RS
Beginning 70 feet east of the SW corner of
Lot 2, Block 21, Monticello Townsite
Survey; north 100 feet, east 72 feet, south
100 feet, west 72 feet to beginning,
County of San Juan, State of Utah
249 East First South Street
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
September 22, 1993
Rust Geotech
February 13, 1995
Diamond Back Services, Inc.
9861 Titan Park Circle
Littleton, Colorado
September 6, 1995
September 12, 1995
Interior:
Exterior:
0 cubic yards
7 cubic yards
33 square meters (m2)
July 1996
2
DOE ID No.: MS-00439-RS
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of exterior residual radioactive
material (Appendix Figure 2.1). Once excavation was complete, the
affected areas were resurveyed for possible remaining residual radioactive
material and, upon attaining satisfactory results, were backfilled with
uncontaminated material. The property was restored to a physical
condition comparable to that which existed prior to remedial action
activities.
2.2 Previously Unidentified Contamination
The radiological assessment identified 7 cubic yards of contamination,
6 inches deep, within the property. The remedial action process included
the removal of approximately 7 cubic yards of residual radioactive
material, 6 inches deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID No.: MS-00439-RS
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by the Remedial Action
Contractor during May and June 1990, and during September and
December 1994, as described in the final REA dated February
1995. Appendix Figure 2.1 shows the extent of assessed
contamination and identifies the areas recommended to undergo
remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the excavation were
collected. These samples were blended to form a composite
sample representing the verification area (Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 12 to 19 microroentgens per
hour (//R/h), as indicated on Appendix Figure 2.1. The result of
analysis for radium-226 in one composite soil sample was
3.9 picocuries per gram (pCi/g), as indicated in Appendix
Table 3.1.
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on the DOE-approved abbreviated-measurement method,
the RDC was 0.0141 working level (WL), as indicated in Appendix
Table 3.2. Appendix Figure 2.1 shows the measurement location
on the ground floor (the lowest habitable level of the structure).
RDC measurements were taken before remediation of the property.
4
DOE ID No.: MS-00439-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at 249 East First South Street, in
Monticello, Utah, is recommended for certification as required by DOE
guidelines, and the appropriate records should be documented.
Certification Data Summary
Applicability
Habitable Stnictiires
Exposure Rate:
Radon Decay-Product
Concentration:
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Standards
Shall not exceed 20 //R/h
above background.*
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Shall not exceed 5 pCi/g
above background in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
Survey Results
Range for the ground
floor was 12 to 13 //R/h.
Average was 0.0141 WL,
based on the DOE-
approved abbreviated-
measurement method.
< 5 pCi/g above
background.**
Soil sample result was
3.9 pCi/g.**
*The background exposure rate is approximately 13//R/h.
The background radium-226 concentration is approximately 2.0 pCi/g.
**The hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-00439-RS
4.0 APPENDIX
Appendix Tables:
Table 3.1 Post-Excavation Sample/Measurement Results
Table 3.2 Radon Decay-Product Concentration Measurement
Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
SJW:06-03-96
MS-00439.RS WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00439-RS
Address: 249 East First South Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range U/R/h) Ticket No. Method" (pCi/g)
V-1 16-19 NCL 805 OCS 3.9
See Appendix Figure 2.1 for the verification area.
"OCS = Opposed Crystal System
7
Table 3.2
Radon Decay-Product Concentration Measurement Results
DOE ID No.: MS-00439-RS
Address: 249 East First South Street, Monticello, Utah
Instrument Type: Landauer Radtrak Detector
Detector
Number Start Date End Date
Radon
Concentration
(pCi/L)
Working
Level
3964328
3964345
3964153
03-02-95
03-02-95
03-02-95
06-06-95
06-06-95
06-06-95
2.83 0.0142
2.44 0.0122
3.17 0.0159
Average: 0.0141
See Appendix Figure 2.1 for the measurement location.
8
10
30
28
26
24
22
20 -
18 -
16
12 -
Y
10
12 1 4 16
6 f 6 X A
18 20 22 24 26
"1 T
28
O
ST
V-1
16-19 SHED^
12-13
PARAGE
12-13
15-16
r RDC)
ONE STORY
FRAME HOUSE
12-13
13-15
i i ^
V-1
16-19
c.
o 15-16
~77T~ ~rrr
EAST FIRST SOUTH STREET
SCALE IN FEET
20 10 0 20 40
M:\FAS\033\0003\RM00439V 06/17/96 3:22pm T50780
I I 1 I I I I
NORTH
I I
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT. UTILITY LOCATION PLAT. OR OTHER IMPROVEMENT SURVEY
PLAT AND IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE. BUILDING, OR OTHER FUTURE IMPROVEMENT LINES.
30
i r
®
®
nv.vn
LV.YJ
12-15
12
v-1
16-17
(RDC)
32 34 36 38
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN /zR/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE-RATE RANGE
RADON DECAY-PRODUCT CONCENTRATION
MEASUREMENT LOCATION
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
40
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
RESIOCNCC-NO. or OCCUPANTS
NON-RESIDEHCE-UAN-HRS./WK.
INSTRUUCNT NO.
SURVCT OATE
VERIFICATION
BY CK. A.E. APP. NO. DATE •T CK. A.C. APP.
|RAN
m OCS
DRAWN
CHECKE
PROJ. E
U.S. DEPARTMENT OF ENERGY
GRANO JUNCTION PROJECTS OFFICE. COLORADO
249 EAST FIRST SOUTH STREET
MONTICELLO, UTAH
APPROVAL
Rust Qeotech
A WW TtdMtavw Cenpvr
DATE APPROVAL DOE DATE
OOEIONO. MS-00439-RS
o«o.No. 3-B00439-V1 1
SHT. OF
30
28
26
24
22
20
- 18
- 16
14
1 2
10
10 12 1 4 1 6 18 20 22 24 26 28 30 32 34 36 38 40
OAK RIDGE NATIONAL LABORATORY
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
FOR THE U.S. DEPARTMENT OF ENERGY
PHONE: [phone]
FAX: [phone]
POST OFFICE BOX 2S67
GRAND JUNCTION, COLORADO 81502
NOV 2 7 1996
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by the U.S.
Department of Energy for Residual Radioactive Material at Formerly Utilized Sites Remedial
Action Program (FUSRAP) and Remote Surplus Facilities Management Program Sites (SFMP)
[Revision 2, March 1987]. This evaluation is based on an independent verification review of the
Remedial Action Contractor's completion report, and field monitoring of RDC measurements.
This recommendation is based upon the Independent Verification Contractor's assessment of the
226Ra concentration in the soil, indoor radon daughter concentration, and indoor gamma exposure
rates at this property.
This property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
Location Number:
Location Address:
Property Owner:
Owner Address:
MS00439-RS
249 East 1st South Street
Monticello. Utah 84535

Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
249 EAST 1ST SOUTH STREET
MONTICELLO, UTAH (MS00439-RS)
M. K. Jensen
November 1996
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 3
REFERENCES 6
iii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 4
2. Results of ORNL analysis of the Remedial Action Contractor (RAC) soil samples
from 249 East 1 st South Street, Monticello, Utah (MS00439-RS) 5
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site
Decommissioning Projects, U.S. Department of Energy. The author wishes to acknowledge
A. R. Jones and S. M. Smith for technical reviews.
vii
ABSTRACT
In 1980, the site of a vanadium and uranium mill at Monticello, Utah, was accepted into
the U.S. Department of Energy (DOE) Surplus Facilities Management Program, with the
objectives of restoring the government-owned mill site to safe levels of radioactivity, dispos-
ing of or containing the tailings in an environmentally safe manner, and perfonning remedial
actions on off-site (vicinity) properties that had been contaminated by radioactive material
resulting from mill operations. During 1995, the Remedial Action Contractor (RAC) desig-
nated by DOE, performed remedial action on the vicinity property at 249 East 1st South
Street, Monticello, Utah. The Environmental Technology Section (ETS) of Oak Ridge
National Laboratory was assigned the responsibility of verifying the data supporting the
adequacy of remedial action and confmiiing the site's compliance with DOE guidelines. The
ETS found that the site successfully meets the DOE remedial action objectives. Procedures
used by the ETS are described in the Environmental Technology Section Procedures Manual
(ORNL 1993).
ix
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 249 EAST 1ST SOUTH STREET
MONTICELLO, UTAH (MS00439-RS)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the United States (U.S.) government
through the Defense Plant Corporation to provide vanadium during World War II. Various
government agencies operated the mill until 1947. In 1948 the Atomic Energy Commission
(AEC) obtained the mill and operated it under contract through 1959 to provide both uranium
and vanadium. Mill operations were tenninated on January 1,1960. In 1961, the mill tail-
ings piles were leveled and graded, covered with rock and soil, and seeded with native
grasses. During 1974 and 1975, the ore stockpiles were removed from the site, and the mill
foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city of
Monticello, in San Juan County, Utah. The site is bordered on the south and southeast by
land held by the U.S. Bureau of Land Management. Other boundaries are the city of Monti-
cello and private property.
During the AEC era, the mill processed approximately one million tons of uranium ore.
Vanadium and uranium were the only substances extracted in the milling process. Other
constituents of the ore remained in the tailings and were not separated prior to disposal.
During the years of active mill operation, the mill tailings were normally moist, so erosion
was minimal. However, throughout the mill's operating period, area residents used these
tailings as fill material and as aggregate in mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy (DOE)
initiated the Surplus Facilities Management Program (SFMP) in 1978 to ensure the safe
caretaking and decommissioning of government facilities that had been retired from service
but still had radioactive contamination. In 1980, the mill site at Monticello was accepted into
the SFMP, and the Monticello Remedial Action Project (MRAP) was established to restore
the government-owned mill site to safe levels of radioactivity, to dispose of or contain the
tailings in an environmentally safe manner, and to perform remedial actions on off-site
(vicinity) properties that had been contaminated by radioactive material resulting from mill
operations. The Monticello mill site and the tailings remain in the custody of the DOE Grand
Junction, Colorado, Projects Office. In 1983, remedial actions for vicinity properties were
separated from MRAP with establishment of the Monticello Vicinity Properties (MVP)
Project (US DOE 1990b).
"The verification of remedial action was performed by members of the Environmental Assessment Group in the
Environmental Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE
contract DE-AC05-96OR22464 with Lockheed Martin Energy Research Corporation.
2
During 1995, the RAC designated by DOE, performed remedial action on the vicinity
property that is the subject of this report, a single family residence located at 249 East 1st
South Street, Monticello, Utah. The remedial action plan required excavation of all exterior
contarnination. When the excavation was completed, the property was resurveyed, mcluding
soil sampling, to ensure the removal of all contamination, backfilled with uncontaminated
material, and restored to a condition comparable to that which existed prior to remedial
action (Geotech 1996).
The DOE adopted a policy to assign an independent contractor to verify the data
supporting the adequacy of remedial action and to confirm the site's compliance with DOE
guidelines. The Environmental Technology Section (ETS) of Oak Ridge National Labor-
atory (ORNL) has been assigned the responsibility of this task at the 249 East 1st South
Street site. This report describes the methods and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available documen-
tation adequately and accurately describes the post-remedial-action radiological conditions
ofthe entire property that is to be certified and (2) that the remedial action reduced contami-
nation to below applicable DOE guidelines (DOE 1990a).
Document Reviews
Review of the RAC property completion report (Geotech 1996) indicates the property
was remediated as evaluated by DOE on the basis of U.S. Environmental Protection Agency
standards and the DOE guidelines (US DOE 1990a). Excess residual radioactive materials
were present, thus it was appropriate to designate this property for remedial action.
The pre-remedial-action survey performed by the RAC identified 7 yd3 of mill tailings
6 inches deep. During the actual removal process, a total of 7 yd3 of contaminated earth and
uranium mill tailings, 6 inches deep, were removed from a 33 m2 area.
The RAC performed a post-excavation survey prior to backfilling the excavated areas.
This survey consisted of gamma scans with a scintillometer of the ground level of the struc-
ture, a surface scan of the exterior, and soil sampling. Samples representative of the bottom
15-cm (6-in.) soil layers of one excavated verification area were collected and blended to
form a representative composite soil sample.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation
levels have not been subtracted. Similarly, background concentrations have not been sub-
tracted from radionuclide concentrations in soil samples. Applicable DOE guidelines for
protection against radiation are given in Table 1.
Gamma Measurements
Gamma exposure rate measurements taken by the RAC at the ground-level ofthe resi-
dence ranged from 12 to 13 uR/h. Exterior surface gamma measurements taken from the
excavated areas prior to backfilling ranged from 16 to 19 uR/h.
Soil Sample Analysis
Prior to backfilling, the RAC collected soil samples representative of the excavated area
from the bottom 15-cm (6-in.) soil layers. These samples were blended to form a composite
soil sample representative of an average over the exterior verification area. The RAC's
analysis of this sample showed a ^Ra concentration of 3.9 pCi/g. ORNL ETS obtained this
sample and performed a confirmatory analysis which showed a 226Ra concentration of 3.7
pCi/g. These values are below the DOE guideline value of 15 pCi/g for soil layers > 15 cm
below the surface. Gamma ranges and/or soil sample results demonstrate compliance to the
DOE Hot Spot Guidelines for areas <25 m2 (Table 1). Results ofthe RAC and ORNL soil
sample analyses are given in Table 2.
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were determined
by the Alpha-track method. To monitor radon levels, the RAC placed three alpha-track de-
tectors on the ground floor of the residence located on this property for a period of approxi-
mately three months (from March 2,1995 to June 6,1995) prior to remedial action. ORNL
verified the placement and retrieval of the detectors at this property as part ofthe Type B
verification activities. The average annual working level (WL) of radon progeny concen-
tration, as determined by the TechVOps-Landauer Corporation, was 0.0141, which is below
the 0.03-WL guideline given in Table 1. The procedures and methods used to obtain the
annual average WL are deemed adequate and the results accurate by the IVC.
CONCLUSION
Results of the RAC soil sample analysis and confirmatory split soil sample analysis by
ORNL show that radionuclide concentrations are within applicable DOE guidelines. Based
on the results of the post-remedial-action data, which are confirmed by the verification
assessment data, these radiological measurements fall below the limits prescribed by DOE
guidelines. It is concluded that the site successfully meets the DOE remedial action objec-
tives.
4
Table 1. Applicable guidelines for protection against radiation
Mode of exposure
Radionuclide con-
centrations in soil
Exposure conditions
Maximum permissible con-
centration of 226Ra in soil
above background levels,
averaged over a 100-m2 area
Guideline value
5 pCi/g averaged over the
first 15 cm of soil below the
surface; 15 pCi/g when ave-
raged over 15-cm-thick soil
layers more than 15 cm
below the surface
Ra226 concentrations, in any
surface or subsurface area
less than 25 m2, is below the
guideline by a factor of
(1007A),/2, where A is the
area of the elevated region
0.03 WL
Radionuclide con-
centrations in soil
for Hot Spot areas
Maximum Permissible con-
centration of Ra226 in soil
above background level, for
areas less than 25 m2
Exposure to 222Rn
progeny
Average annual radon proge-
ny concentration (including
background)
(DOE 1990a)
5
Table 2. Results of ORNL analysis of the Remedial Action Contractor (RAC)
soil samples from 249 East 1st South Street, Monticello, Utah (MS00439-RS)
226Ra concentration (pCi/g)
ORNL RAC
sample sample Depth ORNL RAC
No." No/ (cm)
XI NCL 805 >15 3.7 3.9
° An X-type sample is a split of the sample taken by the remedial action contractor.
* Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated areas
were taken by the RAC, and these samples were blended to form a composite soil sample,
which represents an average over one of the verification areas.
6
REFERENCES
Geotech 1996. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00439-RS, Address: 249 East First South Street, Monticello,
Utah 84535. RUST Geotech, Grand Junction, Colorado, July 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment Group)
Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National Laboratory,
Grand Junction, Colorado.
U.S. DOE 1990a. Verification and Certification Protocol for the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination and
Decommissioning Program, Revision 3, November 1990. U.S. Department of Energy,
Washington, D.C.
U.S. DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision and
Record of Decision Summary. U.S. Department of Energy, Grand Junction Projects Office,
Grand Junction, Colorado.
DOE ID No.: MS-00464-RS
Property Address: 147 West First North Street
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech of Energy (PQE)
YES NO NOT TAKEN YES NO NOT TAKEN
Ra-226 is < 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [ ]
Ra-226 is <, 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2.
In-situ [ ] Lab [X]
Interior gamma is <, 20 /yR/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is < 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21,
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
I ] [X] [ ]
[X] [ ] [ ]
MM [ 1
[A [ J I ]
tM [ ] I ]
[*) I ] [ ]
[ ] [ ]
M [ ] [ ]
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
•llllllllll Illlllll
SFCERTIFED SFMS-09036
DOE ID No.: MS-00464-RS
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
tAf/fC
Date
DOE EVALUATION
[ A Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Date
anda sby
Manager, onticello Programs
Rust Geotech
Certification Official7
U.S. Department of Energy
PROPERTY COMPLETION REPORT
DOE ID NO.: MS-00464-RS
ADDRESS: 147 WEST FIRST NORTH STREET
MONTICELLO, UTAH 84535
AUGUST 1996
Prepared for
U.S. Department of Energy
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
by
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
Manager, Monticello Programs
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.1.3 Radon Decay-Product Concentration (RDC) Measurement .... 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
i
DOE ID No.: MS-00464-RS
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Inclusion Survey Contractor. DOE reviewed
these evaluation results and determined that the property contained mill
tailings (residual radioactive material) exceeding DOE hot spot criteria.
The Remedial Action Contractor was notified of the inclusion of this
property into the MVP Project and was authorized by DOE to conduct
remedial action as required to bring the property into conformance with
EPA standards and DOE hot spot criteria.
1
DOE ID No.: MS-00464-RS
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
Property Address:
Property Owners:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
MS-00464-RS
Beginning 30 feet east of the NW corner of
Lot 12, Block K, Redd-Palmer Subdivision
Plat C, Monticello Townsite Addition; south
107.25 feet, west 30 feet, south
107.25 feet, west 100 feet, north
214.5 feet, east to beginning, County of
San Juan, State of Utah
147 West First North Street
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
August 20, 1992
Rust Geotech
November 16, 1993
Diamond Back Services, Inc.
9861 Titan Park Circle
Littleton, Colorado
August 30, 1994
September 26, 1994
Interior:
Exterior:
0 cubic yards
1 cubic yard
4 square meters (m2)
August 1996
2
DOE ID No.: MS-00464-RS
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of exterior residual radioactive
material (Appendix Figure 2.1). Once excavation was complete, the
affected areas were resurveyed for possible remaining residual radioactive
material and, upon attaining satisfactory results, were backfilled with
uncontaminated material. The property was restored to a physical
condition comparable to that which existed prior to remedial action
activities.
2.2 Previously Unidentified Contamination
The radiological assessment identified contamination, 6 inches deep,
within the property. The quantity of contamination for this property was
not specified because it was assessed as part of Block MS-09036-BK.
The remedial action process included the removal of approximately
1 cubic yard of residual radioactive material, 6 to 12 inches deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID No.: MS-00464-RS
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by the Remedial Action
Contractor during June 1992, as described in the final REA dated
November 1993. Appendix Figure 2.1 shows the extent of
assessed contamination and identifies the areas recommended to
undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the excavation were
collected. An individual soil sample was collected for Area V-2.
The remaining samples were blended to form a composite sample
representing Area V-3. Additionally, in-situ measurements were
taken for Areas V-1, V-4, and V-5 (Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 12 to 1,449 microroentgens per
hour (//R/h), as indicated on Appendix Figure 2.1. Elevated
exposure rates were associated with a point source (assay
samples) that was left in place at the owners' request. The results
of analyses for radium-226 in one individual soil sample and one
composite soil sample were 1.7 and 8.8 picocuries per
gram (pCi/g), as indicated in Appendix Table 3.1. In-situ
measurement results for radium-226 in Areas V-1, V-4, and V-5
were all less than 1.0 pCi/g (Appendix Table 3.1).
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on measurements representing an annual average, the RDC
was 0.0175 working level (WL), as indicated in Appendix
Table 3.2. Appendix Figure 2.1 shows the measurement location
on the ground floor (the lowest habitable level of the structure).
4
DOE ID No.: MS-00464-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at 147 West First North Street, in
Monticello, Utah, is recommended for certification as required by DOE
guidelines, and the appropriate records should be documented.
Certification Data Summary
Applicability
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Standards
Shall not exceed 20 //R/h
above background.*
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Survey Results
Range for the ground
floor was 12 to 13 //R/h.
Annual average was
0.0175 WL.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
In-situ measurements
were less than
1.0 pCi/g.**
Soil sample results were
1.7 and 8.8 pCi/g.**
*The background exposure rate is approximately 13//R/h.
The background radium-226 concentration is approximately 2.0 pCi/g.
**The hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-00464-RS
4.0 APPENDIX
Appendix Tables:
Table 3.1 Post-Excavation Sample/Measurement Results
Table 3.2 Radon Decay-Product Concentration Measurement
Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
SJW:7/23/96
MS-00464.RS WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00464-RS
Address: 147 West First North Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (/yR/h) Ticket No. Method8 (pCi/g)
V-1 15-16 DS < 1.0
V-2 19-23 NCF396 OCS 8.8
V-3 12-16 NCG 097 OCS 1.7
V-4 12 - 14 DS < 1.0
V-5 13-15 DS < 1.0
See Appendix Figure 2.1 for the verification areas.
flOCS = Opposed Crystal System; DS = Delta Scanner
7
Table 3.2
Radon Decay-Product Concentration Measurement Results
DOE ID No.: MS-00464-RS
Address: 147 West First North Street, Monticello, Utah
Instrument Type: Landauer Radtrak Detector
Detector
Number Start Date End Date
Radon
Concentration
(pCi/L)
Working
Level
3851666
3851508
3851530
10-10-94
10-10-94
10-10-94
09-27-95
09-27-95
09-27-95
3.75
3.45
3.27
0.0188
0.0173.
0.0164
Annual Average: 0.0175
See Appendix Figure 2.1 for the measurement location.
8
10
30
28
26
24
22
20
18
16
1 4
12
Y
10
12 14 16 18 20 22
i—T
12
12-14 V-3 V-1 LLL 7 12-16 5-16
V-5
V-3 13-15
12-16
Id 1 ONE STORY
BRICK AND FRAME HOUSE
RDC) 12~13
12
V-2
19-23
I
12-14
DETAIL A
SHED —
13-15r
V-3
12-16
59-1,449
SHED
II 2—1 31
12-14
V-4
12-4
I DETAIL B
SCALE IN FEET
20 10 0 20 40
M:\FAS\033\0003\RM00464V 01/22/97 11:01 om S50730
— X
24 26
T
28 30
WEST FIRST NORTH ST.
rr
12
SEE DETAIL A
12-14
i | SEE DETAIL B Lji
•
t
L i2jii\
NOT TO SCALE
NORTH
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT. UTILITY LOCATION PLAT, OR OTHER IMPROVEMENT SURVEY
PLAT AND IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE, BUILDING. OR OTHER FUTURE IMPROVEMENT LINES.
®
<£>
r?.v7i
Lv.vj
12-15
12
V-1
16-17
(RDC)
-X-
32 34 36 38
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN //R/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE-RATE RANGE
RADON DECAY-PRODUCT CONCENTRATION
MEASUREMENT LOCATION
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
POINT SOURCES REMOVED
POINT SOURCE (ASSAY SAMPLES)
40
- 24
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
RESIOCNCE-NO. OF OCCUPANTS
NON-RESIDENCC-MAN-HRS./WK.
INSTRUUCNT MO.
U.S. DEPARTMENT OF ENERGY
GRANO JUNCTION PROJECTS OFFICE, COLORAOO
OES'GNED ^
HO*.-
, DATE
147 WEST FIRST NORTH STREET
MONTICELLO, UTAH
DATE APPROVAL OOE
ootioNo. MS-00464-RS
D.C.HO. 3-BQQ464-V1 ,M1 1 „ 1
30
28
26
22
20
18
16
1 4
12
10
10 12 14 16 18 20 22 24 26 28 30 32 34 36 38 40
I-
OAK RIDGE NATIONAL LABORATORY PHONE: [phone]
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION FAX: [phone]
FOR THE U.S. DEPARTMENT OF ENERGY
2597 B% Road
GRAND JUNCTION, COLORADO 81503
MAR 2 5 1997
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by the U.S.
Department of Energy for Residual Radioactive Material at Formerly Utilized Sites Remedial Action
Program (FUSRAP) and Remote Surplus Facilities Management Program Sites (SFMP) [Revision
2, March 1987]. This evaluation is based on an independent verification review of the Remedial
Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment of the 226Ra
concentration in the soil, indoor radon daughter concentration, and indoor gamma exposure rates at
this property.
This property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
Location Number: MS00464-RS
Location Address: 147 West 1st North Street
Monticello. Utah 84535
Property Owner:

Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
147 WEST 1ST NORTH STREET
MONTICELLO, UTAH (MS00464-RS)
M. K. Jensen
March 1997
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81503
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 4
REFERENCES 7
iii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 5
2. Results of ORNL analysis of the RAC soil samples from 147 West 1st North Street,
Monticello, Utah (MS00464-RS) 6
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site Decommissioning
Projects, U.S. Department of Energy. The author wishes to acknowledge A. R. Jones and A. D.
Laase for technical reviews.
vii
ABSTRACT
In 1980, the site of a vanadium and uranium mill at Monticello, Utah, was accepted into the
U.S. Department of Energy (DOE) Surplus Facilities Management Program, with the objectives of
restoring the government-owned mill site to safe levels of radioactivity, disposing of or containing
the tailings in an environmentally safe manner, and performing remedial actions on off-site (vicinity)
properties that had been contaminated by radioactive material resulting from mill operations. During
1994, the Remedial Action Contractor (RAC) designated by DOE, performed remedial action on the
vicinity property at 147 West 1st North Street, Monticello, Utah. The Environmental Technology
Section (ETS) of Oak Ridge National Laboratory was assigned the responsibility of verifying the
data supporting the adequacy of remedial action and confirming the site's compliance with DOE
guidelines. The ETS found that the site successfully meets the DOE remedial action objectives. All
deficiencies noted during the initial review have been resolved with the revised completion report.
Procedures used by the ETS are described in the Environmental Technology Section Procedures
Manual (ORNL 1993).
ix
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 147 WEST 1ST NORTH STREET
MONTICELLO, UTAH (MS00464-RS)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the United States (U.S.) government through
the Defense Plant Corporation to provide vanadium during World War II. Various government
agencies operated the mill until 1947. In 1948, the Atomic Energy Commission (AEC) obtained the
mill and operated it under contract through 1959 to provide both uranium and vanadium. Mill
operations were terminated on January 1, 1960. In 1961, the mill tailings piles were leveled and
graded, covered with rock and soil, and seeded with native grasses. During 1974 and 1975, the ore
stockpiles were removed from the site and the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city of
Monticello, in San Juan County, Utah. The site is bordered on the south and southeast by land held
by the U.S. Bureau of Land Management. Other boundaries are the city of Monticello and private
property.
During the AEC era, the mill processed approximately one million tons of uranium ore. Vana-
dium and uranium were the only substances extracted in the milling process. Other constituents of
the ore remained in the tailings and were not separated prior to disposal. During the years of active
mill operation, the mill tailings were normally moist, so erosion was minimal. However, throughout
the mill's operating period, area residents used these tailings as fill material and as aggregate in mortar
and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy (DOE) initiated
the Surplus Facilities Management Program (SFMP) in 1978 to ensure the safe caretaking and de-
commissioning of government facilities that had been retired from service but still had radioactive
contamination. In 1980, the mill site at Monticello was accepted into the SFMP, and the Monticello
Remedial Action Project (MRAP) was established to restore the government-owned mill site to safe
levels of radioactivity, to dispose of or contain the tailings in an environmentally safe manner, and to
perform remedial actions on off-site (vicinity) properties that had been contaminated by radioactive
material resulting from mill operations. The Monticello mill site and the tailings remain in the custody
of the DOE Grand Junction, Colorado, Projects Office. In 1983, remedial actions for vicinity
properties were separated from MRAP with establishment of the Monticello Vicinity Properties
(MVP) Project (US DOE 1990b).
"The verification of remedial action was performed by members ofthe Environmental Assessment Group in the Environmental
Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE contract DE-AC05-
960R22464 with Lockheed Martin Energy Research Corporation.
2
During 1994, the Remedial Action Contractor (RAC) designated by DOE, performed remedial
action on the vicinity property that is the subject of this report, a single family residence located at
147 West 1st North Street, Monticello, Utah. The remedial action plan required excavation of all
exterior contamination. When the excavation was completed, the property was resurveyed, including
soil sampling, to ensure the removal of all contamination, backfilled with uncontaminated material,
and restored to a condition comparable to that which existed prior to remedial action (Geotech 1996).
DOE adopted a policy to assign an independent contractor to verify the data supporting the
adequacy of remedial action and to confirm the site's compliance with DOE guidelines. The
Environmental Technology Section (ETS) of Oak Ridge National Laboratory (ORNL) has been
assigned the responsibility of this task at the 147 West 1st North Street site. This report describes
the methods and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available documentation
adequately and accurately describes the post-remedial-action radiological conditions of the entire
property that is to be certified and (2) that the remedial action reduced contamination to below
applicable DOE guidelines (US DOE 1990a).
Document Reviews
Review of the RAC property completion report (Geotech 1996) indicates the property was reme-
diated as evaluated by DOE on the basis of U.S. Environmental Protection Agency standards and
the DOE guidelines (US DOE 1990a). Excess residual radioactive materials were present, thus it
was appropriate to designate this property for remedial action.
This property was assessed as part of Block 36, therefore, the quantity of material assessed is
not available. During the actual removal process, a total of 1 yd3 of contaminated earth and uranium
mill tailings, 6 to 12 inches deep, were removed from a 4 m2 area.
The RAC performed a post-excavation survey prior to backfilling the excavated areas. This
survey consisted of gamma scans with a scintillometer of the ground level of the structure, a surface
scan of the exterior, and soil sampling. Samples representative of the bottom 15-cm (6-in.) soil
layers of one excavated verification area (V3) were collected and blended to form a representative
composite soil sample. An individual sample representative of the bottom 15 cm soil layer of area
V2 was also collected. In addition, in-situ delta measurements were taken at VI, V4, and V5 after
removal of point sources.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation levels have
not been subtracted. Similarly, background concentrations have not been subtracted from radionu-
clide concentrations in soil samples. Applicable DOE guidelines for protection against radiation are
given in Table 1.
Gamma Measurements
Gamma exposure rate measurements taken by the RAC at the ground-level of the residence
ranged from 12 to 13 uR/h. Exterior surface gamma measurements taken from the excavated areas
prior to backfilling ranged from 12 to 23 uR/h. Elevated gamma exposure rates of 59 to 1449 pR/h
remaining in one of the sheds are attributed to an assay sample belonging to the property owner.
Soil Sample Analysis
Prior to backfilling, the RAC collected soil samples representative of the excavated areas from
the bottom 15-cm (6-in.) soil layers. The samples from area V3 were blended to form a composite
soil sample representative of an average over the exterior verification area. An individual soil
sample was taken from the bottom 15-cm (6-in.) soil layer in area V2. The RAC's analysis of these
samples showed 226Ra concentrations ranging from 1.7 to 8.8 pCi/g. Additionally, in-situ delta
measurements taken at areas V1, V4, and V5 measured <1 pCi/g. ORNL ETS obtained the two soil
samples and performed a confirmatory analysis which showed 226Ra concentrations ranging from
2.4 to 12 pCi/g. These values are below the DOE guideline value of 15 pCi/g for soil layers > 15
cm below the surface. Gamma ranges and/or soil sample results demonstrate compliance to the DOE
Hot Spot Guidelines for areas <25 m2 (Table 1). Results of the RAC and ORNL soil sample analyses
are given in Table 2.
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were determined by the
Alpha-track method. To monitor radon levels, the RAC placed three alpha-track detectors on the
ground floor of the residence located on this property for a period of approximately one year (from
October 10, 1994 to September 27, 1995). The average annual working level (WL) of radon
progeny concentration, as determined by the Tech./Ops-Landauer Corporation, was 0.0175, which
is below the 0.03-WL guideline given in Table 1.
4
CONCLUSION
Results of RAC soil sample analysis and confirmatory split soil sample analysis by ORNL,
show that radionuclide concentrations are within applicable DOE guidelines. Based on the results
of the post-remedial-action data, which are confirmed by the verification assessment data, these
radiological measurements fall below the limits prescribed by DOE guidelines. All deficiencies
noted in the initial review have been identified and corrected in the revised completion report as
discussed in a meeting between the RAC and ORNL on January 15,1997. It is concluded that the
site successfully meets the DOE remedial action objectives.
5
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of 226Ra in soil
above background levels,
averaged over a 100-m2
area
5 pCi/g averaged over the first 15 cm
of soil below the surface; 15 pCi/g
when averaged over 15-cm-thick soil
layers more than 15 cm below the
surface
Radionuclide con-
centrations in soil
for Hot Spot areas
Exposure to 222Rn
progeny
Maximum Permissible con-
centration of Ra226 in soil
above background level,
for areas less than 25 m2
Average annual radon
progeny concentration
(including background)
Ra226 concentrations, in any surface
or subsurface area less than 25 m2,
is below the guideline by a factor of
(100/Af, where A is the area ofthe
elevated region
0.03 WL
(US DOE 1990a)
6
Table 2. Results of ORNL analysis of the RAC soil samples from
147 West 1st North Street, Monticello, Utah (MS00464-RS)
226Ra concentration
ORNL RAC (pCi/g)
sample sample Depth
No." No.* (cm) ORNL
RAC
X2 NCF396 >15 12 8.8
X3 NCG 097 >15 2.4 1.7
" An X-type sample is a split of the sample taken by the remedial action contractor.
* Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated areas were
taken by the RAC, and these samples were blended to form a composite soil sample, which
represents an average over one of the verification areas.
7
REFERENCES
Geotech 1996. Property Completion Report for Monticello Vicinity Property Remedial Action for
DOE ID NO: MS00464-RS, Address: 147 West First North Street, Monticello, Utah 84535, RUST
Geotech, Grand Junction, Colorado, August 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment Group)
Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National Laboratory, Grand
Junction, Colorado.
US DOE 1990a. Verification and Certification Protocol for the Office of Environmental Restoration,
Formerly Utilized Sites Remedial Action Programs and Decontamination and Decommissioning
Program. Revision 3, November 1990. U.S. Department of Energy, Washington, D.C.
US DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision and Record
of Decision Summary. U.S. Department of Energy, Grand Junction Projects Office, Grand Junction,
Colorado.
DOE ID No.: MS-00482-MR
Property Address: 564 Oak Crest Drive
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech of Energy (DOE)—
YES NO NOT TAKEN YES NO NOT TAKEN
Ra-226 is < 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2. [X]* [ ] [ ] [X] [ ] [ ]
In-situ [X] Lab [ ]
Ra-226 is < 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2. [X] [ ] [ ] [x] [ ] [ ]
In-situ [ ] Lab [X]
Interior gamma is < 20 //R/h
above background in any
occupied or habitable
structure. [X] [ ] [ ] [X] [ ] [ ]
The radon decay-product
concentration in any
occupied or habitable
structure is < 0.02
working level or, at
most, 0.03 working level. [X] [ ] [ ] [7>] [ ] [ ]
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21. [ ] [X] [ ] [ ] LX] [ ]
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987). [X] [ ] [ ] [V] [ ] [ ]
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
•llllllllll Ililllllllll
SFCERTIFED SFMS-00482
DOE ID No.: MS-00482-MR
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
/anda S/Busby'' Date
Manager, Monticello Programs
Rust Geotech
DOE EVALUATION
[V] Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
4 •4
icial Certification 01
U.S. Department of Energy
Date
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
DOE ID NO.: MS-00482-MR
ADDRESS: 564 OAK CREST DRIVE
MONTICELLO, UTAH 84535
JULY 1996
Prepared for
U.S. Department of Energy
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
' Wanda S. Busby
Manager, Monticello Programs
FOR
by
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.1.3 Radon Decay-Product Concentration (RDC) Measurement .... 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
i
DOE ID No.: MS-00482-MR
1.0 SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Inclusion Survey Contractor. DOE reviewed
these evaluation results and determined that the property contained mill
tailings (residual radioactive material) exceeding EPA standards. The
Remedial Action Contractor was notified of the inclusion of this property
into the MVP Project and was authorized by DOE to conduct remedial
action as required to bring the property into conformance with EPA
standards and DOE hot spot criteria.
1
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
Property Address:
Property Owners:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
DOE ID No.: MS-00482-MR
MS-00482-MR
Lot 21 and the E2 of Lot 20, Oak Heights,
City of Monticello, County of San Juan,
State of Utah
564 Oak Crest Drive
Monticello, Utah 84535

Major Residential (MR)
Oak Ridge National Laboratory
November 6, 1992
Rust Geotech
November 29, 1994
Diamond Back Services, Inc.
9861 Titan Park Circle
Littleton, Colorado
August 31, 1995
September 28, 1995
Interior: 16 cubic yards
Exterior: 1 cubic yard
22 square meters (m2)
July 1996
2
DOE ID No.: MS-00482-MR
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of interior and exterior residual
radioactive material (Appendix Figures 2.1a through 2.1d). Once
excavation was complete, the affected areas were resurveyed for possible
remaining residual radioactive material and, upon attaining satisfactory
results, were backfilled with uncontaminated material. The property was
restored to a physical condition comparable to that which existed prior to
remedial action activities.
2.2 Previously Unidentified Contamination
The radiological assessment identified 16 cubic yards of contamination,
ranging from 2 to 384 inches high, within the property. The remedial
action process included the removal of approximately 17 cubic yards of
residual radioactive material, ranging from 12 inches deep to 384 inches
high.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Figures 2.1a
through 2.1d.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID No.: MS-00482-MR
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by the Remedial Action
Contractor during August 1993 and September 1994, as described
in the final REA dated November 1994. Appendix Figures 2.1a
through 2.1d show the extent of assessed contamination and
identify the areas recommended to undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, an individual soil sample was collected
at the bottom of the exterior excavation (Appendix Figure 2.1).
Interior Findings: Surface exposure-rate values, determined during
the gamma scans, ranged from 13 to 17 microroentgens per
hour (//R/h) for the remediated portions of the partial basement, 13
to 16 //R/h for the rest of the partial basement, 11 to 13 //R/h for
the remediated portions and the rest of the ground floor, and 10 to
13 //R/h for the remediated portion and rest of the second floor
(Appendix Figures 2.1b, 2.1c and 2.1d).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 11 to 19 //R/h (Appendix
Figure 2.1a). The result of analysis for radium-226 in one
individual soil sample was less than 1.0 picocuries per
gram (pCi/g), as indicated in Appendix Table 3.1.
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on measurements representing an annual average, the RDC
was 0.0102 working level (WL), as indicated in Appendix
Table 3.2. Appendix Figure 2.1b shows the measurement location
in the partial basement (the lowest habitable level of the
structure). RDC measurements were taken by Oak Ridge National
Laboratory before remediation of the property.
4
DOE ID Nov. MS-00482-MR
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at 564 Oak Crest Drive, in Monticello,
Utah, is recommended for certification as required by DOE guidelines,
and the appropriate records should be documented.
Certification Data Summary
Applicability
Habitable Structures
Exposure Rate:
Standards
Shall not exceed 20 //R/h
above background.*
Survey Results
Exposure rate ranges
were 13 to 17 //R/h for
the remediated portions
of the partial basement,
13 to 16 //R/h for the rest
of the partial basement,
11 to 13 //R/h for the
remediated portions and
the rest of the ground
floor, and 10 to 13 //R/h
for the remediated
portion and rest of the
second floor.
Radon Decay-Product
Concentration:
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Annual average was
0.0102 WL.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
< 5 pCi/g above
background.**
Soil sample result was
< 1.0pCi/g.**
*The background exposure rate is approximately 14//R/h.
The background radium-226 concentration is approximately 2.0 pCi/g.
* *The hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-00482-MR
4.0 APPENDIX
Appendix Tables:
Table 3.1 Post-Excavation Sample/Measurement Results
Table 3.2 Radon Decay-Product Concentration Measurement
Results
Appendix Figures:
Figure 2.1a Exterior Extent of Contamination - RADIOLOGICAL AS-BUILT
Figures 2.1 b Interior Extent of Contamination - RADIOLOGICAL AS-BUILT
through 2.1d
SJW:06-06-96
MS-00482.MR WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00482-MR
Address: 564 Oak Crest Drive, Monticello, Utah
A less-than sign (<) indicates that the minimum detection limit based on Compton
background was reached.
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (//R/h) Ticket No. Method" (pCi/g)
EXTERIOR
V-2 17-19 NCL 739 OCS < 1.0
INTERIOR
V-1 13-17 Not applicable
V-3 11-13 Not applicable
V-4 10-13 Not applicable
See Appendix Figures 2.1a through 2.1d for the verification areas.
"OCS = Opposed Crystal System
7
Table 3.2
Radon Decay-Product Concentration Measurement Results
DOE ID No.: MS-00482-MR
Address: 564 Oak Crest Drive, Monticello, Utah
Instrument Type: Landauer Radtrak Detector
Radon
Detector Concentration Working
Number Start Date End Date (pCi/L) Level
1621711
1514039
1621708
11-02-89
11-02-89
11-02-89
10-16-90
10-16-90
10-16-90
2.00
2.10
2.00
0.0100
0.0105
0.0100
Annual Average: 0.0102
See Appendix Figure 2.1b for the measurement location.
8
10
30
28
26
24
22 -
20
18 -
1 6
1 4
12
10
12 1 4 1 6 18 20 22 24 26 28
1 1 1 f I
r
13-15
GARAGE
11-13
13-15
TWO STORY FRAME HOUSE
W/PARTIAL BASEMENT
SEE FIGURES 2.1b, 2.1c
AND 2.1 d
v-2
17-19
A) 24 12
13-15
•777-
M:\FAS\033\0003\RM00432V 06/27/96 1:12pm T50780
-777-"777"
OAK CREST DRIVE
J I I I I
30
©
LV.VJ
12-15
12
V-1
16-17
[12]
32 34 36 38
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN juR/h
ASSESSED AREA IDENTIFIER
AREA OF ASSESSED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE-RATE RANGE
HEIGHT IN INCHES OF ASSESSED CONTAMINATED
BRICK AND MORTAR REMOVED AND REPLACED
NORTH
SCALE IN FEET
20 10 0 20 40
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT. UTILITY LOCATION PLAT, OR OTHER IMPROVEMENT SURVEY
PLAT AND IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE, BUILDING, OR OTHER FUTURE IMPROVEMENT LINES.
RADIOLOGICAL AS-BUILT
FIGURE 2.1a
EXTERIOR EXTENT OF CONTAMINATION
NO. DATE
RESIDENCE-NO. OF OCCUPANTS
NON-RESIDENCE-MAN-HRS./WK.
INSTRUMENT NO.
SURVEY OATE
VERIFICATION
40
CK. AC. APP.
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE. COLORADO
DESIGNED IS
CHECKED
PRO/, CNGR.
SUBMITTED
35i
564 OAK CREST DRIVE
MONTICELLO, UTAH
Rust Qeotech
AVWJTii>«*>.iC»gM
0*75 I APPROVAL OOC
OOCIDNO. MS-00482-MR
0.C.N0. 3-B00482-V1 ,HT 1 or 4
30
28
26
24
22
20
18
16
1 4
12
10
10 12 14 1 6 18 20 22 24 26 28 30 32 34 36 38 40
10
30
12 1 4 16 18 20 22 24 26 28
i—r
30 32 34 36 38 40
30
28
26
24
22
20
18 —
16
14
12
Y
10
PARTIAL BASEMENT
13-16
V-1
13-17
RDC
B) 2
NOT TO SCALE
NORTH
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT, UTILITY LOCATION PLAT, OR OTHER IMPROVEMENT SURVEY
PLAT AND IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE, BUILDING, OR OTHER FUTURE IMPROVEMENT LINES.
X M:\FAS\033\0003\RA00482V 06/26/96 11:10am T50780
©
r7.\Yi
Lv.vj
12-15
12
v-i
16-17
[12]
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN /iR/h
ASSESSED AREA IDENTIFIER
AREA OF ASSESSED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION AREA IDENTIFIER AND
EXCAVATION EXPOSURE-RATE RANGE
RADON DECAY-PRODUCT CONCENTRATION
MEASUREMENT LOCATION
HEIGHT IN INCHES OF ASSESSED CONTAMINATED
MORTARED HEARTH REMOVED BUT NOT REPLACED
28
26
24
22
20
18
RADIOLOGICAL AS-BUILT
FIGURE 2.1b
INTERIOR EXTENT OF CONTAMINATION
16
RESIDENCE-NO. OF OCCUPANTS
NON-RESIDENCE-UAN-HRS./WK.
INSTRUUENT NO.
SURVEY DATE
VERIFICATION
rr CK. A.C. APP.
14
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE. COLORAOO
a ML 564 OAK CREST DRIVE
MONTICELLO, UTAH
12
Rust Qeotech
AWiaVrtoglMCOTav
OATE I APPROVAL DOE •DATT
OOCIDNO. MS-00482-MR
OWC.NO. 3-BQ0482-V2 8H, 2 „ 4
10
10 12 1 4 1 6 18 20 22 24 26 28 30 32 34 36 38 40
10
30
28
26
24 -
22 -
20
18
16
1 4
12
12 14 1 6 18 20 22 24 26 28 30
x-x-42
36
D)[ 50 J*"* 42
V-3 GROUND FLOOR
11-13 11-13
c)[2r" v-3
11-13
E)[36]
X-X [42] [36 X-X [46
E)[36j*"*
NOT TO SCALE
[46]
Y
10
©
LV.vj
12-15
v-1
16-17
[12]
[12]
-X-
X"X"
F)[29] x-x-
32 34 36 38
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN /iR/h
ASSESSED AREA IDENTIFIER
AREA OF ASSESSED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
VERIFICATION AREA IDENTIFIER AND
EXCAVATION EXPOSURE-RATE RANGE
HEIGHT IN INCHES OF ASSESSED CONTAMINATED
MORTARED HEARTH REMOVED BUT NOT REPLACED
HEIGHT IN INCHES OF ASSESSED CONTAMINATED
MORTAR REMOVED AND REPLACED
40
RADIOLOGICAL AS-BUILT
FIGURE 2.1c
INTERIOR EXTENT OF CONTAMINATION
M:\FAS\033\0003\R800482V 07/17/96 08:10am T50780
NORTH
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT. UTILITY LOCATION PLAT, OR OTHER IMPROVEMENT SURVEY
PLAT AND IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE, BUILDING, OR OTHER FUTURE IMPROVEMENT LINES.
I
RESIDENCE-NO. OF OCCUPANTS
NON-RESIOENCE-MAN-HRS./WK.
INSTRUUENT NO.
SURVEY DATE
VERIFICATION
BY CK. A.E. APP. NO. OATE BY CK. A.C. APP.
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE. COLORADO
CHECKED ^
PROJ ENCR. 3£
564 OAK CREST DRIVE
MONTICELLO, UTAH
GEOTECH INC.
OATE APPROVAL OOE
OOEIONO. MS-00482-MR
DwcHo. 3-B00482-V3 SHT 3 or 4
30
28
26
24
22
20
18
16
14
12
10
10 12 1 4 1 6 18 20 22 24 26 28 30 32 34 36 38 40
10
30
12 14
i—i 1 r
16 18 20 22 24 26 28 30 32 34 36 38 40
30
28
26
24
22
20
18
16
14
12
Y
10
SECOND FLOOR
10-13
G)[384l
V-4
10-13
NOT TO SCALE
NORTH
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT, UTILITY LOCATION PLAT, OR OTHER IMPROVEMENT SURVEY
PLAT AND IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE, BUILDING. OR OTHER FUTURE IMPROVEMENT LINES.
M:\FAS\033\0003\RC00482V 06/17/96 2:47pm T50780
I I I
®
Lv.vj
12-15
12
v-1
16-17
[12]
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN /iR/h
ASSESSED AREA IDENTIFIER
AREA OF ASSESSED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION AREA IDENTIFIER AND
EXCAVATION EXPOSURE-RATE RANGE
HEIGHT IN INCHES OF ASSESSED CONTAMINATED
CHIMNEY REMOVED BUT NOT REPLACED
RADIOLOGICAL AS-BUILT
FIGURE 2.1 d
INTERIOR EXTENT OF CONTAMINATION
RESIOENCE-NO. OF OCCUPANTS
NON-RESIOENCE-UAN-HRS./WK.
INSTRUUENT NO.
SURVEY DATE
CK. A.E. APP. 9Y CK. A.C. APP,
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE. COLORADO
•r-r DRAWN
fcRT
CHECKED
PROJ. EN
564 OAK CREST DRIVE
MONTICELLO, UTAH
APPROVAL
Rust Qeotech
APPROVAL DOE OATC
DOCIONO MS-00482-MR
owe.HO. 3-BQQ482-V4 MT 4 or 4
28
26
24
22
20
18
16
14
12
10
10 12 1 4 1 6 18 20 22 24 26 28 30 32 34 36 38 40
OAK RIDGE NATIONAL LABORATORY PHONE: [phone]
FAX: [phone] MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
FOR THE U.S. DEPARTMENT OF ENERGY
POST OFFICE BOX 2567
GRANO JUNCTION. COLORADO 81502 DEC 3 l 1996
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by the U.S.
Department of Energy for Residual Radioactive Material at Formerly Utilized Sites Remedial
Action Program (FUSRAP) and Remote Surplus Facilities Management Program Sites (SFMP)
[Revision 2, March 1987]. This evaluation is based on an independent verification review of the
Remedial Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment ofthe
226Ra concentration in the soil, indoor radon daughter concentration, and indoor gamma exposure
rates at this property.
This property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
Location Number:
Location Address:
MS00482-MR
564 Oak Crest Drive
Monticello. Utah 84535

•Sams
Property Owner:
Owner Address:
Tenant Name:
Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
564 OAK CREST DRIVE
MONTICELLO, UTAH (MS00482-MR)
N. F. Kirby
November 1996
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 3
REFERENCES 6
iii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 4
2. Results of ORNL analysis of the RAC soil samples from 564 Oak Crest Drive,
Monticello, Utah (MS00482-MR) 5
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site Deconimission-
ing Projects, U.S. Department of Energy. The author wishes to acknowledge M. K. Jensen for
analysis of soil samples and A. R. Jones and S. M. Smith for technical reviews.
vii
ABSTRACT
In 1980, the site of a vanadium and uranium mill at Monticello, Utah, was accepted into the
U.S. Department of Energy (DOE) Surplus Facilities Management Program, with the objectives
of restoring the government-owned mill site to safe levels of radioactivity, disposing of or
containing the tailings in an environmentally safe manner, and perforrning remedial actions on
off-site (vicinity) properties that had been contaminated by radioactive material resulting from
mill operations. During 1995, the Remedial Action Contractor (RAC), designated by DOE, per-
formed remedial action on the vicinity property at 564 Oak Crest Drive, Monticello, Utah. The
Environmental Technology Section (ETS) of Oak Ridge National Laboratory was assigned the
responsibility of verifying the data supporting the adequacy of remedial action and confirming
the site's compliance with DOE guidelines. All deficiencies noted in the initial review have been
resolved with additional documentation to the property folio. The ETS found that the site suc-
cessfully meets the DOE remedial action objectives. Procedures used by the ETS are described
in the Environmental Technology Section Procedures Manual (ORNL 1993).
ix
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 564 OAK CREST DRIVE
MONTICELLO, UTAH (MS00482-MR)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the United States (U.S.) government
through the Defense Plant Corporation to provide vanadium during World War II. Various
government agencies operated the mill until 1947. In 1948, the Atomic Energy Commission
(AEC) obtained the mill and operated it under contract through 1959 to provide both uranium
and vanadium. Mill operations were terminated on January 1,1960. In 1961, the mill tailings
piles were leveled and graded, covered with rock and soil, and seeded with native grasses.
During 1974 and 1975, the ore stockpiles were removed from the site, and the mill foundations
were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city of
Monticello, in San Juan County, Utah. The site is bordered on the south and southeast by land
held by the U.S. Bureau of Land Management. Other boundaries are the city of Monticello and
private property.
During the AEC era, the mill processed approximately one million tons of uranium ore.
Vanadium and uranium were the only substances extracted in the milling process. Other con-
stituents of the ore remained in the tailings and were not separated prior to disposal. During the
years of active mill operation, the mill tailings were normally moist, so erosion was minimal.
However, throughout the mill's operating period, area residents used these tailings as fill material
and as aggregate in mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy (DOE)
initiated the Surplus Facilities Management Program (SFMP) in 1978 to ensure the safe
caretaking and decommissioning of government facilities that had been retired from service but
still had radioactive contamination. In 1980, the mill site at Monticello was accepted into the
SFMP, and the Monticello Remedial Action Project (MRAP) was established to restore the
government-owned mill site to safe levels of radioactivity, to dispose of or contain the tailings
in an environmentally safe manner, and to perform remedial actions on off-site (vicinity)
properties that had been contaminated by radioactive material resulting from mill operations.
The Monticello mill site and the tailings remain in the custody of the DOE Grand Junction,
Colorado, Projects Office. In 1983, remedial actions for vicinity properties were separated from
MRAP with establishment of the Monticello Vicinity Properties (MVP) Project (US DOE
1990b).
*The verification of remedial action was performed by members of the Environmental Assessment Group in the Environmental
Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE contract DE-AC05-
960R22464 with Lockheed Martin Energy Research Corporation.
2
During 1995, the RAC, designated by DOE, performed remedial action on the vicinity
property that is the subject of this report, a single family residence located at 564 Oak Crest
Drive, Monticello, Utah. The remedial action plan required excavation of all exterior and
removal of all interior contamination. When the excavation and removal was complete the
property was resurveyed, including soil sampling, to ensure the removal of all contamination,
the exterior was backfilled with uncontaminated material and restored to a condition comparable
to that which existed prior to remedial action (Geotech 1996).
The DOE adopted a policy to assign an independent contractor to verify the data supporting
the adequacy of remedial action and to confirm the site's compliance with DOE guidelines. The
Environmental Technology Section (ETS) of Oak Ridge National Laboratory (ORNL) has been
assigned the responsibility of this task at the 564 Oak Crest Drive site. This report describes the
methods and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available documentation
adequately and accurately describes the post-remedial-action radiological conditions of the entire
property that is to be certified and (2) that the remedial action reduced contamination to below
applicable DOE guidelines (US DOE 1990a).
Document Reviews
Review of the RAC property completion report (Geotech 1996) indicates the property was
remediated as evaluated by DOE on the basis of U.S. Environmental Protection Agency stan-
dards and the DOE guidelines (US DOE 1990a). Excess residual radioactive materials were pre-
sent, thus it was appropriate to designate this property for remedial action.
The pre-remedial-action survey performed by the RAC identified 16 yd3 of mill tailings 2
to 384 inches high. During the actual removal process, a total of 17 yd3 of contaminated brick
and mortar with uranium mill tailings, 12 inches deep to 384 inches high, were removed from
a 22 m2 area.
The RAC performed a post-excavation survey prior to backfilling and reconstruction ofthe
excavated areas. This survey consisted of gamma scans with a scintillometer of the ground level
ofthe structure, surface gamma scans of the exterior, and soil sampling. An individual soil sam-
ple was collected for the verification area.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation levels
have not been subtracted. Similarly, background concentrations have not been subtracted from
radionuclide concentrations in soil samples. Applicable DOE guidelines for protection against
radiation are given in Table 1.
Gamma Measurements
Gamma exposure rate measurements taken by the RAC at the ground-level of the residence
ranged from 11 to 13 uR/h and on the second floor ranged from 10 to 13 uR/h. Exterior surface
gamma measurements taken from the excavated areas prior to backfilling ranged from 17 to 19
uR/h and the remainder of the exterior measurements ranged from 13 to 15 uR/h.
Soil Sample Analysis
Prior to backfilling, the RAC collected an individual soil sample representative of the
exterior excavated area from the bottom 15-cm (6-in.) soil layers. The RAC's analysis of this
sample showed a 226Ra concentration of <1.0 pCi/g. ORNL ETS obtained this sample and
performed a confirmatory analysis which showed a 226Ra concentration of 1.4 pCi/g. These
values are below the DOE guideline value of 15 pCi/g for soil layers >15 cm below the surface.
Gamma ranges and/or soil sample results in folio demonstrate compliance to the DOE Hot Spot
Guidelines for areas <25 m2 (Table 1). Results of the RAC and ORNL soil sample analyses are
given in Table 2.
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were determined by
the Alpha-track method during the inclusion survey. To monitor radon levels, ORNL placed
three alpha-track detectors in the partial basement of the residence located on this property for
a period of approximately one year (from November 2,1989 to October 16,1990). The average
annual working level (WL) of radon progeny concentration, as determined by the Tech./Ops-
Landauer Corporation, was 0.0102, which is below the 0.03-WL guideline given in Table 1.
CONCLUSION
Results ofthe RAC's gamma exposure rate measurement, soil sample analysis, and ORNL's
confirmatory split soil sample analysis and RDC results show that radionuclide concentrations
are within applicable DOE guidelines. Based on the results of the post-remedial-action data,
which are confirmed by the verification assessment data, these radiological measurements fall
below the limits prescribed by DOE guidelines. All deficiencies noted in the initial review have
been resolved by the RAC as discussed in a meeting between the RAC and ORNL on November
7,1996. It is concluded that the site successfully meets the DOE remedial action objectives.
4
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Radionuclide con-
centrations in soil
for Hot Spot areas
Exposure to ^Rn
progeny
Maximum permissible con-
centration of 226Ra in soil
above background levels,
averaged over a 100-m2
area
Maximum Permissible con-
centration of Ra226 in soil
above background level, for
areas less than 25 m2
Average annual radon
progeny concentration
(including background)
5 pCi/g averaged over the first
15 cm of soil below the
surface; 15 pCi/g when ave-
raged over 15-cm-thick soil
layers more than 15 cm below
the surface
Ra226 concentrations, in any
surface or subsurface area less
than 25 m2, is below the
guideline by a factor of
(100/A)'/j, where A is the area
of the elevated region
0.03 WL
(US DOE 1990a)
5
Table 2. Results of ORNL analysis ofthe RAC soil samples from
564 Oak Crest Drive, Monticello, Utah (MS00482-MR)
226Ra concentration (pCi/g)
ORNL RAC
sample sample Depth ORNL RAC
No.fl No (cm)
X2 NCL739 >15 1.4 <1.0
a An X-type sample is a split of the sample taken by the remedial action contractor.
REFERENCES
Geotech 1996. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00482-MR, Address: 564 Oak Crest Drive, Monticello, Utah
84535, RUST Geotech, Grand Junction, Colorado, July 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment Group)
Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National Laboratory,
Grand Junction, Colorado.
US DOE 1990a. Verification and Certification Protocol for the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination and
Decommissioning Program. Revision 3, November 1990. U.S. Department of Energy,
Washington, D.C.
US DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision and
Record of Decision Summary. U.S. Department of Energy, Grand Junction Projects Office,
Grand Junction, Colorado.
DOE ID No.: MS-00499-MR
Property Address: 416 West Center Street
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Gftotech of Energy (DOE)
Ra-226 is ^ 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [ ]
Ra-226 is <. 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2.
In-situ [ ] Lab [ ]
Interior gamma is <; 20 //R/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is £ 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21.
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[ ] [ ] [X]
[X] [ ] [ ]
[X] [ ] [ ]
t ] [X] [ ]
[X] [ ] t ]
YES NO NOT TAKEN
[X] [ ] [ ]
[ ] [ ]
M [ ] [ 1
[V] [ ] [ ]
[ ] m [ 1
[V/] [ ] [ ]
COMMENTS: *Surface areas were verified on the basis of gamma exposure
rates that do not exceed 30 percent above normal background. • SFCERTIFED III
SFMS-00499
t 1
DOE ID No.: MS-00499-MR
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Wanda S. Busby / 7 Date
Manager, Monticello Programs
Rust Geotech
DOE EVALUATION
[X] Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
<L4,
Ceftificatiot
U.S. Department of Energy
Date
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00499-MR
ADDRESS: 416 WEST CENTER STREET
MONTICELLO, UTAH 84535
JUNE 1996
Prepared for
U.S. Department of Energy
by
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
Wanda S. Busby '
Manager, Monticello Programs
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
™,IIIMI Ililllllllll
SFMS-00499
TABLE OF CONTENTS
Section Page
1.0 SUMMARY . . . . 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.1.3 Radon Decay-Product Concentration (RDC) Measurement .... 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
i
DOE ID No.: MS-00499-MR
1.0 SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Inclusion Survey Contractor. DOE reviewed
these evaluation results and determined that the property contained mill
tailings (residual radioactive material) exceeding EPA standards. The
Remedial Action Contractor was notified of the inclusion of this property
into the MVP Project and was authorized by DOE to conduct remedial
action as required to bring the property into conformance with EPA
standards and DOE hot spot criteria.
1
DOE ID No.: MS-00499-MR
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
Property Address:
Property Owners:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
MS-00499-MR
Beginning at a point which is east 230 feet
and south 40 feet from the NE corner of
Lot 40, Blue Mountain Heights No. 2
Subdivision, and an addition to the City of
Monticello, Utah; south 110 feet, east
110 feet, north 110 feet, west 110 feet to
point of beginning, subject to existing
easements, waterways, roadways, and
other land use restrictions, County of San
Juan, State of Utah
416 West Center Street
Monticello, Utah 84535

Major Residential (MR)
Oak Ridge National Laboratory
September 22, 1993
Rust Geotech
November 30, 1994
Diamond Back Services. Inc.
9861 Titan Park Circle
Littleton, Colorado
June 15, 1995
August 22, 1995
Interior: 7 cubic yards
Exterior: 0 cubic yards
2 square meters (m2)
June 1996
2
DOE ID No.: MS-00499-MR
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of interior residual radioactive
material (Appendix Figure 2.1). Once removal was complete, the affected
area was resurveyed for possible remaining residual radioactive material
and, upon attaining satisfactory results, was reconstructed with
uncontaminated material. The property was restored to a physical
condition comparable to that which existed prior to remedial action
activities.
2.2 Previously Unidentified Contamination
The radiological assessment identified approximately 7 cubic yards of
contamination within the property. The remedial action process included
the removal of approximately 7 cubic yards of residual radioactive
material, ranging from 42 to 180 inches high.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID No.: MS-00499-MR
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by the Remedial Action
Contractor during April 1994, as described in the final REA dated
November 1994. Appendix Figure 2.1 shows the extent of
assessed contamination and identifies the area recommended to
undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to
reconstruction.
Interior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 13 to 16 microroentgens per
hour (jt/R/h) for the remediated portion of the ground floor, and 12
to 16//R/h for the rest of the ground floor (Appendix Figure 2.1).
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on measurements representing an annual average, the RDC
was 0.0085 working level (WL), as indicated in Appendix
Table 3.1. Appendix Figure 2.1 shows the measurement location
on the ground floor (the lowest habitable level of the structure).
RDC measurements were taken by Oak Ridge National Laboratory
before remediation of the property.
4
DOE ID No.: MS-00499-MR
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at 416 West Center Street, in
Monticello, Utah, is recommended for certification as required by DOE
guidelines, and the appropriate records should be documented.
Certification Data Summary
Applicability
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Standards
Shall not exceed 20 //R/h
above background.*
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Survey Results
Ranges were 13 to
16 //R/h for the
remediated portion of the
ground floor, and 12 to
16 //R/h for the rest of
the ground floor.
Annual average was
0.0085 WL.
Land
Radium-226 Concentration
in Surface Soil:
Shall not exceed
5 picocuries per gram
(pCi/g) above background
in the 15-cm surface
layer, averaged over
100 m2.
< 5 pCi/g above
background.
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 15 pCi/g
above background in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
< 15 pCi/g above
background.
*The background exposure rate is approximately 14//R/h.
The hot spot criteria were met based on gamma scans.
5
DOE ID No.: MS-00499-MR
4.0 APPENDIX
Appendix Table:
Table 3.1 Radon Decay-Product Concentration Measurement
Results
Appendix Figure:
Figure 2.1 Interior Extent of Contamination - RADIOLOGICAL
AS-BUILT
RKJ:06-07-96
MS-00499.MR WP61
REV080195
6
Table 3.1
Radon Decay-Product Concentration Measurement Results
DOE ID No.: MS-00499-MR
Address: 416 West Center Street, Monticello, Utah
Instrument Type: Landauer Radtrak Detector
Detector
Number Start Date End Date
Radon
Concentration
(pCi/L)
Working
Level
3275834
3275832
3275874
09-30-91
09-30-91
09-30-91
09-10-92
09-10-92
09-10-92
1.70
1.70
1.70
0.0085
0.0085
0.0085
Annual Average: 0.0085
See Appendix Figure 2.1 for the measurement location.
7
30
28
26
24
22
20
18
16
n 10-16
SHED
11-12
LU
Lu
rr
Ln
SEE
DETAIL A Lfi
LU
X
rr 12-16 ZD
o
ONE STORY
FRAME HOUSE
rr o
10-16
10-16
14
12
Y
^CENTER STREET
10
SCALE IN FEET
20 10 0 20 40
M:\FAS\033\0003\RM00499V 06/14/96 2:31pm T50780
J I I I I I L_
ft
NORTH
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT, UTILITY LOCATION PLAT. OR OTHER IMPROVEMENT SURVEY
PLAT AND IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE. BUILDING, OR OTHER FUTURE IMPROVEMENT LINES.
©
LV.vj
12-15
v-1
16-17
[12]
v-i 180]
13-16
[42](A 96
GROUND
FLOOR RDC
DETAIL A
NOT TO SCALE
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN ^R/h
ASSESSED AREA IDENTIFIER
AREA OF ASSESSED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
VERIFICATION AREA IDENTIFIER AND
EXPOSURE-RATE RANGE
OAK RIDGE NATIONAL LABORATORY RADON
DECAY-PRODUCT CONCENTRATION MEASUREMENT
LOCATION
HEIGHT IN INCHES OF ASSESSED CONTAMINATED
WALLS, FIREPLACE, AND CHIMNEY REMOVED
AND REPLACED
28
- 26
24
RADIOLOGICAL AS-BUILT
FIGURE 2.1
INTERIOR EXTENT OF CONTAMINATION
RESIOENCE-NO. OF OCCUPANTS
NON-RESIOENCE-MAN-HBS./WK.
INSTRUMENT NO.
SURVEY OATE
CK. A.E. APP. NO. DATE
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE, COtORADO
416 WEST CENTER STREET
MONTICELLO, UTAH
APPROVAL
Rust Geotech
AttMtl
DATI I APPROVAL DOE
OOEIDNO. MS-00499-MR
DWC.NO. 3-B00499-V1 ,„ 1 nr 1
22
20
18
16
14
12
10
10 12 1 4 16 18 20 22 24 26 28 30 32 34 36 38 40
OAK RIDGE NATIONAL LABORATORY PHONE: pro) 2+WK200
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION FAX: [phone]
FOR THE U.S. DEPARTMENT OF ENERGY
POST OFFICE BOX 2567
GRAND JUNCTION, COLORADO 81502 m 3 0 1996
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by the U.S.
Department of Energy for Residual Radioactive Material at Formerly Utilized Sites Remedial Action
Program (FUSRAP) and Remote Surplus Facilities Management Program Sites (SFMP) [Revision
2, March 1987]. This evaluation is based on an independent verification review of the Remedial
Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment ofthe
indoor radon daughter concentration and indoor gamma exposure rates at this property.
This property is recommended for certification by the U.S. Department of Energy.
Sincerely,
A"r^
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
Location Number: MS00499-MR
Location Address: 416 West Center Street
Monticello. Utah 84535
Property Owner:

Tenant Name: Same
Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
416 WEST CENTER STREET
MONTICELLO, UTAH (MS00499-MR)
N. F. Kirby
August 1996
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Radon Measurement Results 3
CONCLUSION 3
REFERENCES 5
iii
LIST OF TABLES
Applicable guidelines for protection against radiation
IV
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site
Decommissioning Projects, U.S. Department of Energy. The author wishes to
acknowledge A. R. Jones and M. K. Jensen for technical reviews.
Vll
ABSTRACT
In 1980 the site of a vanadium and uranium mill at Monticello, Utah, was accepted
into the U.S. Department of Energy's (DOE's) Surplus Facilities Management Program,
with the objectives of restoring the government-owned mill site to safe levels of radio-
activity, disposing of or containing the tailings in an environmentally safe manner, and
performing remedial actions on off-site (vicinity) properties that had been contaminated
by radioactive material resulting from mill operations. During 1995, RUST Geotech, the
remedial action contractor designated by DOE, performed remedial action on the vicinity
property at 416 West Center Street, Monticello, Utah. The Environmental Technology
Section (ETS) of Oak Ridge National Laboratory was assigned the responsibility of veri-
fying the data supporting the adequacy of remedial action and confirming the site's compli
ance with DOE guidelines. The ETS found that the site successfully meets the DOE re-
medial action objectives. Procedures used by the ETS are described in the Environmental
Technology Section Procedures Manual (ORNL 1993).
IX
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 416 WEST CENTER STREET
MONTICELLO, UTAH (MS00499-MR)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the U.S. government through the
Defense Plant Corporation to provide vanadium during World War II. Various govern-
ment agencies operated the mill until 1947. In 1948 the Atomic Energy Commission
(AEC) obtained the mill and operated it under contract through 1959 to provide both
uranium and vanadium. Mill operations were terminated on January 1, 1960. In 1961 the
mill tailings piles were leveled and graded, covered with rock and soil, and seeded with na-
tive grasses. During 1974 and 1975, the ore stockpiles were removed from the site, and
the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city
of Monticello, in San Juan County, Utah. The site is bordered on the south and southeast
by land held by the U.S. Bureau of Land Management. Other boundaries are the city of
Monticello and private property.
During the AEC era, the mill processed approximately one million tons of uranium
ore. Vanadium and uranium were the only substances extracted in the milling process.
Other constituents of the ore remained in the tailings and were not separated prior to dis-
posal. During the years of active mill operation, the mill tailings were normally moist, so
erosion was minimal. However, throughout the mill's operating period, area residents
used these tailings as fill material and as aggregate in mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy
(DOE) initiated the Surplus Facilities Management Program (SFMP) in 1978 to ensure
the safe caretaking and decommissioning of government facilities that had been retired
from service but still had radioactive contamination. In 1980 the mill site at Monticello
was accepted into the SFMP, and the Monticello Remedial Action Project (MRAP) was
established to restore the government-owned mill site to safe levels of radioactivity, to
dispose of or contain the tailings in an environmentally safe manner, and to perform reme-
dial actions on off-site (vicinity) properties that had been contaminated by radioactive ma-
terial resulting from mill operations. The Monticello mill site and the tailings remain in the
custody of the DOE Grand Junction, Colorado, Projects Office. In 1983 remedial actions
for vicinity properties were separated from MRAP with establishment of the Monticello
Vicinity Properties (MVP) Project (U.S. DOE 1990b).
"The verification of remedial action was performed by members of the Environmental Assessment Group in the
Environmental Technology Section ofthe Health Sciences Research Division at Oak Ridge National Laboratory under DOE contract
DE-AC05-96OR22464 with Lockheed Martin Energy Research Corporation.
2
During 1995, RUST Geotech Inc. (Geotech), the remedial action contractor (RAC)
designated by DOE, performed remedial action on the vicinity property that is the subject
of this report, a single family residence located at 416 West Center Street, Monticello,
Utah. The remedial action plan required removal of all interior contamination. When the
remediation was completed, the property was resurveyed to ensure the removal of all con-
tamination and restored to a condition comparable to that which existed prior to remedial
action (Geotech 1996).
The DOE adopted a policy to assign an independent contractor to verify the data sup
porting the adequacy of remedial action and to confirm the site's compliance with DOE
guidelines. The Environmental Technology Section (ETS) of Oak Ridge National Labor-
atory (ORNL) has been assigned the responsibility of this task at the 416 West Center
Street site. This report describes the methods and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available doc-
umentation adequately and accurately describes the post-remedial-action radiological
conditions of the entire property that is to be certified and (2) that the remedial action
reduced contamination to below applicable DOE guidelines (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1996) in-
dicates the property was remediated as evaluated by DOE on the basis of Environmental
Protection Agency standards and the DOE guidelines (DOE 1990a). Excess residual
radioactive materials were present, thus it was appropriate to designate this property for
remedial action.
The pre-remedial-action survey performed by Geotech identified 7 yd3 of mill tailings.
During the actual removal process, a total of 7 yd3 of contaminated brick and mortar
containing uranium mill tailings, 42 to 180 inches high, were removed from a 2 m2 area.
A post-excavation survey was performed by Geotech prior to reconstruction. This
survey consisted of gamma scans with a scintillometer of the ground level of the structure,
and the verification area.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation
levels have not been subtracted. Applicable DOE guidelines for protection against
radiation are given in Table 1.
Gamma Measurements
Gamma exposure rate measurements taken by Geotech from the remediated area of
the residence ranged from 13 to 16 uR/h and the remainder of the ground level ranged
from 12 to 16 uR/h. Exterior surface gamma measurements ranged from 10 to 16 pR/h.
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were deter-
mined by the Alpha-track method during the inclusion survey. To monitor radon levels,
Oak Ridge National Laboratory placed three alpha-track detectors on the ground floor
of the residence located on this property for a period of approximately one year (from
September 30, 1991 to September 10, 1992). The average annual working level (WL)
of radon progeny concentration, as determined by the Tech./Ops-Landauer Corporation,
was 0.0085, which is well below the 0.03-WL guideline given in Table 1.
CONCLUSION
Results of Geotech's gamma exposure rate measurements and ORNL's RDC results
show radionuclide concentrations are within applicable DOE guidelines. Based on the re-
sults ofthe post-remedial-action data, which are confirmed by the verification assessment
data, these radiological measurements fall below the limits prescribed by DOE guidelines.
It is concluded that the site successfully meets the DOE remedial action objectives.
4
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of 226Ra in soil
above background levels,
averaged over a 100-m2 area
5 pCi/g averaged over the
first 15 cm of soil below the
surface; 15 pCi/g when ave-
raged over 15-cm-thick soil
layers more than 15 cm
below the surface
Radionuclide con-
centrations in soil
for Hot Spot areas
Exposure to 222Rn
progeny
Maximum Permissible con-
centration of Ra226 in soil
above background level, for
areas less than 25 m2
Average annual radon proge-
ny concentration (including
background)
Ra concentrations, in any
surface or subsurface area
less than 25 m2, is below the
guideline by a factor of
(100/A)*, where A is the
area of the elevated region
0.03 WL
(DOE 1990a)
5
REFERENCES
Geotech 1996. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00499-MR, Address: 416 West Center Street, Monticello,
Utah 84535, Geotech, Grand Junction, Colorado, June 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
U.S. DOE 1990a. Verification and Certification Protocol for the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination
and Decommissioning Program, Revision 3, November 1990. U.S. Department of
Energy, Washington, D.C.
U. S. DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision
and Record of Decision Summary. U.S. Department of Energy, Grand Junction Projects
Office, Grand Junction, Colorado.
DOE ID No.: MS-00523-RS
Property Address: 164 West Center Street
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech of Energy (DQE)
Ra-226 is ^ 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [ ]
Ra-226 is < 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2.
In-situ [ ] Lab [X]
Interior gamma is <, 20 //R/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is <, 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21.
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
hfl [ ] [ 1
[ I
[X [ ] [ I
[ ] [Xl [ 1
[XI [ ] [ ]
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
Ililllllllll •Illlllll
SFCERTIFED SFMS-09036
DOE ID No.: MS-00523-RS
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
22 anda Date
Manager, Monticello Programs
Rust Geotech
DOE EVALUATION
[V] Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Date
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
DOE ID NO.: MS-00523-RS
ADDRESS: 164 WEST CENTER STREET
MONTICELLO, UTAH 84535
AUGUST 1996
Prepared for
U.S. Department of Energy
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
/ Wanda S. Busby
Manager, Monticello Programs
FOR
by
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.1.3 Radon Decay-Product Concentration (RDC) Measurement .... 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
DOE ID No.: MS-00523-RS
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Inclusion Survey Contractor. DOE reviewed
these evaluation results and determined that the property contained mill
tailings (residual radioactive material) exceeding EPA standards and DOE
hot spot criteria. The Remedial Action Contractor was notified of the
inclusion of this property into the MVP Project and was authorized by DOE
to conduct remedial action as required to bring the property into
conformance with EPA standards and DOE hot spot criteria.
1
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
Property Address:
Property Owner:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
DOE ID No.: MS-00523-RS
MS-00523-RS
Lot 9, Redd-Palmer Subdivision, Plat C,
Monticello Townsite Addition, County of
San Juan, State of Utah
164 West Center Street
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
January 31, 1991
Rust Geotech
November 16, 1993
Diamond Back Services, Inc.
9861 Titan Park Circle
Littleton, Colorado
August 30, 1994
September 27, 1994
Interior: 0 cubic yards
Exterior: 10 cubic yards
44 square meters (m2)
August 1996
2
DOE ID No.: MS-00523-RS
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of exterior residual radioactive
material (Appendix Figure 2.1). Once excavation was complete, the
affected areas were resurveyed for possible remaining residual radioactive
material and, upon attaining satisfactory results, were backfilled with
uncontaminated material. The property was restored to a physical
condition comparable to that which existed prior to remedial action
activities.
2.2 Previously Unidentified Contamination
The radiological assessment identified contamination, 6 inches deep,
within the property. The quantity of contamination for this property was
not specified because it was assessed as part of Block MS-09036-BK.
The remedial action process included the removal of approximately
10 cubic yards of residual radioactive material, ranging from 6 to
12 inches deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID No.: MS-00523-RS
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by the Remedial Action
Contractor during June 1992, as described in the final REA dated
November 1993. Appendix Figure 2.1 shows the extent of
assessed contamination and identifies the areas recommended to
undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the excavation were
collected. These samples were blended to form composite
samples representing the verification areas (Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 12 to 28 microroentgens per
hour (/yR/h), as indicated on Appendix Figure 2.1. The results of
analyses for radium-226 in three composite soil samples ranged
from 1.3 to 7.5 picocuries per gram (pCi/g), as indicated in
Appendix Table 3.1.
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on measurements representing an annual average, the RDC
was 0.0073 working level (WL), as indicated in Appendix
Table 3.2. Appendix Figure 2.1 shows the measurement location
in the partial basement (the lowest habitable level of the
structure).
4
DOE ID No.: MS-00523-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at 164 West Center Street, in
Monticello, Utah, is recommended for certification as required by DOE
guidelines, and the appropriate records should be documented.
Certification Data Summary
Applicability
Habitable Structures
Exposure Rate:
Standards
Shall not exceed 20 //R/h
above background.*
Survey Results
Ranges were 12 to
13 //R/h for the partial
basement, and 11 to
13 //R/h for the ground
floor.
Radon Decay-Product
Concentration:
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Annual average was
0.0073 WL.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
< 5 pCi/g above
background.**
Soil sample results
ranged from 1.3 to
7.5 pCi/g.**
*The background exposure rate is approximately 13 //R/h.
The background radium-226 concentration is approximately 2.0 pCi/g.
**The hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-00523-RS
4.0 APPENDIX
Appendix Tables:
Table 3.1 Post-Excavation Sample/Measurement Results
Table 3.2 Radon Decay-Product Concentration Measurement
Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
SJW:07-24-96
MS-00523.RS WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00523-RS
Address: 164 West Center Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range OwR/h) Ticket No. Method" (pCi/g)
V-1 18-28 NCG 098 OCS 7.5
V-2 13-19 NCG 101 OCS 4.2
V-3 15 - 24 NCA 960 OCS 1.3
See Appendix Figure 2.1 for the verification areas.
aOCS = Opposed Crystal System
7
Table 3.2
Radon Decay-Product Concentration Measurement Results
DOE ID No.: MS-00523-RS
Address: 164 West Center Street, Monticello, Utah
Instrument Type: Landauer Radtrak Detector
Detector
Number Start Date End Date
Radon
Concentration
(pCi/L)
Working
Level
3851581
3851615
3851624
10-10-94
10-10-94
10-10-94
09-27-95
09-27-95
09-27-95
1.29
1.45
1.60
0.0065
0.0073
0.0080
Annual Average: 0.0073
See Appendix Figure 2.1 for the measurement location.
8
42
40
38
36
34
32
30
28
26
24
22
20
18
16
14
12
10
I 12 14 16 18 20 22 24 26 28 30
—I 1 1 1 1 I I
32 34 36 38 40 42 44 46 48 50
T—r T i—r i r
12-16
V-2
U-19
V-3
15-24
TWO STORY
GARAGE v-l v-3
15-24 8-28 12-13 12-15
12-13
RDC
12-15
0
<D
12-15
12
v-i
16-17
ONE STORY
FRAME HOUSE
11- 13
W/PARTIAL
BASEMENT
12- 13
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN /iR/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE—RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE—RATE RANGE
RADON DECAY-PRODUCT CONCENTRATION
MEASUREMENT LOCATION
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
"777 777-
WEST CENTER STREET
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
L
SCALE IN FEET
20 10 0 20 40
U:\FAS\03J\0OOJ\RU00S23v 08/0/96 08:21am T507BO
12 14 16 18 20
NORTH
I
22
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT, UTILITY LOCATION PLAT. OR OTHER IMPROVEMENT SURVEY
PLAT AND IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE, BUILDING. OR OTHER FUTURE IMPROVEMENT LINES.
U.S. DEPARTMENT OF ENERGY
CMNO JUNCTION PftOjCCTS Office. COLORADO
9¥
164 WEST CENTER STREET
MONTICELLO. UTAH
I fell IJWIOMLMC
Rust CMMtMh MS-00523-RS
24 26 28 30 32 34 36 38 40 42 44 46 48 5C
OAK RIDGE NATIONAL LABORATORY
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
FOR THE U.S. DEPARTMENT OF ENERGY
2597 B*/. Road
GRAND JUNCTION, COLORADO 81503
PHONE: [phone]
FAX: [phone]
FEB 2 8 M7
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by the U.S.
Department of Energy for Residual Radioactive Material at Formerly Utilized Sites Remedial
Action Program (FUSRAP) and Remote Surplus Facilities Management Program Sites (SFMP)
[Revision 2, March 1987]. This evaluation is based on an independent verification review of the
Remedial Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment of the
226Ra concentration in the soil, indoor radon daughter concentration, and indoor gamma exposure
rates at this property.
This property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
Location Number: MS00523-RS
Location Address: 164 West Center Street
Monticello. Utah 84535
Property Owner:

Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
164 WEST CENTER STREET
MONTICELLO, UTAH (MS00523-RS)
M. K. Jensen
January 1997
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81503
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 4
REFERENCES 7
in
LIST OF TABLES
1. Applicable guidelines for protection against radiation 5
2. Results of ORNL analysis of the RAC soil samples from 164 West Center Street,
Monticello, Utah (MS00523-RS) 6
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site Decommissioning
Projects, U.S. Department of Energy. The author wishes to acknowledge A. R. Jones and A. D.
Laase for technical reviews.
vii
ABSTRACT
In 1980, the site of a vanadium and uranium mill at Monticello, Utah, was accepted into the
U.S. Department of Energy (DOE) Surplus Facilities Management Program, with the objectives of
restoring the government-owned mill site to safe levels of radioactivity, disposing of or containing
the tailings in an environmentally safe manner, and performing remedial actions on off-site (vicinity)
properties that had been contaminated by radioactive material resulting from mill operations. During
1994, the Remedial Action Contractor (RAC) designated by DOE, performed remedial action on the
vicinity property at 164 West Center Street, Monticello, Utah. The Environmental Technology
Section (ETS) of Oak Ridge National Laboratory was assigned the responsibility of verifying the
data supporting the adequacy of remedial action and confirming the site's compliance with DOE
guidelines. The ETS found that the site successfully meets the DOE remedial action objectives. All
deficiencies noted in the initial review have been resolved with the revised completion report and
additional documentation in the property folio. Procedures used by the ETS are described in the
Environmental Technology Section Procedures Manual (ORNL 1993).
ix
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 164 WEST CENTER STREET
MONTICELLO, UTAH (MS00523-RS)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the United States (U.S.) government through
the Defense Plant Corporation to provide vanadium during World War II. Various government
agencies operated the mill until 1947. In 1948, the Atomic Energy Commission (AEC) obtained the
mill and operated it under contract through 1959 to provide both uranium and vanadium. Mill
operations were terminated on January 1, 1960. In 1961, the mill tailings piles were leveled and
graded, covered with rock and soil, and seeded with native grasses. During 1974 and 1975, the ore
stockpiles were removed from the site and the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city of
Monticello, in San Juan County, Utah. The site is bordered on the south and southeast by land held
by the U.S. Bureau of Land Management. Other boundaries are the city of Monticello and private
property.
During the AEC era, the mill processed approximately one million tons of uranium ore. Vana-
dium and uranium were the only substances extracted in the milling process. Other constituents of
the ore remained in the tailings and were not separated prior to disposal. During the years of active
mill operation, the mill tailings were normally moist, so erosion was minimal. However, throughout
the mill's operating period, area residents used these tailings as fill material and as aggregate in mortar
and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy (DOE) initiated
the Surplus Facilities Management Program (SFMP) in 1978 to ensure the safe caretaking and de-
commissioning of government facilities that had been retired from service but still had radioactive
contamination. In 1980, the mill site at Monticello was accepted into the SFMP, and the Monticello
Remedial Action Project (MRAP) was established to restore the government-owned mill site to safe
levels of radioactivity, to dispose of or contain the tailings in an environmentally safe manner, and to
perform remedial actions on off-site (vicinity) properties that had been contaminated by radioactive
material resulting from mill operations. The Monticello mill site and the tailings remain in the custody
of the DOE Grand Junction, Colorado, Projects Office. In 1983, remedial actions for vicinity
properties were separated from MRAP with establishment of the Monticello Vicinity Properties
(MVP) Project (US DOE 1990b).
•The verification of remedial action was performed by members of the Environmental Assessment Group in the Environmental
Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE contract DE-AC05-
960R22464 with Lockheed Martin Energy Researcli Corporation.
2
During 1994, the Remedial Action Contractor (RAC) designated by DOE, performed remedial
action on the vicinity property that is the subject of this report, a single family residence located at
164 West Center Street, Monticello, Utah. The remedial action plan required excavation of all
exterior contamination. When the excavation was completed, the property was resurveyed, including
soil sampling, to ensure the removal of all contamination, backfilled with uncontaminated material,
and restored to a condition comparable to that which existed prior to remedial action (Geotech 1996).
DOE adopted a policy to assign an independent contractor to verify the data supporting the
adequacy of remedial action and to confirm the site's compliance with DOE guidelines. The Environ-
mental Technology Section (ETS) of Oak Ridge National Laboratory (ORNL) has been assigned the
responsibility of this task at the 164 West Center Street site. This report describes the methods and
results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available documentation
adequately and accurately describes the post-remedial-action radiological conditions of the entire
property that is to be certified and (2) that the remedial action reduced contamination to below
applicable DOE guidelines (US DOE 1990a).
Document Reviews
Review of the RAC property completion report (Geotech 1996) indicates the property was reme-
diated as evaluated by DOE on the basis of U.S. Environmental Protection Agency standards and the
DOE guidelines (US DOE 1990a). Excess residual radioactive materials were present, thus it was
appropriate to designate this property for remedial action.
This property was assessed as part of Block 36, therefore, the quantity of material assessed is
not available. During the actual removal process, a total of 10 yd3 of contaminated earth and uranium
mill tailings, 6 to 12 inches deep, were removed from a 44 m2 area.
The RAC performed a post-excavation survey prior to backfilling the excavated areas. This
survey consisted of gamma scans with a scintillometer of the ground level and partial basement ofthe
structure, a surface scan ofthe exterior, and soil sampling. Samples representative of the bottom 15-
cm (6-in.) soil layers of three excavated verification areas were collected and blended to form
representative composite soil samples for each verification area.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation levels have
not been subtracted. Similarly, background concentrations have not been subtracted from radionu-
clide concentrations in soil samples. Applicable DOE guidelines for protection against radiation are
given in Table 1.
Gamma Measurements
Gamma exposure rate measurements taken by the RAC in the basement and at the ground-level
of the residence ranged from 12 to 13 u.R/h and 11 to 13 pR/h, respectively. Exterior surface gamma
measurements taken from the excavated areas prior to backfilling ranged from 13 to 28 uR/h.
Soil Sample Analysis
Prior to backfilling, the RAC collected soil samples representative of the excavated areas from
the bottom 15-cm (6-in.) soil layers. These samples were blended to form composite soil samples
representative of an average over the three exterior verification areas. The RAC's analysis of these
samples showed 226Ra concentrations ranging from 1.3 to 7.5 pCi/g in the composite sample. ORNL
ETS obtained two of these samples and performed a confirmatory analysis which showed 226Ra
concentrations ranging from 6.4 to 11 pCi/g. These values are below the DOE guideline value of
15 pCi/g for soil layers > 15 cm below the surface. Results of the RAC and ORNL soil sample
analyses are given in Table 2.
As a result of a meeting between the RAC and IVC on May 26, 1994, anomalous readings,
defined as > 30% above the average of the excavation, will be investigated to show compliance to
the DOE hot spot guideline. The RAC remediated this property after this procedure change. The
IVC observed that 28 uR/h exceeds 30% of the excavation average of 23 pR/h. The IVC will allow
a correlation developed by the RAC to estimate 226Ra pCi/g concentrations based on gamma
exposure rates. The anomalous reading of 28 uR/h on this property using the RAC's correlation
yields a 226Ra concentration of 8.1 pCi/g. This value is well below the minimum concentration of
30 pCi/g needed, when assuming the maximum area under the hot spot guideline of 25 m2, for
subsurface samples. Gamma ranges and/or soil sample results demonstrate compliance to the DOE
Hot Spot Guidelines for areas <25 m2 (Table 1).
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were determined by the
Alpha-track method. To monitor radon levels, the RAC placed three alpha-track detectors on the
ground floor of the residence located on this property for a period of approximately one year (from
October 10, 1994 to September 27, 1995). The average annual working level (WL) of radon
progeny concentration, as determined by the Tech./Ops-Landauer Corporation, was 0.0073, which
is well below the 0.03-WL guideline given in Table 1.
4
CONCLUSION
Results of RAC soil sample analysis and confirmatory split soil sample analysis by ORNL,
show that radionuclide concentrations are within applicable DOE guidelines. Based on the results
of the post-remedial-action data, which are confirmed by the verification assessment data, these
radiological measurements fall below the limits prescribed by DOE guidelines. All deficiencies
noted in the initial review have been identified and corrected as discussed in a meeting between the
RAC and ORNL on January 15, 1997. It is concluded that the site successfully meets the DOE
remedial action objectives.
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of 226Ra in soil
above background levels,
averaged over a 100-m2
area
5 pCi/g averaged over the first 15 cm
of soil below the surface; 15 pCi/g
when averaged over 15-cm-thick soil
layers more than 15 cm below the
surface
Radionuclide con-
centrations in soil
for Hot Spot areas
Exposure to 222Rn
progeny
Maximum Permissible con-
centration of Ra226 in soil
above background level,
for areas less than 25 m2
Average annual radon
progeny concentration
(including background)
Ra226 concentrations, in any surface
or subsurface area less than 25 m2,
is below the guideline by a factor of
(100/A),/Y where A is the area of the
elevated region
0.03 WL
(US DOE 1990a)
6
Table 2. Results of ORNL analysis of the RAC soil samples from
164 West Center Street, Monticello, Utah (MS00523-RS)
226Ra concentration (pCi/g)
ORNL RAC
sample sample Depth ORNL RAC
No.° No^ (cm)
XI NCG 098 >15 11 7.5
X2 NCG 101 >15 6.4 4.2
" An X-type sample is a split of the sample taken by the remedial action contractor.
b Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated areas were
taken by the RAC, and these samples were blended to form a composite soil sample, which
represents an average over one of the verification areas.
7
REFERENCES
Geotech 1996. Property Completion Report for Monticello Vicinity Property Remedial Action for
DOE ID NO: MS00523-RS, Address: 164 West Center Street, Monticello, Utah 84535, RUST
Geotech, Grand Junction, Colorado, August 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment Group)
Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National Laboratory, Grand
Junction, Colorado.
US DOE 1990a. Verification and Certification Protocol for the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination and
Decommissioning Program. Revision 3, November 1990. U.S. Department of Energy, Washington,
D.C.
US DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision and Record
of Decision Summary. U.S. Department of Energy, Grand Junction Projects Office, Grand Junction,
Colorado.
DOE ID Nos.: MS-00524-RS
Property Address: 49 North First West Street
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech of Energy (PQE)
Ra-226 is * 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [ ]
Ra-226 is < 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2.
In-situ [ ] Lab [X]
Interior gamma is £ 20 //R/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is < 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21.
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
[/] I ] [ J
I ] [ J
[MM I 1
[ ] bd [ 1
[)f [ ] I ]
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
1INIII1IN1 1111111111
SFCERTIFED SFMS-09036
DOE ID No.: MS-00524-RS
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
'tun t/lifa
/anda S./Busby / Date
Manager, Monticello Programs
Rust Geotech
DOE EVALUATION
Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Cdftificati&n Official/
U.S. Department of Energy
3i ^ fy
Date
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00524-RS
ADDRESS: 49 NORTH FIRST WEST STREET
MONTICELLO, UTAH 84535
AUGUST 1996
Prepared for
U.S. Department of Energy
by
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
Manager, Monticello Programs
Wanda's! Busby^
ir, Montici
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.1.3 Radon Decay-Product Concentration (RDC) Measurement .... 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
i
DOE ID No.: MS-00524-RS
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Inclusion Survey Contractor. DOE reviewed
these evaluation results and determined that the property contained mill
tailings (residual radioactive material) exceeding EPA standards. The
Remedial Action Contractor was notified of the inclusion of this property
into the MVP Project and was authorized by DOE to conduct remedial
action as required to bring the property into conformance with EPA
standards and DOE hot spot criteria.
1
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
Property Address:
Property Owners:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
DOE ID No.: MS-00524-RS
MS-00524-RS
Lot 10, Redd-Palmer Subdivision, Plat C,
Monticello Townsite Addition, County of
San Juan, State of Utah
49 North First West Street
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
June 18, 1991
Rust Geotech
November 16, 1993
Diamond Back Services, Inc.
9861 Titan Park Circle
Littleton, Colorado
August 30, 1994
September 27, 1994
Interior: 0 cubic yards
Exterior: 29 cubic yards
147 square meters (m2)
August 1996
2
DOE ID No.: MS-00524-RS
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of exterior residual radioactive
material (Appendix Figure 2.1). Once excavation was complete, the
affected areas were resurveyed for possible remaining residual radioactive
material and, upon attaining satisfactory results, were backfilled with
uncontaminated material. The property was restored to a physical
condition comparable to that which existed prior to remedial action
activities.
2.2 Previously Unidentified Contamination
The radiological assessment identified contamination, 6 inches deep,
within the property. The quantity of contamination for this property was
not specified because it was assessed as part of Block MS-09036-BK.
The remedial action process included the removal of approximately
29 cubic yards of residual radioactive material, 6 inches deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID No.: MS-00524-RS
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by the Remedial Action
Contractor during June 1992, as described in the final REA dated
November 1993. Appendix Figure 2.1 shows the extent of
assessed contamination and identifies the areas recommended to
undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the excavation were
collected. These samples were blended to form composite
samples representing the verification areas (Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 12 to 18 microroentgens per
hour (jt/R/h), as indicated on Appendix Figure 2.1. The results of
analyses for radium-226 in two composite soil samples were 3.3
and 3.8 picocuries per gram (pCi/g), as indicated in Appendix
Table 3.1.
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on measurements representing an annual average, the RDC
was 0.0120 working level (WL), as indicated in Appendix
Table 3.2. Appendix Figure 2.1 shows the measurement location
on the ground floor (the lowest habitable level of the structure).
The partial basement was uninhabitable.
4
DOE ID No.: MS-00524-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at 49 North First West Street, in
Monticello, Utah, is recommended for certification as required by DOE
guidelines, and the appropriate records should be documented.
Certification Data Summary
Applicability
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Standards
Shall not exceed 20 //R/h
above background.*
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Shall not exceed 5 pCi/g
above background in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
Survey Results
Range for the ground
floor was 12 to 13 //R/h.
Annual average was
0.0120 WL.
< 5 pCi/g above
background.**
Soil sample results were
3.3 and 3.8 pCi/g.**
*The background exposure rate is approximately 13 //R/h.
The background radium-226 concentration is approximately 2.0 pCi/g.
**The hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-00524-RS
4.0 APPENDIX
Appendix Tables:
Table 3.1 Post-Excavation Sample/Measurement Results
Table 3.2 Radon Decay-Product Concentration Measurement
Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
SJW-.07-24-96
MS-00524.RS WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00524-RS
Address: 49 North First West Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (//R/h) Ticket No. Method" (pCi/g)
V-1 15-18 NCG 099 OCS 3.3
V-2 14-18 NCG 100 OCS 3.8
See Appendix Figure 2.1 for the verification areas.
"OCS = Opposed Crystal System
7
Table 3.2
Radon Decay-Product Concentration Measurement Results
DOE ID No.: MS-00524-RS
Address: 49 North First West Street, Monticello, Utah
Instrument Type: Landauer Radtrak Detector
Detector
Number Start Date End Date
Radon
Concentration
(pCi/L)
Working
Level
3851662
3851537
3851604
10-10-94
10-10-94
10-10-94
09-27-95
09-27-95
09-27-95
2.53
2.27
2.40
0.0127
0.0114
0.0120
Annual Average: 0.0120
See Appendix Figure 2.1 for the measurement location.
8
42
40
38
36
34
32
30
28
26
24
22
20
'18
16
14
12
10
12 14 16 18 20 22 24 26 28 30 32 34 36 38 40 42 44 46 48
T—i—i—i—i—i—i—i—i—i—i—i—i—i—i—i—i—i—i—i—!—i—i—i—i—i—i—i—i—i—i—i—i—i—i—i—i—i—T
12-14
0 V-l 0 15-18
•<D(D
LU
V-2
1*-1B
L_
«S>
SHED
12-13
SHED-
12-13
(RDC)
ONE STORY
FRAME HOUSE
WITH
UNINHABITABLE
BASEMENT
12-13
12-14
UJ
Ld
CC
r—
CO
CO
Ld
CO
CC
U-
X
r—
cc o
©
<D
Lv.vj
12-15
mi
V-1
16-17
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN MR/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE—RATE RANGE
RADON DECAY-PRODUCT CONCENTRATION
MEASUREMENT LOCATION
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
L
SCALE IN FEET
20 10 0 20 40
M:\FAS\033\0003\RU00324V 06/13/96 08:13am TS0790
) X I I 1 I I 1 L_
o
NORTH
THIS ORAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT OF ENERGY ANO ITS CONTRACTORS. IT IS NOT A LANO SURVEY PLAT, UTILITY LOCATION PLAT, OR OTHER IMPROVEMENT SURVEY PLAT ANO IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT OF FENCE, BUILDING, OR OTHER FUTURE IMPROVEMENT LINES.
Xt-*[|IBOKt-IMN-iW» /M
*MmuwfM HQ.
Vf«inCMiM
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PMQJCCH CDCE. COLORADO
-T-T
[Ml '
49 NORTH FIRST WEST STREET
MONTICELLO. UTAH
I kit IWIMM.BAI
nutr Rust Ocotoch MS-00524-RS
3-C00524-V1 ,
12 14 16 18 20 22 24 26 28 30 32 34 36 38 40 42 44 46 48 5i
OAK RIDGE NATIONAL LABORATORY
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
FOR THE U.S. DEPARTMENT OF ENERGY
2567 BV. Road
GRAND JUNCTION, COLORADO 81503
PHONE: [phone]
FAX: [phone]
FEB 1 8 7997
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by the U.S.
Department of Energy for Residual Radioactive Material at Formerly Utilized Sites Remedial Action
Program (FUSRAP) and Remote Surplus Facilities Management Program Sites (SFMP) [Revision
2, March 1987]. This evaluation is based on an independent verification review of the Remedial
Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment ofthe 226Ra
concentration in the soil, indoor radon daughter concentration, and indoor gamma exposure rates at
this property.
This property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
MS00524-RS
49 North 1 st West Street
Monticello. Utah 84535

Location Number:
Location Address:
Property Owner:
Owner Address:
Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERD7ICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
49 NORTH 1ST WEST STREET
MONTICELLO, UTAH (MS00524-RS)
M. K. Jensen
January 1997
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81503
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 3
REFERENCES 6
iii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 4
2. Results of ORNL analysis of the RAC soil samples from 49 North 1 st West Street,
Monticello, Utah (MS00524-RS) 5
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site Decommissioning
Projects, U.S. Department of Energy. The author wishes to acknowledge A. R. Jones and A. D.
Laase for technical reviews.
vii
ABSTRACT
In 1980, the site of a vanadium and uranium mill at Monticello, Utah, was accepted into the U.S.
Department of Energy (DOE) Surplus Facilities Management Program, with the objectives of
restoring the government-owned mill site to safe levels of radioactivity, disposing of or containing
the tailings in an environmentally safe manner, and performing remedial actions on off-site (vicinity)
properties that had been contaminated by radioactive material resulting from mill operations. During
1994, the Remedial Action Contractor (RAC) designated by DOE, performed remedial action on the
vicinity property at 49 North 1st West Street, Monticello, Utah. The Environmental Technology
Section (ETS) of Oak Ridge National Laboratory was assigned the responsibility of verifying the data
supporting the adequacy of remedial action and confirming the site's compliance with DOE guidelines.
The ETS found that the site successfully meets the DOE remedial action objectives. Procedures used
by the ETS are described in the Environmental Technology Section Procedures Manual (ORNL
1993).
ix
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 49 NORTH 1ST WEST STREET
MONTICELLO, UTAH (MS00524-RS)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the United States (U.S.) government through
the Defense Plant Corporation to provide vanadium during World War II. Various government
agencies operated the mill until 1947. In 1948, the Atomic Energy Commission (AEC) obtained the
mill and operated it under contract through 1959 to provide both uranium and vanadium. Mill
operations were terminated on January 1, 1960. In 1961, the mill tailings piles were leveled and
graded, covered with rock and soil, and seeded with native grasses. During 1974 and 1975, the ore
stockpiles were removed from the site and the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city of
Monticello, in San Juan County, Utah. The site is bordered on the south and southeast by land held
by the U.S. Bureau of Land Management. Other boundaries are the city of Monticello and private
property.
During the AEC era, the mill processed approximately one million tons of uranium ore. Vana-
dium and uranium were the only substances extracted in the milling process. Other constituents of
the ore remained in the tailings and were not separated prior to disposal. During the years of active
mill operation, the mill tailings were normally moist, so erosion was minimal. However, throughout
the mill's operating period, area residents used these tailings as fill material and as aggregate in mortar
and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy (DOE) initiated
the Surplus Facilities Management Program (SFMP) in 1978 to ensure the safe caretaking and de-
commissioning of government facilities that had been retired from service but still had radioactive
contamination. In 1980, the mill site at Monticello was accepted into the SFMP, and the Monticello
Remedial Action Project (MRAP) was established to restore the government-owned mill site to safe
levels of radioactivity, to dispose of or contain the tailings in an environmentally safe manner, and to
perform remedial actions on off-site (vicinity) properties that had been contaminated by radioactive
material resulting from mill operations. The Monticello mill site and the tailings remain in the custody
of the DOE Grand Junction, Colorado, Projects Office. In 1983, remedial actions for vicinity
properties were separated from MRAP with establishment of the Monticello Vicinity Properties
(MVP) Project (US DOE 1990b).
•The verification of remedial action was performed by members ofthe Environmental Assessment Group in the Environmental
Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE contract DE-AC05-
960R22464 with Lockheed Martin Energy Research Corporation.
2
During 1994, the Remedial Action Contractor (RAC) designated by DOE, performed remedial
action on the vicinity property that is the subject of this report, a single family residence located at
49 North 1 st West Street, Monticello, Utah. The remedial action plan required excavation of all
exterior contamination. When the excavation was completed, the property was resurveyed, including
soil sampling, to ensure the removal of all contamination, backfilled with uncontaminated material,
and restored to a condition comparable to that which existed prior to remedial action (Geotech 1996).
DOE adopted a policy to assign an independent contractor to verify the data supporting the
adequacy of remedial action and to confirm the site's compliance with DOE guidelines. The Environ-
mental Technology Section (ETS) of Oak Ridge National Laboratory (ORNL) has been assigned the
responsibility of this task at the 49 North 1st West Street site. This report describes the methods and
results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available documentation
adequately and accurately describes the post-remedial-action radiological conditions of the entire
property that is to be certified and (2) that the remedial action reduced contamination to below
applicable DOE guidelines (US DOE 1990a).
Document Reviews
Review of the RAC property completion report (Geotech 1996) indicates the property was reme-
diated as evaluated by DOE on the basis of U.S. Environmental Protection Agency standards and the
DOE guidelines (US DOE 1990a) Excess residual radioactive materials were present, thus it was
appropriate to designate this property for remedial action.
This property was assessed as part of Block 36, therefore, the quantity of material assessed is
not available. During the actual removal process, a total of 29 yd3 of contaminated earth and uranium
mill tailings, 6 inches deep, were removed from a 147 m2 area.
The RAC performed a post-excavation survey prior to backfilling the excavated areas. This
survey consisted of gamma scans with a scintillometer of the ground level of the structure, a surface
scan ofthe exterior, and soil sampling. Samples representative of the bottom 15-cm (6-in.) soil layers
of two excavated verification areas were collected and blended to form representative composite soil
samples for each verification area.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation levels have
not been subtracted. Similarly, background concentrations have not been subtracted from radionu-
clide concentrations in soil samples. Applicable DOE guidelines for protection against radiation are
given in Table 1.
Gamma Measurements
Gamma exposure rate measurements taken by the RAC at the ground-level of the residence
ranged from 12 to 13 uR/h. Exterior surface gamma measurements taken from the excavated areas
prior to backfilling ranged from 14 to 18 uR/h.
Soil Sample Analysis
Prior to backfilling, the RAC collected soil samples representative of the excavated areas from
the bottom 15-cm (6-in.) soil layers. These samples were blended to form composite soil samples
representative of an average over the two exterior verification areas. The RAC's analysis of these
samples showed 226Ra concentrations ranging from 3.3 to 3.8 pCi/g in the composite sample. ORNL
ETS obtained these these samples and performed a confirmatory analysis which showed 226Ra
concentrations ranging from 2.8 to 3.4 pCi/g. These values are below the DOE guideline value of
15 pCi/g for soil layers > 15 cm below the surface. Gamma ranges and/or soil sample results
demonstrate compliance to the DOE Hot Spot Guidelines for areas <25 m2 (Table 1). Results of the
RAC and ORNL soil sample analyses are given in Table 2.
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were determined by the
Alpha-track method. To monitor radon levels, the RAC placed three alpha-track detectors on the
ground floor of the residence located on this property for a period of approximately one year (from
October 10, 1994 to September 27, 1995). The average annual working level (WL) of radon
progeny concentration, as determined by the Tech./Ops-Landauer Corporation, was 0.0120, which
is below the 0.03-WL guideline given in Table 1.
CONCLUSION
Results of RAC soil sample analysis and confirmatory split soil sample analysis by ORNL, show
that radionuclide concentrations are within applicable DOE guidelines. Based on the results of the
post-remedial-action data, which are confirmed by the verification assessment data, these radiological
measurements fall below the limits prescribed by DOE guidelines. It is concluded that the site
successfully meets the DOE remedial action objectives.
4
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of 226Ra in soil
above background levels,
averaged over a 100-m2
area
5 pCi/g averaged over the first 15 cm
of soil below the surface; 15 pCi/g
when averaged over 15-cm-thick soil
layers more than 15 cm below the
surface
Radionuclide con-
centrations in soil
for Hot Spot areas
Exposure to 222Rn
progeny
Maximum Permissible con-
centration of Ra226 in soil
above background level,
for areas less than 25 m2
Average annual radon
progeny concentration
(including background)
Ra226 concentrations, in any surface
or subsurface area less than 25 m2,
is below the guideline by a factor of
(100/A)'71, where A is the area of the
elevated region
0.03 WL
(US DOE 1990a)
5
Table 2. Results of ORNL analysis of the RAC soil samples from
49 North 1st West Street, Monticello, Utah (MS00524-RS)
226Ra concentration (pCi/g)
ORNL RAC
sample sample Depth ORNL RAC
No* No^ (cm)
XI NCG 099 >15 2.8 3.3
X2 NCG100 >15 3.4 3.8
" An X-type sample is a split of the sample taken by the remedial action contractor.
* Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated areas were
taken by the RAC, and these samples were blended to form a composite soil sample, which
represents an average over one ofthe verification areas.
6
REFERENCES
Geotech 1996. Property Completion Report for Monticello Vicinity Property Remedial Action for
DOE ID NO: MS00524-RS, Address: 49 North First West Street, Monticello, Utah 84535, RUST
Geotech, Grand Junction, Colorado, August 1996 .
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment Group)
Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National Laboratory, Grand
Junction, Colorado.
US DOE 1990a. Verification and Certification Protocol for the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination and
Decommissioning Program. Revision 3, November 1990. U.S. Department of Energy, Washington,
D.C.
US DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision and Record
of Decision Summary. U.S. Department of Energy, Grand Junction Projects Office, Grand Junction,
Colorado.
DOE ID No.: MS-00551-RS
Property Address: 249 North First West Street
Vicinity Property Certification Summary and Recommendation
Summary Evaluation
Certification Criteria MACTEC-ERS
U.S. Department
of Energy (DOE)
Ra-226 is <: 5 pCi/g above background
in top 15-cm-thick layer of soil
averaged over 100 m2
In situ [X] Lab [ ]
Ra-226 is i 15 pCi/g above
background in any 15-cm-thick layer of
soil more than 15 cm below the
surface averaged over 100 m2.
In situ [ ]Lab[X]
Interior gamma is < 20 uR/h above
background in any occupied or
habitable structure.
The radon decay-product
concentration in any occupied or
habitable structure is < 0.02 WL or, at
most, 0.03 WL.
Supplemental standards were applied
in accordance with EPA standard
40 CFR 192.21.
Hot spot criteria met as outlined by
DOE guidelines for FUSRAP (Rev.2,
March 1987)
Yes No Not Taken Yes No Not Taken
[X]a [ ]
[X] [ ]
[X] [ ]
[X] [ ]
[ ] [X]
[X] [ ]
[ ]
[ ]
[ ]
[ ]
[ ]
[ ]
[X] [ ]
M [ 1
[*] [ ]
[ ] [M
[xl [ 1
[ 1
[ ]
[ I
[ I
[ I
[ 1
aThe excavations were backfilled with materials that were measured at the source indicating that the Ra-226
concentrations are in the range of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
Ililllllllll llllllllll
SFCERTIFED SFMS-09053
lof2
DOE ID No.: MS-O0551-RS
MACTEC-ERS Recommendation
On the basis of the Property Completion Report evaluation, this property is recommended for
[X] Certification by DOE.
[ ] Certification by DOE with the concurrence of the U. S. Nuclear Regulatory Commission
because supplemental standards were applied according to 40 CFR 192.21.
Manager, Monticello Programs
MACTEC-ERS
DOE Evaluation
On the basis of the Property Completion Report recommendation, this property
[ X] Should be certified by DOE.
[ ] Should be certified by DOE with the concurrence of the U.S. Nuclear Regulatory
Commission because supplemental standards were applied according to 40 CFR 192.21.
Date
U.S. Department of Energy
Work performed under DOE Contract No. DE-AC13-96GJ87335, Task Order No. 96-05.02.14
2 of 2
Monticello Vicinity Properties Project
Property Completion Report
for
Monticello
Vicinity Property Remedial Action
for
DOE D3 No.: MS-00551-RS
Address: 249 North First West Street
Monticello, Utah 84535
November 1996
Prepared for
U.S. Department of Energy
Albuquerque Operations Office
Grand Junction Office
Prepared by
MACTEC-Environmental Restoration Services, LLC (MACTEC-ERS)*
Grand Junction, Colorado
Michael C. Butherus ^
Manager, Monticello Programs
Work performed under DOE Contract No. DE-AC13-96GJ87335
Task Order No. 96-05.02.14
*MACTEC-ERS has been granted authorization to conduct remedial action by the U.S. Department of Energy.
Remedial action was performed in accordance with the U.S. Environmental Protection Agency "Standards for Cleanup
of Land and Buildings Contaminated with Residual Radioactive Materials from Inactive Uranium Processing Sites,"
40 CFR 192, Subpart B; and "Implementation,"In 40 CFR 192, Subpart C.and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
DOE TD No.: MS-O0551-RS
Contents
Page
1.0 Summary 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Remedial Action Summary 2
2.0 Operations Summary 3
2.1 Remedial Action Plan 3
2.2 Assessed and Remediated Contamination 3
3.0 Verification Summary 4
3.1 Radiological Survey Data 4
3.1.1 Preremedial Action Survey 4
3.1.2 Postexcavation Survey 4
3.1.3 Radon Decay-Product Concentration Measurements 4
3.2 Recommendation for Certification 5
Table
Table 1. Certification Data Summary 5
Appendix
Appendix A. Radiological Conditions A-1
IXMi/Grand Junction Office
November 1996
MVP Property Completion Report
Page ii
DOE ID No.: MS-00551-RS
1.0 Summary
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce the potential hazard
to the public due to long-term exposure to low-level radioactivity associated with the offsite mill
tailings derived from the former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States Government through its agent,
the Defense Plant Corporation, to provide additional sources of vanadium needed during World
War II. Various government agencies operated the mill until 1947. The AEC obtained the mill in
1948 and operated it through 1959 under cost-type contracts to process both uranium and
vanadium ore. Mill operations were terminated on January 1, 1960.
The mill processed approximately one million tons of ore during the AEC operations. Throughout
the operating period, mill tailings from the Monticello millsite were removed from the site and
used for construction-related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for Remedial Actions at Inactive
Uranium Processing Sites" (40 CFR Part 192) for all cleanup activities under the MVP Project.
These standards were prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and open lands. Cleanup
activities also were conducted to meet the hot spot criteria established by radiological protection
guidelines in the DOE Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management Program Sites
(Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot spot criteria and
determined to contain mill tailings (radioactive material) exceeding EPA standards and/or DOE
hot spot criteria. The Remedial Action Contractor was notified of the inclusion of this property
into the MVP Project and was authorized by DOE to conduct remedial action as required to bring
the property into conformance with EPA standards and DOE hot spot criteria.
IXMi/Grand Junction Office
November 1996
MVP Property Completion Report
Page I
DOE ID No.: MS-00551-RS
1.3 Remedial Action Summary
DOE ID No.:
Legal Description:
Property Address:
Property Owners:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological and Engineering Assessment (REA):
Construction Subcontractor:
Preconstruction Conference Record:
Notice of Final Completion Inspection:
Volume of Material Removed in Cubic Yards (yd3):
Area Cleaned Up in Square Meters (m2):
Property Completion Report Submitted:
MS-00551-RS
Beginning 709.5 feet north ofthe NE
corner of Lot 4, Block K, Monticello
Townsite Survey; west 214.5 feet,
north 96.25 feet, east 214.5 feet,
south 96.25 feet to beginning; except
the west 94.5 feet thereof, County of
San Juan, State of Utah
249 North First West Street
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
Grand Junction Office
January 23, 1991
MACTEC-ERS
January 1994
Diamond Back Services, Inc.
August 16, 1994
October 12, 1994
Exterior: 4
Interior: 0
21
November 1996
lXJLVGrand Junction Office
November 19%
MVP Property Completion Report
Page 2
DOE ID No.: MS-00551-RS
2.0 Operations Summary
2.1 Remedial Action Plan
The remedial action plan specified removal of radioactive material. Once excavation was
completed, the affected areas were resurveyed for possible remaining radioactive material and,
upon attaining satisfactory results, were backfilled with uncontaminated material. The property
was restored to a physical condition comparable to that which existed before remedial action
activities.
2.2 Assessed and Remediated Contamination
The radiological assessment identified contamination, ranging from 6 to 12 inches (in.) deep,
within the property boundary. The quantity of contamination for this property was not specified
because it was assessed as part of Block MS-O9053-BK. The remedial action process included
removal of approximately 4 yd3 of radioactive material, ranging from 6 to 12 in. deep. The areas
of assessed and excavated contamination are shown on Figure A-1.
lX)I:/Grand Junction Office
November 1996
MVP Property Completion Report
Page 3
DOE ID No.: MS-00551-RS
3.0 Verification Summary
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Preremedial Action Survey
The Remedial Action Contractor conducted a radiological survey during June 1992, as described
in the final REA. Figure A-1 shows the extent of assessed contamination and identifies the areas
recommended for remedial action.
3.1.2 Postexcavation Survey
A scintillometer was used to perform a surface gamma scan after the removal of radioactive
material and before backfilling. Following the gamma scan, soil samples representative of the
6-in.-thick soil layer at the bottom of the excavation were collected. These samples, representing
the verification area, were analyzed for radium-226. The results of the gamma scans and soil
sample analyses are presented in Table A-1.
3.1.3 Radon Decay-Product Concentration Measurement
Radon decay-product concentration (RDC) measurements were taken on the lowest habitable
level ofthe house, as shown on Figure A-1. The measurement results are presented in Table A-2.
1X)E/Grand Junction Office
November 19%
MVP Property Completion Report
Page 4
DOE ID No.: MS-00551-RS
3.2 Recommendation for Certification
Radioactive materials have been removed from this property to the extent required by EPA
standards (40 CFR 192, Subparts B and C) and DOE hot spot criteria, as presented in the
Certification Data Summary (Table 1). Therefore, the property located at 249 North First West
Street, in Monticello, Utah, is recommended for certification as required by DOE guidelines.
Table 1. Certification Data Summary
Applicability Standard Survey Results
Radium-226
Concentration in
Surface Soil
Radium-226
Concentration in
Subsurface Soil
Exposure Rate
Land
Shall not exceed 5 pCi/g above
background8 in the 15-cm-thick
surface layer, averaged over
100 m2.
Shall not exceed 15 pCi/g
above background3 in any
15-cm-thick soil layer more than
15 cm below the surface,
averaged over 100 m2.
Habitable Structures
< 5 pCi/g above background on the
basis of gamma exposure rates that do
not exceed 30 percent above normal
background."
Soil sample result was 5.5 pCi/g.b
Shall not exceed 20 uR/h above
background.0
Range for the ground floor was 12 to
13pR/h.
Radon Decay-
Product
Concentration
Annual average shall not
exceed 0.02 WL, to the extent
practicable, and shall in no
case exceed 0.03 WL.
Average was 0.0059 WL, on the basis
of the DOE-approved abbreviated-
measurement method.
Key: cm = centimeters; m1 = square meters; pCi/g = picocuries per gram; uR/h = microroentgens per hour;
WL = working level
"The background radium-226 concentration for Monticello Vicinity Properties is approximately 2.0 pCi/g.
bThe hot spot criteria were met based on gamma scans and/or soil sample results.
cThe background exposure rate for this property is approximately 13 uR/h.
IX)L7Grand Junction Office
November 19%
MVP Property Completion Report
Page 5
DOE ID No.: MS-00551-RS
Appendix A
Radiological Conditions
Table A-1. Postexcavation Survey Results
Table A-2. Radon Decay-Product Concentration Measurement Results
Figure A-1. Radiological As-Built
DOE ID No.: MS-00551-RS
Table A-1. Postexcavation Survey Results
Gamma Radium-226
Verification Exposure Rate Soil Sample Measurement Concentration
Area* Range (uR/h) Ticket No. Method (pCi/g)
V-1 15-19 NCA 969 OCS 5.5
Key: OCS = opposed crystal system; pCi/g = picocuries per gram; uR/h = microroentgens per hour,
V = verification area
'See Figure A-1 for location of verification area.
DOIi/Orand Junction Office
November IWC
MVP Property Completion Report
Page A 2
DOE ID No.: MS-00551-RS
Table A-2. Radon Decay-Product Concentration Measurement Results*
Detector"
Number Start Date End Date
Radon
Concentration
(pCi/L) WL
3964149
3964357
3964293
02-27-95
02-27-95
02-27-95
05-30-95
05-30-95
05-30-95
1.02
0.92
1.57
Average:
0.0051
0.0046
0.0079
0.0059
Key: pCi/L = picocuries per liter; WL = working level
'See Figure A-1 for measurement location.
"Terradex Radtrak Detector.
IX)L/Grand Junction Office
November 1996
MVP Property Completion Report
Page A 3
10
30
I 2. 14 16 18 20
n—i—i—i—i—i—r
22 24 26
T
28 30 32 34 36 38
T
40
30 i—T
28
26
24
22
20 -
12-14
ONE STORY
FRAME HOUSE
12-13
12-14
V-1
RDC
12 SHEDS'
1 2//R/h CARPORT
_J
UJ
UJ or
i—
CO
to
UJ
t—
CO a:
or o
©
FV.Y/I
LV.VJ
12-15
12
V-10
LEGEND
ALL DEPTHS/HEIGHTS IN INCHES
ALL EXPOSURE RATES IN /zR/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
EXPOSURE—RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION AREA IDENTIFIER
RADON DECAY-PRODUCT CONCENTRATION
MEASUREMENT LOCATION
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
28
26
24
22
20
18 18
16 16
14
12
Y ft
NORTH
SCALE IN FEET
20 10 0 20
M:\FAS\033\0003\RM00551V 10/30/96 2:16pm S50730
— X
10
10 12 1 4 16 18
40
J L
20
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT, UTILITY LOCATION PLAT. OR OTHER IMPROVEMENT SURVEY
PLAT AND IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE. BUILDING, OR OTHER FUTURE IMPROVEMENT LINES.
22 24
J L
26 28
fi235c-6R U.S. DEPARTMENT OF ENERGY
GRANO JUNCTION OFFICE, COLORADO wiaw
249 NORTH
FIRST WEST STREET
MONTICELLO, UTAH
EBTTRB—r~
COMPLETION REPORTS
3^
5H
-Hir
MONTICELLO VICINITY PROPERTIES
FIGURE A-1
RADIOLOGICAL AS-BUILT
WEET5S" MS-005S1-RS
NUHMUS.
30 32 34
3-B00551-V1
36
1 1
14
12
1 0
38 40
OAK RIDGE NATIONAL LABORATORY
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
FOR THE U.S. DEPARTMENT OF ENERGY
PHONE: [phone]
FAX: [phone]
2597 B'/A Road
GRAND JUNCTION, COLORADO 61503
Wfl 2 5 W7
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by the U.S.
Department of Energy for Residual Radioactive Material at Formerly Utilized Sites Remedial Action
Program (FUSRAP) and Remote Surplus Facilities Management Program Sites (SFMP) [Revision
2, March 1987]. This evaluation is based on an independent verification review of the Remedial
Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment of the 226Ra
concentration in the soil, indoor radon daughter concentration, and indoor gamma exposure rates at
this property.
This property is recommended for certification by the U.S. Department of Energy.
Sincerely,
v
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
MS0055l'-RS
249 North 1st West Street
Monticello. Utah 84535

Location Number:
Location Address:
Property Owner:
Owner Address:
Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
249 NORTH 1ST WEST STREET
MONTICELLO, UTAH (MS00551-RS)
M. K. Jensen
March 1997
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81503
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 3
REFERENCES 6
in
LIST OF TABLES
1. Applicable guidelines for protection against radiation 4
2. Results of ORNL analysis ofthe RAC soil samples from 249 North 1st West Street,
Monticello, Utah (MS00551 -RS) 5
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site Decommissioning
Projects, U.S. Department of Energy. The author wishes to acknowledge T. L. Meyer and P. D.
Roundtree for technical reviews.
vii
ABSTRACT
In 1980, the site of a vanadium and uranium mill at Monticello, Utah, was accepted into the U.S.
Department of Energy (DOE) Surplus Facilities Management Program, with the objectives of
restoring the government-owned mill site to safe levels of radioactivity, disposing of or containing
the tailings in an environmentally safe manner, and performing remedial actions on off-site (vicinity)
properties that had been contaminated by radioactive material resulting from mill operations. During
1994, the Remedial Action Contractor (RAC) designated by DOE, performed remedial action on the
vicinity property at 249 North 1st West Street, Monticello, Utah. The Environmental Technology
Section (ETS) of Oak Ridge National Laboratory was assigned the responsibility of verifying the data
supporting the adequacy of remedial action and confirming the site's compliance with DOE guidelines.
The ETS found that the site successfully meets the DOE remedial action objectives. Procedures used
by the ETS are described in the Environmental Technology Section Procedures Manual (ORNL
1993).
ix
1
RESULTS OF THE INDEPENDENT VERD7ICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 249 NORTH 1ST WEST STREET
MONTICELLO, UTAH (MS00551-RS)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the United States (U.S.) government through
the Defense Plant Corporation to provide vanadium during World War II. Various government
agencies operated the mill until 1947. In 1948, the Atomic Energy Commission (AEC) obtained the
mill and operated it under contract through 1959 to provide both uranium and vanadium. Mill
operations were terminated on January 1, 1960. In 1961, the mill tailings piles were leveled and
graded, covered with rock and soil, and seeded with native grasses. During 1974 and 1975, the ore
stockpiles were removed from the site and the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city of
Monticello, in San Juan County, Utah. The site is bordered on the south and southeast by land held
by the U.S. Bureau of Land Management. Other boundaries are the city of Monticello and private
property.
During the AEC era, the mill processed approximately one million tons of uranium ore. Vana-
dium and uranium were the only substances extracted in the milling process. Other constituents of
the ore remained in the tailings and were not separated prior to disposal. During the years of active
mill operation, the mill tailings were normally moist, so erosion was minimal. However, throughout
the mill's operating period, area residents used these tailings as fill material and as aggregate in mortar
and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy (DOE) initiated
the Surplus Facilities Management Program (SFMP) in 1978 to ensure the safe caretaking and de-
commissioning of government facilities that had been retired from service but still had radioactive
contamination. In 1980, the mill site at Monticello was accepted into the SFMP, and the Monticello
Remedial Action Project (MRAP) was established to restore the government-owned mill site to safe
levels of radioactivity, to dispose of or contain the tailings in an environmentally safe manner, and to
perform remedial actions on off-site (vicinity) properties that had been contaminated by radioactive
material resulting from mill operations. The Monticello mill site and the tailings remain in the custody
ofthe DOE Grand Junction, Colorado, Projects Office. In 1983, remedial actions for vicinity
properties were separated from MRAP with establishment of the Monticello Vicinity Properties
(MVP) Project (US DOE 1990b).
*The verification of remedial action was performed by members ofthe Environmental Assessment Group in the Environmental
Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE contract DE-AC05-
960R22464 with Lockheed Martin Energy Research Corporation.
2
During 1994, the Remedial Action Contractor (RAC) designated by DOE, performed remedial
action on the vicinity property that is the subject of this report, a private residence located at 249
North 1st West Street, Monticello, Utah. The remedial action plan required excavation of all exterior
contamination. When the excavation was completed, the property was resurveyed, including soil
sampling, to ensure the removal of all contamination, backfilled with uncontaminated material, and
restored to a condition comparable to that which existed prior to remedial action (MACTEC-ERS
1996).
DOE adopted a policy to assign an independent contractor to verify the data supporting the
adequacy of remedial action and to confirm the site's compliance with DOE guidelines. The Environ-
mental Technology Section (ETS) of Oak. Ridge National Laboratory (ORNL) has been assigned the
responsibility of this task at the 249 North 1st West Street site. This report describes the methods
and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available documentation
adequately and accurately describes the post-remedial-action radiological conditions of the entire
property that is to be certified and (2) that the remedial action reduced contamination to below
applicable DOE guidelines (US DOE 1990a)
Document Reviews
Review of the RAC property completion report (MACTEC-ERS 1996) indicates the property
was remediated as evaluated by DOE on the basis of U.S. Environmental Protection Agency
standards and the DOE guidelines (US DOE 1990a). Excess residual radioactive materials were
present, thus it was appropriate to designate this property for remedial action.
This property was assessed as part of Block 53, therefore, the quantity of material assessed is
not available. During the actual removal process, a total of 4 yd3 of contaminated earth and uranium
mill tailings, 6 to 12 inches deep, were removed from a 21 m2 area.
The RAC performed a post-excavation survey prior to backfilling the excavated areas. This
survey consisted of gamma scans with a scintillometer of the ground level of the structure, a surface
scan of the exterior, and soil sampling. Samples representative of the bottom 15-cm (6-in.) soil layers
ofthe excavated verification area were collected and blended to form a representative composite soil
sample.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation levels have
not been subtracted. Similarly, background concentrations have not been subtracted from radionu-
clide concentrations in soil samples. Applicable DOE guidelines for protection against radiation are
given in Table 1.
Gamma Measurements
Gamma exposure rate measurements taken by the RAC at the ground-level of the residence
ranged from 12 to 13 uR/h. Exterior surface gamma measurements taken from the excavated areas
prior to backfilling ranged from 15 to 19 uR/h.
Soil Sample Analysis
Prior to backfilling, the RAC collected soil samples representative of the excavated areas from
the bottom 15-cm (6-in.) soil layers. These samples were blended to form a composite soil sample
representative of an average over the exterior verification area. The RAC's analysis of this sample
showed a 226Ra concentration of 5.5 pCi/g. ORNL ETS obtained this sample and performed a
confirmatory analysis which showed a 226Ra concentration of 5.4 pCi/g. These values are below the
DOE guideline value of 15 pCi/g for soil layers > 15 cm below the surface. Gamma ranges and/or
soil sample results demonstrate compliance to the DOE Hot Spot Guidelines for areas <25 m2 (Table
1). Results of the RAC and ORNL soil sample analyses are given in Table 2.
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were determined by the
Alpha-track method. To monitor radon levels, the RAC placed three alpha-track detectors on the
ground floor ofthe residence located on this property for a period of approximately three months
(from February 27, 1995 to May 30, 1995). The average annual working level (WL) of radon
progeny concentration, as determined by the Tech./Ops-Landauer Corporation, was 0.0059, which
is well below the 0.03-WL guideline given in Table 1.
CONCLUSION
Results of RAC soil sample analysis and confirmatory split soil sample analysis by ORNL, show
that radionuclide concentrations are within applicable DOE guidelines. Based on the results of the
post-remedial-action data, which are confirmed by the verification assessment data, these radiological
measurements fall below the limits prescribed by DOE guidelines. It is concluded that the site
successfully meets the DOE remedial action objectives.
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of 226Ra in soil
above background levels,
averaged over a 100-m2
area
5 pCi/g averaged over the first 15 cm
of soil below the surface; 15 pCi/g
when averaged over 15-cm-thick soil
layers more than 15 cm below the
surface
Radionuclide con-
centrations in soil
for Hot Spot areas
Exposure to 222Rn
progeny
Maximum Permissible con-
centration of Ra226 in soil
above background level,
for areas less than 25 m2
Average annual radon
progeny concentration
(including background)
Ra226 concentrations, in any surface
or subsurface area less than 25 m2,
is below the guideline by a factor of
(100/A)'/2, where A is the area of the
elevated region
0.03 WL
(US DOE 1990a)
5
Table 2. Results of ORNL analysis of the RAC soil samples from
249 North 1st West Street, Monticello, Utah (MS00551-RS)
226Ra concentration (pCi/g)
ORNL RAC
sample sample Depth ORNL RAC
No.° No^ (cm)
XI NCA 969 >15 5.4 5.5
a An X-type sample is a split of the sample taken by the remedial action contractor.
* Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated areas were
taken by the RAC, and these samples were blended to form a composite soil sample, which
represents an average over one of the verification areas.
6
REFERENCES
MACTEC-ERS 1996. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00551-RS, Address: 249 North First West Street, Monticello, Utah
84535, MACreC-Environmental Restoration Services, Grand Junction, Colorado, November 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment Group)
Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National Laboratory, Grand
Junction, Colorado.
US DOE 1990a. Verification and Certification Protocol for the Office of Environmental Restoration,
Formerly Utilized Sites Remedial Action Programs and Decontamination and Decommissioning
Program. Revision 3, November 1990. U.S. Department of Energy, Washington, D.C.
US DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision and Record
of Decision Summary. U.S. Department of Energy, Grand Junction Projects Office, Grand Junction,
Colorado.
DOE ID No.: MS-00600-MR
Property Address: 32 Park View Drive
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech of Energy (PQE)
Ra-226 is < 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [ ]
Ra-226 is ^ 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2.
In-situ [ ] Lab [ ]
Interior gamma is < 20 yt/R/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is < 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21.
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[ ] [ ] txr
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
LX] [ ] [ I
[ ] [ ] LX1
[X] [ ] [ ]
M [ ] [ ]
[ ] [X] [ ]
[V] [ ] [ ]
COMMENTS: * Exterior areas were verified on the basis of surface gamma
exposure rates that do not exceed 30 percent above normal background.
•llllllllll •III1I1IIVI
SFCERTIFED
DOE ID No.: MS-00600-MR
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Wanda S. Basby x Date
Manager, Monticello Programs
Rust Geotech
DOE EVALUATION
[*] Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Certification Official
U.S. Department of Energy
Date
PROPERTY COMPLETION REPORT
FOR
MONTICELLO .
VICINITY PROPERTY REMEDIAL ACTION
DOE ID NO.: MS-00600-MR
ADDRESS: 32 PARK VIEW DRIVE
MONTICELLO, UTAH 84535
AUGUST 1996
Prepared for
U.S. Department of Energy
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
' Warura S. Busby
Manager, Monticello Programs
FOR
by
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.1.3 Radon Decay-Product Concentration (RDC) Measurement .... 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
i
DOE ID No.: MS-00600-MR
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Inclusion Survey Contractor. DOE reviewed
these evaluation results and determined that the property contained mill
tailings (residual radioactive material) exceeding EPA standards. The
Remedial Action Contractor was notified of the inclusion of this property
into the MVP Project and was authorized by DOE to conduct remedial
action as required to bring the property into conformance with EPA
standards and DOE hot spot criteria.
1
DOE ID No.: MS-00600-MR
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
MS-00600-MR
Beginning at the southeast corner of Lot 46, Blue Mountain Heights
Subdivision; southwesterly to a point which is south 21 degrees 15 minutes
east 20 feet from the southwest corner of Lot 46, north 21 degrees 15 minutes
west 93.94 feet; northeasterly to a point which is southeasterly 10 feet on a
150 foot radius curve to the right from the northeast corner of Lot 46;
southeasterly 100 feet on a 150 foot radius curve to the right to the point of
beginning, City of Monticello, County of San Juan, State of Utah
Property Address:
Property Owners:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
32 Park View Drive
Monticello, Utah 84535

Major Residential (MR)
Oak Ridge National Laboratory
November 6, 1992
Rust Geotech
November 30, 1994
Diamond Back Services, Inc.
9861 Titan Park Circle
Littleton, Colorado
June 27, 1995
September 28, 1995
Interior:
Exterior:
35 cubic yards
0 cubic yards
11 square meters (m2)
August 1996
2
DOE ID No.: MS-00600-MR
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of interior residual radioactive
material (Appendix Figure 2.1). Once excavation was complete, the
affected area was resurveyed for possible remaining residual radioactive
material and, upon attaining satisfactory results, was backfilled with
uncontaminated material. The property was restored to a physical
condition comparable to that which existed prior to remedial action
activities.
2.2 Previously Unidentified Contamination
The radiological assessment identified 35 cubic yards of contamination,
ranging from 12 to 102 inches high, within the property. The remedial
action process included the removal of approximately 35 cubic yards of
residual radioactive material, ranging from 12 to 102 inches high.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID No.: MS-00600-MR
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by the Remedial Action
Contractor during July 1993, as described in the final REA dated
November 1994. Appendix Figure 2.1 shows the extent of
assessed contamination and identifies the area recommended to
undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
(Appendix Figure 2.1).
Interior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 13 to 16 microroentgens per
hour (//R/h) for the remediated portions of the ground floor, and 14
to 16 //R/h for the rest of the ground floor (Appendix Figure 2.1).
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on the DOE-approved abbreviated-measurement method,
the RDC was 0.0183 working level (WL), as indicated in Appendix
Table 3.1. Appendix Figure 2.1 shows the measurement location
in the basement (the lowest habitable level of the structure). RDC
measurements were taken before remediation of the property.
4
DOE ID No.: MS-00600-MR
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at 32 Park View Drive, in Monticello,
Utah, is recommended for certification as required by DOE guidelines,
and the appropriate records should be documented.
Certification Data Summary
Applicability
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Standards
Shall not exceed 20 //R/h
above background.*
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Survey Results
Ranges were 13 to
16 //R/h for the
remediated portion of the
ground floor, and 14 to
16 //R/h for the rest of
the ground floor. Range
for the basement was 14
to 16//R/h.
Average was 0.0183 WL,
based on the DOE-
approved abbreviated-
measurement method.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
< 5 pCi/g above
background.**
< 15 pCi/g above
background.**
*The background exposure rate is approximately 14//R/h.
The background radium-226 concentration is approximately 2.0 pCi/g.
**The hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-00600-MR
4.0 APPENDIX
Appendix Table:
Table 3.1 Radon Decay-Product Concentration Measurement
Results
Appendix Figure:
Figure 2.1 Interior Extent of Contamination - RADIOLOGICAL
AS-BUILT
SJW:06-24-96
MS-00600.MR WP61
REV080195
6
Table 3.1
Radon Decay-Product Concentration Measurement Results
DOE ID No.: MS-00600-MR
Address: 32 Park View Drive, Monticello, Utah
Instrument Type: Landauer Radtrak Detector
Radon
Detector Concentration Working
Number Start Date End Date (pCi/L) Level
3964383 02-28-95 05-30-95 3.36 0.0168
3964329 02-28-95 05-30-95 3.78 0.0189
3964308 02-28-95 05-30-95 3.82 0.0191
Average: 0.0183
See Appendix Figure 2.1 for the measurement location.
7
10
30
28
26
24
22
20
18
16
14
12
12 1 4 16 18 20 22 24 26 28 30
02
v-i
FLOOR RO 13-14
12 B
V-4
3-16
V-2
\ 13-15
\
\ 02
ON 5TO RY
ICK OU SE ® W/BAS NT
DETAIL A
NOT TO SCALE
LY.YJ EE ETAI
12-15
STO RY ON
ETAL LD NG Ti v-i 7^
16-17
rn
(RDC)
Ti [RDC)
[12] n
13-16
SCALE IN FEET
DATE
/rs 20 10 20 40
32 34 36 38 40
10
NORTH
X M:\FAS\033\0003\RM00600V 07/17/96 09:25am T50780
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT, UTILITY LOCATION PLAT. OR OTHER IMPROVEMENT SURVEY
PLAT AND IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE, BUILDING, OR OTHER FUTURE IMPROVEMENT LINES.
I I
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN yuR/h
ASSESSED AREA IDENTIFIER
AREA OF ASSESSED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
VERIFICATION AREA IDENTIFIER AND
EXCAVATION EXPOSURE-RATE RANGE
RADON DECAY—PRODUCT CONCENTRATION
MEASUREMENT LOCATION
HEIGHT IN INCHES OF ASSESSED CONTAMINATED _
MORTARED BRICK REMOVED AND REPLACED
RADIOLOGICAL AS-BUILT
FIGURE 2.1
INTERIOR EXTENT OF CONTAMINATION
RESIDENCE-NO. OF OCCUPANTS
NON-RESIOEHCC-UAN-HRS./WK.
INSTRUUENT NO.
VERIFICATION
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE, COLORADO
:OJ. ENCiT
CRA^ND
32 PARK VIEW DRIVE
MONTICELLO, UTAH
Rust Oeotech
A Witt THfNiogiM CMOT
APPROVAL OOE
0OE.ON0. MS-00600-MR
QWC.NO. 3-B00600-V1 SHT 1 or 1
30
28
26
24
22
20
18
1 6
1 4
1 2
10
10 12 1 4 16 18 20 22 24 26 28 30 32 34 36 38 40
OAK RIDGE NATIONAL LABORATORY PHONE: [phone]
FAX: [phone] MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
FOR THE U.S. DEPARTMENT OF ENERGY
POST OFFICE BOX 2567
GRAND JUNCTION, COLORADO 81502
EC 3 ! 7996
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by the U.S.
Department of Energy for Residual Radioactive Material at Formerly Utilized Sites Remedial Action
Program (FUSRAP) and Remote Surplus Facilities Management Program Sites (SFMP) [Revision
2, March 1987]. This evaluation is based on an independent verification review of the Remedial
Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment of the
indoor radon daughter concentration, and indoor and outdoor gamma exposure rates at this property.
This property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
Location Number:
Location Address:
MS00600-MR
32 Park View Drive
Monticello. Utah 84535
Property Owner:
Owner Address:

Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
32 PARK VIEW DRIVE
MONTICELLO, UTAH (MS00600-MR)
M. K. Jensen
December 1996
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81503
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Radon Measurement Results 3
CONCLUSION 3
REFERENCES 5
iii
LIST OF TABLES
Applicable guidelines for protection against radiation
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site Decommissioning
Projects, U.S. Department of Energy. The author wishes to acknowledge A. R. Jones for technical
reviews.
vii
ABSTRACT
In 1980, the site of a vanadium and uranium mill at Monticello, Utah, was accepted into the U.S.
Department of Energy (DOE) Surplus Facilities Management Program, with the objectives of
restoring the government-owned mill site to safe levels of radioactivity, disposing of or containing
the tailings in an environmentally safe manner, and performing remedial actions on off-site (vicinity)
properties that had been contaminated by radioactive material resulting from mill operations. During
1995, the Remedial Action Contractor (RAC) designated by DOE, performed remedial action on the
vicinity property at 32 Park View Drive, Monticello, Utah. The Environmental Technology Section
(ETS) of Oak Ridge National Laboratory was assigned the responsibility of verifying the data
supporting the adequacy of remedial action and confirming the site's compliance with DOE guidelines.
The ETS found that the site successfully meets the DOE remedial action objectives. Procedures used
by the ETS are described in the Environmental Technology Section Procedures Manual (ORNL
1993).
ix
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 32 PARK VIEW DRIVE
MONTICELLO, UTAH (MS00600-MR)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the United States (U.S.) government through
the Defense Plant Corporation to provide vanadium during World War II. Various government
agencies operated the mill until 1947. In 1948, the Atomic Energy Commission (AEC) obtained the
mill and operated it under contract through 1959 to provide both uranium and vanadium. Mill
operations were terminated on January 1, 1960. In 1961, the mill tailings piles were leveled and
graded, covered with rock and soil, and seeded with native grasses. During 1974 and 1975, the ore
stockpiles were removed from the site and the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city of
Monticello, in San Juan County, Utah. The site is bordered on the south and southeast by land held
by the U.S. Bureau of Land Management. Other boundaries are the city of Monticello and private
property.
During the AEC era, the mill processed approximately one million tons of uranium ore. Vana-
dium and uranium were the only substances extracted in the milling process. Other constituents of
the ore remained in the tailings and were not separated prior to disposal. During the years of active
mill operation, the mill tailings were normally moist, so erosion was minimal. However, throughout
the mill's operating period, area residents used these tailings as fill material and as aggregate in mortar
and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy (DOE) initiated
the Surplus Facilities Management Program (SFMP) in 1978 to ensure the safe caretaking and de-
commissioning of government facilities that had been retired from service but still had radioactive
contamination. In 1980, the mill site at Monticello was accepted into the SFMP, and the Monticello
Remedial Action Project (MRAP) was established to restore the government-owned mill site to safe
levels of radioactivity, to dispose of or contain the tailings in an environmentally safe manner, and to
perform remedial actions on off-site (vicinity) properties that had been contaminated by radioactive
material resulting from mill operations. The Monticello mill site and the tailings remain in the custody
of the DOE Grand Junction, Colorado, Projects Office. In 1983, remedial actions for vicinity
properties were separated from MRAP with establishment of the Monticello Vicinity Properties
(MVP) Project (US DOE 1990b).
*The verification of remedial action was performed by members ofthe Environmental Assessment Group in the Environmental
Technology Section ofthe Health Sciences Research Division at Oak Ridge National Laboratory under DOE contract DE-AC05-
960R22464 with Lockheed Martin Energy Research Corporation.
2
During 1995, the Remedial Action Contractor (RAC) designated by DOE, performed remedial
action on the vicinity property that is the subject of this report, a single family residence located at
32 Park View Drive, Monticello, Utah. The remedial action plan required removal of all structural
contamination. When the removal was completed, the property was resurveyed to ensure all of the
contamination was removed, reconstructed with uncontaminated material, and restored to a condition
comparable to that which existed prior to remedial action (Geotech 1996).
DOE adopted a policy to assign an independent contractor to verify the data supporting the
adequacy of remedial action and to confirm the site's compliance with DOE guidelines. The Environ-
mental Technology Section (ETS) of Oak Ridge National Laboratory (ORNL) has been assigned the
responsibility of this task at the 32 Park View Drive site. This report describes the methods and
results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available documentation
adequately and accurately describes the post-remedial-action radiological conditions of the entire
property that is to be certified and (2) that the remedial action reduced contamination to below
applicable DOE guidelines (US DOE 1990a).
Document Reviews
Review of the RAC property completion report (Geotech 1996) indicates the property was reme-
diated as evaluated by DOE on the basis of U.S. Environmental Protection Agency standards and the
DOE guidelines (US DOE 1990a). Excess residual radioactive materials were present, thus it was
appropriate to designate this property for remedial action.
The pre-remedial-action survey performed by the RAC identified 35 yd3 of contamination
ranging from 12 to 102 inches high. During the actual removal process, a total of 35 yd3 of contami-
nation, 12 to 102 inches high, were removed from a 11 nr area.
The RAC performed a post-excavation survey prior to reconstruction. This survey consisted
of gamma scans with a scintillometer of the ground level and basement of the structure, and a surface
scan of the exterior.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation levels have
not been subtracted. Applicable DOE guidelines for protection against radiation are given in
Table 1.
Gamma Measurements
Gamma exposure rate measurements taken by the RAC at the basement and ground-level of the
residence ranged from 14 to 16 uR/h. Exterior surface gamma measurements taken from the
excavated areas prior to reconstruction ranged from 13 to 16 uR/h.
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were determined by the
Alpha-track method. To monitor radon levels, the RAC placed three alpha-track detectors in the
basement of the residence located on this property for a period of approximately three months (from
February 28, 1995 to May 30, 1995). This measurement was taken prior to remedial action. The
average annual working level (WL) of radon progeny concentration, as determined by the Tech./-
Ops-Landauer Corporation, was 0.0183, which is below the 0.03-WL guideline given in Table 1.
CONCLUSION
Results of the RAC gamma exposure rate measurements are vvithin applicable DOE guidelines.
Based on the results of the post-remedial-action data, which are confirmed by the verification
assessment data, these radiological measurements fall below the limits prescribed by DOE
guidelines. It is concluded that the site successfully meets the DOE remedial action objectives.
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of 226Ra in soil
above background levels,
averaged over a 100-m2
area
5 pCi/g averaged over the first 15 cm
of soil below the surface; 15 pCi/g
when averaged over 15-cm-thick soil
layers more than 15 cm below the
surface
Radionuclide con-
centrations in soil
for Hot Spot areas
Exposure to 222Rn
progeny
Maximum Permissible con-
centration of Ra226 in soil
above background level,
for areas less than 25 m2
Average annual radon
progeny concentration
(including background)
Ra226 concentrations, in any surface
or subsurface area less than 25 m2,
is below the guideline by a factor of
(1007A)'/2, where A is the area ofthe
elevated region
0.03 WL
(US DOE 1990a)
REFERENCES
Geotech 1996. Property Completion Report for Monticello Vicinity Property Remedial Action
for DOE ID NO: MS00600-MR, Address: 32 Park View Drive, Monticello, Utah 84535, RUST
Geotech, Grand Junction, Colorado, August 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment Group)
Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National Laboratory, Grand
Junction, Colorado.
US DOE 1990a. Verification and Certification Protocol for the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination and
Decommissioning Program. Revision 3, November 1990. U.S. Department of Energy,
Washington, D.C.
US DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision and
Record of Decision Summary. U.S. Department of Energy, Grand Junction Projects Office,
Grand Junction, Colorado.
DOE ID No.: MS-00608-RS
Property Address: 265 Cedar Lane
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech of Energy (DOE)
YES NO NOT TAKEN YES NO NOT TAKEN
Ra-226 is < 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [ ]
[X]* [ ] [ ] p] i ] [ ]
Ra-226 is < 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2. [X] [ ] [ ] [/][][]
In-situ [ ] Lab [X]
Interior gamma is <• 20 juR/h
above background in any
occupied or habitable
structure. [X] [ ] [ ] [XI [ ] [ ]
The radon decay-product
concentration in any
occupied or habitable
structure is < 0.02
working level or, at
most, 0.03 working level. [X] [ ] [ ] [>] [ ] [ ]
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21. [ ] [X] [ ] [ ] [A [ ]
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987). [X] [ ] [ ] [y] [ ] I ]
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
illinium liiiiiiiiiR
SFCERTIFED SFMS-00608
DOE ID No.: MS-00608-RS
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
j^L^^r^^ .(Fit 7/frAC
Wanda S. Busby ' Date
.Ivloi Manager, wlonticello Programs
Rust Geotech
DOE EVALUATION
[X] Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Certification Official
U.S. Department of Energy
Date
PROPERTY COMPLETION REPORT
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
DOE ID NO.: MS-00608-RS
ADDRESS: 265 CEDAR LANE
MONTICELLO, UTAH 84535
JULY 1996
Prepared for
U.S. Department of Energy
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
p Wa/<d'a S. Bus6y
Manager, Monticello Programs
FOR
FOR
by
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.1.3 Radon Decay-Product Concentration (RDC) Measurement .... 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
i
DOE ID No.: MS-00608-RS
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Inclusion Survey Contractor. DOE reviewed
these evaluation results and determined that the property contained mill
tailings (residual radioactive material) exceeding EPA standards and DOE
hot spot criteria. The Remedial Action Contractor was notified of the
inclusion of this property into the MVP Project and was authorized by DOE
to conduct remedial action as required to bring the property into
conformance with EPA standards and DOE hot spot criteria.
1
DOE ID No.: MS-00608-RS
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
Property Address:
Property Owners:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
MS-00608-RS
Lot 75, and the south 5 feet of Lot 76, Blue
Mountain Heights No. 3 Subdivision,
Monticello Townsite Addition, County of
San Juan, State of Utah
265 Cedar Lane
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
November 6, 1992
Rust Geotech
April 7, 1994
Crowley Construction, Inc.
East Route HC Box 66
Monticello, Utah
September 14, 1994
September 26, 1994
Interior: 0 cubic yards
Exterior: 3 cubic yards
9 square meters (m2)
July 1996
2
DOE ID No.: MS-00608-RS
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of exterior residual radioactive
material (Appendix Figure 2.1). Once excavation was complete, the
affected areas were resurveyed for possible remaining residual radioactive
material and, upon attaining satisfactory results, were backfilled with
uncontaminated material. The property was restored to a physical
condition comparable to that which existed prior to remedial action
activities.
2.2 Previously Unidentified Contamination
The radiological assessment identified 2 cubic yards of contamination,
ranging from 6 to 12 inches deep, within the property. The remedial
action process included the removal of approximately 3 cubic yards of
residual radioactive material, 12 inches deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID No.: MS-00608-RS
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by the Remedial Action
Contractor during July 1993, as described in the final REA dated
April 1994. Appendix Figure 2.1 shows the extent of assessed
contamination and identifies the areas recommended to undergo
remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the excavation were
collected. These samples were blended to form a composite
sample representing the verification area (Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 12 to 16 microroentgens per
hour (^R/h), as indicated on Appendix Figure 2.1. The result of
analysis for radium-226 in one composite soil sample was
1.6 picocuries per gram (pCi/g), as indicated in Appendix
Table 3.1.
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on measurements representing an annual average, the RDC
was 0.0050 working level (WL), as indicated in Appendix
Table 3.2. Appendix Figure 2.1 shows the measurement location
on the ground floor (the lowest habitable level of the structure).
4
DOE ID No.: MS-00608-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at 265 Cedar Lane, in Monticello, Utah,
is recommended for certification as required by DOE guidelines, and the
appropriate records should be documented.
Certification Data Summary
Applicability Standards Survey Results
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 20 yuR/h
above background.*
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Shall not exceed 5 pCi/g
above background in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
Range for the ground
floor was 12 to 13 //R/h.
Annual average was
0.0050 WL.
< 5 pCi/g above
background.**
Soil sample result was
1.6 pCi/g.**
*The background exposure rate is approximately 13 ywR/h.
The background radium-226 concentration is approximately 2.0 pCi/g.
**The hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-00608-RS
4.0 APPENDIX
Appendix Tables:
Table 3.1 Post-Excavation Sample/Measurement Results
Table 3.2 Radon Decay-Product Concentration Measurement
Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
SJW:06-21-96
MS-00608.RS WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00608-RS
Address: 265 Cedar Lane, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (//R/h) Ticket No. Method0 (pCi/g)
V-1 12-15 NCG 102 OCS 1.6
See Appendix Figure 2.1 for the verification area.
"OCS = Opposed Crystal System
7
Table 3.2
Radon Decay-Product Concentration Measurement Results
DOE ID No.: MS-00608-RS
Address: 265 Cedar Lane, Monticello, Utah
Instrument Type: Landauer Radtrak Detector
Radon
Detector Concentration Working
Number Start Date End Date (pCi/L) Level
3851462 10-11-94 09-27-95 1.03 0.0052
3851612 10-11-94 09-27-95 0.94 0.0047
3851587 10-11-94 09-27-95 1.02 0.0051
Annual Average: 0.0050
See Appendix Figure 2.1 for the measurement location.
8
10
30
12 1 4 1 6 18 20 22 24 26 28 30 32 34 36 38 40
30
28
26
24
22
20 —
6 12
12
2 1 2
V-1
12-15
Ld
<
Cd 13-16 < RDC
Lu
ONE STORY
BRICK AND
FRAME HOUSE
W/CRAWL
SPACE
12-13
13-15
SHED
/13-14
©
F7.\vl
Lv.vj
12-15
12
V-1
16-17
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN juR/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE-RATE RANGE
RADON DECAY-PRODUCT CONCENTRATION
MEASUREMENT LOCATION
28
26
24
22
20
18 18
16
14
12
Y
10
SCALE IN FEET
20 10 0 20 40
M:\FAS\033\0003\RM00608V 07/17/96 08:26am T50780
J L
NORTH
.I L
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT, UTILITY LOCATION PLAT, OR OTHER IMPROVEMENT SURVEY
PLAT AND IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE, BUILDING. OR OTHER FUTURE IMPROVEMENT LINES.
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
RESIDENCE-NO. OF OCCUPANTS
N0N-RES10ENCE-MAN-HRS./WK.
INSTRUUENT NO.
SURVEY OATE
CK. A.E. APP. NO. 1Y CK. A.t. APP.
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE. COLORAOO
30 265 CEDAR LANE
MONTICELLO, UTAH
Rust Oeoteeh
AWUtMnkgia Conor
OATE APPROVAL DOE
DOE ID NO. MS-00608-RS
DWO.NO. 3-B00608-V1 ,„ 1 „, 1
16
14
12
10
10 12 1 4 1 6 18 20 22 24 26 28 30 32 34 36 38 40
t
OAK RIDGE NATIONAL LABORATORY PHONE: [phone]
FAX: [phone] MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
FOR THE U.S. DEPARTMENT OF ENERGY
2597 B 3/4 Road
GRANO JUNCTION, COLORADO 61503
NOV 2 7 1996
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by the U.S.
Department of Energy for Residual Radioactive Material at Formerly Utilized Sites Remedial
Action Program (FUSRAP) and Remote Surplus Facilities Management Program Sites (SFMP)
[Revision 2, March 1987]. This evaluation is based on an independent verification review of the
Remedial Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment of the
concentration in the soil, indoor radon daughter concentration, and indoor gamma exposure
rates at this property.
This property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
Location Number:
Location Address:
MS00608-RS
265 Cedar Lane
Property Owner:
Owner Address:
Monticello. Utah 84535

Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
265 CEDAR LANE
MONTICELLO, UTAH (MS00608-RS)
M. K. Jensen
November 1996
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 3
REFERENCES 6
iii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 4
2. Results of ORNL analysis of the Remedial Action Contractor (RAC) soil samples from
265 Cedar Lane, Monticello, Utah (MS00608-RS) 5
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site Decommissioning
Projects, U.S. Department of Energy. The author wishes to acknowledge A. R. Jones and N. F.
Kirby for technical reviews.
vii
ABSTRACT
In 1980, the site of a vanadium and uranium mill at Monticello, Utah, was accepted into the
U.S. Department of Energy (DOE) Surplus Facilities Management Program, with the objectives of
restoring the government-owned mill site to safe levels of radioactivity, disposing of or containing
the tailings in an environmentally safe manner, and performing remedial actions on off-site (vicinity)
properties that had been contaminated by radioactive material resulting from mill operations. During
1994, the Remedial Action Contractor (RAC) designated by DOE, performed remedial action on the
vicinity property at 265 Cedar Lane, Monticello, Utah. The Environmental Technology Section
(ETS) of Oak Ridge National Laboratory was assigned the responsibility of verifying the data
supporting the adequacy of remedial action and confirming the site's compliance with DOE guide-
lines. The ETS found that the site successfully meets the DOE remedial action objectives. Proce-
dures used by the ETS are described in the Environmental Technology Section Procedures Manual
(ORNL 1993).
ix
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 265 CEDAR LANE
MONTICELLO, UTAH (MS00608-RS)*
INTRODUCTION
The rnill at Monticello, Utah, was built in 1942 by the United States (U.S.) government through
the Defense Plant Corporation to provide vanadium during World War II. Various government
agencies operated the mill until 1947. In 1948, the Atomic Energy Commission (AEC) obtained the
mill and operated it under contract through 1959 to provide both uranium and vanadium. Mill
operations were terminated on January 1, 1960. In 1961, the mill tailings piles were leveled and
graded, covered with rock and soil, and seeded with native grasses. During 1974 and 1975, the ore
stockpiles were removed from the site and the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city of
Monticello, in San Juan County, Utah. The site is bordered on the south and southeast by land held
by the U.S. Bureau of Land Management. Other boundaries are the city of Monticello and private
property.
During the AEC era, the mill processed approximately one million tons of uranium ore. Vana-
dium and uranium were the only substances extracted in the milling process. Other constituents of
the ore remained in the tailings and were not separated prior to disposal. During the years of active
mill operation, the mill tailings were normally moist, so erosion was minimal. However, throughout
the mill's operating period area residents used these tailings as fill material and as aggregate in
mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy (DOE) initiated
the Surplus Facilities Management Program (SFMP) in 1978 to ensure the safe caretaking and de-
commissioning of government facilities that had been retired from service but still had radioactive
contamination. In 1980, the mill site at Monticello was accepted into the SFMP, and the Monticello
Remedial Action Project (MRAP) was established to restore the government-owned mill site to safe
levels of radioactivity, to dispose of or contain the tailings in an environmentally safe manner, and
to perform remedial actions on off-site (vicinity) properties that had been contaminated by
radioactive material resulting from mill operations. The Monticello mill site and the tailings remain
in the custody of the DOE Grand Junction, Colorado, Projects Office. In 1983, remedial actions for
vicinity properties were separated from MRAP with establishment of the Monticello Vicinity
Properties (MVP) Project (US DOE 1990b).
•The verification of remedial action was performed by members of the Environmental Assessment Group in the Environmental
Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE contract DE-AC05-
960R22464 with Lockheed Martin Energy Research Corporation.
2
During 1994, the Remedial Action Contractor (RAC) designated by DOE, performed remedial
action on the vicinity property that is the subject of this report, a single family residence located at
265 Cedar Lane, Monticello, Utah. The remedial action plan required excavation of all exterior
contamination. When the excavation was completed, the property was resurveyed, including soil
sampling, to ensure the removal of all contamination, backfilled with uncontaminated material, and
restored to a condition comparable to that which existed prior to remedial action (Geotech 1996).
The DOE adopted a policy to assign an independent contractor to verify the data supporting the
adequacy of remedial action and to confirm the site's compliance with DOE guidelines. The
Environmental Technology Section (ETS) of Oak Ridge National Laboratory (ORNL) has been
assigned the responsibility of this task at the 265 Cedar Lane site. This report describes the methods
and results of that verification.
PROCEDURES
Objectives
The objectives ofthe verification activities were to confirm (1) that available documentation
adequately and accurately describes the post-remedial-action radiological conditions of the entire
property that is to be certified and (2) that the remedial action reduced contamination to below
applicable DOE guidelines (DOE 1990a).
Document Reviews
Review of the RAC property completion report (Geotech 1996) indicates the property was reme-
diated as evaluated by DOE on the basis of U.S. Environmental Protection Agency standards and
the DOE guidelines (DOE 1990a). Excess residual radioactive materials were present, thus it was
appropriate to designate this property for remedial action.
The pre-remedial-action survey performed by the RAC identified 2 yd3 of mill tailings 6 to 12
inches deep. During the actual removal process, a total of 3 yd3 of contaminated earth and uranium
mill tailings, 12 inches deep, were removed from a 9 m2 area.
The RAC performed a post-excavation survey prior to backfilling the excavated areas. This
survey consisted of gamma scans with a scintillometer of the ground level of the structure, a surface
scan ofthe exterior, and soil sampling. Samples representative of the bottom 15-cm (6-in.) soil
layers of one excavated verification area were collected and blended to form a representative
composite soil sample.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation levels have
not been subtracted. Similarly, background concentrations have not been subtracted from radionu-
clide concentrations in soil samples. Applicable DOE guidelines for protection against radiation are
given in Table 1.
Gamma Measurements
Gamma exposure rate measurements taken by the RAC at the ground-level of the residence
ranged from 12 to 13 uR/h. Exterior surface gamma measurements taken from the excavated areas
prior to backfilling ranged from 12 to 15 pR/h.
Soil Sample Analysis
Prior to backfilling, the RAC collected soil samples representative of the excavated area from
the bottom 15-cm (6-in.) soil layers. These samples were blended to form a composite soil sample
representative of an average over the exterior verification area. The RAC's analysis of this sample
showed a 226Ra concentration of 1.6 pCi/g. ORNL ETS obtained this sample and performed a
confirmatory analysis which showed a 226Ra concentration of 1.3 pCi/g. These values are below the
DOE guideline values of 15 pCi/g for soil layers > 15 cm below the surface. Gamma ranges and/or
soil sample results demonstrate compliance to the DOE Hot Spot Guidelines for areas <25 m2 (Table
1). Results of the RAC and ORNL soil sample analyses are given in Table 2.
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were detennined by the
Alpha-track method. To monitor radon levels, the RAC placed three alpha-track detectors on the
ground floor ofthe residence located on this property for a period of approximately one year (from
October 11, 1994 to September 27, 1995). The average annual working level (WL) of radon
progeny concentration, as determined by the TechVOps-Landauer Corporation, was 0.0050, which
is well below the 0.03-WL guideline given in Table 1.
CONCLUSION
Results ofthe RAC soil sample analysis and confirmatory split soil sample analysis by ORNL
show that radionuclide concentrations are within applicable DOE guidelines. Based on the results
of the post-remedial-action data, which are confirmed by the verification assessment data, these
radiological measurements fall below the limits prescribed by DOE guidelines. It is concluded that
the site successfully meets the DOE remedial action objectives.
4
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of 226Ra in soil
above background levels,
averaged over a 100-m2 area
5 pCi/g averaged over the first 15 cm
of soil below the surface; 15 pCi/g
when averaged over 15-cm-thick soil
layers more than 15 cm below the
surface
Radionuclide con-
centrations in soil
for Hot Spot areas
Exposure to 222Rn
progeny
Maximum Permissible con-
centration of Ra226 in soil
above background level, for
areas less than 25 m2
Average annual radon
progeny concentration
(including background)
Ra226 concentrations, in any surface
or subsurface area less than 25 m2, is
below the guideline by a factor of
(1007A)'/j, where A is the area of the
elevated region
0.03 WL
(DOE 1990a)
5
Table 2. Results of ORNL analysis ofthe Remedial Action Contractor (RAC)
soil samples from 265 Cedar Lane, Monticello, Utah (MS00608-RS)
Ra concentration (pCi/g)
ORNL RAC
sample sample Depth ORNL RAC
No." No/; £cm)
XI NCG 102 >15 1.3 1.6
" An X-type sample is a split of the sample taken by the remedial action contractor.
* Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated areas were taken by
the RAC, and these samples were blended to form a composite soil sample, which represents an average
over one of the verification areas.
6
REFERENCES
Geotech 1996. Property Completion Report for Monticello Vicinity Property Remedial Action for
DOE ID NO: MS00608-RS, Address: 265 Cedar Lane, Monticello, Utah 84535, Rust Geotech,
Grand Junction, Colorado, July 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment Group)
Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National Laboratory, Grand
Junction, Colorado.
U.S. DOE 1990a. Verification and Certification Protocol for the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination and
Decommissioning Program. Revision 3, November 1990. U.S. Department of Energy, Washington,
D.C.
U.S. DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision and Record
of Decision Summary. U.S. Department of Energy, Grand Junction Projects Office, Grand Junction,
Colorado.
DOE ID Nos.: MS-00620-RS
Property Address: 596 Circle Drive
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust fiantftnh nf Fnfirgy (DOE)
YES NO NOT TAKEN YES NO NOT TAKEN
Ra-226 is z 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2. [X]* [ ] [ ] [>fl [ ] [ ]
In-situ [X] Lab [ ]
Ra-226 is ^ 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2. [X] [ ] [ ] [yl [ ] [ ]
In-situ [ ] Lab [X]
Interior gamma is ^ 20 //R/h
above background in any
occupied or habitable
structure. [X] [ ] [ ] ["A [ ] M
The radon decay-product
concentration in any
occupied or habitable
structure is <, 0.02
working level or, at
most, 0.03 working level. [X] [ ] [ ] MM [ 1
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21. [ ] [X] [ ] [ ] [M [ ]
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987). [X] [ ] [ ] [>J [ ] [ ]
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
DOE ID No.: MS-00620-RS
RUST GEOTECH RECOMMENDATION
On the basis of the Property Completion Report evaluation, this property is
recommended for
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Michael C. Butherus
Manager, Monticello Programs
MACTEC-ERS
Date
DOE EVALUATION
[/\ Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
prtification Official
.S. Department of Energy
fry ?=f
Date
PROPERTY COMPLETION REPORT
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
DOE ID NO.: MS-00620-RS
ADDRESS: 596 CIRCLE DRIVE
MONTICELLO, UTAH 84535
MARCH 1996
Prepared for
U.S. Department of Energy
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
Manager, Monticello Programs
FOR
FOR
by
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
Ill
SFOCPLRPTS SFMS-00127
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.1.3 Radon Decay-Product Concentration (RDC) Measurement .... 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
DOE ID No.: MS-00620-RS
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Inclusion Survey Contractor. DOE reviewed these
evaluation results and determined that the property contained mill tailings
(residual radioactive material) exceeding DOE hot spot criteria. The
Remedial Action Contractor was notified of the inclusion of this property
into the MVP Project and was authorized by DOE to conduct remedial
action as required to bring the property into conformance with EPA
standards and DOE hot spot criteria.
1
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
Property Address:
Property Owners:
Property Category:
Inclusion Survey Contractor:
inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
DOE ID No.: MS-00620-RS
MS-00620-RS
Beginning 503.15 feet south and
187.55 feet east of the center of
Section 36, T33S., R23E., Salt Lake Base
Meridian; south 25 degrees 51 minutes east
104.3 feet, south 59 degrees 26 minutes
west 176 feet, north 38 degrees
00 minutes west 132.5 feet, north
66 degrees 48 minutes east 203 feet more
or less to the point of beginning, City of
Monticello, County of San Juan, State
of Utah
596 Circle Drive
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
January 31, 1991
Rust Geotech
September 9, 1994
Diamond Back Services, Inc.
9861 Titan Park Circle
Littleton, Colorado
May 22, 1995
July 13, 1995
Interior: 0 cubic yards
Exterior: 6 cubic yards
28 square meters (m2)
March 1996
2
DOE ID No.: MS-00620-RS
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of exterior residual radioactive
material (Appendix Figure 2.1). Once excavation was complete, the
affected areas were resurveyed for possible remaining residual radioactive
material and, upon attaining satisfactory results, were backfilled with
uncontaminated material. The property was restored to a physical
condition comparable to that which existed prior to remedial action
activities.
2.2 Previously Unidentified Contamination
The radiological assessment identified contamination, 6 inches deep to
18 inches high, within the property. The quantity of contamination for this
property was not specified because it was assessed as part of Group 3.
The remedial action process included the removal of approximately 6 cubic
yards of residual radioactive material, ranging from 18 inches deep to 8
inches high.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID No.: MS-00620-RS
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by the Remedial Action
Contractor during May 1992, as described in the final REA dated
September 1994. Appendix Figure 2.1 shows the extent of
assessed contamination and identifies the areas recommended to
undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the excavation were
collected. These samples were blended to form composite
samples representing the verification areas. Additionally, an in-situ
measurement was taken for Area V-1 (Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 12 to 20 microroentgens per
hour (/;R/h), as indicated on Appendix Figure 2.1. The results of
analyses for radium-226 in two composite soil samples and one in-
situ measurement ranged from 1.3 to 3.5 picocuries per
gram (pCi/g), as indicated in Appendix Table 3.1.
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on the DOE-approved abbreviated-measurement method, the
RDC was 0.0167 working level (WL), as indicated in
Appendix Table 3.2. Appendix Figure 2.1 shows the measurement
location in the basement (the lowest habitable level of the
structure).
4
DOE ID No.: MS-00620-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at 596 Circle Drive, in Monticello, Utah,
is recommended for certification as required by DOE guidelines, and the
appropriate records should be documented.
Certification Data Summary
Applicability Standards Survey Results
Habitable Structures
Exposure Rate: Shall not exceed 20 //R/h
above background.*
Range for the basement
was 12 to 15//R/h.
Radon Decay-Product
Concentration:
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Average was 0.01 67 WL,
based on the DOE-
approved abbreviated-
measurement method.
Land
Radium-226 Concentration Shall not exceed 5 pCi/g In-situ measurement
in Surface Soil: above backgroundt in the result was 1.7 pCi/g.
1 5-cm surface layer,
averaged over 100 m2.
Radium-226 Concentration Shall not exceed 15 pCi/g Soil sample results were
in Subsurface Soils: above background1 in any 1.3 and 3.5 pCi/g. * *
15-cm-thick soil layer
more than 1 5 cm below
the surface, averaged
over 100 m2.
*The background exposure rate is approximately 13 //R/h.
The background radium-226 concentration is approximately 2.0 pCi/g.
**The hot spot criteria were met based on gamma scans and/or soil sample results.
5
\
DOE ID No.: MS-00620-RS
4.0 APPENDIX
Appendix Tables:
Table 3.1 Post-Excavation Sample/Measurement Results
Table 3.2 Radon Decay-Product Concentration Measurement
Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
SJW: 12-05-95
MS-00620.RS WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00620-RS
Address: 596 Circle Drive, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range i/jR/h) Ticket No. Method3 (pCi/g)
V-1 16-18 N/A DS 1.7
V-2 14-17 NCJ 026 OCS 1.3
V-3 14-20 NCJ 028 OCS 3.5
See Appendix Figure 2.1 for the verification areas.
aOCS = Opposed Crystal System; DS = Delta Scanner
7
Table 3.2
Radon Decay-Product Concentration Measurement Results
DOE ID No.: MS-00620-RS
Address: 596 Circle Drive, Monticello, Utah
Instrument Type: Landauer Radtrak Detector
Detector
Number Start Date End Date
Tracks Per
mm2
Radon
Concentration
(pCi/L)
Working
Level
3973886
3973999
3973896
07-25-95
07-25-95
07-25-95
11-15-95
11-15-95
11-15-95
10.7
10.4
10.3
3.40 0.0170
3.31 0.0166
3.28 0.0164
Average: 0.0167
See Appendix Figure 2.1 for the measurement location.
8
36
34
32
30
28
26
24
22
20
18
16
1 4
12
10
1
12 14 16 18 20 22 24 26 28 30 32 34 36 38 40 42 46 48 5
12-15
GARAGE^.
«"12-13 J X 6
6(6X1
8
ROC V-3
14-20 V-1
16-18
TWO ST0RY\
FRAME HOUSE
,W/BASEMENT
\ 12-15
2 X G K18]
12-15 V-2
14-17
\ 12-15
\
\
V-3
\ 14-20
\
\ GARAGE
12-13
\
\
\ 12~15 S
©
<£>
12-15
EH
v-i
16-17
[12)
-X-
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN /iR/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST—REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE-RATE RANGE
RADON DECAY-PRODUCT CONCENTRATION
MEASUREMENT LOCATION
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
HEIGHT IN INCHES OF ASSESSED CONTAMINATED
GROUT REMOVED AND REPLACED
ASSESSED AREA H (BOX OF ORE SAMPLES)
WAS REMOVED AND NOT REPLACED
L
SCALE IN FEET
20 10 0 20 40
M.\FAS\0JJ\000J\RU00620V 02/20/96 09:39am T30780
NORTH
I I I I I
12 14 16 20 22 24 26 28 30
THIS DRAWING IS FOR THE SOLE USE OF THE U S. DEPARTMENT
OF ENERGY ANO ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT. UTILITY LOCATION PL>T. OR OTHER IMPROVEMENT SURVEY
PLAT AND IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE. BUILDING. OR OTHER FUTURE IMPROVEMENT LINES.
32 34 36 38
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
I
I
i_L
U.S. OEPARTUENT OF ENERGY
c*«io JUNCTION MOJCCTS O.HCE. c;.:»>30
..... -J-J* 596 CIRCLE DRIVE
MONTICELLO. UTAH
I 0.1 |»w/>«.ttJ. '
MS-00620-RS
40 42 44 46
3-CSC520-V1,
48
OAK RIDGE NATIONAL LABORATORY PHONE: [phone]
FAX: (970) 24S-6220 MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
FOR THE U.S. DEPARTMENT OF ENERGY
POST OFFICE BOX 2M7
GRANO JUNCTION, COLORADO 81502
m 2 8 1996
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by the
U.S. Department of Energy for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program (FUSRAP) and Remote Surplus Facilities Management Program
Sites (SFMP) [Revision 2, March 1987]. This evaluation is based on an independent
verification review of the Remedial Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment of
the 226Ra concentration in the soil, indoor radon daughter concentration, and indoor gamma
exposure rates at this property.
Therefore, this property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
Location Number:
Location Address: 549 Circle Drive
MS00127-MR
Monticello, Utah 84535
Property Owner:
Owner Address:

Tenant Name: Same
Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
549 CIRCLE DRIVE
MONTICELLO, UTAH (MS00127-MR)
M. J. Wilson-Nichols
June 1996
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv *
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 4
REFERENCES 7
iii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 5
2. Results of ORNL analysis of Geotech soil samples from 549 Circle Drive,
Monticello, Utah (MSOO 127-MR) 6
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site Decom-
missioning Projects, U.S. Department of Energy. The author wishes to acknowledge M.
K. Jensen for analysis of soil samples and J. R. Sauvage for technical reviews.
vii
ABSTRACT
In 1980 the site of a vanadium and uranium mill at Monticello, Utah, was accepted
into the U.S. Department of Energy's (DOE's) Surplus Facilities Management Program,
with the objectives of restoring the government-owned mill site to safe levels of radio-
activity, disposing of or containing the tailings in an environmentally safe manner, and
performing remedial actions on off-site (vicinity) properties that had been contaminated
by radioactive material resulting from mill operations. During 1995, RUST Geotech, the
remedial action contractor designated by DOE, performed remedial action on the vicinity
property at 549 Circle Drive, Monticello, Utah. The Environmental Technology Section
(ETS) of Oak Ridge National Laboratory was assigned the responsibility of verifying the
data supporting the adequacy of remedial action and confirming the site's compliance with
DOE guidelines. The ETS found that the site successfully meets the DOE remedial action
objectives. Procedures used by the ETS are described in the Environmental Technology
Section Procedures Manual (ORNL 1993).
ix
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 549 CHICLE DRIVE
MONTICELLO, UTAH (MS00127-MR)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the U.S. government through the
Defense Plant Corporation to provide vanadium during World War II. Various govern-
ment agencies operated the mill until 1947. In 1948 the Atomic Energy Commission
(AEC) obtained the mill and operated it under contract through 1959 to provide both
uranium and vanadium. Mill operations were terminated on January 1, 1960. In 1961 the
mill tailings piles were leveled and graded, covered with rock and soil, and seeded with na-
tive grasses. During 1974 and 1975, the ore stockpiles were removed from the site, and
the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city
of Monticello, in San Juan County, Utah. The site is bordered on the south and southeast
by land held by the U.S. Bureau of Land Management. Other boundaries are the city of
Monticello and private property.
During the AEC era, the mill processed approximately one million tons of uranium
ore. Vanadium and uranium were the only substances extracted in the milling process.
Other constituents of the ore remained in the tailings and were not separated prior to dis-
posal. During the years of active mill operation, the mill tailings were normally moist, so
erosion was minimal. However, throughout the mill's operating period, area residents
used these tailings as fill material and as aggregate in mortar and concrete:
Under the authority of the Atomic Energy Act, the U.S. Department of Energy
(DOE) initiated the Surplus Facilities Management Program (SFMP) in 1978 to ensure
the safe caretaking and decommissioning of government facilities that had been retired
from service but still had radioactive contamination. In 1980 the mill site at Monticello
was accepted into the SFMP, and the Monticello Remedial Action Project (MRAP) was
established to restore the government-owned mill site to safe levels of radioactivity, to
dispose of or contain the tailings in an environmentally safe manner, and to perform reme-
dial actions on off-site (vicinity) properties that had been contaminated by radioactive ma-
terial resulting from mill operations. The Monticello mill site and the tailings remain in the
custody of the DOE Grand Junction, Colorado, Projects Office. In 1983 remedial actions
for vicinity properties were separated from MRAP with establishment of the Monticello
Vicinity Properties (MVP) Project (U.S. DOE 1990b).
*The verification of remedial action was performed by members of the Environmental Assessment Group in the
Environmental Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE
contract DE-AC05-96OR22464 with Lockheed Martin Energy Research Corporation.
2
During 1995, RUST Geotech Inc. (Geotech), the remedial action contractor (RAC)
designated by DOE, performed remedial action on the vicinity property that is the subject
of this report, a single family residence located at 549 Circle Drive, Monticello, Utah. The
remedial action plan required excavation of all exterior contamination. When the excava-
tion was completed, the property was resurveyed, including soil sampling, to ensure the
removal of all contamination, backfilled with uncontaminated material, and restored to a
condition comparable to that which existed prior to remedial action (Geotech 1996).
The DOE adopted a policy to assign an independent contractor to verify the data
supporting the adequacy of remedial action and to confirm the site's compliance with DOE
guidelines. The Environmental Technology Section (ETS) of Oak Ridge National Labor-
atory (ORNL) has been assigned the responsibility of this task at the 549 Circle Drive site.
This report describes the methods and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available docu-
mentation adequately and accurately describes the post-remedial-action radiological
conditions of the entire property that is to be certified and (2) that the remedial action
reduced contamination to below applicable DOE guidelines (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1996) in-
dicates the property was remediated as evaluated by DOE on the basis of Environmental
Protection Agency standards and the DOE guidelines (DOE 1990a). Excess residual
radioactive materials were present, thus it was appropriate to designate this property for
remedial action.
This property was assessed as part of Group 3, therefore, the quantity of material
assessed is not available. During the actual removal process, a total of 7 yd3 of contami-
nated earth and uranium mill tailings, 6 inches deep, was removed from a 37 m2 area.
A post-excavation survey was performed by Geotech prior to backfilling the exca-
vated areas. This survey consisted of gamma scans with a scintillometer of the ground
level of the structure, a surface scan of the exterior, and soil sampling. Samples repre-
sentative of the bottom 15-cm (6-in.) soil layers of three excavated verification areas were
collected and blended to form representative composite soil samples for each verification
area.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation
levels have not been subtracted. Similarly, background concentrations have not been sub-
tracted from radionuclide concentrations in soil samples. Applicable DOE guidelines for
protection against radiation are given in Table 1.
Gamma Measurements
Gamma exposure rate measurements taken by Geotech at the ground-level ofthe
residence ranged from 11 to 13 uR/h. Exterior surface gamma measurements taken from
the excavated areas prior to backfilling ranged from 15 to 23 uR/h.
Soil Sample Analysis
Prior to backfilling, Geotech collected soil samples representative of the excavated
areas from the bottom 15-cm (6-in.) soil layers. These samples were blended to form a
composite soil sample representative of an average over the three exterior verification
areas. Geotech's analysis of this sample showed a 226Ra concentration of 4.5 pCi/g.
ORNL ETS obtained this sample and performed a confirmatory analysis which showed a
22<Ra concentration of 6.2 pCi/g. These values are below the EPA standard value of 15
pCi/g for soil layers > 15 cm below the surface. Gamma ranges and/or soil sample results
demonstrate compliance to the DOE Hot Spot Guidelines for areas <25 m2 (Table 1).
As a result of a meeting between the RAC and IVC on May 26, 1994, anomalous
readings, defined as > 30% above the average of the excavation, will be investigated to
show compliance to the DOE hot spot guideline. The IVC observed that 23 uR/h exceeds
30% of the excavation average of 21 uR/h for Region C, which is attributed to contami-
nation extending into the street. The IVC will allow a correlation developed by the RAC
to estimate 226Ra pCi/g concentrations based on gamma exposure rates. The anomalous
reading of 23 uR/h on this property using the RAC's correlation yields a 226Ra concen-
tration of 4.4 pCi/g. This value is well below the minimum concentration of 30 pCi/g
needed, when assuming the maximum area under the hot spot guideline of 25 m2, for
subsurface samples. Results of Geotech and ORNL soil sample analyses are given in
Table 2.
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were deter-
mined by the Alpha-track method. To monitor radon levels, Geotech placed three alpha-
track detectors in the basement of the residence located on this property for a period of
approximately three months (from March 8, 1995 to June 7, 1995). The average annual
working level (WL) of radon progeny concentration, as determined by the Tech./Ops-
Landauer Corporation, was 0.0100, which is well below the 0.03-WL guideline given in
Table 1.
4
CONCLUSION
Results of Geotech soil sample analysis and confirmatory split soil sample analysis
by ORNL show that radionuclide concentrations are within applicable DOE guidelines.
Based upon the results of the post-remedial-action data, which are confirmed by the veri-
fication assessment data, these radiological measurements fall below the limits prescribed
by DOE guidelines. It is concluded that the site successfully meets the DOE remedial
action objectives.
5
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of ^Ra in soil
above background levels,
averaged over a 100-m2 area
5 pCi/g averaged over the
first 15 cm of soil below the
surface; 15 pCi/g when ave-
raged over 15-cm-thick soil
layers more than 15 cm
below the surface
Radionuclide
concentrations in soil
for Hot Spot areas
Exposure to 222Rn
progeny
Maximum Permissible
concentration of Ra226 in soil
above background level, for
areas less than 25 m2
Average annual radon proge-
ny concentration (including
background)
Ra226 concentrations, in any
surface or subsurface area
less than 25 m2, is below the
guideline by a factor of
(1 Oft/A)*, where A is the
area ofthe elevated region
0.03 WL
(DOE 1990a)
6
Table 2. Results of ORNL analysis of Geotech soil samples
from 549 Circle Drive, Monticello Utah (MS00127-MR)
226Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No." Nof (cm)
XI VI 15 to 30 6.2 4.5
" An X-type sample is a split of the sample taken by the remedial action contractor.
6 Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated areas
were taken by Geotech, and these samples were blended to form a composite soil
sample, which represents an average over one of the verification areas.
7
REFERENCES
Geotech 1996. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MSOO 127-MR, Address: 549 Circle Drive, Monticello, Utah
84535, Geotech, Grand Junction, Colorado, March 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
U.S. DOE 1990a. Verification and Certification Protocol for the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination
and Decommissioning Program, Revision 3, November 1990. U.S. Department of
Energy, Washington, D.C.
U.S. DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision
and Record of Decision Summary. U.S. Department of Energy, Grand Junction Projects
Office, Grand Junction, Colorado.
DOE ID No.: MS-00622-RS
Property Address: 533 Circle Drive
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech of Energy (DOE)
YES NO NOT TAKEN YES NO NOT TAKEN
Ra-226 is s 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [ ]
[X]* [ ] [ I [X] [ 1 [ 1
Ra-226 is < 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2. [X] [ ] [ ] [>] [ ] [ ]
In-situ [ ] Lab [X]
Interior gamma is <, 20 //R/h
above background in any
occupied or habitable
structure. [X] [ ] [ ] [>] [ ] [ ]
The radon decay-product
concentration in any
occupied or habitable
structure is <. 0.02
working level or, at
most, 0.03 working level. [X] [ ] [ ] [X) [ ] [ ]
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21. [ ] [X] [ ] [ ] [A I ]
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987). [X] [ ] [ ] [>i [ ] [ ]
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
Ililllllllll 11111111111
SFCERTIFED SFMS-00127
DOE ID No.: MS-00622-RS
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
/anda S' BQsby Date
Manager, Monticello Programs
Rust Geotech
DOE EVALUATION
M Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
C^m^rloTi^ Dafe ^ ^ ^
U.S. Department of Energy
PROPERTY COMPLETION REPORT
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
DOE ID NO.: MS-00622-RS
ADDRESS: 533 CIRCLE DRIVE
MONTICELLO, UTAH 84535
MARCH 1996
Prepared for
U.S. Department of Energy
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
•llllllllll 11111111111
FOR
FOR
by
Manager, Monticello Programs
SFOCPLRPTS SFMS-00127
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.1.3 Radon Decay-Product Concentration (RDC) Measurement .... 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
DOE ID No.: MS-00622-RS
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Inclusion Survey Contractor. DOE reviewed these
evaluation results and determined that the property contained mill tailings
(residual radioactive material) exceeding EPA standards and DOE hot spot
criteria. The Remedial Action Contractor was notified of the inclusion of
this property into the MVP Project and was authorized by DOE to conduct
remedial action as required to bring the property into conformance with
EPA standards and DOE hot spot criteria.
1
DOE ID No.: MS-00622-RS
1.3 Summary of Remedial Action
DOE ID No.: MS-00622-RS
Legal Description:
Beginning 375.69 feet south and 185.16 feet east of the center of Section 36,
T33S., R23E., Salt Lake Base Meridian; north 01 degrees 25 minutes east
128.6 feet, north 42 degrees 12 minutes east 41.7 feet, north 72 degrees
53 minutes east 93.8 feet, south 15 degrees 04 minutes east 172.5 feet, south
82 degrees 24 minutes west 168.5 feet to the point of beginning, City of
Monticello, County of San Juan, State of Utah
Property Address: 533 Circle Drive
Monticello, Utah 84535
Property Owners:

Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Residential Simple (RS)
Oak Ridge National Laboratory
March 5, 1992
Remedial Action Contractor: Rust Geotech
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
September 9, 1994
Diamond Back Services, Inc.
9861 Titan Park Circle
Littleton, Colorado
May 22, 1995
July 13, 1995
Interior: 0 cubic yards
Exterior: 8 cubic yards
23 square meters (m2)
March 1996
2
DOE ID No.: MS-00622-RS
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of exterior residual radioactive
material (Appendix Figure 2.1). Once excavation was complete, the
affected areas were resurveyed for possible remaining residual radioactive
material and, upon attaining satisfactory results, were backfilled with
uncontaminated material. The property was restored to a physical
condition comparable to that which existed prior to remedial action
activities.
2.2 Previously Unidentified Contamination
The radiological assessment identified contamination, 30 inches deep to
24 inches high, within the property. The quantity of contamination for this
property was not specified because it was assessed as part of Group 3.
The remedial action process included the removal of approximately 8 cubic
yards of residual radioactive material, ranging from 30 inches deep to 24
inches high.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID No.: MS-00622-RS
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by the Remedial Action
Contractor during May 1992, as described in the final REA dated
September 1994. Appendix Figure 2.1 shows the extent of
assessed contamination and identifies the areas recommended to
undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the excavation were
collected. These samples were blended to form composite
samples representing the verification areas (Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 12 to 21 microroentgens per
hour (//R/h), as indicated on Appendix Figure 2.1. The results of
analyses for radium-226 in two composite soil samples were
3.4 and 5.7 picocuries per gram (pCi/g), as indicated in Appendix
Table 3.1.
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on the DOE-approved abbreviated-measurement method, the
RDC was 0.0019 working level (WL), as indicated in
Appendix Table 3.2. Appendix Figure 2.1 shows the measurement
location on the ground floor (the lowest habitable level of the
structure).
4
DOE ID No.: MS-00622-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at 533 Circle Drive, in Monticello, Utah,
is recommended for certification as required by DOE guidelines, and the
appropriate records should be documented.
Applicability
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Certification Data Summary
Standards
Shall not exceed 20 //R/h
above background.*
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Survey Results
Range for the ground
floor was 12 to 14 //R/h.
Average was 0.0019 WL,
based on the DOE-
approved abbreviated-
measurement method.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
< 5 pCi/g above
background.**
Soil sample results were
3.4 and 5.7 pCi/g.**
*The background exposure rate is approximately 13 //R/h.
The background radium-226 concentration is approximately 2.0 pCi/g.
**The hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-00622-RS
4.0 APPENDIX
Appendix Tables:
Table 3.1 Post-Excavation Sample/Measurement Results
Table 3.2 Radon Decay-Product Concentration Measurement
Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
SJW: 12-06-95
MS-00622.RS WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00622-RS
Address: 533 Circle Drive, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (//R/h) Ticket No. Method" (pCi/g)
V-1 13-21 NCJ 021 OCS 3.4
V-2 14-21 NCJ 022 OCS 5.7
See Appendix Figure 2.1 for the verification areas.
aOCS = Opposed Crystal System
7
Table 3.2
Radon Decay-Product Concentration Measurement Results
DOE ID No.: MS-00622-RS
Address: 533 Circle Drive, Monticello, Utah
Instrument Type: Landauer Radtrak Detector
Radon
Detector Tracks Per Concentration Working
Number Start Date End Date mm2 (pCi/L) Level
3973965 07-25-95 11-15-95
3973829 07-25-95 11-15-95
3973953 07-25-95 11-15-95
1.1 0.34 0.0017
1.1 0.34 0.0017
1.4 0.44 0.0022
Average: 0.0019
See Appendix Figure 2.1 for the measurement location.
8
40
38
36
34
32
30
28
26
24
22
20
18
16
14
12
10
1
4U 42 46 48 51
/
/
30
13-21
ONE
STORY
FRAME
HOUSE
W/CRAWL
SPACE \
12
V-2
12-14 14-21
12-15 / 24]
30
30
V-2
14-21
GARAGE
! 13-21
L
SCALE IN FEET
20 10 0 20 40
U-.\FAS\033\0O03\»ii0O«22V 03/03/»t 3-.t2ni\ T307eO
NORTH
©
<s>
Lv.vj
12-15
12
v-i
16-17
[12]
lEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN uR/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE —RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE —RATE RANGE
RADON DECAY—PRODUCT CONCENTRATION
MEASUREMENT LOCATION
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
HEIGHT IN INCHES OF ASSESSED CONTAMINATED
CONCRETE STOOP REMOVED AND REPLACED
ASSESSED DEPTH OF CONTAMINATION NOT PROVIDED
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. OEPARTUENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT, UTILITY LOCATIOH PLAT. OR OTHER IMPROVEMENT SURVEY
PLAT AND IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE, BUILDING, OR OTHER FUTURE IMPROVEMENT LINES
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICC. COLORADO
533 CIRCLE DRIVE
MONTICELLO, UTAH
I Ml ItfMWT
«•*"• US-00622-RS
3-C00622-V1.. 1 » 1
12 14 16 18 20 22 24 26 28 30 32 34 36 38 40 42 44 46 48 5(
OAK RIDGE NATIONAL LABORATORY PHONE: <970) 24M200
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION FAX: [phone]
FOR THE US. DEPARTMENT OF ENERGY
POST OFFICE BOX 2567
GRAND JUNCTION, COLORADO 81502
JUL 3 I 1996
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by the
U.S. Department of Energy for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program (FUSRAP) and Remote Surplus Facilities Management Program
Sites (SFMP) [Revision 2, March 1987]. This evaluation is based on an independent
verification review of the Remedial Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment of
the 226Ra concentration in the soil, indoor radon daughter concentration, and indoor gamma
exposure rates at this property.
Therefore, this property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
MS00622-RS
533 Circle drive
Monticello, Utah 84535

Alex Van Hemert
Location Number:
Location Address:
Property Owner:
Owner Address:
Tenant Name:
Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE B INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
533 CTRCLE DRIVE
MONTICELLO, UTAH (MS00622-RS)
A. R. Jones
July 1996
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES v
LIST OF FIGURES v
ACKNOWLEDGMENTS vii
ABSTRACT viii
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
GEOTECH SURVEY RESULTS 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
ORNL SURVEY RESULTS 6
Gamma Measurements 6
Soil Sample Analysis 6
CONCLUSION 6
REFERENCES 8
ii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 4
2. Results of ORNL and Geotech analyses of soil samples from 533 Circle Drive
Monticello, Utah (MS00622-RS) 5
LIST OF FIGURES
1. Property Map 7
v
ACKNOWLEDGMENTS
Research for this project was sponsored by the U.S. Department of Energy, Office of
Environmental Restoration, Southwestern Area Programs. The author wishes to acknow-
ledge M. K. Jensen for analysis of soil samples and M. J. Wilson-Nichols and N. F. Kirby
for technical reviews.
vii
ABSTRACT
In 1980 the site of a vanadium and uranium mill at Monticello, Utah, was accepted
into the U.S. Department of Energy's (DOE's) Surplus Facilities Management Program,
with the objectives of restoring the government-owned mill site to safe levels of radioac-
tivity, disposing of or containing the tailings in an environmentally safe manner, and per-
forming remedial actions on off-site (vicinity) properties that had been contaminated by
radioactive material resulting from mill operations. During 1995, RUST Geotech Inc., the
remedial action contractor designated by DOE, performed remedial action on the vicinity
property at 533 Circle Drive, Monticello, Utah. The Environmental Technology Section
(ETS) of Oak Ridge National Laboratory was assigned the responsibility of verifying the
data supporting the adequacy of remedial action and confirming the site's compliance with
DOE guidelines. The ETS found that the site successfully meets the DOE remedial action
objectives. All deficiencies noted in the initial review have been resolved in the revised
completion report. Procedures used by ETS are described in the Environmental Tech-
nology Section Procedures Manual (ORNL 1993).
viii
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 533 CIRCLE DRIVE
MONTICELLO, UTAH (MS00622-RS)'
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the U.S. government through the
Defense Plant Corporation to provide vanadium during World War II. Various govern-
ment agencies operated the mill until 1947. In 1948 the Atomic Energy Commission
(AEC) obtained the mill and operated it under contract through 1959 to provide both
uranium and vanadium. Mill operations were terminated on January 1, 1960. In 1961 the
mill tailings piles were leveled and graded, covered with rock and soil, and seeded with na-
tive grasses. During 1974 and 1975, the ore stockpiles were removed from the site, and
the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city
of Monticello, in San Juan County, Utah. The site is bordered on the south and southeast
by land held by the U.S. Bureau of Land Management. Other boundaries are the city of
Monticello and private property.
During the AEC era, the mill processed approximately one million tons of uranium
ore. Vanadium and uranium were the only substances extracted in the milling process.
Other constituents of the ore remained in the tailings and were not separated prior to dis-
posal. During the years of active mill operation, the mill tailings were normally moist, so
erosion was minimal. However, throughout the mill's operating period, area residents
used these tailings as fill material and as aggregate in mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy
(DOE) initiated the Surplus Facilities Management Program (SFMP) in 1978 to ensure
the safe caretaking and decommissioning of government facilities that had been retired
from service but still had radioactive contamination. In 1980 the mill site at Monticello
was accepted into the SFMP, and the Monticello Remedial Action Project (MRAP) was
established to restore the government-owned mill site to safe levels of radioactivity, to
dispose of or contain the tailings in an environmentally safe manner, and to perform re-
medial actions on off-site (vicinity) properties that had been contaminated by radioactive
material resulting from mill operations. The Monticello mill site and the tailings remain in
the custody of the DOE Grand Junction, Colorado, Projects Office. In 1983 remedial ac-
tions for vicinity properties were separated from MRAP with establishment of the Monti-
cello Vicinity Properties (MVP) Project (U.S. DOE 1990b).
The verification of remedial action was performed by members of the Environmental
Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory
under DOE contract DE-AC05-96OR22464 with Lockheed Martin Energy Research Corp.
2
During 1995, RUST Geotech Inc. (Geotech), the remedial action contractor (RAC)
designated by DOE, performed remedial action on the vicinity property that is the subject
of this report, a private residence located at 533 Circle Drive, Monticello, Utah. The re-
medial action plan required excavation of all exterior contamination, backfilling with un-
contaminated material, and restoration to a condition comparable to that which existed
prior to remedial action (Geotech 1996). When the excavation stage was completed, the
property was resurveyed, including soil sampling, by Geotech and by an independent con-
tractor to verify the data supporting the adequacy of remedial action and to confirm the
site's compliance with DOE guidelines. The Environmental Technology Section (ETS) of
Oak Ridge National Laboratory (ORNL) has been designated the Independent Verification
Contractor for the 533 Circle Drive site. This report describes the methods and results of
the verification surveys.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available doc-
umentation adequately and accurately describes the post-remedial-action radiological
conditions of the entire property that is to be certified and (2) that the remedial action
reduced contamination to below applicable DOE guidelines (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1996) indi-
cates the property was remediated as evaluated by DOE on the basis of Environmental
Protection Agency standards (DOE 1990a) and that excess residual radioactive materials
were present. Thus, it was appropriate to designate this property for remedial action.
This property was assessed as part of Group 3, therefore, the quantity of material
assessed is not available. During the actual removal process, a total of 8 yd3 of contami-
nated earth and uranium mill tailings, 30 inches deep to 24 inches high, were removed
from a 23 m2 area.
A post-excavation survey was performed by Geotech prior to backfilling of the exca-
vated areas. This survey consisted of gamma scans with a scintillometer, ground-level and
basement scans of the building, a surface scan of the exterior, and soil sampling. Samples
representative of the bottom 15-cm (6-in.) soil layers of two excavated areas were collect-
ed and blended to form representative composite soil samples for each verification area.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation
levels have not been subtracted. Similarly, background concentrations have not been sub-
tracted from radionuclide concentrations in soil samples. Applicable DOE guidelines for
protection against radiation are given in Table 1.
GEOTECH SURVEY RESULTS
Gamma Measurements
Gamma exposure rate measurements taken by Geotech over the ground-level of the
residence ranged from 12 to 14 /zR/h. Exterior surface gamma measurements taken from
the excavated areas prior to backfilling ranged from 13 to 21 pR/h.
Soil Sample Analysis
Prior to backfilling, Geotech collected soil samples representative of the excavated
areas from the bottom 15-cm (6-in.) soil layers. These samples were blended to form a
composite soil sample representative of an average over the two exterior verification
areas. Geotech's analysis of these samples showed ^Ra concentrations of 3.4 and
5.7 pCi/g in the composite samples. ORNL ETS obtained one of these soil samples and
performed a confirmatory analysis, which showed a ^Ra concentration of 1.8 pCi/g.
These values are below the EPA standard value of 15 pCi/g for soil layers >15 cm below
the surface (Table 1). Gamma ranges and/or soil sample results demonstrate compliance
to the DOE Hot Spot Guideline for areas < 25 m2 (Table 1). Results of Geotech and
ORNL soil sample analyses are given in Table 2.
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were deter-
mined by the alpha-track method. To monitor radon levels, Geotech placed three Alpha-
track detectors on the ground floor of the residence located on this property for a period
of approximately three months (from July 25, 1995 to November 15, 1995). The IVC
was present during placement and retrieval of the detectors to verify the RDC measure-
ments. The average annual working level (WL) of radon progeny concentration, as deter-
mined by the Tech./Ops-Landauer Corporation, was 0.0019, which is well below the 0.03-
WL guideline given in Table 1. The procedures and methods used to obtain the annual
average WL are deemed adequate and the results accurate by the IVC.
4
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of ^Ra in soil
above background levels,
averaged over a 100-m2 area
5 pCi/g averaged over the
first 15 cm of soil below the
surface; 15 pCi/g when
averaged over 15-cm-thick
soil layers more than 15 cm
below the surface.
Radionuclide con-
centrations in soil for
Hot Spot areas
Exposure to 222Rn
progeny
Maximum permissible con-
centration of 226Ra in soil
above background level, for
areas less than 25m2.
Average annual radon
progeny concentration
(including background).
Ra226 concentration, in any
surface or subsurface area
less than 25 m2, is below the
guideline of (100/Af,
where A is the area of the
elevated region.
0.03 WL
(DOE 1990a)
5
Table 2. Results of ORNL and Geotech analyses of soil samples
from 533 Circle Drive, Monticello, Utah (MS00622-RS)
^Ra concentration (pCi/gl
ORNL Geotech
sample sample Depth
number number (cm) Confirmatory ORNL Geotech
Xla NCJ 0216 >15 1.8 3.4
X2d NCJ 022* >15 1.8 5.7
U2CC 2.9
V2H/ 27.1
* An X-type sample is a split of the sample taken by the remedial action contractor and
confirmatory analysis performed by ORNL.
6 Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated
areas were taken by RUST Geotech Inc., and these samples were blended to form
composite soil samples, which represent an average over verification areas.
c Composite samples collected by ORNL from approximately the same excavated
locations sampled by Geotech.
d Individual sample collected by ORNL from the area of highest gamma exposure rates
within the verification area.
6
ORNL SURVEY RESULTS
Gamma Measurements
Measurements taken by ORNL over the ground surface in the excavated areas prior
to backfilling ranged from 13 to 19 uR/h (Figure 1).
Soil Sample Analysis
ORNL sampled one of the excavated areas prior to backfilling (area V-2), collecting
aliquots representative of those areas from the bottom 15-cm (6-in.) soil layers. These
samples were blended to form a composite soil sample representative of an average over
the exterior verification area. ORNL's analysis of this composite sample showed a 226Ra
concentrations of 2.9 pCi/g. ORNL also collected an individual soil sample from the
location of the highest gamma exposure rate. Analysis of this sample showed a U6Ra.
concentration of 27 pCi/g. This sample is representative of a subsurface area approxi-
mately 1 m2. These values are below the DOE guideline value of 15 pCi/g for soil layers
>15 cm below the surface, and the hot-spot guideline value for a 1 m2 area (Table 1).
Results of ORNL sample analyses are given in Table 2.
CONCLUSION
The results of all Geotech and ORNL soil sample analyses show that radionuclide
concentrations are within applicable DOE guidelines. Based upon the results of the post-
remedial-action data, which are confirmed by the verification assessment data, these radio-
logical measurements fall below the limits prescribed by DOE guidelines. All deficiencies
noted in the initial review have been identified by the RAC and corrected in the revised
completion report as discussed in a meeting between Geotech and ORNL on June 18,
1996. It is concluded that the site successfully meets the DOE remedial action objectives.
3
uR/h V1
ttR/h V2
V2 TORY
AM E3 HO SE
CS W >
or a V1 RDC UJ
or
a
i
t
L._
GARAGE V2 168 FT VI I
\
\
\ -n
\ •
\
\
\
\
EXPLANATION
Concrete
Assessed
contamination
Assessed area
not found
Excavated
area
JRDO
"vT
Remaining
contamination
RDC
Measurement
Area identifier &
Composite sample
Individual sample
from V-area HOG
FEET
U SO 30
3 t
NETERS
MS00622
533 CIRCLE DRIVE
MONTICELLO, UTAH
Figure 1. Property Map
8
REFERENCES
Geotech 1996, Properly Completion Report for Monticello Vicinity Property Remedied
Action for DOE ID NO: MS00622-RS, Address: 533 Circle Drive, Monticello, Utah
84535, Geotech, Grand Junction, Colorado, March, 1996.
ORNL, 1993. Environmental Technology Section Procedures Manual. ORNL 6645/R2
Oak Ridge National Laboratory, Grand Junction, Colorado.
U.S. DOE 1990a. Verification and Certification Protocolfor the Office of
Environmental Restoration, Formerly Utilized Sites Remedial Action Programs and
Decontamination and Decommissioning Program, Revision 3, November 1990. U.S.
Department of Energy, Washington, D.C.
U.S. DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision
and Record of Decision Summary. U.S. Department of Energy, Grand Junction Projects
Office, Grand Junction, Colorado.
DOE ID No.: MS-00726-VL
Property Address: Parcel No. A33230250606, North Main Street
Vicinity Property Certification Summary and Recommendation
Summary Evaluation
Certification Criteria MACTEC-ERS
U.S. Department
of Energy (DOE)
Ra-226 is < 5 pCi/g above background
in top 15-cm-thick layer of soil
averaged over 100 m2
In situ [X] Lab [ ]
Ra-226 is < 15 pCi/g above
background in any 15-cm-thick layer of
soil more than 15 cm below the
surface averaged over 100 m2.
In situ [ ]Lab[X]
Interior gamma is < 20 uR/h above
background in any occupied or
habitable structure.
The radon decay-product
concentration in any occupied or
habitable structure is < 0.02 WL or, at
most, 0.03 WL.
Supplemental standards were applied
in accordance with EPA standard
40 CFR 192.21.
Hot spot criteria met as outlined by
DOE guidelines for FUSRAP (Rev.2,
March 1987)
Yes No Not Taken Yes No Not Taken
[X]a [ ]
[X] [ ]
[ ] [ ]
[ ] [ ]
[ ] [X]
[X] [ ]
[ ]
[ ]
[X]b
[X]b
[ ]
[ ]
[ ]
iA [ ]
[ ] [ ]
[ ] [ ]
[ ] [A
[X] [ ]
[ ]
[ ]
[ 1
[ ]
aThe excavations were backfilled with materials that were measured at the source indicating that the Ra-226
concentrations are in the range of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
bVacant lot.
•Illlllll llllllllll
SFCERTIFED SFMS-00726
1 of 2
DOE ID No.: MS-00726-VL
MACTEC-ERS Recommendation
On the basis of the Property Completion Report evaluation, this property is recommended for
[X] Certification by DOE.
[ ] Certification by DOE with the concurrence of the U.S. Nuclear Regulatory Commission
because supplemental standards were applied according to 40 CFR 192.21.
Manager, Monticello Programs
MACTEC-ERS
DOE Evaluation
On the basis of the Property Completion Report recommendation, this property
|>] Should be certified by DOE.
[ ] Should be certified by DOE with the concurrence of the U.S. Nuclear Regulatory
Commission because supplemental standards were applied according to 40 CFR 192.21.
Date
U.S. Department of Energy
Work performed under DOE Contract No. DE-AC13-96GJ87335, Task Order No. 96-05.02.14
2 Of 2
Monticello Vicinity Properties Project
Property Completion Report
for
Monticello
Vicinity Property Remedial Action
for
DOE ID No.: MS-00726-VL
Address: Parcel No. A33230250606, North Main Street
Monticello, Utah 84535
December 1996
Prepared for
U.S. Department of Energy
Albuquerque Operations Office
Grand Junction Office
Prepared by
MACTEC-Environmental Restoration Services, LLC (MACTEC-ERS)*
Grand Junction, Colorado
/! / /
Michael C. Butherus
Manager, Monticello Programs
Work performed under DOE Contract No. DE-AC 13-96GJ87335
Task Order No. 96-05.02.14
*MACTEC-ERS has been granted authorization to conduct remedial action by the U.S. Department of Energy.
Remedial action was done in accordance with the U.S. Environmental Protection Agency "Standards for Cleanup of
Land and Buildings Contaminated with Residual Radioactive Materials from Inactive Uranium Processing Sites,"
40 CFR 192, Subpart B; and "Implementation," in 40 CFR 192, Subpart C, and the U.S. Department of Energy
Formerly Utilized Sites Remedial Action Program hot spot criteria.
DOE ID No.: MS-00726-VL
Contents
Page
1.0 Summary 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Remedial Action Summary 2
2.0 Operations Summary 3
2.1 Remedial Action Plan 3
2.2 Assessed and Remediated Contamination 3
3.0 Verification Summary 4
3.1 Radiological Survey Data 4
3.1.1 Preremedial Action Survey 4
3.1.2 Postexcavation Survey 4
3.2 Recommendation for Certification 5
Table
Table 1. Certification Data Summary 5
Appendix
Appendix A. Radiological Conditions A-1
DOE'Graiid Junction Office MVP Property Completion Report
December 1996 Page ii
DOE ID No.: MS-00726-VL
1.0 Summary
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce the potential hazard
to the public due to long-term exposure to low-level radioactivity associated with the offsite mill
tailings derived from the former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States Government through its agent,
the Defense Plant Corporation, to provide additional sources of vanadium needed during World
War II. Various government agencies operated the mill until 1947. The AEC obtained the mill in
1948 and operated it through 1959 under cost-type contracts to process both uranium and
vanadium ore. Mill operations were terminated on January 1, 1960.
The mill processed approximately one million tons of ore during the AEC operations. Throughout
the operating period, mill tailings from the Monticello millsite were removed from the site and
used for construction-related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for Remedial Actions at Inactive
Uranium Processing Sites" (40 CFR Part 192) for all cleanup activities under the MVP Project.
These standards were prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and open lands. Cleanup
activities also were conducted to meet the hot spot criteria established by radiological protection
guidelines in the DOE Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management Progr am Sites
(Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot spot criteria and
determined to contain mill tailings (radioactive material) exceeding EPA standards and/or DOE
hot spot criteria. The Remedial Action Contractor* was notified of the inclusion of this property
into the MVP Project and was authorized by DOE to conduct remedial action as required to bring
the property into conformance with EPA standards and DOE hot spot criteria.
The Remedial Action Contractor, MACTEC-ERS, was awarded the U.S. Department of Energy Grand Junction
Office (DOE-GJO) Technical Assistance and Remediation contract and commenced work on September 5, 1996. The
MACTEC-ERS team consists of International Technology Corporation, Science Application International Corporation,
Roy F. Weston, Inc., and Rust Federal Services, Inc. Rust Geotech was the DOE-GJO contractor from October 1,
1986, through September 4, 1996, and implemented some ofthe tasks discussed in this report
DOE/Grand Junction Office
December 1996
MVP Property Completion Report
Page 1
DOE ID No.: MS-00726-VL
1.3 Remedial Action Summary
DOE D3 No.:
Legal Description:
Property Address:
Property Owner:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological and Engineering Assessment (REA):
Construction Subcontractor:
Preconstruction Conference Record:
Notice of Final Completion Inspection:
Volume of Material Removed in Cubic Yards (yd3):
Area Cleaned Up in Square Meters (m2):
Property Completion Report Submitted:
MS-00726-VL
Beginning 1,130 feet south and
644 feet east of the N4 corner of
Section 25, T33S, R23E, Salt Lake
Base Meridian; north 90 feet, east
163 feet, south 90 feet, west 163 feet
to the beginning, City of Monticello,
County of San Juan, State of Utah
Parcel.No. A33230250606,
North Main Street
Monticello, Utah 84535

Vacant Lot (VL)
Oak Ridge National Laboratory
Grand Junction Office
August 30, 1991
MACTEC-ERS
June 23, 1994
Diamond Back Services, Inc.
July 18, 1995
August 14, 1995
Exterior: 18
Interior: 0
50
December 1996
DOK/Grand Junction Office
December 1996
MVP Property Completion Report
Page 2
DOE ID No.: MS-00726-VL
2.0 Operations Summary
2.1 Remedial Action Plan
The remedial action plan specified removal of radioactive material. Once excavation was
completed, the affected areas were resurveyed for possible remaining radioactive material and,
upon attaining satisfactory results, were backfilled with uncontaminated material. The property
was restored to a physical condition comparable to that which existed before remedial action
activities.
2.2 Assessed and Remediated Contamination
The radiological assessment identified contamination, ranging from 6 to 12 inches (in.) deep,
within the property boundary. The quantity of contamination for this property was not specified
because it was assessed as part of Group 17. The remedial action process included removal of
approximately 18 yd3 of residual radioactive material, ranging from 6 to 24 in. deep. The areas
of assessed and excavated contamination are shown on Figure A-1.
IX)n/Grand Junction Office
December 1996
MVP Property Completion Report
Page 3
DOE ID No.: MS-00726-VL
3.0 Verification Summary
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Preremedial Action Survey
The Remedial Action Contractor conducted a radiological survey during July 1992, as described
in the final REA. Figure A-1 shows the extent of assessed contamination and identifies the areas
recommended for remedial action.
3.1.2 Postexcavation Survey
A scintillometer was used to perform a surface gamma scan after the removal of radioactive
material and before backfilling. Following the gamma scan, soil samples representative ofthe
6-in.-thick soil layer at the bottom ofthe excavation were collected. These samples, representing
the verification area, were analyzed for radium-226. The results of the gamma scans and soil
sample analyses are presented in Table A-1.
DOE/Grand Junction Office
December 1996
MVP Properly Completion Report
Page 4
DOE ID No.: MS-00726-VL
3.2 Recommendation for Certification
Radioactive materials have been removed from this property to the extent required by EPA
standards (40 CFR 192, Subparts B and C) and DOE hot spot criteria, as indicated in the
Certification Data Summary (Table 1). Therefore, the property located at Parcel
No. A33230250606, North Main Street, in Monticello, Utah, is recommended for certification as
required by DOE guidelines.
Table 1. Certification Data Summary
Applicability Standard Survey Results
Radium-226
Concentration in
Surface Soil
Radium-226
Concentration in
Subsurface Soil
Exposure Rate
Land
Shall not exceed 5 pCi/g above
background3 in the 15-cm-thick
surface layer, averaged over
100 m2.
Shall not exceed 15 pCi/g
above background3 in any
15-cm-thick soil layer more than
15 cm below the surface,
averaged over 100 m2.
Habitable Structures
< 5 pCi/g above background on the
basis of gamma exposure rates that do
not exceed 30 percent above normal
background.b
Soil sample result was 2.4 pCi/g.b
Shall not exceed 20 pR/h above
background.
Not applicable: vacant lot.
Radon Decay- Annual average shall not Not applicable: vacant lot.
Product exceed 0.02 WL, to the extent
Concentration practicable, and shall in no
case exceed 0.03 WL.
Key: cm = centimeters; mJ = square meters; pCi/g = picocuries per gram; uR/h = microroentgens per hour;
WL = working level
aThe background radium-226 concentration for Monticello Vicinity Properties is approximately 2 0 pCi/g.
'The hot spot criteria were met based on gamma scans and/or soil sample results.
DOFI/Grand Junction Oflice
December 19%
MVP Property Completion Report
Page 5
DOE ID No.: MS-00726-VL
Appendix A
Radiological Conditions
Table A-1. Postexcavation Survey Results
Figure A-1. Radiological As-Built
DOE ID No.: MS-00726-VL
Table A-1. Postexcavation Survey Results
Gamma Radium-226
Verification Exposure Rate Soil Sample Measurement Concentration!
Area" Range (pR/h) Ticket No. Method pCi/g)
V-1 16-23 NAR 131 OCS 2.4
Key: OCS = opposed crystal system; pCi/g = picocuries per gram; uR/h = microroentgens per hour;
V = verification area
aSee Figure A-1 for location of verification area.
DOE/Grand Junction Office
December 1996
MVP Property Completion Report
Page A 2
10
30
12 14 16
i—r
18 20 22 24 26 28 30 32 34 36 38 40
30
28
26
24
22
20
18
16
1 4
12-15 V-1
12-15
24
18
ATA
V-1
12-15 12-15
9 7
O
NORTH
©
<D
r77.-77l
Lv.vj
12-15
12
V-10
UJ
UJ
ct.
I— to
<
2
or
O
— 28
26
- 24
22
LEGEND
ALL DEPTHS/HEIGHTS IN INCHES
ALL EXPOSURE RATES IN /zR/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION AREA IDENTIFIER
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
20
18
1 6
1 4
1 2
Y
SCALE IN FEET
20 10 0 20
10
M:\FAS\033\0003\RM00726V 12/02/96 1:57pm M50312
—— X
I I I I I I
40
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT, UTILITY LOCATION PLAT, OR OTHER IMPROVEMENT SURVEY
PLAT AND IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE. BUILDING, OR OTHER FUTURE IMPROVEMENT LINES.
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION OFFICE. COLORADO
KMfl I4CA!MN
PARCEL A33230250606
NORTH MAIN STREET
MONTICELLO, UTAH
Iti Ktx
COMPLETION REPORTS
BATT
MONTICELLO VICINITY PROPERTIES
FIGURE A-1
RADIOLOGICAL AS-BUILT
PROJECT NO. MS-00726-VL
FAS-033-0003-RM00726V 1 1
1 2
10
10 1 2 1 4 1 6 18 20 22 24 26 28 30 32 34 36 38 40
OAK RIDGE NATIONAL LABORATORY PHONE: [phone]
FAX: [phone] MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
FOR THE U.S. DEPARTMENT OF ENERGY
2597 BV. Road
GRAND JUNCTION, COLORADO 81503
APR 16 mi
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by the U.S.
Department of Energy for Residual Radioactive Material at Formerly Utilized Sites Remedial Action
Program (FUSRAP) and Remote Surplus Facilities Management Program Sites (SFMP) [Revision
2, March 1987]. This evaluation is based on an independent verification review of the Remedial
Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment ofthe 226Ra
concentration in the soil and outdoor gamma exposure rates at this property.
This property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
Location Number:
Location Address:
MS00726-VL
Parcel No. A33230250606. North Main Street
Monticello. Utah 84535
Property Owner:
Owner Address:

Attachments
LIFE SCIENCES DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
PARCEL NO. A33230250606, NORTH MAIN STREET
MONTICELLO, UTAH (MS00726-VL)
M. K. Jensen
April 1997
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81503
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 3
REFERENCES 6
in
LIST OF TABLES
1. Applicable guidelines for protection against radiation 4
2. Results of ORNL analysis of the RAC soil samples from Parcel No. A33230250606,
North Main Street, Monticello, Utah (MS00726-VL) 5
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site Decommissioning
Projects, U.S. Department of Energy. The author wishes to acknowledge A. D. Laase and S. M.
Smith for technical reviews.
vii
ABSTRACT
In 1980, the site of a vanadium and uranium mill at Monticello, Utah, was accepted into the
U.S. Department of Energy (DOE) Surplus Facilities Management Program, with the objectives of
restoring the government-owned mill site to safe levels of radioactivity, disposing of or containing
the tailings in an environmentally safe manner, and performing remedial actions on off-site (vicinity)
properties that had been contaminated by radioactive material resulting from mill operations. During
1995, the Remedial Action Contractor (RAC) designated by DOE, performed remedial action on the
vicinity property at Parcel No. A33230250606, North Main Street, Monticello, Utah. The
Environmental Technology Section (ETS) of Oak Ridge National Laboratory was assigned the
responsibility of verifying the data supporting the adequacy of remedial action and confirming the
site's compliance with DOE guidelines. The ETS found that the site successfully meets the DOE
remedial action objectives. Procedures used by the ETS are described in the Environmental
Technology Section Procedures Manual (ORNL 1993).
ix
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT PARCEL NO. A33230250606, NORTH MAIN STREET
MONTICELLO, UTAH (MS00726-VL)*
INTRODUCTION
The rnill at Monticello, Utah, was built in 1942 by the United States (U.S.) government through
the Defense Plant Corporation to provide vanadium during World War U. Various government
agencies operated the mill until 1947. In 1948, the Atomic Energy Commission (AEC) obtained the
mill and operated it under contract through 1959 to provide both uranium and vanadium. Mill
operations were terminated on January 1, 1960. In 1961, the mill tailings piles were leveled and
graded, covered with rock and soil, and seeded with native grasses. During 1974 and 1975, the ore
stockpiles were removed from the site and the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city of
Monticello, in San Juan County, Utah. The site is bordered on the south and southeast by land held
by the U.S. Bureau of Land Management. Other boundaries are the city of Monticello and private
property.
During the AEC era, the mill processed approximately one million tons of uranium ore. Vana-
dium and uranium were the only substances extracted in the milling process. Other constituents of
the ore remained in the tailings and were not separated prior to disposal. During the years of active
mill operation, the mill tailings were normally moist, so erosion was minimal. However, throughout
the mill's operating period, area residents used these tailings as fill material and as aggregate in
mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy (DOE) initiated
the Surplus Facilities Management Program (SFMP) in 1978 to ensure the safe caretaking and de-
commissioning of government facilities that had been retired from service but still had radioactive
contamination. In 1980, the mill site at Monticello was accepted into the SFMP, and the Monticello
Remedial Action Project (MRAP) was established to restore the government-owned mill site to safe
levels of radioactivity, to dispose of or contain the tailings in an environmentally safe manner, and
to perform remedial actions on off-site (vicinity) properties that had been contaminated by radio-
active material resulting from mill operations. The Monticello mill site and the tailings remain in
the custody of the DOE Grand Junction, Colorado, Projects Office. In 1983, remedial actions for
vicinity properties were separated from MRAP with establishment of the Monticello Vicinity Proper-
ties (MVP) Project (US DOE 1990b).
*The verification of remedial action was performed by members of the Environmental Assessment Group in the Environmental
Technology Section ofthe Life Sciences Division at Oak Ridge National Laboratory under DOE contract DE-AC05-96OR22464
with Lockheed Martin Energy Research Corporation.
2
During 1995, the Remedial Action Contractor (RAC) designated by DOE, performed remedial
action on the vicinity property that is the subject of this report, a vacant lot located at Parcel No.
A33230250606, North Main Street, Monticello, Utah. The remedial action plan required excavation
of all exterior contamination. When the excavation was completed, the property was resurveyed,
including soil sampling, to ensure the removal of all contamination, backfilled with uncontaminated
material, and restored to a condition comparable to that which existed prior to remedial action
(MACTEC-ERS 1996).
DOE adopted a policy to assign an independent contractor to verify the data supporting the
adequacy of remedial action and to confirm the site's compliance with DOE guidelines. The Environ-
mental Technology Section (ETS) of Oak Ridge National Laboratory (ORNL) has been assigned the
responsibility of this task at Parcel No. A33230250606, North Main Street site. This report describes
the methods and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available documentation
adequately and accurately describes the post-remedial-action radiological conditions of the entire
property that is to be certified and (2) that the remedial action reduced contamination to below
applicable DOE guidelines (US DOE 1990a).
Document Reviews
Review of the RAC property completion report (MACTEC-ERS 1996) indicates the property
was remediated as evaluated by DOE on the basis of U.S. Environmental Protection Agency
standards and the DOE guidelines (US DOE 1990a). Excess residual radioactive materials were
present, thus it was appropriate to designate this property for remedial action.
This property was assessed as part of Group 17, therefore, the quantity of material assessed is
not available. During the actual removal process, a total of 18 yd3 of contaminated earth and uranium
mill tailings, 6 to 24 inches deep, were removed from a 50 m2 area.
The RAC performed a post-excavation survey prior to backfilling the excavated areas. This
survey consisted of gamma scans with a scintillometer of the exterior, and soil sampling. Samples
representative ofthe bottom 15-cm (6-in.) soil layers of the excavated verification area were collected
and blended to form a representative composite soil sample.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation levels have
not been subtracted. Similarly, background concentrations have not been subtracted from radionu-
clide concentrations in soil samples. Applicable DOE guidelines for protection against radiation are
given in Table 1.
Gamma Measurements
Exterior surface gamma exposure rate measurements taken from the excavated areas prior to
backfilling ranged from 16 to 23 uR/h.
Soil Sample Analysis
Prior to backfilling, the RAC collected soil samples representative of the excavated areas from
the bottom 15-cm (6-in.) soil layers. These samples were blended to form a composite soil sample
representative of an average over the exterior verification area. The RAC's analysis of this sample
showed a 226Ra concentration of 2.4 pCi/g. ORNL ETS obtained this sample and performed a
confirmatory analysis which showed a 226Ra concentration of 1.7 pCi/g. These values are below the
DOE guideline value of 15 pCi/g for soil layers > 15 cm below the surface. Additionally, a soil
sample was taken at the highest gamma reading in the excavation to show compliance to the DOE
Hot Spot Guideline. The RAC's analysis of this sample showed a 226Ra concentration of 2.7 pCi/g.
Gamma ranges and/or soil sample results demonstrate compliance to the DOE Hot Spot Guidelines
for areas <25 m2 (Table 1). Results of the RAC and ORNL soil sample analyses are given in Table
2.
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were not determined as
this property is a vacant lot.
CONCLUSION
Results of RAC soil sample analysis and confirmatory split soil sample analysis by ORNL, show
that radionuclide concentrations are within applicable DOE guidelines. Based on the results of the
post-remedial-action data, which are confirmed by the verification assessment data, these radiological
measurements fall below the limits prescribed by DOE guidelines. It is concluded that the site
successfully meets the DOE remedial action objectives.
4
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of 226Ra in soil
above background levels,
averaged over a 100-m2
area
5 pCi/g averaged over the first 15 cm
of soil below the surface; 15 pCi/g
when averaged over 15-cm-thick soil
layers more than 15 cm below the
surface
Radionuclide con-
centrations in soil
for Hot Spot areas
Exposure to 222Rn
progeny
Maximum Permissible con-
centration of Ra226 in soil
above background level,
for areas less than 25 m2
Average annual radon
progeny concentration
(including background)
Ra226 concentrations, in any surface
or subsurface area less than 25 m2,
is below the guideline by a factor of
(100/A)'/2, where A is the area of the
elevated region
0.03 WL
(US DOE 1990a)
5
Table 2. Results of ORNL analysis of the RAC soil samples from
Parcel No. A33230250606, North Main Street, Monticello, Utah (MS00726-VL)
226Ra concentration (pCi/g)
ORNL RAC
sample sample Depth ORNL RAC
No." No^ (cm)
XI NAR 131 >15 1.7 2.4
" An X-type sample is a split of the sample taken by the remedial action contractor.
* Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated areas were
taken by the RAC, and these samples were blended to form a composite soil sample, which
represents an average over one of the verification areas.
6
REFERENCES
MACTEC-ERS 1996. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00726-VL, Address: Parcel No. A33230250606, North Main Street,
Monticello, Utah 84535, MACTEC-ERS, Grand Junction, Colorado, December 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment Group)
Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National Laboratory, Grand
Junction, Colorado.
US DOE 1990a. Verification and Certification Protocol for the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination and
Decommissioning Program. Revision 3, November 1990. U.S. Department of Energy, Washington,
D.C.
US DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision and Record
of Decision Summary. U.S. Department of Energy, Grand Junction Projects Office, Grand Junction,
Colorado.
DOE ID No.: MS-00748-CS
Property Address: Parcel No. A33230254803, North Main Street
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Gfintenh of Energy (DOE)
YES NO NOT TAKEN YES NO NOT TAKEN
Ra-226 is <; 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [ ]
[X]* [ ] [ 1 [ 1
Ra-226 is ^ 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2. [X] [ ] [ ] [/*][] [ ]
In-situ [ ] Lab [X]
Interior gamma is £ 20 //R/h
above background in any
occupied or habitable
structure. [X] [ ] [ ] [>] [ ] [ ]
The radon decay-product
concentration in any
occupied or habitable
structure is <. 0.02
working level or, at
most, 0.03 working level. [X] [ ] [ ] [)4 [ ] [ ]
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21. [ ] [X] [ ] [ ] [XI [ ]
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987). [X] [ ] [ ] MM [ ]
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
Ililllllllll llllllllll
SFCERTIFED SFMS-00748
DOE ID No.: MS-00748-CS
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with the concurrence of
the U.S. Nuclear Regulatory Commission because supplemental
standards were applied per 40 CFR 192.21.
[fl Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with the
concurrence of the U.S. Nuclear Regulatory Commission because
supplemental standards were applied per 40 CFR 192.21.
Manager, Monticello Programs
Rust Geotech
Date
DOE EVALUATION
U.S. Department of Energy
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00748-CS
ADDRESS: PARCEL NO. A33230254803
NORTH MAIN STREET
MONTICELLO, UTAH 84535
AUGUST 1996
Prepared for
U.S. Department of Energy
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
by
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
' Wander S. Busby
Manager, Monticello Programs
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.1.3 Radon Decay-Product Concentration (RDC) Measurement .... 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
DOE ID No.: MS-00748-CS
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Inclusion Survey Contractor. DOE reviewed
these evaluation results and determined that the property contained mill
tailings (residual radioactive material) exceeding EPA standards and DOE
hot spot criteria. The Remedial Action Contractor was notified of the
inclusion of this property into the MVP Project and was authorized by DOE
to conduct remedial action as required to bring the property into
conformance with EPA standards and DOE hot spot criteria.
1
DOE ID No.: MS-00748-CS
.3 Summary of Remedial Action
DOE ID No.: MS-00748-CS
Legal Description:
Beginning 2,290 feet south and 858 feet east of the N4 corner of Section 25,
T33S., R23E., Salt Lake Base Meridian; southerly along the west boundary of
Highway 191 610.6 feet, more or less, south 89 degrees 40 minutes
12 seconds west 215.451 feet, north 00 degrees 34 minutes 56 seconds west
607.53 feet, north 88 degrees 50 minutes 57 seconds east 213.21 feet to the
beginning, City of Monticello, County of San Juan, State of Utah.
Property Address: Parcel No. A33230254803
North Main Street
Monticello, Utah 84535
Property Owner:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Completion of Remediation:
Volume of Material Removed:
Area Cleaned Up:

Commercial Structure (CS)
Oak Ridge National Laboratory
February 21, 1991
Rust Geotech
February 3, 1994
Bayless and Bayless, Inc.
435 East First
Pueblo, Colorado
July 29, 1992
Interior: 0 cubic yards
Exterior: 50 cubic yards
103 square meters (m2)
Property Completion Report
Submitted: August 1996
DOE ID No.: MS-00748-CS
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action involved removal of exterior residual radioactive
material (Appendix Figure 2.1). Once excavation was complete, the
affected areas were resurveyed for possible remaining residual radioactive
material and, upon attaining satisfactory results, were backfilled with
uncontaminated material. The property was restored to a physical
condition comparable to that which existed prior to remedial action
activities.
2.2 Previously Unidentified Contamination
Assessed contamination on the property was remediated before the REA
was released (see Section 2.3). The remedial action process included the
removal of approximately 50 cubic yards of residual radioactive material,
ranging from 7 to 16 inches deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
Contamination detected during the inclusion survey was remediated in
July 1992 in conjunction with the assessment survey to facilitate the
property owner's construction schedule.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID No.: MS-00748-CS
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by the Remedial Action
Contractor during July 1992, as described in the final REA dated
February 1994. Appendix Figure 2.1 shows the extent of
assessed contamination and identifies the areas recommended to
undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the excavation were
collected. These samples were blended to form a composite
sample representing the verification area (Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 13 to 18 microroentgens per
hour (//R/h), as indicated on Appendix Figure 2.1. The result of
analysis for radium-226 in one composite soil sample was
1.5 picocuries per gram (pCi/g), as indicated in Appendix
Table 3.1. The composite sample included soil samples collected
from MS-01064-CS (Area V-8).
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on the DOE-approved abbreviated-measurement method,
the RDC was 0.0017 working level (WL), as indicated in
Appendix Table 3.2. Appendix Figure 2.1 shows the measurement
location on the ground floor (the lowest habitable level of the
structure).
4
DOE ID No.: MS-00748-CS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at Parcel No. A33230254803,
North Main Street, in Monticello, Utah, is recommended for certification
as required by DOE guidelines, and the appropriate records should be
documented.
Certification Data Summary
Applicability
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Standards
Shall not exceed 20 jjR/h
above background.*
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Survey Results
Exposure rate for the
ground floor was 12 to
15 jt/R/h.
Average was 0.0017 WL,
based on the DOE-
approved abbreviated-
measurement method.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
< 5 pCi/g above
background.**
Soil sample result was
1.5 pCi/g.**
*The background exposure rate is approximately 14 jjR/h.
The background radium-226 concentration is approximately 2.0 pCi/g.
**The hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-00748-CS
4.0 APPENDIX
Appendix Tables:
Table 3.1 Post-Excavation Sample/Measurement Results
Table 3.2 Radon Decay-Product Concentration Measurement
Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
MRW:07-31-96
MS-00748 WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00748-CS
Address: Parcel No. A33230254803, North Main Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range OuR/h) Ticket No. Method" (pCi/g)
V-1 13-18 NAT 337 OCS 1.5
See Appendix Figure 2.1 for the verification area.
"OCS = Opposed Crystal System
7
.3*
Table 3.2
Radon Decay-Product Concentration Measurement Results
DOE ID No.: MS-00748-CS
Address: Parcel No. A33230254803, North Main Street, Monticello, Utah
Instrument Type: Landauer Radtrak Detector
Detector
Number Start Date End Date
Radon
Concentration
(pCi/L)
Working
Level
4147089
4147180
4147255
02-27-96
02-27-96
02-27-96
05-28-96
05-28-96
05-28-96
0.33 0.0017
0.33 0.0017
0.33 0.0017
Average: 0.0017
See Appendix Figure 2.1 for the measurement location.
8
so
48
46
44
42
40
38
36
34
32
30
28
26
24
22
20
18
16
14
12
10
,2 14 16 18 20 22 24 26 28 30 32 34 | 36 38 40 42 44 46 48 50 52 54 56 58 60 62 64 66 68 70 72 74
1—r—i—i—i—i—i—i—i—i—i—i—i—i—i—i—i—i—1—i—i—>—i—i—i—1—1—1—1—i—~i—i—i—i—i—i—i—i—1—i—i—i—i—i—1—i—i—1—1—i—i—i—i—i—i—i—1—i—i—i—i—i—r~
NORTH MAIN STREET AKA HIGHWAY 191
LU. HI
XX 13-14*-
v-1
13-IB
13-14*
(ROJ)
TWO STORY HOTEL
12-15
13-14*
•L
SCALE IN FEET
20 10 0 20 40
W:\ril\U3\000J\IIUMmv 01/lt/ft M'4lam 190710
J I I I I I L_ J L J I
V-l
18-17
.LEGEND.
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN >*R/h
POST-REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE—RATE RANGE
RADON DECAY-PRODUCT CONCENTRATION
MEASUREMENT LOCATION
OAK RIDGE NATIONAL LABORATORY DATA
POINT SOURCES (URANIUM ORE)
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
THIS DRAWING 15 FOR THE SOLE USE OF THE U.S. DEPART!!!NT
OF ENERGY AND ITS CONTRACTORS, IT IS NOT A LAND SURVEY PLAT. UTILITY LOCATION PLAT. OA OTHER IMPROVEMENT SURVEY PLAT AND TJ NOT TO BE RELIED UPON FOR THE ESTABLISHMENT OF FENCE. BUILDING. OR OTHER FUTURE IMPROVEMENT LINES.
KtllMKC-M Ot KCUPMTt
MSTItUMHT *Q.
SUffW 0*11
CK. A.E APP. NO. OATE BY CK. A.E. APP.
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PR0jecT5 OFflCE. COLORADO
PARCEL NO. A33230254803
NORTH MAIN STREET
MONTICELLO, UTAH
MKT Rust OWotech 001 JO NO MS-00748-CS
3-D0074«-vl wr ' OF '
12 14 16 18 26 28 34
OAK RIDGE NATIONAL LABORATORY
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
FOR THE U.S. DEPARTMENT OF ENERGY
PHONE: [phone]
FAX: [phone]
2597 Road
GRAND JUNCTION, COLORADO 81503
2 5 Ml
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by the U.S.
Department of Energy for Residual Radioactive Material at Formerly Utilized Sites Remedial
Action Program (FUSRAP) and Remote Surplus Facilities Management Program Sites (SFMP)
[Revision 2, March 1987]. This evaluation is based on an independent verification review of the
Remedial Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment of the
^Ra concentration in the soil, indoor radon daughter concentration, and indoor gamma exposure
rates at this property.
This property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/TVC Project Manager
Environmental Assessment Group
Location Number: MS00748
Location Address: Parcel No. A33230254803
North Main Street
Monticello. Utah 84535
Property Owner:

Tenant Name: Days Inn
Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
PARCEL NO. A33230254803, NORTH MAIN STREET
MONTICELLO, UTAH (MS00748)
A. R. Jones
March 1997
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81503
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 3
REFERENCES 5
iii
LIST OF TABLES
Applicable guidelines for protection against radiation
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site Decommissioning
Projects, U.S. Department of Energy. The author wishes to acknowledge M. K. Jensen and S. M.
Smith for technical reviews.
vii
ABSTRACT
In 1980, the site of a vanadium and uranium mill at Monticello, Utah, was accepted into the
U.S. Department of Energy (DOE) Surplus Facilities Management Program, with the objectives of
restoring the government-owned mill site to safe levels of radioactivity, disposing of or containing
the tailings in an environmentally safe manner, and performing remedial actions on off-site (vicinity)
properties that had been contaminated by radioactive material resulting from mill operations. During
1992, the Remedial Action Contractor (RAC) designated by DOE, performed remedial action on the
vicinity property at Parcel No. A33230254803, North Main Street, Monticello, Utah. The
Environmental Technology Section (ETS) of Oak Ridge National Laboratory was assigned the
responsibility of verifying the data supporting the adequacy of remedial action and confirming the
site's compliance with DOE guidelines. The ETS found that the site successfully meets the DOE
remedial action objectives. All deficiencies noted in the initial review have been resolved with
additional documentation to the property folio. Procedures used by the ETS are described in the
Environmental Technology Section Procedures Manual (ORNL 1993).
ix
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT PARCEL NO. A33230254803, NORTH MAIN STREET
MONTICELLO, UTAH (MS00748)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the United States (U.S.) government through
the Defense Plant Corporation to provide vanadium during World War II. Various government
agencies operated the mill until 1947. In 1948, the Atomic Energy Commission (AEC) obtained the
mill and operated it under contract through 1959 to provide both uranium and vanadium. Mill
operations were terminated on January 1, 1960. In 1961, the mill tailings piles were leveled and
graded, covered with rock and soil, and seeded with native grasses. During 1974 and 1975, the ore
stockpiles were removed from the site and the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city of
Monticello, in San Juan County, Utah. The site is bordered on the south and southeast by land held
by the U.S. Bureau of Land Management. Other boundaries are the city of Monticello and private
property.
During the AEC era, the mill processed approximately one million tons of uranium ore. Vana-
dium and uranium were the only substances extracted in the milling process. Other constituents of
the ore remained in the tailings and were not separated prior to disposal. During the years of active
mill operation, the mill tailings were normally moist, so erosion was minimal. However, throughout
the mill's operating period, area residents used these tailings as fill material and as aggregate in
mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy (DOE) initiated
the Surplus Facilities Management Program (SFMP) in 1978 to ensure the safe caretaking and de-
commissioning of government facilities that had been retired from service but still had radioactive
contamination. In 1980, the mill site at Monticello was accepted into the SFMP, and the Monticello
Remedial Action Project (MRAP) was established to restore the government-owned mill site to safe
levels of radioactivity, to dispose of or contain the tailings in an environmentally safe manner, and
to perform remedial actions on off-site (vicinity) properties that had been contaminated by radio-
active material resulting from mill operations. The Monticello mill site and the tailings remain in
the custody of the DOE Grand Junction, Colorado, Projects Office. In 1983, remedial actions for
vicinity properties were separated from MRAP with establishment of the Monticello Vicinity Proper-
ties (MVP) Project (US DOE 1990b).
*The verification of remedial action was performed by members of the Environmental Assessment Group in the Environmental
Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE contract DE-AC05-
960R22464 with Lockheed Martin Energy Research Corporation.
2
During 1992, the Remedial Action Contractor (RAC) designated by DOE, performed remedial
action on the vicinity property that is the subject of this report, vacant land and a motel located at
Parcel No. A33230254803, North Main Street, Monticello, Utah. The remedial action plan required
excavation of all exterior contamination. When the excavation was completed, the property was
resurveyed, including soil sampling, to ensure the removal of all contamination, backfilled with
uncontaminated material, and restored to a condition comparable to that which existed prior to
remedial action (Geotech 1996).
DOE adopted a policy to assign an independent contractor to verify the data supporting the
adequacy of remedial action and to confirm the site's compliance with DOE guidelines. The Environ-
mental Technology Section (ETS) of Oak Ridge National Laboratory (ORNL) has been assigned the
responsibility of this task at the Parcel No. A33230254803, North Main Street site. This report
describes the methods and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available documentation
adequately and accurately describes the post-remedial-action radiological conditions of the entire
property that is to be certified and (2) that the remedial action reduced contamination to below
applicable DOE guidelines (US DOE 1990a).
Document Reviews
Review ofthe RAC property completion report (Geotech 1996) indicates the property was reme-
diated as evaluated by DOE on the basis of U.S. Environmental Protection Agency standards and the
DOE guidelines (US DOE 1990a). Excess residual radioactive materials were present, thus it was
appropriate to designate this property for remedial action.
This property, MS00748, and the adjacent property, MS01064, overlay historical property
MS00136. The historical property was remediated in 1986 and certified by DOE in 1991. During
the assessments of MS00748 and MS01064, it was discovered that the area remediated under
MSOO 136 was recontaminated. The completion reports for MS00748 and MS01064 reflect the final
radiological status of these properties.
Removal on this property occurred during the remedial engineering assessment to accommodate
the property owner. Therefore, no assessed volume is available. During the actual removal process,
a total of 50 yd3 of contaminated earth and uranium mill tailings, 7 to 16 inches deep, were removed
from a 103 m2 area.
The RAC performed a post-excavation survey prior to backfilling the excavated areas. This
survey consisted of gamma scans with a scintillometer of the ground level of the structure, a surface
scan ofthe exterior, and soil sampling. Samples representative of the bottom 15-cm (6-in.) soil layers
ofthe excavated verification area were collected and blended to form a representative composite soil
sample. The RAC is unable to locate or inadvertently disposed of the samples requested for ORNL
confirmatory analysis.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation levels have
not been subtracted. Similarly, background concentrations have not been subtracted from radionu-
clide concentrations in soil samples. Applicable DOE guidelines for protection against radiation are
given in Table 1.
Gamma Measurements
Gamma exposure rate measurements taken by the RAC at the ground-level of the structure
ranged from 12 to 15 uR/h. Exterior surface gamma measurements taken from the excavated areas
prior to backfilling ranged from 13 to 18 uR/h.
Soil Sample Analysis
Prior to backfilling, the RAC collected soil samples representative of the excavated areas from
the bottom 15-cm (6-in.) soil layers. These samples were blended to form a composite soil sample
representative of an average over the exterior verification area. The RAC's analysis of this sample
showed a ^Ra concentration of 1.5 pCi/g. ORNL ETS was unable to obtain samples for confirma-
tory analysis. This value is below the DOE guideline value of 15 pCi/g for soil layers > 15 cm below
the surface. Gamma ranges and/or soil sample results demonstrate compliance to the DOE Hot Spot
Guidelines for areas <25 m2 (Table 1).
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were determined by the
Alpha-track method. To monitor radon levels, the RAC placed three alpha-track detectors on the
ground floor ofthe structure located on this property for a period of approximately three months
(from February 27, 1996 to May 28, 1996). The average annual working level (WL) of radon
progeny concentration, as determined by the Tech./Ops-Landauer Corporation, was 0.0017, which
is well below the 0.03-WL guideline given in Table 1.
CONCLUSION
Results of RAC soil sample analysis show that radionuclide concentrations are within applicable
DOE guidelines. Based on the results of the post-remedial-action data, which are confirmed by the
verification assessment data, these radiological measurements fall below the limits prescribed by DOE
guidelines. All deficiencies noted in the initial review have been identified by the RAC as discussed
in a meeting between Geotech and ORNL on January 15, 1997, and corrected with additional
documentation to the property folio. It is concluded that the site successfully meets the DOE
remedial action objectives.
4
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of 226Ra in soil
above background levels,
averaged over a 100-m2
area
5 pCi/g averaged over the first 15 cm
of soil below the surface; 15 pCi/g
when averaged over 15-cm-thick soil
layers more than 15 cm below the
surface
Radionuclide con-
centrations in soil
for Hot Spot areas
Exposure to 222Rn
progeny
Maximum Permissible con-
centration of Ra226 in soil
above background level,
for areas less than 25 m2
Average annual radon
progeny concentration
(including background)
Ra226 concentrations, in any surface
or subsurface area less than 25 m2,
is below the guideline by a factor of
(1007A)'/2, where A is the area of the
elevated region
0.03 WL
(US DOE 1990a)
5
REFERENCES
Geotech 1996. Property Completion Report for Monticello Vicinity Property Remedial Action
for DOE ID NO: MS00748-CS, Address: Parcel No. A33230254803, North Main Street,
Monticello, Utah 84535, RUST Geotech, Grand Junction, Colorado, August 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment Group)
Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National Laboratory, Grand
Junction, Colorado.
US DOE 1990a. Verification and Certification Protocol for the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination and
Decommissioning Program. Revision 3, November 1990. U.S. Department of Energy,
Washington, D.C.
US DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision and
Record of Decision Summary. U.S. Department of Energy, Grand Junction Projects Office,
Grand Junction, Colorado.
DOE ID No.: MS-00749-RS
Property Address: 264 North Second West Street
Vicinity Property Certification Summary and Recommendation
Summary Evaluation
Certification Criteria MACTEC-ERS
U.S. Department
of Energy (DOE)
Ra-226 is < 5 pCi/g above
background in top 15-cm-thick layer of
soil averaged over 100 m2
In situ [X] Lab [ ]
Ra-226 is < 15 pCi/g above
background in any 15-cm-thick layer
of soil more than 15 cm below the
surface averaged over 100 m2.
In situ [ ]Lab[X]
Interior gamma is <, 20 uR/h above
background in any occupied or
habitable structure.
The radon decay-product
concentration in any occupied or
habitable structure is <; 0.02 WL or, at
most, 0.03 WL.
Supplemental standards were applied
in accordance with EPA standard
40 CFR 192.21.
hot-spot criteria met as outlined by
DOE guidelines for FUSRAP (Rev.2,
March 1987).
Yes No Not Taken Yes No Not Taken
[X]a [ ]
[X] [ ]
[X] [ ]
[X] [ ]
[ ] [X]
[X] [ ]
[ ]
[ ]
[ ]
[ ]
[ ]
[ ]
[/] [ ]
[A [ ]
[ ] [$
[V] [ ]
[ ]
[ ]
[ ]
[ ]
[ ]
[ ]
aThe excavations were backfilled with materials that were measured at the source indicating that the Ra-226
concentrations are in the range of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
llllllllll
SFCERTIFED
SFMS-09053
1 of 2
DOE ID No.: MS-00749-RS
MACTEC-ERS Recommendation
On the basis of the Property Completion Report evaluation, this property is recommended for
[X] Certification by DOE.
[ ] Certification by DOE with the concurrence of the U.S. Nuclear Regulatory Commission
because supplemental standards were applied according to 40 CFR 192.21.
Manager, Monticello Programs
MACTEC-ERS
DOE Evaluation
On the basis of the Property Completion Report recommendation, this property
[/] Should be certified by DOE.
[ ] Should be certified by DOE with the concurrence of the U.S. Nuclear Regulatory
Commission because supplemental standards were applied according to 40 CFR 192.21.
Date
U.S. Department of Energy
Work performed under DOE Contract No. DE-AC13-96GJ87335, Task Order No. 96-05.02.14
2 of 2
Monticello Vicinity Properties Project
Property Completion Report
for
Monticello
Vicinity Property Remedial Action
for
DOE ID No.: MS-00749-RS
Address: 264 North Second West Street
Monticello, Utah 84535
December 1996
Prepared for
U.S. Department of Energy
Albuquerque Operations Office
Grand Junction Office
Prepared by
MACTEC-Environmental Restoration Services, LLC (MACTEC-ERS)*
Grand Junction, Colorado
/ >' • •
Michael C. Butherus^
Manager, Monticello Programs
Work performed under DOE Contract No. DE-AC 13-96GJ87335
Task Order No. 96-05.02.14
*MACTEC-ERS has been granted authorization to conduct remedial action by the U.S. Department of Energy.
Remedial action was performed in accordance with the U.S. Environmental Protection Agency 'Standards for
Cleanup of Land and Buildings Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192, Subpart B; and "Implementation," in 40 CFR 192, Subpart C, and the U.S. Department of
Energy Formerly Utilized Sites Remedial Action Program hot-spot criteria.
DOE ID No.: MS-00749-RS
Contents
Page
1.0 Surnmary 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Remedial Action Summary 2
2.0 Operations Summary 3
2.1 Remedial Action Plan 3
2.2 Assessed and Remediated Contamination 3
3.0 Verification Summary 4
3.1 Radiological Survey Data 4
3.1.1 Preremedial Action Survey 4
3.1.2 Postexcavation Survey 4
3.1.3 Radon Decay-Product Concentration Measurements 4
3.2 Recommendation for Certification 5
Table
Table 1. Certification Data Summary 5
Appendix
Appendix A. Radiological Conditions A-1
DOE/Grand Junction Office
December 1996
MVP Property Completion Report
Page ii
DOE ID No.: MS-00749-RS
1.0 Summary
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce the potential hazard
to the public due to long-term exposure to low-level radioactivity associated with the off-site mill
tailings derived from the former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States Government through its agent,
the Defense Plant Corporation, to provide additional sources of vanadium needed during World
War II. Various government agencies operated the mill until 1947. The AEC obtained the mill in
1948 and operated it through 1959 under cost-type contracts to process both uranium and
vanadium ore. Mill operations were terminated on January 1, 1960.
The mill processed approximately one million tons of ore during the AEC operations. Throughout
the operating period, mill tailings from the Monticello millsite were removed from the site and
used for construction-related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for Remedial Actions at Inactive
Uranium Processing Sites" (40 CFR Part 192) for all cleanup activities under the MVP Project.
These standards were prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and open lands. Cleanup
activities also were conducted to meet the hot-spot criteria established by radiological protection
guidelines in the DOE Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management Program Sites
(Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot-spot criteria and
determined to contain mill tailings (radioactive material) exceeding EPA standards and/or DOE
hot-spot criteria. The Remedial Action Contractor* was notified of the inclusion of this property
into the MVP Project and was authorized by DOE to conduct remedial action as required to bring
the property into conformance with EPA standards and DOE hot-spot criteria.
The Remedial Action Contractor, MACTEC-ERS, was awarded the U.S. Department of Energy Grand Junction
Office (DOE-GJO) Technical Assistance and Remediation contract and commenced work on September 5, 1996. The
MACTEC-ERS team consists of International Technology Corporation, Science Application International Corporation,
Roy F. Weston, Inc., and Rust Federal Services, Inc. Rust Geotech was the DOE-GJO contractor from October 1,
1986, through September 4, 1996, and implemented some ofthe tasks discussed in this report
DOE/Grand Junction Office
December 1996
MVP Property Completion Report
Page I
DOE ID No.: MS-00749-RS
1.3 Remedial Action Summary
DOE ID No.:
Legal Description:
MS-00749-RS
Beginning at the NE corner of the SE4SW4 of Section 25, T33S, R23E, Salt Lake Base Meridian;
south 00 degrees 06 minutes east 100 feet, west 120 feet, north 00 degrees 06 minutes west
100 feet, east 120 feet to the beginning, County of San Juan, State of Utah
Property Address:
Property Owners:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological and Engineering Assessment (REA):
Construction Subcontractor:
Preconstruction Conference Record:
Notice of Final Completion Inspection:
Volume of Material Removed in Cubic Yards (yd3):
Area Cleaned Up in Square Meters (m2):
Property Completion Report Submitted:
264 North Second West Street
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
Grand Junction Office
August 27, 1991
MACTEC-ERS
January 1994
Diamond Back Services, Inc.
August 16, 1994
October 12, 1994
Exterior:
Interior:
7
0
33
December 1996
DOE/Grand Junction Office
December 1996
MVP Property Completion Report
Page 2
DOE ID No.: MS-00749-RS
2.0 Operations Summary
2.1 Remedial Action Plan
The remedial action plan specified removal of radioactive material. Once excavation was
completed, the affected area was resurveyed for possible remaining radioactive material and,
upon attaining satisfactory results, was backfilled with uncontaminated material. The property
was restored to a physical condition comparable to that which existed before remedial action
activities.
2.2 Assessed and Remediated Contamination
The radiological assessment identified contamination, 6 inches (in.) deep, within the property
boundary. The quantity of contamination for this property was not specified because it was
assessed as part of Block MS-09053-BK. The remedial action process included removal of
approximately 7 yd3 of radioactive material, 6 in. deep. The area of assessed and excavated
contamination is shown on Figure A-1.
DOE/Grand Junction Office
December 19%
MVP Property Completion Report
Page 3
DOE ID No.: MS-00749-RS
3.0 Verification Summary
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Preremedial Action Survey
The Remedial Action Contractor conducted a radiological survey during June 1992, as described
in the final REA. Figure A-1 shows the extent of assessed contamination and identifies the area
recommended for remedial action.
3.1.2 Postexcavation Survey
A scintillometer was used to perform a surface gamma scan after the removal of radioactive
material and before backfilling. Following the gamma scan, soil samples representative of the
6-in.-thick soil layer at the bottom of the excavation were collected. These samples, representing
the verification area, were analyzed for radium-226. The results of the gamma scan and soil
sample analyses are presented in Table A-1.
3.1.3 Radon Decay-Product Concentration Measurements
Radon decay-product concentration (RDC) measurements were taken on the lowest habitable
level ofthe house, as shown on Figure A-1. The measurement results are presented in
Table A-2.
DOE/Grand Junction Office
December 1996
MVP Property Completion Report
Page 4
DOE JD No.: MS-00749-RS
3.2 Recommendation for Certification
Radioactive materials have been removed from this property to the extent required by EPA
standards (40 CFR 192, Subparts B and C) and DOE hot-spot criteria, as indicated in the
Certification Data Summary (Table 1). Therefore, the property located at 264 North Second
West Street, in Monticello, Utah, is recommended for certification as required by DOE
guidelines.
Table 1. Certification Data Summary
Applicability Standard Survey Results
Radium-226
Concentration in
Surface Soil
Radium-226
Concentration in
Subsurface Soil
Exposure Rate
Land
Shall not exceed 5 pCi/g above
background3 in the 15-cm-thick
surface layer, averaged over
100 m2.
Shall not exceed 15 pCi/g
above background3 in any
15-cm-thick soil layer more
than 15 cm below the surface,
averaged over 100 m2.
Habitable Structures
< 5 pCi/g above background on the
basis of gamma exposure rates that do
not exceed 30 percent above normal
background."
Soil sample result was 6.3 pCi/g.b
Shall not exceed 20 pR/h
above background.0
Range for the basement was 11 to
15uR/h.
Radon Decay-
Product
Concentration
Annual average shall not
exceed 0.02 WL, to the extent
practicable, and shall in no
case exceed 0.03 WL.
Annual average was 0.0046 WL.
Key: cm = centimeters; m2 = square meters; pCi/g = picocuries per gram; uR/h = microroentgens per hour;
WL = working level
I^The background radium-226 concentration for Monticello Vicinity Properties is approximately 2.0 pCi/g.
H"he hot-spot criteria were met based on gamma scans and/or soil sample results.
"The background exposure rate for this property is approximately 13 uR/h.
DOE/Grand Junction Office
December 1996
MVP Property Completion Report
Page 5
DOE ID No.: MS-00749-RS
Appendix A
Radiological Conditions
Table A-1. Postexcavation Survey Results
Table A-2. Radon Decay-Product Concentration Measurement Results
Figure A-1. Radiological As-Built
DOE TD No.: MS-00749-RS
Table A-1. Postexcavation Survey Results
Gamma Radium-226
Verification Exposure Rate Soil Sample Measurement Concentration
Area' Range (uR/h) Ticket No. Method (pCi/g)
V-1 15-20 NCA 966 OCS 6.3
Key: OCS = opposed crystal system; pCi/g = picocuries per gram; uR/h = microroentgens per hour;
V = verification area
aSee Figure A-1 for location of verification area.
DOE/Grand Junction Office
December 1996
MVP Property Completion Report
Page A-2
DOE ID No.: MS-00749-RS
Table A-2. Radon Decay-Product Concentration Measurement Results*
Detector"
Number Start Date End Date
Radon
Concentration
(pCi/L) WL
3851709
3851522
3851540
12-08-94
12-08-94
12-08-94
11-15-95
11-15-95
11-15-95
0.963 0.0048
0.936 0.0047
0.834 0.0042
Annual Average: 0.0046
Key: pCi/L = picocuries per liter; WL = working level
aSee Figure A-1 for measurement location.
"Terradex Radtrak Detector.
DOE/Grand Junction Office
December 1996
MVP Property Completion Report
Page A-3
10
30
12 14 16 18 20
n—i—i—i—T
22 24 26 28 30 32 34 36 38 40
30
28
26
24
22
20
18
rr t-in
to
LJ
o
z
o
o
Ld
to
o
N
\
\
\
13-15
V-1
(RDC)
13-15
ONE STORY
BRICK HOUSE
W/BSMT
11-15
_J 13-15
28
©
I77.-7?!
LV.-/J
12-15
12
V-10
(RDC)
LEGEND
ALL DEPTHS/HEIGHTS IN INCHES
ALL EXPOSURE RATES IN //R/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION AREA IDENTIFIER
RADON DECAY-PRODUCT CONCENTRATION
MEASUREMENT LOCATION
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
26
24
22
20
18
1 6 16
1 4 1 4
1 2
Y SCALE IN FEET
1 0
M:\FAS\033\0003\RM00749V 12/16/96 4:39pm M50312
"T x l l I I I I L
20 10 0 20 40 NORTH
I I
>«OJCCT LOCATION
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION OFFICE. COLORADO
264 NORTH SECOND
WEST STREET
MONTICELLO, UTAH
xraeia
COMPLETION REPORTS MONTICELLO VICINITIES PROPERTY
FIGURE A-1
RADIOLOGICAL AS-BUILT
'""MS-00749-RS
FAS-033-0003-RM00749V 1 1
1 2
10
10 1 2 1 4 1 6 18 20 22 24 26 28 30 32 34 36 38 40
OAK RIDGE NATIONAL LABORATORY PHONE: [phone]
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION FAX: [phone]
FOR THE U.S. DEPARTMENT OF ENERGY
2597 BV. Road
GRAND JUNCTION, COLORADO 81503 APR I 6 i3S7
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by the U.S.
Department of Energy for Residual Radioactive Material at Formerly Utilized Sites Remedial Action
Program (FUSRAP) and Remote Surplus Facilities Management Program Sites (SFMP) [Revision
2, March 1987]. This evaluation is based on an independent verification review of the Remedial
Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment of the 226Ra
concentration in the soil, indoor radon daughter concentration, and indoor gamma exposure rates at
this property.
This property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
Location Number: MS00749-RS
Location Address: 264 North 2nd West Street
Monticello. Utah 84535
Property Owner:

Attachments
LIFE SCIENCES DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
264 NORTH 2ND WEST STREET
MONTICELLO, UTAH (MS00749-RS)
M. K. Jensen
April 1997
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81503
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 3
REFERENCES 6
in
LIST OF TABLES
1. Applicable guidelines for protection against radiation 5
2. Results of ORNL analysis of the RAC soil samples from 264 North 2nd West Street,
Monticello, Utah (MS00749-RS) 6
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site Decommissioning
Projects, U.S. Department of Energy. The author wishes to acknowledge S. M. Smith and S. C. Hall
for technical reviews.
vii
ABSTRACT
In 1980, the site of a vanadium and uranium mill at Monticello, Utah, was accepted into the U.S.
Department of Energy (DOE) Surplus Facilities Management Program, with the objectives of
restoring the government-owned mill site to safe levels of radioactivity, disposing of or containing
the tailings in an environmentally safe manner, and performing remedial actions on off-site (vicinity)
properties that had been contaminated by radioactive material resulting from mill operations. During
1994, the Remedial Action Contractor (RAC) designated by DOE, performed remedial action on the
vicinity property at 264 North 2nd West Street, Monticello, Utah. The Environmental Technology
Section (ETS) of Oak Ridge National Laboratory was assigned the responsibility of verifying the data
supporting the adequacy of remedial action and confirming the site's compliance with DOE guidelines.
The ETS found that the site successfully meets the DOE remedial action objectives. Procedures used
by the ETS are described in the Environmental Technology Section Procedures Manual (ORNL
1993).
ix
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 264 NORTH 2ND WEST STREET
MONTICELLO, UTAH (MS00749-RS)*
INTRODUCTION
The rnill at Monticello, Utah, was built in 1942 by the United States (U.S.) government through
the Defense Plant Corporation to provide vanadium during World War U. Various government
agencies operated the mill until 1947. In 1948, the Atomic Energy Commission (AEC) obtained the
mill and operated it under contract through 1959 to provide both uranium and vanadium. Mill
operations were terminated on January 1, 1960. In 1961, the mill tailings piles were leveled and
graded, covered with rock and soil, and seeded with native grasses. During 1974 and 1975, the ore
stockpiles were removed from the site and the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city of
Monticello, in San Juan County, Utah. The site is bordered on the south and southeast by land held
by the U.S. Bureau of Land Management. Other boundaries are the city of Monticello and private
property.
During the AEC era, the mill processed approximately one million tons of uranium ore. Vana-
dium and uranium were the only substances extracted in the milling process. Other constituents of
the ore remained in the tailings and were not separated prior to disposal. During the years of active
mill operation, the mill tailings were normally moist, so erosion was minimal. However, throughout
the mill's operating period, area residents used these tailings as fill material and as aggregate in
mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy (DOE) initiated
the Surplus Facilities Management Program (SFMP) in 1978 to ensure the safe caretaking and de-
commissioning of government facilities that had been retired from service but still had radioactive
contamination. In 1980, the mill site at Monticello was accepted into the SFMP, and the Monticello
Remedial Action Project (MRAP) was established to restore the government-owned mill site to safe
levels of radioactivity, to dispose of or contain the tailings in an environmentally safe manner, and
to perform remedial actions on off-site (vicinity) properties that had been contaniinated by radio-
active material resulting from mill operations. The Monticello mill site and the tailings remain in
the custody of the DOE Grand Junction, Colorado, Projects Office. In 1983, remedial actions for
vicinity properties were separated from MRAP with establishment of the Monticello Vicinity Proper-
ties (MVP) Project (US DOE 1990b).
*The verification of remedial action was performed by members of the Environmental Assessment Group in the Environmental
Technology Section of the Life Sciences Division at Oak Ridge National Laboratory under DOE contract DE-AC05-96OR22464
with Lockheed Martin Energy Research Corporation.
2
During 1994, the Remedial Action Contractor (RAC) designated by DOE, performed remedial
action on the vicinity property that is the subject of this report, a single family residence located at
264 North 2nd West Street, Monticello, Utah. The remedial action plan required excavation of all
exterior contamination. When the excavation was completed, the property was resurveyed, including
soil sampling, to ensure the removal of all contamination, backfilled with uncontaminated material,
and restored to a condition comparable to that which existed prior to remedial action (MACTEC-
ERS 1996).
DOE adopted a policy to assign an independent contractor to verify the data supporting the
adequacy of remedial action and to confirm the site's compliance with DOE guidelines. The Environ-
mental Technology Section (ETS) of Oak Ridge National Laboratory (ORNL) has been assigned the
responsibility of this task at the 264 North 2nd West Street site. This report describes the methods
and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available documentation
adequately and accurately describes the post-remedial-action radiological conditions of the entire
property that is to be certified and (2) that the remedial action reduced contamination to below
applicable DOE guidelines (US DOE 1990a).
Document Reviews
Review of the RAC property completion report (MACTEC-ERS 1996) indicates the property
was remediated as evaluated by DOE on the basis of U.S. Environmental Protection Agency
standards and the DOE guidelines (US DOE 1990a). Excess residual radioactive materials were
present, thus it was appropriate to designate this property for remedial action.
This property was assessed as part of Block 53, therefore, the quantity of material assessed is
not available. During the actual removal process, a total of 7 yd3 of contaminated earth and material,
6 inches deep, were removed from a 33 nr area.
The RAC performed a post-excavation survey prior to backfilling the excavated areas. This
survey consisted of gamma scans with a scintillometer of the ground level of the structure, a surface
scan of the exterior, and soil sampling. Samples representative of the bottom 15-cm (6-in.) soil layers
ofthe excavated verification area were collected and blended to form a representative composite soil
sample.
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation levels have
not been subtracted. Similarly, background concentrations have not been subtracted from radionu-
clide concentrations in soil samples. Applicable DOE guidelines for protection against radiation are
given in Table 1.
Gamma Measurements
Gamma exposure rate measurements taken by the RAC ranged from 11-15 uR/h in the basement
and 10-12 u/Rh at the ground-level of the residence. Exterior surface gamma measurements taken
from the excavated areas prior to backfilling ranged from 15 to 20 uR/h.
Soil Sample Analysis
Prior to backfilling, the RAC collected soil samples representative of the excavated areas from
the bottom 15-cm (6-in.) soil layers. These samples were blended to form a composite soil sample
representative of an average over the exterior verification area. The RAC's analysis of this sample
showed a 226Ra concentration of 6.3 pCi/g. ORNL ETS obtained this sample and performed a
confirmatory analysis which showed a 226Ra concentration of 9.2 pCi/g. These values are below the
DOE guideline value of 15 pCi/g for soil layers > 15 cm below the surface. Results of the RAC and
ORNL soil sample analyses are given in Table 2. Gamma ranges and/or soil sample results
demonstrate compliance to the DOE Hot Spot Guidelines for areas <25 m2 (Table 1).
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were determined before
remedial action by the Alpha-track method. To monitor radon levels, the RAC placed three alpha-
track detectors on the ground floor of the residence located on this property for a period of
approximately one year (from December 8, 1994 to November 15, 1995). The average annual
working level (WL) of radon progeny concentration, as determined by the Tech./Ops-Landauer
Corporation, was 0.0046, which is well below the 0.03-WL guideline given in Table 1.
CONCLUSION
Results of RAC soil sample analysis and confirmatory split soil sample analysis by ORNL, show
that radionuclide concentrations are within applicable DOE guidelines. Based on the results of the
post-remedial-action data, which are confirmed by the verification assessment data, these radiological
measurements fall below the limits prescribed by DOE guidelines. It is concluded that the site
successfully meets the DOE remedial action objectives.
4
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of 226Ra in soil
above background levels,
averaged over a 100-m2
area
5 pCi/g averaged over the first 15 cm
of soil below the surface; 15 pCi/g
when averaged over 15-cm-thick soil
layers more than 15 cm below the
surface
Radionuclide con-
centrations in soil
for Hot Spot areas
Exposure to 222Rn
progeny
Maximum Permissible con-
centration of Ra226 in soil
above background level,
for areas less than 25 m2
Average annual radon
progeny concentration
(including background)
Ra226 concentrations, in any surface
or subsurface area less than 25 m2,
is below the guideline by a factor of
(100/A)'7', where A is the area of the
elevated region
0.03 WL
(US DOE 1990a)
5
Table 2. Results of ORNL analysis of the RAC soil samples from
264 North 2nd West Street, Monticello, Utah (MS00749-RS)
226Ra concentration (pCi/g)
ORNL RAC
sample sample Depth
No." No/ (cm) ORNL RAC
XI NCA 966 >15 9.2 6.3
a An X-type sample is a split of the sample taken by the remedial action contractor.
* Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated areas were
taken by the RAC, and these samples were blended to form a composite soil sample, which
represents an average over one of the verification areas.
6
REFERENCES
MACTEC-ERS 1996. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00749-RS, Address: 264 North Second West Street, Monticello, Utah
84535, MACTEC-ERS, Grand Junction, Colorado, December 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment Group)
Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National Laboratory, Grand
Junction, Colorado.
US DOE 1990a. Verification and Certification Protocol for the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination and
Decommissioning Program. Revision 3, November 1990. U.S. Department of Energy, Washington,
D.C.
US DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision and Record
of Decision Summary. U.S. Department of Energy, Grand Junction Projects Office, Grand Junction,
Colorado.
DOE ID No.: MS-00750-RS
Property Address: 248 North Second West Street
Vicinity Property Certification Summary and Recommendation
Summary Evaluation
Certification Criteria MACTEC-ERS
U.S. Department
of Energy (DOE)
Ra-226 is <; 5 pCi/g above
background in top 15-cm-thick layer of
soil averaged over 100 m2
In situ [X] Lab [ ]
Ra-226 is ^ 15 pCi/g above
background in any 15-cm-thick layer
of soil more than 15 cm below the
surface averaged over 100 m2.
In situ [ ]Lab[X]
Interior gamma is < 20 pR/h above
background in any occupied or
habitable structure.
The radon decay-product
concentration in any occupied or
habitable structure is < 0.02 WL or, at
most, 0.03 WL.
Supplemental standards were applied
in accordance with EPA standard
40 CFR 192.21.
hot-spot criteria met as outlined by
DOE guidelines for FUSRAP (Rev.2,
March 1987).
Yes No Not Taken Yes No Not Taken
[X]a [ ]
[X] [ ]
[X] [ ]
[X] [ ]
[ ] [X]
[X] [ ]
[ ]
[ ]
[ ]
[ ]
[ ]
[ ]
[>] [ ]
[A [ ]
M I ]
[A I ]
[ ) [>T
IM LL
[ ]
[ ]
[ ]
[ ]
[ ]
[ ]
The excavations were backfilled with materials that were measured at the source indicating that the Ra-226
concentrations are in the range of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
•IIIPII1IIIR lllliun
SFCERTIFED SFMS-09053
7o0
1 of 2
DOE ID No.: MS-OO750-RS
MACTEC-ERS Recommendation
On the basis of the Property Completion Report evaluation, this property is recommended for
[X] Certification by DOE.
[ ] Certification by DOE with the concurrence of the U.S. Nuclear Regulatory Commission
because supplemental standards were applied according to 40 CFR 192.21.
Manager, Monticello Programs
MACTEC-ERS
DOE Evaluation
On the basis of the Property Completion Report recommendation, this property
NX] Should be certified by DOE.
[ ] Should be certified by DOE with the concurrence of the U.S. Nuclear Regulatory
Commission because supplemental standards were applied according to 40 CFR 192.21.
//
Date
U.S. Department of Energy
Work performed under DOE Contract No. DE-AC13-96GJ87335, Task Order No. 96-05.02.14
2 Of 2
Monticello Vicinity Properties Project
Property Completion Report
for
Monticello
Vicinity Property Remedial Action
for
DOE ID No.: MS-00750-RS
Address: 248 North Second West Street
Monticello, Utah 84535
December 1996
Prepared for
U.S. Department of Energy
Albuquerque Operations Office
Grand Junction Office
Prepared by
MACTEC-Environmental Restoration Services, LLC (MACTEC-ERS)*
Grand Junction, Colorado
i//
Michael C. Butherus ^
Manager, Monticello Programs
Work performed under DOE Contract No. DE-AC 13-96GJ87335
Task Order No. 96-05.02.14
•MACTEC-ERS has been granted authorization to conduct remedial action by the U.S. Department of Energy.
Remedial action was performed in accordance with the U.S. Environmental Protection Agency "Standards for
Cleanup of Land and Buildings Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192, Subpart B; and "Implementation," in 40 CFR 192, Subpart C, and the U.S. Department of
Energy Formerly Utilized Sites Remedial Action Program hot-spot criteria.
DOE TD No.: MS-O0750-RS
Contents
Page
1.0 Summary 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Remedial Action Summary 2
2.0 Operations Summary 3
2.1 Remedial Action Plan 3
2.2 Assessed and Remediated Contamination 3
3.0 Verification Summary 4
3.1 Radiological Survey Data 4
3.1.1 Preremedial Action Survey 4
3.1.2 Postexcavation Survey 4
3.1.3 Radon Decay-Product Concentration Measurements 4
3.2 Recommendation for Certification 5
Table
Table 1. Certification Data Summary 5
Appendix
Appendix A. Radiological Conditions A-1
DOE/Grand Junction Office MVP Property Completion Report
December 1996 Page ii
DOE TD No.: MS-00750-RS
1.0 Summary
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce the potential hazard
to the public due to long-term exposure to low-level radioactivity associated with the off-site mill
tailings derived from the former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States Government through its agent,
the Defense Plant Corporation, to provide additional sources of vanadium needed during World
War II. Various government agencies operated the mill until 1947. The AEC obtained the mill in
1948 and operated it through 1959 under cost-type contracts to process both uranium and
vanadium ore. Mill operations were terminated on January 1, 1960.
The mill processed approximately one million tons of ore during the AEC operations. Throughout
the operating period, mill tailings from the Monticello millsite were removed from the site and
used for construction-related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for Remedial Actions at Inactive
Uranium Processing Sites" (40 CFR Part 192) for all cleanup activities under the MVP Project.
These standards were prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and open lands. Cleanup
activities also were conducted to meet the hot-spot criteria established by radiological protection
guidelines in the DOE Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management Program Sites
(Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot-spot criteria and
determined to contain mill tailings (radioactive material) exceeding EPA standards and/or DOE
hot-spot criteria. The Remedial Action Contractor* was notified of the inclusion of this property
into the MVP Project and was authorized by DOE to conduct remedial action as required to bring
the property into conformance with EPA standards and DOE hot-spot criteria.
The Remedial Action Contractor, MACTEC-ERS, was awarded the U.S. Department of Energy Grand Junction
Office (DOE-GJO) Technical Assistance and Remediation contract and commenced work on September 5, 1996. The
MACTEC-ERS team consists of International Technology Corporation, Science Application International Corporation,
Roy F. Weston, Inc., and Rust Federal Services, Inc. Rust Geotech was the DOE-GJO contractor from October 1,
1986, through September 4, 1996, and implemented some ofthe tasks discussed in this report.
DOE/Grand Junction Office
December 19%
MVT Property Completion Report
Page 1
DOE ID No.: MS-00750-RS
1.3 Remedial Action Summary
DOE ID No.:
Legal Description:
MS-00750-RS
Beginning south 00 degrees 06 Minutes east 100 feet from the NE corner of the SE4SW4 of
Section 25, T33S, R23E, Salt Lake Base Meridian; south 00 degrees 06 Minutes east 126 feet,
west 120 feet, north 00 degrees 06 minutes west 126 feet, east 120 feet to the beginning, County
of San Juan, State of Utah
Property Address:
Property Owner:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological and Engineering Assessment (REA):
Construction Subcontractor:
Preconstruction Conference Record:
Notice of Final Completion Inspection:
Volume of Material Removed in Cubic Yards (yd3):
Area Cleaned Up in Square Meters (m2):
Property Completion Report Submitted:
248 North Second West Street
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
Grand Junction Office
August 30,1991
MACTEC-ERS
January 1994
Diamond Back Services, Inc.
August 16, 1994
October 3, 1994
Exterior:
Interior:
3
0
14
December 1996
I)OR/Grand Junction Office
December 1996
MVP Property Completion Report
Page 2
DOE ID No.: MS-O0750-RS
2.0 Operations Summary
2.1 Remedial Action Plan
The remedial action plan specified removal of radioactive material. Once excavation was
completed, the affected areas were resurveyed for possible remaining radioactive material and,
upon attaining satisfactory results, were backfilled with uncontaminated material. The property
was restored to a physical condition comparable to that which existed before remedial action
activities.
2.2 Assessed and Remediated Contamination
The radiological assessment identified contamination, 6 inches (in.) deep, within the property
boundary. The quantity of contamination for this property was not specified because it was
assessed as part of Block MS-09053-BK. The remedial action process included removal of
approximately 3 yd3 of radioactive material, 6 in. deep. The areas of assessed and excavated
contamination are shown on Figure A-1.
DOE/Grand Junction Office
December 1996
MVP Property Completion Report
Page 3
DOE ID No.: MS-00750-RS
3.0 Verification Summary
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Preremedial Action Survey
The Remedial Action Contractor conducted a radiological survey during June 1992, as described
in the final REA. Figure A-1 shows the extent of assessed contamination and identifies the areas
recommended for remedial action.
3.1.2 Postexcavation Survey
A scintillometer was used to perform a surface gamma scan after the removal of radioactive
material and before backfilling. Following the gamma scan, soil samples representative of the
6-in.-thick soil layer at the bottom of the excavation were collected. These samples, representing
the verification area, were analyzed for radium-226. The results of the gamma scan and soil
sample analyses are presented in Table A-1.
3.1.3 Radon Decay-Product Concentration Measurements
Radon decay-product concentration (RDC) measurements were taken on the lowest habitable
level of the house, as shown on Figure A-1. The measurement results are presented in
Table A-2.
DOE/Grand Junction Office
December 1996
MVP Property Completion Report
Page 4
DOE ID No.: MS-00750-RS
3.2 Recommendation for Certification
Radioactive materials have been removed from this property to the extent required by EPA
standards (40 CFR 192, Subparts B and C) and DOE hot-spot criteria, as indicated in the
Certification Data Summary (Table 1). Therefore, the property located at 248 North Second West
Street, in Monticello, Utah, is recommended for certification as required by DOE guidelines.
Table 1. Certification Data Summary
Applicability Standard Survey Results
Radium-226
Concentration in
Surface Soil
Radium-226
Concentration in
Subsurface Soil
Exposure Rate
Land
Shall not exceed 5 pCi/g above
background8 in the 15-cm-thick
surface layer, averaged over
100 m2.
Shall not exceed 15 pCi/g
above background3 in any
15-cm-thick soil layer more
than 15 cm below the surface,
averaged over 100 m2.
Habitable Structures
< 5 pCi/g above background on the
basis of gamma exposure rates that do
not exceed 30 percent above normal
background.13
Soil sample result was 5.8 pCi/g.b
Shall not exceed 20 pR/h
above background.0
Range for the basement was 11 to
13pR/h.
Radon Decay-
Product
Concentration
Annual average shall not
exceed 0.02 WL, to the extent
practicable, and shall in no
case exceed 0.03 WL.
Annual average was 0.0093 WL.
Key: cm = centimeters; m2 = square meters; pCi/g = picocuries per gram; uR/h = microroentgens per hour;
WL = working level
The background radium-226 concentration for Monticello Vicinity Properties is approximately 2.0 pCi/g.
The hot-spot criteria were met based on gamma scans and/or soil sample results.
The background exposure rate for this property is approximately 12 uR/h.
DOE/Grand Junction Office
December 19%
MVP Property Completion Report
Page 5
DOE ID No.: MS-00750-RS
Appendix A
Radiological Conditions
Table A-1. Postexcavation Survey Results
Table A-2. Radon Decay-Product Concentration Measurement Results
Figure A-1. Radiological As-Built
DOE ID No.: MS-00750-RS
Table A-1. Postexcavation Survey Results
Gamma Radium-226
Verification Exposure Rate Soil Sample Measurement Concentration
Area* Range (pR/h) Ticket No. Method (pCi/g)
V-1 14-20 NCA 963 OCS 5.8
Key: OCS = opposed crystal system; pCi/g = picocuries per gram; uR/h = microroentgens per hour;
V = verification area
aSee Figure A-1 for location of verification area.
DOE/Grand Junction Office
December 1996
MVP Property Completion Report
Page A-2
DOE ID No.: MS-00750-RS
Table A-2. Radon Decay-Product Concentration Measurement Results*
Detector6
Number Start Date End Date
Radon
Concentration
<pCi/L) WL
3857550
3857590
3857607
10-27-94
10-27-94
10-27-94
09-28-95
09-28-95
09-28-95
2.02 0.0101
1.80 0.0090
1.78 0.0089
Annual Average: 0.0093
Key: pCi/L = picocuries per liter; WL = working level
aSee Figure A-1 for measurement location.
Terradex Radtrak Detector.
DOE/Grand Junction Office
December 1996
MVP Property Completion Report
Page A-3
10
30
12 14 16 18 20 22 24 26 28 30 32
T"
34 36 38 40
30
28
26
24
22 -
20
18
16
UJ
LU
Cd
\-
CO
CO
LU
o o
LU
to
Cd
o
V
V
N
ONE STORY
BRICK HOUSE
W/BSMT
11-13
r 12-15
(RDC)
12-15
V-1
6 C6
V-1
o 12-15
©
<5>
I77.v?l
Lv.vj
12-15
12
V-10
LEGEND
ALL DEPTHS/HEIGHTS IN INCHES
ALL EXPOSURE RATES IN /zR/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION AREA IDENTIFIER
RADON DECAY-PRODUCT CONCENTRATION
MEASUREMENT LOCATION
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
28
26
24
22
20
18
1 6
1 4 1 4
12
Y
M:\FAS\033\0003\RM00750V 12/17/96 08:09am M50312
—- X
10
SCALE IN FEET
10 1 2 1 4 1 6
20 10
18
0 20
20 22
40
NORTH
J L
24 26 28
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION OFFICE. COLORADO
248 NORTH SECOND
WEST STREET
MONTICELLO, UTAH
OTKsa
CM» TICW
lUMn WME
COMPLETION REPORTS
2W
MONTICELLO VICINITY PROPERTIES
FIGURE A-1
RADIOLOGICAL AS-BUILT
MS-00750-RS
DMAttNC MOT
FAS-033-0003-RM00750V 1 1
1 2
10
30 32 34 36 38 40
OAK RIDGE NATIONAL LABORATORY
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
FOR THE U.S. DEPARTMENT OF ENERGY
PHONE: [phone]
FAX: [phone]
2597 BY. Road
GRAND JUNCTION, COLORADO 81503 ^ j jgg^
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by the U.S.
Department of Energy for Residual Radioactive Material at Formerly Utilized Sites Remedial Action
Program (FUSRAP) and Remote Surplus Facilities Management Program Sites (SFMP) [Revision
2, March 1987]. This evaluation is based on an independent verification review of the Remedial
Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment of the 226Ra
concentration in the soil, indoor radon daughter concentration, and indoor gamma exposure rates at
this property.
This property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
Location Number: MS00750-RS
Location Address: 248 North 2nd West Street
Monticello. Utah 84535
Property Owner:

Attachments
LIFE SCIENCES DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
248 NORTH 2ND WEST STREET
MONTICELLO, UTAH (MS00750-RS)
M. K. Jensen
March 1997
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81503
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 3
REFERENCES 6
iii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 5
2. Results of ORNL analysis of the RAC soil samples from 248 North 2nd West Street,
Monticello, Utah (MS00750-RS) 6
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site Decommissioning
Projects, U.S. Department of Energy. The author wishes to acknowledge S. M. Smith and A. R.
Jones for technical reviews.
vii
ABSTRACT
In 1980, the site of a vanadium and uranium mill at Monticello, Utah, was accepted into the U.S.
Department of Energy (DOE) Surplus Facilities Management Program, with the objectives of
restoring the government-owned mill site to safe levels of radioactivity, disposing of or containing
the tailings in an environmentally safe manner, and performing remedial actions on off-site (vicinity)
properties that had been contaminated by radioactive material resulting from mill operations. During
1994, the Remedial Action Contractor (RAC) designated by DOE, performed remedial action on the
vicinity property at 248 North 2nd West Street, Monticello, Utah. The Environmental Technology
Section (ETS) of Oak Ridge National Laboratory was assigned the responsibility of verifying the data
supporting the adequacy of remedial action and confirming the site's compliance with DOE guidelines.
The ETS found that the site successfully meets the DOE remedial action objectives. Procedures used
by the ETS are described in the Environmental Technology Section Procedures Manual (ORNL
1993).
ix
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 248 NORTH 2ND WEST STREET
MONTICELLO, UTAH (MS00750-RS)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the United States (U.S.) government through
the Defense Plant Corporation to provide vanadium during World War U. Various government
agencies operated the mill until 1947. In 1948, the Atomic Energy Commission (AEC) obtained the
mill and operated it under contract through 1959 to provide both uranium and vanadium. Mill
operations were terminated on January 1, 1960. In 1961, the mill tailings piles were leveled and
graded, covered with rock and soil, and seeded with native grasses. During 1974 and 1975, the ore
stockpiles were removed from the site and the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city of
Monticello, in San Juan County, Utah. The site is bordered on the south and southeast by land held
by the U.S. Bureau of Land Management. Other boundaries are the city of Monticello and private
property.
During the AEC era, the mill processed approximately one million tons of uranium ore. Vana-
dium and uranium were the only substances extracted in the milling process. Other constituents of
the ore remained in the tailings and were not separated prior to disposal. During the years of active
mill operation, the mill tailings were normally moist, so erosion was minimal. However, throughout
the mill's operating period, area residents used these tailings as fill material and as aggregate in
mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy (DOE) initiated
the Surplus Facilities Management Program (SFMP) in 1978 to ensure the safe caretaking and de-
commissioning of government facilities that had been retired from service but still had radioactive
contamination. In 1980, the mill site at Monticello was accepted into the SFMP, and the Monticello
Remedial Action Project (MRAP-) was established to restore the government-owned mill site to safe
levels of radioactivity, to dispose of or contain the tailings in an environmentally safe manner, and
to perform remedial actions on off-site (vicinity) properties that had been contaniinated by radio-
active material resulting from mill operations. The Monticello mill site and the tailings remain in
the custody of the DOE Grand Junction, Colorado, Projects Office. In 1983, remedial actions for
vicinity properties were separated from MRAP with establishment of the Monticello Vicinity Proper-
ties (MVP) Project (US DOE 1990b).
•The verification of remedial action was performed by members of the Environmental Assessment Group in the Environmental
Technology Section of the Life Sciences Division at Oak Ridge National Laboratory under DOE contract DE-AC05-96OR22464
with Lockheed Martin Energy Research Corporation.
2
During 1994, the Remedial Action Contractor (RAC) designated by DOE, performed remedial
action on the vicinity property that is the subject of this report, a single family residence located at
248 North 2nd West Street, Monticello, Utah. The remedial action plan required excavation of all
exterior contamination. When the excavation was completed, the property was resurveyed, including
soil sampling, to ensure the removal of all contamination, backfilled with uncontaminated material,
and restored to a condition comparable to that which existed prior to remedial action (MACTEC-
ERS 1996).
DOE adopted a policy to assign an independent contractor to verify the data supporting the
adequacy of remedial action and to confirm the site's compliance with DOE guidelines. The Environ-
mental Technology Section (ETS) of Oak Ridge National Laboratory (ORNL) has been assigned the
responsibility of this task at the 248 North 2nd West Street site. This report describes the methods
and results of that verification.
PROCEDURES
Objectives
The objectives ofthe verification activities were to confirm (1) that available documentation
adequately and accurately describes the post-remedial-action radiological conditions of the entire
property that is to be certified and (2) that the remedial action reduced contamination to below
applicable DOE guidelines (US DOE 1990a).
Document Reviews
Review of the RAC property completion report (MACTEC-ERS 1996) indicates the property
was remediated as evaluated by DOE on the basis of U.S. Environmental Protection Agency
standards and the DOE guidelines (US DOE 1990a). Excess residual radioactive materials were
present, thus it was appropriate to designate this property for remedial action.
This property was assessed as part of Block 53, therefore, the quantity of material assessed is
not available. During the actual removal process, a total of 3 yd3 of contaminated earth and material,
6 inches deep, were removed from a 14 nr area.
The RAC performed a post-excavation survey prior to backfilling the excavated areas. This
survey consisted of gamma scans with a scintillometer of the ground level of the structure, a surface
scan ofthe exterior, and soil sampling. Samples representative of the bottom 15-cm (6-in.) soil layers
ofthe excavated verification area were collected and blended to form a representative composite soil
sample.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation levels have
not been subtracted. Similarly, background concentrations have not been subtracted from radionu-
clide concentrations in soil samples. Applicable DOE guidelines for protection against radiation are
given in Table 1.
Gamma Measurements
Gamma exposure rate measurements taken by the RAC ranged from 11 to 13 uR/h in the
basement and 12-14 uR/h on the ground floor of the residence. Exterior surface gamma
measurements taken from the excavated areas prior to backfilling ranged from 14 to 20 pR/h.
Soil Sample Analysis
Prior to backfilling, the RAC collected soil samples representative of the excavated areas from
the bottom 15-cm (6-in.) soil layers. These samples were blended to form a composite soil sample
representative of an average over the exterior verification area. The RAC's analysis of this sample
showed a 226Ra concentration of 5.8 pCi/g. ORNL ETS obtained this sample and performed a
confirmatory analysis which showed a 226Ra concentration of 7.0 pCi/g. These values are below the
DOE guideline value of 15 pCi/g for soil layers > 15 cm below the surface. Results of the RAC and
ORNL soil sample analyses are given in Table 2. Gamma ranges and/or soil sample results
demonstrate compliance to the DOE Hot Spot Guidelines for areas <25 m2 (Table 1).
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were determined by the
Alpha-track method. To monitor radon levels, the RAC placed three alpha-track detectors on the
ground floor of the residence located on this property for a period of approximately one year (from
October 27, 1994 to September 28, 1995). The average annual working level (WL) of radon
progeny concentration, as determined by the Tech./Ops-Landauer Corporation, was 0.0093, which
is well below the 0.03-WL guideline given in Table 1.
CONCLUSION
Results of RAC soil sample analysis and confirmatory split soil sample analysis by ORNL,
show that radionuclide concentrations are within applicable DOE guidelines. Based on the results
of the post-remedial-action data, which are confirmed by the verification assessment data, these
radiological measurements fall below the limits prescribed by DOE guidelines. It is concluded that
the site successfully meets the DOE remedial action objectives.
4
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of 226Ra in soil
above background levels,
averaged over a 100-m2
area
5 pCi/g averaged over the first 15 cm
of soil below the surface; 15 pCi/g
when averaged over 15-cm-thick soil
layers more than 15 cm below the
surface
Radionuclide con-
centrations in soil
for Hot Spot areas
Exposure to 222Rn
progeny
Maximum Permissible con-
centration of Ra226 in soil
above background level,
for areas less than 25 m2
Average annual radon
progeny concentration
(including background)
Ra226 concentrations, in any surface
or subsurface area less than 25 m2,
is below the guideline by a factor of
(100/A)'71, where A is the area of the
elevated region
0.03 WL
(US DOE 1990a)
5
Table 2. Results of ORNL analysis of the RAC soil samples from
248 North 2nd West Street, Monticello, Utah (MS00750-RS)
^Ra concentration (pCi/g)
ORNL RAC
sample sample Depth
No." No^ (cm) ORNL RAC
XI NCA 963 >15 7.0 5.8
" An X-type sample is a split of the sample taken by the remedial action contractor.
* Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated areas were
taken by the RAC, and these samples were blended to form a composite soil sample, which
represents an average over one of the verification areas.
6
REFERENCES
MACTEC-ERS 1996. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00750-RS, Address: 248 North Second West Street, Monticello, Utah
84535, MACTEC-ERS, Grand Junction, Colorado, December 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment Group)
Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National Laboratory, Grand
Junction, Colorado.
US DOE 1990a. Verification and Certification Protocol for the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination and
Decommissioning Program. Revision 3, November 1990. U.S. Department of Energy, Washington,
D.C.
US DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision and Record
of Decision Summary. U.S. Department of Energy, Grand Junction Projects Office, Grand Junction,
Colorado.
DOE ID No(s).: MS-00756-HO
Property Address(es): 364 West First North Street
Vicinity Property Certification Summary and Recommendation
Summary Evaluation
Certification Criteria MACTEC-ERS
U.S. Department
of Energy (DOE)
Ra-226 is <: 5 pCi/g above background
in top 15-cm-thick layer of soil
averaged over 100 m2
In situ [X] Lab [ ]
Ra-226 is < 15 pCi/g above
background in any 15-cm-thick layer of
soil more than 15 cm below the
surface averaged over 100 m2.
In situ [ ]Lab[X]
Interior gamma is < 20 uR/h above
background in any occupied or
habitable structure.
The radon decay-product
concentration in any occupied or
habitable structure is s 0.02 WL or, at
most, 0.03 WL.
Supplemental standards were applied
in accordance with EPA standard
40 CFR 192.21.
Hot-spot criteria met as outlined by
DOE guidelines for FUSRAP (Rev.2,
March 1987)
Yes No Not Taken Yes No Not Taken
[X]a [ ]
[X] [ ]
[X] [ ]
[X] [ ]
[ ] [X]
[X] [ ]
[ ]
)
[ ]
[ ]
[ ]
[ ]
[ ]
[/\ [ ) [ ]
IX] [ ]
[>] [ ]
[>3 [ 1
[ ] m
[ ]
[ ]
[ ]
[ ]
[yl [ 1 [ 1
aThe excavations were backfilled with materials that were measured at the source indicating that the Ra-226
concentrations are in the range of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
Ill
SFMS-00756 SFCERTIFED
lof2
DOE JD No(s).: MS-00756-HO
MACTEC-ERS Recommendation
On the basis of the MACTEC-ERS evaluation, this property is recommended for
[X] Certification by DOE.
[ ] Certification by DOE with the concurrence of the U. S. Nuclear Regulatory Commission
because supplemental standards were applied according to 40 CFR 192.21.
Michael C. Butherus
Manager, Monticello Programs
MACTEC-ERS
Date
DOE Evaluation
On the basis of the MACTEC-ERS recommendation, this property
Should be certified by DOE.
[ ] Should be certified by DOE with the concurrence ofthe U.S. Nuclear Regulatory
Commission because supplemental standards were applied according to 40 CFR 192.21.
Certification Official ' Date
U.S. Department of Energy
Work performed under DOE Contract No. DE-AC13-95GJ87335, Task Order No. 96-05.02.14.001
2 Of 2
Monticello Vicinity Properties Project
Property Completion Report
for
Monticello
Vicinity Property Remedial Action
for
DOE DD No(s).: MS-00756-HO
Address(es): 364 West First North Street
Monticello, Utah 84535
October 1996
Prepared for
U.S. Department of Energy
Albuquerque Operations Office
Grand Junction Projects Office
Prepared by
MACTEC-ERS*
Grand Junction, Colorado
Work performed under DOE Contract No. DE-AC13-95GJ87335
Task Order No. 96-05.02.14.001
/. '^iS^-—
Michael C. Butherus
Manager, Monticello Programs
*MACTEC-ERS has been granted authorization to conduct remedial action by the U.S. Department of Energy.
Remedial action was done in accordance with the U.S. Environmental Protection Agency "Standards for Cleanup of
Land and Buildings Contaminated with Residual Radioactive Materials from Inactive Uranium Processing Sites,"
40 CFR 192, Subpart B; and "Implementation," in 40 CFR 192, Subpart C, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot-spot criteria.
DOE ID No.: MS-00756-HO
Contents
Page
1.0 Summary 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Remedial Action Summary 2
2.0 Operations Summary 3
2.1 Remedial Action Plan 3
2.2 Assessed and Remediated Contamination 3
3.0 Verification Summary 4
3.1 Radiological Survey Data 4
3.1.1 Preremedial Action Survey 4
3.1.2 Postexcavation Survey 4
3.1.3 Radon Decay-Product Concentration Measurements 4
3.2 Recommendation for Certification 5
Table
Table 1. Certification Data Summary 5
Appendix
Appendix A. Radiological Conditions A-1
DOE/Grand Junction Projects Office
October 1996
MVP Property Completion Report
Page ii
DOE ID No.: MS-00756-HO
1.0 Summary
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce potential hazards to
the public resulting from long-term exposure to low-level radioactivity associated with the ofF-site
mill tailings derived from the former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States Government through its agent,
the Defense Plant Corporation, to provide additional sources of vanadium needed during World
War II. Various government agencies operated the mill until 1947. The AEC obtained the mill in
1948 and operated it through 1959 under cost-type contracts to process uranium and vanadium
ore. Mill operations were terminated on January 1, 1960.
The mill processed approximately one million tons of ore during AEC operations. Throughout the
operating period, mill tailings were removed from the Monticello millsite and used for
construction-related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for Remedial Actions at Inactive
Uranium Processing Sites" (40 CFR Part 192) for all cleanup activities under the MVP Project.
These standards were prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and open lands. Cleanup
activities also were conducted to meet the hot-spot criteria established by radiological protection
guidelines in the DOE Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management Program Sites
(Revision 2, March 1987),
This vicinity property was evaluated on the basis of EPA standards and DOE hot-spot criteria and
determined to contain mill tailings (radioactive material) exceeding EPA standards and/or DOE
hot-spot criteria. The Remedial Action Contractor was notified of the inclusion of this property
into the MVP Project and was authorized by DOE to conduct remedial action as required to bring
the property into conformance with EPA standards and DOE hot-spot criteria.
DOE/Grand Junction Projects Office
October 1996
MVP Property Completion Report
Page 1
DOE ID No.: MS-00756-HO
1.3 Remedial Action Summary
DOE D3 No(s).:
Legal Description:
MS-00756-HO
Beginning 40 rods west of the quarter corner common to Sections 36 and 25, T33S., R23E., Salt
Lake Base Meridian; north 40 rods, west 40 rods, south 40 rods, east 40 rods to the beginning,
and also beginning 839.63 feet west and 660 feet north ofthe S4 corner of said Section 25, south
89 degrees 59 minutes west 480.37 feet, north 127 feet, south 89 degrees 13 minutes east
480.37 feet, south 00 degrees 1 minute east 120.3 feet to the beginning, County of San Juan, State
ofUtah
Property Address(es):
Property Owner(s):
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological and Engineering Assessment (REA):
Construction Subcontractor:
Preconstruction Conference Record:
Notice of Final Completion Inspection:
Volume of Material Removed in Cubic Yards (yd3):
Area Cleaned Up in Square Meters (m2):
Property Completion Report Submitted:
364 West First North Street
Monticello, Utah 84535

Hospital (HO)
Oak Ridge National Laboratory
Grand Junction Office
June 18, 1991
MACTEC-ERS
February 11, 1994
Diamond Back Services
October 3, 1994
November 28, 1994
Exterior:
Interior:
7
0
34
October 1996
DOE/Grand Junction Projects Office
October 1996
MVP Property Completion Report
Page 2
DOE JJD No.: MS-00756-HO
2.0 Operations Summary
2.1 Remedial Action Plan
The remedial action plan specified removal of radioactive material. Once excavation was
completed, the effected area(s) were resurveyed for possible remaining radioactive material and,
upon attaining satisfactory results, were backfilled with uncontaminated material. The property
was restored to a physical condition comparable to that which existed before remedial action
activities.
2.2 Assessed and Remediated Contamination
The radiological assessment identified 4 yd3 of contamination, ranging from 6 inches (in.) deep to
210 in. high, within the property boundary. The remedial action process included removal of
approximately 7 yd3 of radioactive material, ranging from 48 in. deep to 210 in. high. The area(s)
of assessed and excavated contamination are shown in Figure A-1.
DOE/Grand Junction Projects Office
October 1996
MVP Property Completion Report
Page 3
DOE ID No.: MS-00756-HO
3.0 Verification Summary
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Preremedial Action Survey
The Remedial Action Contractor conducted a radiological survey during July 1992, as described
in the final REA. Figure A-1 shows the area(s) and depth(s) of assessed contamination that are
recommended for remedial action.
3.1.2 Postexcavation Survey
A scintillometer was used to perform a surface gamma scan after removal of radioactive material
and before backfilling. Following the gamma scan, soil samples representative ofthe 6-in-thick
soil layer at the bottom of the excavation were collected. The results of gamma scans and analyses
for radium-226 are presented in Table A-1.
3.1.3 Radon Decay-Product Concentration Measurement
Radon decay-product concentration (RDC) measurements were taken on the lowest habitable
level of the structure, as shown on Figure A-1. The measurement results are presented in
Table A-2.
DOE/Grand Junction Projects Office
October 1996
MVP Property Completion Report
Page 4
DOE ID No.: MS-00756-HO
3.2 Recommendation for Certification
Radioactive materials have been removed from this property to the extent required by EPA
standards (40 CFR 192, Subparts B and C) and DOE hot-spot criteria, as presented in the
Certification Data Summary (Table 1). Therefore, the property located at 364 West First
North Street, in Monticello, Utah, is recommended for certification as required by DOE
guidelines.
Table 1. Certification Data Summary
Applicability Standard Survey Results
Radium-226
Concentration in
Surface Soil
Radium-226
Concentration in
Subsurface Soil
Exposure Rate
Radon Decay-
Product
Concentration
Land
Shall not exceed 5 pCi/g above
background3 in the 15-cm-thick
surface layer, averaged over
100 m2.
Shall not exceed 15 pCi/g
above background3 in any
15-cm-thick soil layer more than
15 cm below the surface,
averaged over 100 m2.
Habitable Structures
< 5 pCi/g above background on the
basis of gamma exposure rates that do
not exceed 30 percent above normal
background.b
Soil sample results were 1.1 and
1.4 pCi/g.b
Shall not exceed 20 uR/h above
background.0
Annual average shall not
exceed 0.02 WL, to the extent
practicable, and shall in no
case exceed 0.03 WL.
Range was 10 to 15 pR/h for the
ground floor.
Average was 0.0017 WL, on the basis
of the DOE-approved abbreviated-
measurement method.
Key: cm = centimeters; m2 = square meters; pCi/g = picocuries per gram; uR/h = microroentgens per hour;
WL = working levels
"The background radium-226 concentration for Monticello Vicinity Properties is approximately 2.0 pCi/g.
"The hot-spot criteria were met based on gamma scans and/or soil sample results.
°The background exposure rate for this property is approximately 13 uR/h.
DOE/Grand Junction Projects Office
October 1996
MVP Property Completion Report
Page 5
DOE ID No.: MS-00756-HO
Appendix A
Radiological Conditions
Table A-1. Postexcavation Survey Results
Table A-2. Radon Decay-Product Concentration Measurement Results
Figure A-1. Radiological As-Built
DOE ID No.: MS-00756-HO
Table A-1. Postexcavation Survey Results
Verification
Area*
Gamma
Exposure Rate
Range (pR/h)
Soil Sample
Ticket No.
Measurement
Method
Radium-226
Concentration
(pCi/g)
V-1
V-2
16-21
14-16
NCA 972
NCA 975
OCS
OCS
1.4
1.1
Key: OCS = opposed crystal system; pCi/g = picocuries per gram; uR/h = microroentgens per hour
V = verification area
'See Figure A-1 for location of verification areas.
DOE/Grand Junction Projects Office
October 4,1996
UMTRA Property Completion Report
Page A-2
DOE ID No.: MS-00756-HO
Table A-2. Radon Decay-Product Concentration Measurement Results*
Radon
Detector1* Concentration
Number Start Date End Date (pCi/L) WL
3964178 02-27-95 05-30-95 0.33
3964317 02-27-95 05-30-95 0.33
3964112 02-27-95 05-30-95 0.33
^ Average:
Key: pCi/L = picocuries per liter; WL = working level
"See Figure A-1 for measurement locations.
bTerradex Radtrak Detector.
0.0017
0.0017
0.0017
0.0017
DOE/Grand Junction Projects Office
October 4,1996
UMTRA Property Completion Report
Page A-3
52
50
48
46
44
42
40
38
56
54
52
50
28
26
24
22
20
18
16
14
12
10
14 16
-i—i—r
22
~i—i—r
44 46
n—i—r
54
i—r
56
T"
58
-r
68
"i—i—r i i i r
(ROC)
ONE STORY BRICK BUILDING W/UNINHABITABLE PARTIAL BASEMENT
10-15
- GARAGE
11-12
12-15
5EE DETAIL A
WEST FIRST NORTH STREET
12-15
T
V-2
210]48
GRAND
STAND
E
V-1
[210
V-2 |
1
DETAIL A
SCALE IN FEET
12-15
[12]
L£S£HD
ALL DEPTHS/HEIGHTS IN INCHES
ALL EXPOSURE RATES IN >iR/h
ASSESSEO AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION AREA IDENTIFIER
RADON DECAY-PRODUCT CONCENTRATION
MEASUREMENT LOCATION
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
HEIGHT OF ASSESSED CONTAMINATION (STEEL BACKSTOP POSTS)
WEST CENTER STREET
SCALE IN FEET
50 25 0
IH.S 0RAWING IS FOR THC SOLE USE OF THE U.S DEPARTMENT
OF ENERGY ANO US CONTRACTORS. IT IS NOT A LAND SURVEY PLAT, UTILITY LOCATION PLAT, OH OTHER IMPROVEMENT SURVEY
PLAT AND IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE, BUILDING. OR OTHER FUTURE IMPROVEMENT LINCS.
364 WEST FIRST
NORTH STREET
MONTICELLO. UTAH
arasa
I M \r»S\03J\0O0J\»¥0OTllV 10/07/9* OS **Qm «S<13>]
I - X
! I ! I I I J I L I I I I I I I I I
COMPLETION REPORTS
CAS nfr—
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OfFiCE, COLORAOO
3?
MONTICELLO VICINITY PROPERTIES
FIGURE A-1
RADIOLOGICAL AS-BUILT
MS-00756-HO
J-000756-V1
1 1
12 1 4 16
OAK RIDGE NATIONAL LABORATORY PHONE: [phone]OO
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION FAX: [phone]
FOR THE U.S. DEPARTMENT OF ENERGY
2597 B'A Road
GRAND JUNCTION, COLORADO 81503 Jjyj 3 ] JgQJ
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by the U.S.
Department of Energy for Residual Radioactive Material at Formerly Utilized Sites Remedial
Action Program (FUSRAP) and Remote Surplus Facilities Management Program Sites (SFMP)
[Revision 2, March 1987]. This evaluation is based on an independent verification review of the
Remedial Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment of the
n6RsL concentration in the soil, indoor radon daughter concentration, and indoor gamma exposure
rates at this property.
This property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
Location Number: MS00756-HO
Location Address: 364 West 1st North Street
Monticello. Utah 84535
Property Owner:

Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERD7ICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
364 WEST 1ST NORTH STREET
MONTICELLO, UTAH (MS00756-HO)
M. K. Jensen
January 1997
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81503
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 3
REFERENCES 6
iii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 4
2. Results of ORNL analysis of the RAC soil samples from 364 West 1 st North Street,
Monticello, Utah (MS00756-HO) 5
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site Decommissioning
Projects, U.S. Department of Energy. The author wishes to acknowledge A. R. Jones and T. L.
Meyer for technical reviews.
vii
ABSTRACT
In 1980, the site of a vanadium and uranium mill at Monticello, Utah, was accepted into the U.S.
Department of Energy (DOE) Surplus Facilities Management Program, with the objectives of
restoring the government-owned mill site to safe levels of radioactivity, disposing of or containing
the tailings in an environmentally safe manner, and performing remedial actions on off-site (vicinity)
properties that had been contaminated by radioactive material resulting from mill operations. During
1994, the Remedial Action Contractor (RAC) designated by DOE, performed remedial action on the
vicinity property at 364 West 1st North Street, Monticello, Utah. The Environmental Technology
Section (ETS) of Oak Ridge National Laboratory was assigned the responsibility of verifying the data
supporting the adequacy of remedial action and confirming the site's compliance with DOE guidelines.
The ETS found that the site successfully meets the DOE remedial action objectives. Procedures used
by the ETS are described in the Environmental Technology Section Procedures Manual (ORNL
1993).
ix
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 364 WEST 1ST NORTH STREET
MONTICELLO, UTAH (MS00756-HO)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the United States (U.S.) government through
the Defense Plant Corporation to provide vanadium during World War II. Various government
agencies operated the mill until 1947. In 1948, the Atomic Energy Commission (AEC) obtained the
mill and operated it under contract through 1959 to provide both uranium and vanadium. Mill
operations were terminated on January 1, 1960. In 1961, the mill tailings piles were leveled and
graded, covered with rock and soil, and seeded with native grasses. During 1974 and 1975, the ore
stockpiles were removed from the site and the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city of
Monticello, in San Juan County, Utah. The site is bordered on the south and southeast by land held
by the U.S. Bureau of Land Management. Other boundaries are the city of Monticello and private
property.
During the AEC era, the mill processed approximately one million tons of uranium ore. Vana-
dium and uranium were the only substances extracted in the milling process. Other constituents of
the ore remained in the tailings and were not separated prior to disposal. During the years of active
mill operation, the mill tailings were normally moist, so erosion was minimal. However, throughout
the mill's operating period, area residents used these tailings as fill material and as aggregate in mortar
and concrete.
Under the authority ofthe Atomic Energy Act, the U.S. Department of Energy (DOE) initiated
the Surplus Facilities Management Program (SFMP) in 1978 to ensure the safe caretaking and de-
commissioning of government facilities that had been retired from service but still had radioactive
contamination. In 1980, the mill site at Monticello was accepted into the SFMP, and the Monticello
Remedial Action Project (MRAP) was established to restore the government-owned mill site to safe
levels of radioactivity, to dispose of or contain the tailings in an environmentally safe manner, and to
perform remedial actions on off-site (vicinity) properties that had been contaminated by radioactive
material resulting from mill operations. The Monticello mill site and the tailings remain in the custody
of the DOE Grand Junction, Colorado, Projects Office. In 1983, remedial actions for vicinity
properties were separated from MRAP with establishment of the Monticello Vicinity Properties
(MVP) Project (US DOE 1990b).
•The verification of remedial action was performed by members ofthe Environmental Assessment Group in the Environmental
Technology Section ofthe Health Sciences Research Division at Oak Ridge National Laboratory under DOE contract DE-AC05-
960R22464 with Lockheed Martin Energy Research Corporation.
2
During 1994, the Remedial Action Contractor (RAC) designated by DOE, performed remedial
action on the vicinity property that is the subject of this report, a hospital and baseball field located
at 364 West 1st North Street, Monticello, Utah. The remedial action plan required excavation of all
exterior contamination. When the excavation was completed, the property was resurveyed, including
soil sampling, to ensure the removal of all contamination, backfilled with uncontaminated material,
and restored to a condition comparable to that which existed prior to remedial action (MACTEC-
ERS 1996).
DOE adopted a policy to assign an independent contractor to verify the data supporting the
adequacy of remedial action and to confirm the site's compliance with DOE guidelines. The
Environmental Technology Section (ETS) of Oak Ridge National Laboratory (ORNL) has been
assigned the responsibility of this task at the 364 West 1st North Street site. This report describes
the methods and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available documentation
adequately and accurately describes the post-remedial-action radiological conditions ofthe entire
property that is to be certified and (2) that the remedial action reduced contamination to below
applicable DOE guidelines (US DOE 1990a).
Document Reviews
Review of the RAC property completion report (MACTEC-ERS 1996) indicates the property
was remediated as evaluated by DOE on the basis of U.S. Environmental Protection Agency
standards and the DOE guidelines (US DOE 1990a). Excess residual radioactive materials were
present, thus it was appropriate to designate this property for remedial action.
The pre-remedial-action survey performed by the RAC identified 4 yd3 of mill tailings 6 inches
deep to 210 inches high. During the actual removal process, a total of 7 yd3 of contaminated earth,
uranium mill tailings, and mill related material 48 inches deep to 210 inches high were removed
from a 34 m2 area. This removal included the steel posts for a baseball backstop, cement posts
buried to anchor the backstop, and surface soils.
The RAC performed a post-excavation survey prior to backfilling the excavated areas. This
survey consisted of gamma scans with a scintillometer of the ground level of the structure, a surface
scan of the exterior, and soil sampling. Samples representative of the bottom 15-cm (6-in.) soil
layers of two excavated verification areas were collected and blended to form representative
composite soil samples for each verification area.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation levels have
not been subtracted. Similarly, background concentrations have not been subtracted from radionu-
clide concentrations in soil samples. Applicable DOE guidelines for protection against radiation are
given in Table 1.
Gamma Measurements
Gamma exposure rate measurements taken by the RAC at the ground-level of the hospital
ranged from 10 to 15 pR/h. Exterior surface gamma measurements taken from the excavated areas
prior to backfilling ranged from 14 to 21 uR/h.
Soil Sample Analysis
Prior to backfilling, the RAC collected soil samples representative of the excavated areas from
the bottom 15-cm (6-in.) soil layers. These samples were blended to form composite soil samples
representative of an average over the two exterior verification areas. The RAC's analysis of these
samples showed 226Ra concentrations ranging from 1.1 to 1.4 pCi/g in the composite sample. ORNL
ETS obtained these samples and performed a confirmatory analysis which showed 226Ra concentra-
tions ranging from 1.3 to 1.6 pCi/g. These values are below the DOE guideline value of 15 pCi/g
for soil layers > 15 cm below the surface. Gamma ranges and/or soil sample results demonstrate
compliance to the DOE Hot Spot Guidelines for areas <25 m2 (Table 1). Results of the RAC and
ORNL soil sample analyses are given in Table 2.
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were determined by the
Alpha-track method. To monitor radon levels, the RAC placed three alpha-track detectors on the
ground floor of the hospital located on this property for a period of approximately three months
(from February 27, 1995 to May 30, 1995). The average annual working level (WL) of radon
progeny concentration, as determined by the Tech./Ops-Landauer Corporation, was 0.0017, which
is well below the 0.03-WL guideline given in Table 1.
CONCLUSION
Results of RAC soil sample analysis and confirmatory split soil sample analysis by ORNL,
show that radionuclide concentrations are within applicable DOE guidelines. Based on the results
of the post-remedial-action data, which are confirmed by the verification assessment data, these
radiological measurements fall below the limits prescribed by DOE guidelines. It is concluded that
the site successfully meets the DOE remedial action objectives.
4
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of 226Ra in soil
above background levels,
averaged over a 100-m2
area
5 pCi/g averaged over the first 15 cm
of soil below the surface; 15 pCi/g
when averaged over 15-cm-thick soil
layers more than 15 cm below the
surface
Radionuclide con-
centrations in soil
for Hot Spot areas
Exposure to 222Rn
progeny
Maximum Permissible con-
centration of Ra226 in soil
above background level,
for areas less than 25 nr
Average annual radon
progeny concentration
(including background)
Ra226 concentrations, in any surface
or subsurface area less than 25 m2,
is below the guideline by a factor of
(1007A)'/2, where A is the area ofthe
elevated region
0.03 WL
(US DOE 1990a)
5
Table 2. Results of ORNL analysis of the RAC soil samples from
364 West 1st North Street, Monticello, Utah (MS00756-HO)
226Ra concentration (pCi/g)
ORNL RAC
sample sample Depth ORNL RAC
No." No^ (cm)
XI NCA 972 >15 1.3 1.4
X2 NCA 975 >15 1.6 1.1
" An X-type sample is a split of the sample taken by the remedial action contractor.
* Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated areas were
taken by the RAC, and these samples were blended to form a composite soil sample, which
represents an average over one of the verification areas.
6
REFERENCES
MACTEC-ERS 1996. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00756-HO, Address: 364 West 1st North Street, Monticello, Utah
84535, MACTEC-ERS, Grand Junction, Colorado, October 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment Group)
Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National Laboratory, Grand
Junction, Colorado.
US DOE 1990a. Verification and Certification Protocol for the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination and
Decommissioning Program. Revision 3, November 1990. U.S. Department of Energy, Washington,
D.C.
US DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision and Record
of Decision Summary. U.S. Department of Energy, Grand Junction Projects Office, Grand Junction,
Colorado.
DOE ID No.: MS-00806-CS
Property Addresses: 480 and 496 North Main Street
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech of Energy (DOE)
Ra-226 is < 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [ ]
Ra-226 is < 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2.
In-situ [ ] Lab [X]
Interior gamma is <; 20 //R/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is s 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21.
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
[>] [ ] [ ]
[Al] I ]
[X] [ ] [ ]
[XI [ 1 I 1
[ ] [XI [ ]
[>] [ ] [ ]
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
lllllllllll Ililllllllll
SFCERTIFED SFMS-00806
DOE ID No.: MS-00806-CS
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
fusby
Manager/Monticello Programs
Rust Geotech
Date
DOE EVALUATION
[/] Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Certffication Official '
U.S. Department of Energy
Date
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00806-CS
ADDRESSES: 480 AND 496 NORTH MAIN STREET
MONTICELLO, UTAH 84535
AUGUST 1996
Prepared for
U.S. Department of Energy
by
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
Wanda/S. Busby
Manager, Monticello Programs
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.1.3 Radon Decay-Product Concentration (RDC) Measurement .... 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
DOE ID No.: MS-00806-CS
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Inclusion Survey Contractor. DOE reviewed
these evaluation results and determined that the property contained mill
tailings (residual radioactive material) exceeding DOE hot spot criteria.
The Remedial Action Contractor was notified of the inclusion of this
property into the MVP Project and was authorized by DOE to conduct
remedial action as required to bring the property into conformance with
EPA standards and DOE hot spot criteria.
1
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
Property Addresses:
Property Owner:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
DOE ID No.: MS-00806-CS
MS-00806-CS
Beginning at a point which is west
102 rods and south 13 rods of the
E4 corner of Section 25, T33S., R23E., Salt
Lake Base Meridian; south 13 rods, east
13 rods, north 13 rods, west 13 rods to
beginning, City of Monticello, County of
San Juan, State of Utah
480 and 496 North Main Street
Monticello, Utah 84535

Commercial Simple (CS)
Oak Ridge National Laboratory
June 18, 1991
Rust Geotech
February 3, 1994
Diamond Back Services, Inc.
9861 Titan Park Circle
Littleton, Colorado
August 9, 1994
September 8, 1994
Interior: 0 cubic yards
Exterior: 2 cubic yards
6 square meters (m2)
August 1996
2
DOE ID No.: MS-00806-CS
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of exterior residual radioactive
material (Appendix Figure 2.1). Once excavation was complete, the
affected areas were resurveyed for possible remaining residual radioactive
material and, upon attaining satisfactory results, were backfilled with
uncontaminated material. The property was restored to a physical
condition comparable to that which existed prior to remedial action
activities.
2.2 Previously Unidentified Contamination
The radiological assessment identified 3 cubic yards of contamination,
ranging from 6 to 12 inches deep, within the property. The remedial
action process included the removal of approximately 2 cubic yards of
residual radioactive material, ranging from 6 to 18 inches deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID No.: MS-00806-CS
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by the Remedial Action
Contractor during June 1992, as described in the final REA dated
February 1994. Appendix Figure 2.1 shows the extent of
assessed contamination and identifies the areas recommended to
undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the excavation were
collected. These samples were blended to form a composite
sample representing the verification area (Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 11 to 23 microroentgens per
hour OvR/h), as indicated on Appendix Figure 2.1. The result of
analysis for radium-226 in one composite soil sample was
3.1 picocuries per gram (pCi/g), as indicated in Appendix
Table 3.1.
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on measurements representing an annual average, the RDC
was 0.0050 working level (WL), as indicated in Appendix
Table 3.2. Appendix Figure 2.1 shows the measurement location
on the ground floor of the house (the lowest habitable level of the
structure). The cellar of the house was uninhabitable. RDC
measurements were not taken in the trailer houses due to
excessive ventilation caused by no permanent foundations.
4
DOE ID No.: MS-00806-CS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at 480 and 496 North Main Street, in
Monticello, Utah, is recommended for certification as required by DOE
guidelines, and the appropriate records should be documented.
Certification Data Summary
Applicability
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Standards
Shall not exceed 20 //R/h
above background.*
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Survey Results
Range for the ground
floor of the house was 12
to 14//R/h. Range for all
the trailer houses was 11
to 14//R/h.
Annual average was
0.0050 WL.
Land.
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
< 5 pCi/g above
background.**
Soil sample result was
3.1 pCi/g.**
*The background exposure rate is approximately 12//R/h.
The background radium-226 concentration is approximately 2.0 pCi/g.
**The hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-00806-CS
4.0 APPENDIX
Appendix Tables:
Table 3.1 Post-Excavation Sample/Measurement Results
Table 3.2 Radon Decay-Product Concentration Measurement
Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
JEK:07/15/96
MS-00806.CS WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00806-CS
Addresses: 480 and 496 North Main Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (jt/R/h) Ticket No. Method" (pCi/g)
V-1 15-23 NCA 953 OCS 3.1
See Appendix Figure 2.1 for the verification area.
"OCS = Opposed Crystal System
7
Table 3.2
Radon Decay-Product Concentration Measurement Results
DOE ID No.: MS-00806-CS
Addresses: 480 and 496 North Main Street, Monticello, Utah
Instrument Type: Landauer Radtrak Detector
Radon
Detector Concentration Working
Number Start Date End Date (pCi/L) Level
3851697
3851711
3851631
10-11-94
10-11-94
10-11-94
10-10-95
10-10-95
10-10-95
1.026
0.975
1.020
0.0051
0.0049
0.0051
Annual Average: 0.0050
See Appendix Figure 2.1 for the measurement location.
8
42
40
38
36
34
32
30
28
26
24
22
20
18
16
14
12
10
12 14 1 6 18 20 22 24 26
n—i—r
28 30 32 34 36 38 40 42 46 48
"T"
50
i—i—r
777 777 777 777 777
V-1
15-23 EAST FIFTH NORTH STREET
LLL L/L LLL LLL LLL
^JTRAILER
HOUSE-
15-23
11-14 \ TRAILER
/HOUSE
12-13
TRAILER
HOUSE
12-13
TRAILER
HOUSE TRAILER
12-14 HOUSE
12-13
o
12-15*
12-15
2-15* TRAILER
•HOUSE
12-14 12-15*
TRAILER
HOUSE
12-14
X *
SHEO
SHED
11-12 TRAILER
HOUSE
12-14
V-TRAILER
HOUSE
12-14 15-23 A X 6
0$ 12-15* ONE STORY
FRAME HOUSE
WITH CELLAR
12-14
v-l
15-23
RDC
SHED
2-13
7-7
L
SCALE IN FEET
20 10 0 20 40
U \FAS\0J3\0003\ftu0080«v 07/29/9« 07.43om T507S0 NORTH
©
<D
tv.vj
12-15
EH
V-1
16-17
LEGEND.
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN luR/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE —RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE—RATE RANGE
RADON DECAY-PRODUCT CONCENTRATION
MEASUREMENT LOCATION
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
OAK RIDGE NATIONAL LABORATORY DATA
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT, UTILITY LOCATION PLAT. OR OTHER IMPROVEMENT SURVEY
PLAT AND IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE. BUILDING, OR OTHER FUTURE IMPROVEMENT LINES
U.S. DEPARTMENT OF ENERGY
GRAM JUNCTION PROJECTS OFflCC. COLORA00
MQJ. USD.
i' 480 AND 496 NORTH MAIN ST
MONTICELLO, UTAH
MS-00B06-CS
12 14 16 18 20 22 24 26 28 30 32 34 36 38 40 42 44 46
3-C00806-V1 ,
48 5'
OAK RIDGE NATIONAL LABORATORY
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
FOR THE U.S. DEPARTMENT OF ENERGY
PHONE: [phone]
FAX: [phone]
POST OFFICE BOX 2567
GRAND JUNCTION. COLORADO 81502
NOV ? 7 I996
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by the U.S.
Department of Energy for Residual Radioactive Material at Formerly Utilized Sites Remedial
Action Program (FUSRAP) and Remote Surplus Facilities Management Program Sites (SFMP)
[Revision 2, March 1987]. This evaluation is based on an independent verification review of the
Remedial Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment of the
22*Ra concentration in the soil, indoor radon daughter concentration, and indoor gamma exposure
rates at this property.
This property is recommended for certification by the U.S. Department of Energy.
Sincerely,
i>£w
Gretchen A. Pierce
MVP/TVC Project Manager
Environmental Assessment Group
MS00806-CS
480 and 496 North Main Street
Monticello. Utah 84535

Same
Location Number:
Location Address:
Property Owner:
Owner Address:
Tenant Name:
Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
480 AND 496 NORTH MAIN STREET
MONTICELLO, UTAH (MS00806-CS)
S. M. Smith
November 1996
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81503
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGiMENTS vii
ABSTRACT..... ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 3
REFERENCES 6
iii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 4
2. Results of ORNL analysis of the RAC soil samples from 480 and 496 North Main Street,
Monticello, Utah (MS00806-CS) 5
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site Decommissioning
Projects, U.S. Department of Energy. The author wishes to acknowledge M. K. Jensen for analysis
of soil samples and J. R. Sauvage and A. R. Jones for technical reviews.
vii
ABSTRACT
In 1980, the site of a vanadium and uranium mill at Monticello, Utah, was accepted into the
U.S. Department of Energy (DOE) Surplus Facilities Management Program, with the objectives of
restoring the government-owned mill site to safe levels of radioactivity, disposing of or containing
the tailings in an environmentally safe manner, and performing remedial actions on off-site (vicinity)
properties that had been contaminated by radioactive material resulting from mill operations. During
1994, the Remedial Action Contractor (RAC) designated by DOE, performed remedial action on the
vicinity property at 480 and 496 North Main Street, Monticello, Utah. The Environmental Technol-
ogy Section (ETS) of Oak Ridge National Laboratory was assigned the responsibility of verifying
the data supporting the adequacy of remedial action and confirming the site's compliance with DOE
guidelines. The ETS found that the site successfully meets the DOE remedial action objectives.
Procedures used by the ETS are described in the Environmental Technology Section Procedures
Manual (ORNL 1993).
ix
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 480 AND 496 NORTH MAIN STREET
MONTICELLO, UTAH (MS00806-CS)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the United States (U.S.) government through
the Defense Plant Corporation to provide vanadium during World War II. Various government
agencies operated the mill until 1947. In 1948, the Atomic Energy Commission (AEC) obtained the
mill and operated it under contract through 1959 to provide both uranium and vanadium. Mill
operations were tenriinated on January 1, 1960. In 1961, the mill tailings piles were leveled and
graded, covered with rock and soil, and seeded with native grasses. During 1974 and 1975, the ore
stockpiles were removed from the site and the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city of
Monticello, in San Juan County, Utah. The site is bordered on the south and southeast by land held
by the U.S. Bureau of Land Management. Other boundaries are the city of Monticello and private
property.
During the AEC era, the mill processed approximately one million tons of uranium ore. Vana-
dium and uranium were the only substances extracted in the milling process. Other constituents of
the ore remained in the tailings and were not separated prior to disposal. During the years of active
mill operation, the mill tailings were normally moist, so erosion was minimal. However, throughout
the mill's operating period, area residents used these tailings as till material and as aggregate in
mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy (DOE) initiated
the Surplus Facilities Management Program (SFMP) in 1978 to ensure the safe caretaking and de-
commissioning of government facilities that had been retired from service but still had radioactive
contamination. In 1980, the mill site at Monticello was accepted into the SFMP, and the Monticello
Remedial Action Project (MRAP) was established to restore the government-owned mill site to safe
levels of radioactivity, to dispose of or contain the tailings in an environmentally safe manner, and
to perform remedial actions on off-site (vicinity) properties that had been contaminated by radio-
active material resulting from mill operations. The Monticello mill site and the tailings remain in
the custody of the DOE Grand Junction, Colorado, Projects Office. In 1983, remedial actions for
vicinity properties were separated from MRAP with establishment of the Monticello Vicinity Proper-
ties (MVP) Project (US DOE 1990b).
"The verification of remedial action was performed by members of the Environmental Assessment Group in the Environmental
Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE contract DE-AC05-
960R22464 with Lockheed Martin Energy Research Corporation.
2
During 1994, the Remedial Action Contractor (RAC) designated by DOE, performed remedial
action on the vicinity property that is the subject of this report, a trailer park located at 480 and 496
North Main Street, Monticello, Utah. The remedial action plan required excavation of all exterior
contamination. When the excavation was completed, the property was resurveyed, including soil
sampling, to ensure the removal of all contamination, backfilled with uncontaminated material, and
restored to a condition comparable to that which existed prior to remedial action (Geotech 1996).
DOE adopted a policy to assign an independent contractor to verify the data supporting the
adequacy of remedial action and to confirm the site's compliance with DOE guidelines. The
Environmental Technology Section (ETS) of Oak Ridge National Laboratory (ORNL) has been
assigned the responsibility of this task at the 480 and 496 North Main Street site. This report
describes the methods and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available documentation
adequately and accurately describes the post-remedial-action radiological conditions of the entire
property that is to be certified and (2) that the remedial action reduced contamination to below
applicable DOE guidelines (US DOE 1990a).
Document Reviews
Review of the RAC property completion report (Geotech 1996) indicates the property was reme-
diated as evaluated by DOE on the basis of U.S. Environmental Protection Agency standards and
the DOE guidelines (US DOE 1990a). Excess residual radioactive materials were present, thus it
was appropriate to designate this property for remedial action. (Using streamlined remedial action
procedures).
The pre-remedial-action survey performed by the RAC identified 3 yd3 of mill tailings 6 to 12
inches deep. During the actual removal process, a total of 2 yd3 of contaminated earth and uranium
mill tailings, 6 to 18 inches deep, were removed from a 6 m2 area.
The RAC performed a post-excavation survey prior to backfilling the excavated areas. This
survey consisted of gamma scans with a scintillometer of the ground level of the structure, a surface
scan ofthe exterior, and soil sampling. A soil sample representative of the bottom 15-cm (6-in.) soil
layers ofthe excavated verification area was collected and blended to form a representative com-
posite soil sample.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation levels have
not been subtracted. Similarly, background concentrations have not been subtracted from radionu-
clide concentrations in soil samples. Applicable DOE guidelines for protection against radiation are
given in Table 1.
Gamma Measurements
Gamma exposure rate measurements taken by the RAC at the ground-level ofthe residence
ranged from 11 to 14 uR/h. Exterior surface gamma measurements taken from the excavated areas
prior to backfilling ranged from 15 to 23 uR/h.
Soil Sample Analysis
Prior to backfilling, the RAC collected an individual soil sample representative of the excavated
area from the bottom 15-cm (6-in.) soil layers. This sample was blended to form a composite soil
sample representative of an average over the exterior verification area. The RAC's analysis of this
sample showed a ^Ra concentration of 3.1 pCi/g. ORNL ETS obtained this sample and performed
a confirmatory analysis which showed a 226Ra concentration of 4.2 pCi/g. These values are below
the DOE guideline value of 15 pCi/g for soil layers >15 cm below the surface. Gamma ranges and/or
soil sample results demonstrate compliance to the DOE Hot Spot Guidelines for areas <25 m2 (Table
1). Results ofthe RAC and ORNL soil sample analyses are given in Table 2.
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were determined by the
Alpha-track method. To monitor radon levels, the RAC placed three alpha-track detectors on the
ground floor ofthe house located on this property for a period of approximately one year (from
October 11,1994 to October 10,1995). The average annual working level (WL) of radon progeny
concentration, as determined by the TechVOps-Landauer Corporation, was 0.0050, which is below
the 0.03-WL guideline given in Table 1.
CONCLUSION
Results of RAC soil sample analysis and confirmatory split soil sample analysis by ORNL,
show that radionuclide concentrations are within applicable DOE guidelines. Based on the results
of the post-remedial-action data, which are confirmed by the verification assessment data, these
radiological measurements fall below the limits prescribed by DOE guidelines. It is concluded that
the site successfully meets the DOE remedial action objectives.
4
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Radionuclide con-
centrations in soil
for Hot Spot areas
Exposure to M2Rn
progeny
Maximum permissible con-
centration of 226Ra in soil
above background levels,
averaged over a 100-m2
area
Maximum Permissible con-
centration of Ra226 in soil
above background level, for
areas less than 25 m2
Average annual radon
progeny concentration
(including background)
5 pCi/g averaged over the first 15 cm
of soil below the surface; 15 pCi/g
when averaged over 15-cm-thick soil
layers more than 15 cm below the
surface
Ra226 concentrations, in any surface
or subsurface area less than 25 m2, is
below the guideline by a factor of
(100/A),/4, where A is the area ofthe
elevated region
0.03 WL
(US DOE 1990a)
5
Table 2. Results of ORNL analysis ofthe RAC soil samples from
480 and 496 North Main Street, Monticello, Utah (MS00806-CS)
Ra concentration (pCi/g)
ORNL RAC
sample sample Depth ORNL RAC
No." No? £crn]
XI NCA953 >15 4.2 3.1
" An X-type sample is a split of the sample taken by the remedial action contractor.
* Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated areas were taken by
the RAC, and these samples were blended to form a composite soil sample, which represents an average
over one of the verification areas.
6
REFERENCES
Geotech 1996. Property Completion Report for Monticello Vicinity Property Remedial Action for
DOE ID NO: MS00806-CS, Address: 480 and 496 North Main Street, Monticello, Utah 84535,
RUST Geotech, Grand Junction, Colorado, August 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment Group)
Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National Laboratory, Grand
Junction, Colorado.
US DOE 1990a. Verification and Certification Protocol for the Office of Environmental Restoration,
Formerly Utilized Sites Remedial Action Programs and Decontamination and Decommissioning
Program. Revision 3, November 1990. U.S. Department of Energy, Washington, D.C.
US DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision and Record
of Decision Summary. U.S. Department of Energy, Grand Junction Projects Office, Grand Junction,
Colorado.
DOE ID No.: MS-00831-RS
Property Address: 432 West Center Street
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech of Energy (DQE)
YES NO NOT TAKEN YES NO NOT TAKEN
Ra-226 is <. 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [ ]
[X]* [ ] [ 1 L*l [ ] [ ]
Ra-226 is ^ 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2. [X] [ ] [ ] W [ ] [ ]
In-situ [ ] Lab [X]
Interior gamma is £ 20 jt/R/h
above background in any
occupied or habitable
structure. [X] [ ] [ ] [XI I I I I
The radon decay-product
concentration in any
occupied or habitable
structure is <; 0.02
working level or, at
most, 0.03 working level. [X] [ ] [ ] L>j [ ] [ ]
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21. [ ] [X] [ ] [ ] [^ I ]
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987). [X] [ ] [ ] [Xl [ ] [ ]
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of oamma
exposure rates that do not exceed 30 percent above normal background.
Ililllllllll Ililllllllll
SFCERTIFED SFMS-00831
DOE ID No.: MS-00831-RS
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
7 anda usby
Manager, Monticello Programs
Rust Geotech
Date
DOE EVALUATION
bO Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
CeVtificatfoTT Official"'
U.S. Department of Energy
£5 Au. U
Date —'
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
DOE ID NO.: MS-00831-RS
ADDRESS: 432 WEST CENTER STREET
MONTICELLO, UTAH 84535
MARCH 1996
Prepared for
U.S. Department of Energy
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
7 VVand^ S. Busfiy
Manager, Monticello Programs
FOR
by
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.1.3 Radon Decay-Product Concentration (RDC) Measurement .... 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
i
DOE ID No.: MS-00831-RS
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Inclusion Survey Contractor. DOE reviewed
these evaluation results and determined that the property contained mill
tailings (residual radioactive material) exceeding DOE hot spot criteria.
The Remedial Action Contractor was notified of the inclusion of this
property into the MVP Project and was authorized by DOE to conduct
remedial action as required to bring the property into conformance with
EPA standards and DOE hot spot criteria.
1
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
Property Address:
Property Owner:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
DOE ID No.: MS-00831-RS
MS-00831-RS
Location No. M-432-3; beginning 120 feet
east of the NE corner of Lot 40, Blue
Mountain Heights Subdivision No. 2, south
150 feet, east 110 feet, north 150 feet,
west 110 feet to the beginning, City of
Monticello, County of San Juan, State of
Utah
432 West Center Street
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
February 26, 1991
Rust Geotech
Not applicable: streamlined remediation
procedures were followed
Not applicable: streamlined remediation
procedures were followed
July 28, 1992
July 29, 1992
Interior: 0 cubic yards
Exterior: 0.5 cubic yards
1.2 square meters (m2)
March 1996
2
DOE ID No.: MS-00831-RS
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
Streamlined remediation procedures were followed for this property.
The remedial action plan involved removal of exterior residual radioactive
material (Appendix Figure 2.1). Once excavation was complete, the
affected area was resurveyed for possible remaining residual radioactive
material and, upon attaining satisfactory results, was backfilled with
uncontaminated material. The property was restored to a physical
condition comparable to that which existed prior to remedial action
activities.
2.2 Previously Unidentified Contamination
The radiological assessment identified approximately 0.3 cubic yards of
contamination, 6 inches deep, within the property. The remedial action
process included the removal of approximately 0.5 cubic yards of residual
radioactive material, 12 inches deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID No.: MS-00831-RS
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by the Remedial Action
Contractor during July 1992. Appendix Figure 2.1 shows the
extent of assessed contamination and identifies the area
recommended to undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, an individual soil sample representative
of the 6-inch-thick soil layer at the bottom of the excavation was
collected (Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 12 to 18 microroentgens per
hour (//R/h), as indicated on Appendix Figure 2.1. The result of
analysis for radium-226 in one individual soil sample was
2.1 picocuries per gram (pCi/g), as indicated in Appendix
Table 3.1.
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on measurements representing an annual average, the RDC
was 0.0077 working level (WL), as indicated in Appendix
Table 3.2. Appendix Figure 2.1 shows the measurement location
on the ground floor (the lowest habitable level of the structure).
4
DOE ID No.: MS-00831-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at 432 West Center Street, in
Monticello, Utah, is recommended for certification as required by DOE
guidelines, and the appropriate records should be documented.
Certification Data Summary
Applicability
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Standards
Shall not exceed 20 //R/h
above background.*
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Survey Rssults
Range for the ground
floor was 12 to 14//R/h.
Annual average was
0.0077 WL.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
< 5 pCi/g above
background.**
Soil sample result was
2.1 pCi/g.**
*The background exposure rate is approximately 13 //R/h.
The background radium-226 concentration is approximately 2.0 pCi/g.
* *The hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-00831-RS
4.0 APPENDIX
Appendix Tables:
Table 3.1 Post-Excavation Sample/Measurement Results
Table 3.2 Radon Decay-Product Concentration Measurement Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
MRW-.01-24-96
MS-00831.RS WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00831-RS
Address: 432 West Center Street, Monticello, Utah
Exposure Soil Sample Meas. Radium-226
Area Rate (//R/h) Number Method" (pCi/g)
V-1 18 R1 OCS 2.1
See Appendix Figure 2.1 for the verification area.
"OCS = Opposed Crystal System
7
Table 3.2
Radon Decay-Product Concentration Measurement Results
DOE ID No.: MS-00831-RS
Address: 432 West Center Street, Monticello, Utah
Instrument Type: Landauer Radtrak Detector
Detector
Number Start Date End Date
Tracks Per
mm2
Radon
Concentration
(pCi/L)
Working
Level
3892208
3892187
3892154
08-18-94
08-18-94
08-18-94
07-25-95
07-25-95
07-25-95
12.3
14.5
13.2
1.42
1.68
1.53
0.0071
0.0084
0.0077
Annual Average: 0.0077
See Appendix Figure 2.1 for the measurement location.
8
10
•30
12 1 4 16 18 20 22 24 26 28 30 32 34 36 38 40
30
-vV--H-
28
26
24
22
20
18
16
14
12
12-15 12-15
SHED
112-15
v-1
18/iR/h
12
^-^ ONE STORY
(RDC) FRAME HOUSE
v—y W/CRAWL SPACE
12-14
12-15
Y
777 .r77-
WEST CENTER STREET
/// LLL.
NORTH
©
®
nv.\vi
LV.vj
12-15
M:\FAS\033\0003\RM00831V 02/26/96 12:04pm T50780
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT. UTILITY LOCATION PLAT. OR OTHER IMPROVEMENT SURVEY
PLAT AND IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE, BUILDING, OR OTHER FUTURE IMPROVEMENT LINES.
10
10 12 1 4 16 18 20 22 24 26 28
12
v-1
16-17
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN /xR/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE RATE
RADON DECAY-PRODUCT CONCENTRATION
MEASUREMENT LOCATION
20 10
SCALE IN FEET
20 40
28
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
MStOCNCe-HO. Of OCCUPANTS
HON-RESfDCHCC-UAN-HRS./WK.
INSTRUMENT NO.
SURVEY OATC
U.S. DEPARTMENT OF ENERGY
GRANO JUNCTION PROJECTS OFFICE. COLORADO
OCSICHCI M.
CHICKED OJ^
PROJ. CNSR.
SUBMITTED
432 WEST CENTER STREET
MONTICELLO, UTAH
APPROVAL
Rust Oeotech
"Birr APPROVAL OOt •SATT
DOE ID NO. MS-00831-RS
DWC.NO. 3-B00831 - V1 1 ~ 1
26
24
22
20
18
16
14
12
10
30 32 34 36 38 40
OAK RIDGE NATIONAL LABORATORY PHONE: (970) 24M200
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION FAX: (970) 24B4220
FOR THE U.S. DEPARTMENT OF ENERGY
POST OFFICE BOX 2567
GRAND JUNCTION, COLORADO 81502
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by the
U.S. Department of Energy for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program (FUSRAP) and Remote Surplus Facilities Management Program
Sites (SFMP) [Revision 2, March 1987]. This evaluation is based on an independent
verification review of the Remedial Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment of
the 226Ra concentration in the soil, indoor radon daughter concentration, and indoor gamma
exposure rates at this property.
Therefore, this property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
Location Number:
Location Address:
Property Owner:
Owner Address:
MSQQ831-RS
432 West Center Street
Monticello. Utah 84535

Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
432 WEST CENTER STREET
MONTICELLO, UTAH (MS00831-RS)
S. M. Smith
June 1996
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 3
REFERENCES 5
iii
LIST OF TABLES
Applicable guidelines for protection against radiation
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site
Deconumssioning Projects, U.S. Department of Energy. The author wishes to
acknowledge M. K. Jensen and N. F. Kirby for technical reviews.
vii
ABSTRACT
In 1980 the site of a vanadium and uranium mill at Monticello, Utah, was accepted
into the U.S. Department of Energy's (DOE's) Surplus Facilities Management Program,
with the objectives of restoring the government-owned mill site to safe levels of radio-
activity, disposing of or containing the tailings in an environmentally safe manner, and
performing remedial actions on off-site (vicinity) properties that had been contaminated
by radioactive material resulting from mill operations. During 1992, RUST Geotech, the
remedial action contractor designated by DOE, performed remedial action on the vicinity
property at 432 West Center Street, Monticello, Utah. The Environmental Technology
Section (ETS) of Oak Ridge National Laboratory was assigned the responsibility of
verifying the data supporting the adequacy of remedial action and confirming the site's
compliance with DOE guidelines. The ETS found that the site successfully meets the
DOE remedial action objectives. All deficiencies noted in the initial review have been
resolved with additional documentation to the property folio and the revised completion
report. Procedures used by the ETS are described in the Environmental Technology
Section Procedures Manual (ORNL 1993).
ix
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 432 WEST CENTER STREET
MONTICELLO, UTAH (MS00831-RS)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the U.S. government through the
Defense Plant Corporation to provide vanadium during World War II. Various govern-
ment agencies operated the mill until 1947. In 1948 the Atomic Energy Commission
(AEC) obtained the mill and operated it under contract through 1959 to provide both
uranium and vanadium. Mill operations were terminated on January 1,1960. In 1961 the
mill tailings piles were leveled and graded, covered with rock and soil, and seeded with
native grasses. During 1974 and 1975, the ore stockpiles were removed from the site, and
the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city
of Monticello, in San Juan County, Utah. The site is bordered on the south and southeast
by land held by the U.S. Bureau of Land Management. Other boundaries are the city of
Monticello and private property.
During the AEC era, the mill processed approximately one million tons of uranium
ore. Vanadium and uranium were the only substances extracted in the milling process.
Other constituents of the ore remained in the tailings and were not separated prior to dis-
posal. During the years of active mill operation, the mill tailings were normally moist, so
erosion was minimal. However, throughout the mill's operating period, area residents
used these tailings as fill material and as aggregate in mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy
(DOE) initiated the Surplus Facilities Management Program (SFMP) in 1978 to ensure
the safe caretaking and decommissioning of government facilities that had been retired
from service but still had radioactive contamination. In 1980 the mill site at Monticello
was accepted into the SFMP, and the Monticello Remedial Action Project (MRAP) was
established to restore the government-owned mill site to safe levels of radioactivity, to
dispose of or contain the tailings in an environmentally safe manner, and to perform
remedial actions on off-site (vicinity) properties that had been contaminated by
radioactive material resulting from mill operations. The Monticello mill site and the
tailings remain in the custody of the DOE Grand Junction, Colorado, Projects Office. In
1983 remedial actions for vicinity properties were separated from MRAP with
establishment ofthe Monticello Vicinity Properties (MVP) Project (U.S. DOE 1990b).
*The verification of remedial action was performed by members of the Environmental Assessment Group in the
Environmental Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE
contract DE-AC05-96OR22464 with Lockheed Martin Energy Research Corporation.
2
During 1992, RUST Geotech Inc. (Geotech), the remedial action contractor (RAC)
designated by DOE, performed remedial action on the vicinity property that is the subject
of this report, a private residence located at 432 West Center Street, Monticello, Utah.
The remedial action plan required excavation of all exterior contamination. When the
excavation was completed, the property was resurveyed, including soil sampling, to
ensure the removal of all contamination, backfilled with uncontaminated material, and
restored to a condition comparable to that which existed prior to remedial action (Geotech
1996).
The DOE adopted a policy to assign an independent contractor to verify the data
supporting the adequacy of remedial action and to confirm the site's compliance with
DOE guidelines. The Environmental Technology Section (ETS) of Oak Ridge National
Laboratory (ORNL) has been assigned the responsibility of this task at the 432 West
Center Street site. This report describes the methods and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available docu-
mentation adequately and accurately describes the post-remedial-action radiological
conditions of the entire property that is to be certified and (2) that the remedial action
reduced contamination to below applicable DOE guidelines (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1996) in-
dicates the property was remediated as evaluated by DOE on the basis of Environmental
Protection Agency standards and the DOE guidelines (DOE 1990a). Excess residual
radioactive materials were present, thus it was appropriate to designate this property for
remedial action using streamlined remedial action procedures.
The pre-remedial-action survey performed by Geotech identified 0.3 yd3 of mill
tailings 6 inches deep. During the actual removal process, a total of 0.5 yd3 of con-
taminated earth and uranium mill tailings, 12 inches deep, were removed from a 1.2 m2
area.
A post-excavation survey was performed by Geotech prior to backfilling the exca-
vated area. This survey consisted of gamma scans with a scintillometer of the ground
level ofthe structure, a surface scan of the exterior, and soil sampling. An individual soil
sample representative of the bottom 15-cm (6-in.) soil layer of the excavated verification
area was collected. The RAC is unable to locate or inadvertently disposed of the samples
requested for ORNL confirmatory analysis.
3
All measurements presented in this report are gross readings. Background radiation
levels have not been subtracted. Similarly, background concentrations have not been sub-
tracted from radionuclide concentrations in soil samples. Applicable DOE guidelines for
protection against radiation are given in Table 1.
Gamma Measurements
Gamma exposure rate measurements taken by Geotech at the ground-level of the
residence ranged from 12 to 14 uR/h. The exterior surface gamma measurement taken
from the excavated area prior to backfilling was 18 uR/h.
Soil Sample Analysis
Prior to backfilling, Geotech collected an individual soil sample representative of the
excavated area from the bottom 15-cm (6-in.) soil layer. Geotech's analysis of this sample
showed a ^Ra concentration of 2.1 pCi/g. ORNL ETS was unable to obtain this sample
for confirmatory analysis. This value is below the EPA standard value of 15 pCi/g for soil
layers > 15 cm below the surface. Gamma ranges and/or soil sample results demonstrate
compliance to the DOE Hot Spot Guidelines for areas <25 m2 (Table 1).
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were deter-
mined by the Alpha-track method. To monitor radon levels, Geotech placed three alpha-
track detectors on the ground floor of the residence located on this property for a period
of approximately one year (from August 18, 1994 to July 25, 1995). The average annual
working level (WL) of radon progeny concentration, as determined by the Tech./Ops-
Landauer Corporation, was 0.0077, which is well below the 0.03-WL guideline given in
Table 1.
CONCLUSION
Results of Geotech soil sample analysis show that radionuclide concentrations are
within applicable DOE guidelines. Based upon the results of the post-remedial-action
data, which are confirmed by the verification assessment data, these radiological measure-
ments fall below the limits prescribed by DOE guidelines. All deficiencies noted in the
initial review have been identified by the RAC and corrected in the revised completion
report as discussed in a meeting between Geotech and ORNL on May 31, 1996. It is
concluded that the site successfully meets the DOE remedial action objectives.
4
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of 226Ra in soil
above background levels,
averaged over a 100-m2 area
5 pCi/g averaged over the
first 15 cm of soil below the
surface; 15 pCi/g when ave-
raged over 15-cm-thick soil
layers more than 15 cm
below the surface
Radionuclide
concentrations in soil
for Hot Spot areas
Exposure to 222Rn
progeny
Maximum Permissible
concentration of Ra226 in soil
above background level, for
areas less than 25 m2
Average annual radon proge-
ny concentration (including
background)
Ra226 concentrations, in any
surface or subsurface area
less than 25 m2, is below the
guideline by a factor of
(1007A),/l, where A is the
area of the elevated region
0.03 WL
(DOE 1990a)
5
REFERENCES
Geotech 1996. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00831-RS, Address: 432 West Center Street, Monticello,
Utah 84535, Geotech, Grand Junction, Colorado, March 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
U.S. DOE 1990a. Verification and Certification Protocol for the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination
and Decommissioning Program, Revision 3, November 1990. U.S. Department of
Energy, Washington, D.C.
U.S. DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision
and Record of Decision Summary. U.S. Department of Energy, Grand Junction Projects
Office, Grand Junction, Colorado.
DOE ID No.: MS-00848-MR
Property Address: 301B Silverstone West Lane
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech of Energy (DOE)
Ra-226 is < 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [ )
Ra-226 is < 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2.
In-situ [ ] Lab [X]
Interior gamma is < 20 //R/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is <, 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21,
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
YES NO NOT TAKEN
[/} [ ] [ ]
[X] [ ] [ ] ly] I ]
I ] I ] tX] [ ] [ ]
(No Habitable Structures)
[ ] [X] [ ]
[X] [ ] [ ]
[ I
[ ] [ ] [X] [ ] [ ]
(No Habitable Structures)
I ] I/] I ]
[)/][] I ]
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of oamma
exposure rates that do not exceed 30 percent above normal background.
•llllllllll IllPlllliU
SFCERTIFED SFMS-00124 .M
DOE ID No.: MS-00848-MR
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Wanda S^Bus /anda SyBusby7 Date
Managerf Monticello Programs
Rust Geotech
DOE EVALUATION
V^] Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Certification Official Date
U.S. Department of Energy
uL
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00848-MR
ADDRESS: 301B SILVERSTONE WEST LANE
MONTICELLO, UTAH 84535
APRIL 1996
Prepared for
U.S. Department of Energy
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
by
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.1.3 Radon Decay-Product Concentration (RDC) Measurement .... 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
DOE ID No.: MS-00848-MR
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Inclusion Survey Contractor. DOE reviewed
these evaluation results and determined that the property contained mill
tailings (residual radioactive material) exceeding EPA standards. The
Remedial Action Contractor was notified of the inclusion of this property
into the MVP Project and was authorized by DOE to conduct remedial
action as required to bring the property into conformance with EPA
standards and DOE hot spot criteria.
1
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
Property Address:
Property Owners:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
DOE ID No.: MS-00848-MR
MS-00848-MR
Beginning at the SE corner of Lot 6,
Silverstone West Subdivision; west
90.5 feet, south 93 feet, northeasterly in a
straight line to the point of beginning, City
of Monticello, County of San Juan, State of
Utah
301B Silverstone West Lane
Monticello, Utah 84535

Major Residential (MR)
Oak Ridge National Laboratory
January 23, 1991
Rust Geotech
November 19, 1993
Diamond Back Services, Inc.
9861 Titan Park Circle
Littleton, Colorado
May 24, 1994
June 30, 1994
Interior: 0 cubic yards
Exterior: 9 cubic yards
38 square meters (m2)
April 1996
2
DOE ID No.: MS-00848-MR
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of exterior residual radioactive
material (Appendix Figure 2.1). Once excavation was complete, the
affected area was resurveyed for possible remaining residual radioactive
material and, upon attaining satisfactory results, was backfilled with
uncontaminated material. The property was restored to a physical
condition comparable to that which existed prior to remedial action
activities.
2.2 Previously Unidentified Contamination
The radiological assessment identified contamination, ranging from 6 to
12 inches deep, within the property. The quantity of contamination for
this property was not specified because it was assessed as part of
MS-00124-MR. The remedial action process included the removal of
approximately 9 cubic yards of residual radioactive material, ranging from
6 to 12 inches deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID No.: MS-00848-MR
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by the Remedial Action
Contractor during August 1990, as described in the final REA
dated November 1993. Appendix Figure 2.1 shows the extent of
assessed contamination and identifies the area recommended to
undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the excavation were
collected. These samples were blended to form a composite
sample representing the verification area (Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 14 to 20 microroentgens per
hour (/yR/h), as indicated on Appendix Figure 2.1. The result of
analysis for radium-226 in one composite soil sample was
3.6 picocuries per gram (pCi/g), as indicated in Appendix
Table 3.1.
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
RDC measurements were not taken on this property because there
were no habitable structures.
4
DOE ID No.: MS-00848-MR
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at 301B Silverstone West Lane, in
Monticello, Utah, is recommended for certification as required by DOE
guidelines, and the appropriate records should be documented.
Certification Data Summary
Applicability Standards Survey Results
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 20 jt/R/h
above background.
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Shall not exceed 5 pCi/g
above background* in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background* in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
Not applicable: no
habitable structure.
Not applicable: no
habitable structure.
< 5 pCi/g above
background.
Soil sample result was
3.6 pCi/g.
*The background radium-226 concentration is approximately 2.0 pCi/g.
The hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-00848-MR
4.0 APPENDIX
Appendix Table:
Table 3.1 Post-Excavation Sample/Measurement Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
SJW:03-13-96
MS-00124-MR WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00848-MR
Address: 301B Silverstone West Lane, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range U/R/h) Ticket No. Method" (pCi/g)
V-1 14-20 NAY 195 OCS 3.6
See Appendix Figure 2.1 for the verification area.
"OCS = Opposed Crystal System
7
10
30
28
26
24
22
20
18 -
16
14
12
12 14 16
i—r
20 22 24 26 28 30 32 34 36 38 40
n—r~ i—i—i—i—r i—i—i—1—•30 i—r
SILVERSTONE WEST LANE
\
\ 14-17
\
\
\
12
\ v-i
14-20
12)
\ 14-17
YJULXJP^
Y
SCALE IN FEET
20 10 0 20 40
M:\FAS\033\0003\RM00848V 04/02/96 2:09pm T50780
C£ THIS DRAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT. UTILITY LOCATION PLAT, OR OTHER IMPROVEMENT SURVEY
PLAT AND IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE. BUILDING. OR OTHER FUTURE IMPROVEMENT LINES.
10 I I 1 I
®
Lv.vj
12-15
12
V-1
16-17
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN fiR/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE-RATE RANGE
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
RESIDENCE-NO. OF OCCUPANTS
NON-RESIOENCE-UAN-HRS./*K.
INSTRUUENT NO.
VERIFICATION
SY CK. A.E. APP. NO. DATE 8T CK. A.E. APP.
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE, COLORADO
32 ORAWK ^--J-
CHECHEOQx- \
PROJ. ENCTi.
0V(
9 301 B SILVERSTONE WEST LANE
MONTICELLO, UTAH
MKT Rust Qeotech
OATC I APPROVAL OOE -aw
DOEIDNO. MS-00848-MR
OWO.NO. 3-B00848-V1 ,„ 1 or 1
28
26
24
22
20
18
- 16
14
12
10
10 12 1 4 16 18 20 22 24 26 28 30 32 34 36 38 40
OAK RIDGE NATIONAL LABORATORY PHONE: (BTO) 24M2OO
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION FAX: [phone]
FOR THE US. DEPARTMENT OF ENERGY
POST OFFICE BOX 2587
GRAND JUNCTION, COLORADO 81502
JUL 3 I 1996
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by
the U.S. Department of Energy for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program (FUSRAP) and Remote Surplus Facilities Management Program
Sites (SFMP) [Revision 2, March 1987]. This evaluation is based on an independent verifi-
cation review of the Remedial Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment of
the ^Ra concentration in the soil at this property.
This property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
Location Number:
Location Address:
Property Owner:
Owner Address:
MS00848-MR
301B Silverstone West Lane
Monticello, Utah 84535

Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
301B SILVERSTONE WEST LANE
MONTICELLO, UTAH (MS00848-MR)
N. F. Kirby
July 1996
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
CONCLUSION 3
REFERENCES 6
iii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 4
2. Results of ORNL analysis of Geotech soil samples from 30 IB Silverstone West
Lane, Monticello, Utah (MS00848-MR) 5
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site
Decommissioning Projects, U.S. Department of Energy. The author wishes to
acknowledge M. K. Jensen for analysis of soil samples and M. J. Wilson-Nichols
and A. R. Jones for technical reviews.
vii
ABSTRACT
In 1980 the site of a vanadium and uranium mill at Monticello, Utah, was accepted
into the U.S. Department of Energy's (DOE's) Surplus Facilities Management Program,
with the objectives of restoring the government-owned mill site to safe levels of radio-
activity, disposing of or containing the tailings in an environmentally safe manner, and
performing remedial actions on off-site (vicinity) properties that had been contaminated
by radioactive material resulting from mill operations. During 1994, RUST Geotech, the
remedial action contractor designated by DOE, performed remedial action on the vicinity
property at 301B Silverstone West Lane, Monticello, Utah. The Environmental Technol-
ogy Section (ETS) of Oak Ridge National Laboratory was assigned the responsibility of
verifying the data supporting the adequacy of remedial action and confirming the site's
compliance with DOE guidelines. The ETS found that the site successfully meets the
DOE remedial action objectives. Procedures used by the ETS are described in the
Environmental Technology Section Procedures Manual (ORNL 1993).
ix
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 301B SILVERSTONE WEST LANE
MONTICELLO, UTAH (MS00848-MR)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the U.S. government through the
Defense Plant Corporation to provide vanadium during World War II. Various govern-
ment agencies operated the mill until 1947. In 1948 the Atomic Energy Commission
(AEC) obtained the mill and operated it under contract through 1959 to provide both
uranium and vanadium. Mill operations were terminated on January 1, 1960. In 1961 the
mill tailings piles were leveled and graded, covered with rock and soil, and seeded with na-
tive grasses. During 1974 and 1975, the ore stockpiles were removed from the site, and
the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city
of Monticello, in San Juan County, Utah. The site is bordered on the south and southeast
by land held by the U.S. Bureau of Land Management. Other boundaries are the city of
Monticello and private property.
During the AEC era, the mill processed approximately one million tons of uranium
ore. Vanadium and uranium were the only substances extracted in the milling process.
Other constituents of the ore remained in the tailings and were not separated prior to dis-
posal. During the years of active mill operation, the mill tailings were normally moist, so
erosion was minimal. However, throughout the mill's operating period, area residents
used these tailings as fill material and as aggregate in mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy
(DOE) initiated the Surplus Facilities Management Program (SFMP) in 1978 to ensure
the safe caretaking and decommissioning of government facilities that had been retired
from service but still had radioactive contamination. In 1980 the mill site at Monticello
was accepted into the SFMP, and the Monticello Remedial Action Project (MRAP) was
established to restore the government-owned mill site to safe levels of radioactivity, to
dispose of or contain the tailings in an environmentally safe manner, and to perform reme-
dial actions on off-site (vicinity) properties that had been contaminated by radioactive ma-
terial resulting from mill operations. The Monticello mill site and the tailings remain in the
custody of the DOE Grand Junction, Colorado, Projects Office. In 1983 remedial actions
for vicinity properties were separated from MRAP with establishment of the Monticello
Vicinity Properties (MVP) Project (U.S. DOE 1990b).
*The verification of remedial action was performed by members of the Environmental Assessment Group in the
Environmental Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE
contract DE-AC05-96OR22464 with Lockheed Martin Energy Research Corporation.
2
During 1994, RUST Geotech Inc. (Geotech), the remedial action contractor (RAC)
designated by DOE, performed remedial action on the vicinity property that is the subject
of this report, a major residential property located at 30 IB Silverstone West Lane,
Monticello, Utah. The remedial action plan required excavation of all exterior contamina-
tion. When the excavation was completed, the property was resurveyed, including soil
sampling, to ensure the removal of all contamination, backfilled with uncontaminated
material, and restored to a condition comparable to that which existed prior to remedial
action (Geotech 1996).
The DOE adopted a policy to assign an independent contractor to verify the data
supporting the adequacy of remedial action and to confirm the site's compliance with DOE
guidelines. The Environmental Technology Section (ETS) of Oak Ridge National Labor-
atory (ORNL) has been assigned the responsibility of this task at the 301B Silverstone
West Lane site. This report describes the methods and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available doc-
umentation adequately and accurately describes the post-remedial-action radiological
conditions of the entire property that is to be certified and (2) that the remedial action
reduced contamination to below applicable DOE guidelines (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1996) in-
dicates the property was remediated as evaluated by DOE on the basis of Environmental
Protection Agency standards and the DOE guidelines (DOE 1990a). Excess residual
radioactive materials were present, thus it was appropriate to designate this property for
remedial action.
The pre-remedial-action survey performed by Geotech identified mill tailings 6 to
12 inches deep. This property was assessed as part of MS00124-MR, therefore, the
quantity of material assessed is not available. During the actual removal process, a total
of 9 yd3 of contaminated earth and uranium mill tailings, 6 to 12 inches deep, were re-
moved from a 38 m2 area.
A post-excavation survey was performed by Geotech prior to backfilling the exca-
vated areas. This survey consisted of surface gamma scans with a scintillometer of the
exterior and soil sampling. Samples representative of the bottom 15-cm (6-in.) soil layers
of the excavated verification area were collected and blended to form a representative
composite soil sample for the verification area.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation
levels have not been subtracted. Similarly, background concentrations have not been sub-
tracted from radionuclide concentrations in soil samples. Applicable DOE guidelines for
protection against radiation are given in Table 1.
Gamma Measurements
Exterior surface gamma measurements taken from the excavated area prior to back-
filling ranged from 14 to 20 uR/h.
Soil Sample Analysis
Prior to backfilling, Geotech collected soil samples representative of the excavated
area from the bottom 15-cm (6-in.) soil layers. These samples were blended to form a
composite soil sample representative of an average over the exterior verification area.
Geotech's analysis of this sample showed a ^Ra concentration of 3.6 pCi/g. ORNL ETS
obtained this sample and performed a confirmatory analysis which showed a ^Ra concen-
tration of 3.1 pCi/g. These values are below the EPA standard value of 15 pCi/g for soil
layers > 15 cm below the surface. Gamma ranges and/or soil sample results demonstrate
compliance to the DOE Hot Spot Guidelines for areas <25 m2 (Table 1). Results of
Geotech and ORNL soil sample analyses are given in Table 2.
CONCLUSION
Results of Geotech soil sample analysis and confirmatory split soil sample analysis
by ORNL show that radionuclide concentrations are within applicable DOE guidelines.
Based on the results of the post-remedial-action data, which are confirmed by the veri-
fication assessment data, these radiological measurements fall below the limits prescribed
by DOE guidelines. It is concluded that the site successfully meets the DOE remedial
action objectives.
4
Table 1. Applicable guidelines for protection against radiation
Mode of exposure
Radionuclide con-
centrations in soil
Exposure conditions
Maximum permissible con-
centration of ^Ra in soil
above background levels,
averaged over a 100-m2 area
Guideline value
5 pCi/g averaged over the
first 15 cm of soil below the
surface; 15 pCi/g when ave-
raged over 15-cm-thick soil
layers more than 15 cm
below the surface
Ra226 concentrations, in any
surface or subsurface area
less than 25 m2, is below the
guideline by a factor of
(100/A)*, where A is the
area of the elevated region
0.03 WL
Radionuclide con-
centrations in soil
for Hot Spot areas
Maximum Permissible con-
centration of Ra226 in soil
above background level, for
areas less than 25 m2
Exposure to ^Rn
progeny
Average annual radon proge-
ny concentration (including
background)
(DOE 1990a)
5
Table 2. Results of ORNL analysis of Geotech soil samples
from 301B Silverstone West Lane, Monticello Utah (MS00848-MR)
226Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No.° No^ (cm)
XI NAY 195 >15 3.1 3.6
" An X-type sample is a split of the sample taken by the remedial action contractor.
4 Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated areas
were taken by Geotech, and these samples were blended to form a composite soil
sample, which represents an average over one of the verification areas.
6
REFERENCES
Geotech 1996. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00848-MR, Address: 30 IB Silverstone West Lane,
Monticello, Utah 84535, Geotech, Grand Junction, Colorado, April 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
U.S. DOE 1990a. Verification and Certification Protocolfor the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination
and Decommissioning Program, Revision 3, November 1990. U.S. Department of
Energy, Washington, D.C.
U.S. DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision
and Record of Decision Summary. U.S. Department of Energy, Grand Junction Projects
Office, Grand Junction, Colorado.
DOE ID No.: MS-00861-RS
Property Address: 349 Abajo Drive
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech nf Energy (DOE)
Ra-226 is s 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [XV
Ra-226 is < 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2.
In-situ [ ] Lab [X]
Interior gamma is <, 20 //R/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is <, 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21.
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
M [ ] I ]
l>] [ 1 [ }
[/] [ ] I 1
[>] [ ] [ 1
[ ] [>] [ 1
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
fPart of a sample was taken from the too laver. and was lab-analvzed.
Ililllllllll •
SFMS-00013 SFCERTIFED
DOE ID No.: MS-00861-RS
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
^2 /anda S^Busby Date
Manager, Monticello Programs
Rust Geotech
DOE EVALUATION
p<] Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Certification Official Date
U.S. Department of Energy
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
DOE ID NO.: MS-00861-RS
ADDRESS: 349 ABAJO DRIVE
MONTICELLO, UTAH 84535
APRIL 1996
Prepared for
U.S. Department of Energy
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
' Wanda S. Busby
Manager, Monticello Programs
FOR
by
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.1.3 Radon Decay-Product Concentration (RDC) Measurement .... 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
DOE ID No.: MS-00861-RS
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Inclusion Survey Contractor. DOE reviewed
these evaluation results and determined that the property contained mill
tailings (residual radioactive material) exceeding EPA standards. The
Remedial Action Contractor was notified of the inclusion of this property
into the MVP Project and was authorized by DOE to conduct remedial
action as required to bring the property into conformance with EPA
standards and DOE hot spot criteria.
1
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
Property Address:
Property Owners:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
DOE ID No.: MS-00861-RS
MS-00861-RS
Parcel No. A33230364200; beginning
1,028 feet north and 1,999 feet east of the
W4 corner of Section 36, T33S., R23E.,
Salt Lake Base Meridian; north 146 feet,
west 130 feet, south 146 feet, east
130 feet to beginning, City of Monticello,
County of San Juan, State of Utah
349 Abajo Drive
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
August 27, 1991
Rust Geotech
September 14, 1994
Diamond Back Services, Inc.
9861 Titan Park Circle
Littleton, Colorado
May 9, 1995
September 14, 1995
Interior: 0 cubic yards
Exterior: 71 cubic yards
290 square meters (m2)
April 1996
2
DOE ID No.: MS-00861-RS
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of exterior residual radioactive
material (Appendix Figure 2.1). Once excavation was complete, the
affected areas were resurveyed for possible remaining residual radioactive
material and, upon attaining satisfactory results, were backfilled with
uncontaminated material. The property was restored to a physical
condition comparable to that which existed prior to remedial action
activities.
2.2 Previously Unidentified Contamination
The radiological assessment identified contamination, ranging from 6 to
12 inches deep, within the property. The quantity of contamination for
this property was not specified because it was assessed as part of
Group 18. The remedial action process included the removal of
approximately 71 cubic yards of residual radioactive material, ranging
from 6 to 15 inches deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID No.: MS-00861-RS
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by the Remedial Action
Contractor during July 1993, as described in the final REA dated
September 1994. Appendix Figure 2.1 shows the extent of
assessed contamination and identifies the areas recommended to
undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the excavation were
collected. These samples were blended to form composite
samples representing the verification areas (Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 13 to 20 microroentgens per
hour (//R/h), as indicated on Appendix Figure 2.1. The results of
analyses for radium-226 in four composite soil samples ranged
from 1.3 to 1.8 picocuries per gram (pCi/g), as indicated in
Appendix Table 3.1.
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on the DOE-approved abbreviated-measurement method,
the RDC was 0.0020 working level (WL), as indicated in Appendix
Table 3.2. Appendix Figure 2.1 shows the measurement location
on the ground floor (the lowest habitable level of the structure).
RDC measurements were taken before remediation of the property.
4
DOE ID No.: MS-00861-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at 349 Abajo Drive, in Monticello, Utah,
is recommended for certification as required by DOE guidelines, and the
appropriate records should be documented.
Certification Data Summary
Applicability
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Standards
Shall not exceed 20 //R/h
above background.*
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Survey Results
Range for the ground
floor was 13 to 15 //R/h.
Average was 0.0020 WL,
based on the DOE-
approved abbreviated-
measurement method.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
< 5 pCi/g above
background.**
Soil sample results
ranged from 1.3 to
1.8 pCi/g.**
*The background exposure rate is approximately 14//R/h.
The background radium-226 concentration is approximately 2.0 pCi/g.
**The hot spot criteria were met based on gamma scans and/or soil sample results.
A part of sample V-1 was from the 15-cm surface layer.
5
DOE ID No.: MS-00861-RS
4.0 APPENDIX
Appendix Tables:
Table 3.1 Post-Excavation Sample/Measurement Results
Table 3.2 Radon Decay-Product Concentration Measurement
Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
SJW:03-11-96
MS-00861-RS WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00861-RS
Address: 349 Abajo Drive, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range OwR/h) Ticket No. Method" (pCi/g)
V-1 14-20 NCK 644 OCS 1.8
V-2 14-17 NCK 592 OCS 1.5
V-3 14-16 NCK 591 OCS 1.3
V-4 14-16 NCK 590 OCS 1.7
See Appendix Figure 2.1 for the verification areas.
"OCS = Opposed Crystal System
7
Table 3.2
Radon Decay-Product Concentration Measurement Results
DOE ID No.: MS-00861-RS
Address: 349 Abajo Drive, Monticello, Utah
Instrument Type: Landauer Radtrak Detector
Detector
Number Start Date End Date
Radon
Concentration
(pCi/L)
Working
Level
3964141
3964161
3964210
03-06-95
03-06-95
03-06-95
06-06-95
06-06-95
06-06-95
0.48
0.40
0.33
0.0024
0.0020
0.0017
Average: 0.0020
See Appendix Figure 2.1 for the measurement location.
8
23 30
T"
32 34 36 38 40
30
28
26
24
22
20
18 -
16
14
12
Y
10
-LLL /// ABAJO DRIVE /f/
13-16
V-2
14-17
3>A
ONE STORY
FRAME HOUSE
13-15
• ••f
» 8
RDC
6 6 X C
V-1 12
V-1 14-20 15
\A V-3 14-20
.SHED-.v. 14-16
i
mm 12
O
•X
SHED SHED
13_15 15-16 ••v
1m 13-16
\k 6 >:
V-4
14-16
o
13-16
X
SCALE IN FEET
20 10 0 20 40
M:\FAS\033\0003\RM00861V 04/02/96 2:28pm T50780 NORTH
I I
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT. UTILITY LOCATION PLAT, OR OTHER IMPROVEMENT SURVEY
PLAT AND IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE. BUILDING. OR OTHER FUTURE IMPROVEMENT LINES.
©
nv.-TTi
Lv.vj
12-15
12
V-1
16-17
(RDC)
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN /xR/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE-RATE RANGE
RADON DECAY-PRODUCT CONCENTRATION
MEASUREMENT LOCATION
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
ASSESSED AREA I (A PILE OF ORE AND PETRIFIED
WOOD) WAS REMOVED BUT NOT REPLACED
28
26
24
22
20
18
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
16
RESIDENCE-NO. or OCCUPANTS
NON-RESIDEHCE-MAN-HRS./OK.
14
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE. COLORAOO
INSTRUMENT NO.
VERIFICATION
349 ABAJO DRIVE
MONTICELLO, UTAH
12
Rust Qeotech
AWUITaMapiCMa*
DATE APPROVAL OOE
DOE ID NO. MS-00861-RS
OWO.NO. 3-BQQ861-RS SHT. 1 SL. 10
10 12 1 4 16 18 20 22 24 26 28 30 32 34 36 38 40
OAK RIDGE NATIONAL LABORATORY
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
FOR THE LLS. DEPARTMENT OF ENERGY
PHONE: [phone]
FAX: [phone]
POST OFFICE BOX 2587
GRANO JUNCTION, COLORADO 81502
SEP 2 0 1996
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by the U.S.
Department of Energy for Residual Radioactive Material at Formerly Utilized Sites Remedial Action
Program (FUSRAP) and Remote Surplus Facilities Management Program Sites (SFMP) [Revision
2, March 1987]. This evaluation is based on an independent verification review of the Remedial
Action Contractor's completion report and field verification.
This recommendation is based upon the Independent Verification Contractor's assessment of the n6Ka
concentration in the soil, indoor radon daughter concentration, and indoor gamma exposure rate at
this property.
Therefore, this property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretclten A. Pierce I "
MVP/IVC Project Manager
Environmental Assessment Group
Location Number: MS00861-RS
Location Address: 349 Abajo Drive
Monticello. Utah 84535
Property Owners:

Tenant Name: Dale A. Barrell
Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE B INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
349 ABAJO DRIVE
MONTICELLO, UTAH (MS00861-RS)
M. K. Jensen
September 1996
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES v
LIST OF FIGURES v
ACKNOWLEDGMENTS vii
ABSTRACT viii
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
GEOTECH SURVEY RESULTS 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
ORNL SURVEY RESULTS 6
Gamma Measurements 6
Soil Sample Analysis 6
CONCLUSION 6
REFERENCES 8
ii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 4
2. Results of ORNL and Geotech analyses of soil samples from 349 Abajo Drive,
Monticello, Utah (MS00861-RS) 5
LIST OF FIGURES
1. Property Map 7
v
ACKNOWLEDGMENTS
Research for this project was sponsored by the U.S. Department of Energy, Office of
Environmental Restoration, Southwestern Area Programs. The author wishes to acknow-
ledge A R. Jones and S. M. Smith for technical reviews.
vii
ABSTRACT
In 1980 the site of a vanadium and uranium mill at Monticello, Utah, was accepted into
the U.S. Department of Energy's (DOE's) Surplus Facilities Management Program, with the
objectives of restoring the government-owned mill site to safe levels of radioactivity, dispos-
ing of or containing the tailings in an environmentally safe manner, and performing remedial
actions on off-site (vicinity) properties that had been contaminated by radioactive material re-
sulting from mill operations. During 1995, RUST Geotech Inc., the remedial action contrac-
tor designated by DOE, performed remedial action on the vicinity property at 349 Abajo
Drive, Monticello, Utah. The Environmental Technology Section (ETS) of Oak Ridge
National Laboratory was assigned the responsibility of verifying the data supporting the ade-
quacy of remedial action and confirming the site's compliance with DOE guidelines. The ETS
found that the site successfully meets the DOE remedial action objectives. Procedures used
by ETS are described in the Environmental Technology Section Procedures Manual (ORNL
1993).
viii
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 349 ABAJO DRIVE
MONTICELLO, UTAH (MS00861-RS)'
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the U.S. government through the Defense
Plant Corporation to provide vanadium during World War JJ. Various government agencies
operated the mill until 1947. In 1948 the Atomic Energy Commission (AEC) obtained the mill
and operated it under contract through 1959 to provide both uranium and vanadium. Mill opera-
tions were terminated on January 1, 1960. In 1961 the mill tailings piles were leveled and
graded, covered with rock and soil, and seeded with native grasses. During 1974 and 1975, the
ore stockpiles were removed from the site, and the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city of
Monticello, in San Juan County, Utah. The site is bordered on the south and southeast by land
held by the U.S. Bureau of Land Management. Other boundaries are the city of Monticello and
private property.
During the AEC era, the mill processed approximately one million tons of uranium ore.
Vanadium and uranium were the only substances extracted in the milling process. Other consti-
tuents of the ore remained in the tailings and were not separated prior to disposal. During the
years of active mill operation, the mill tailings were normally moist, so erosion was minimal.
However, throughout the mill's operating period, area residents used these tailings as fill material
and as aggregate in mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy (DOE)
initiated the Surplus Facilities Management Program (SFMP) in 1978 to ensure the safe care-
taking and decommissioning of government facilities that had been retired from service but still
had radioactive contamination. In 1980 the mill site at Monticello was accepted into the SFMP,
and the Monticello Remedial Action Project (MRAP) was established to restore the government-
owned mill site to safe levels of radioactivity, to dispose of or contain the tailings in an environ-
mentally safe manner, and to perform remedial actions on off-site (vicinity) properties that had
been contaminated by radioactive material resulting from mill operations. The Monticello mill
site and the tailings remain in the custody of the DOE Grand Junction, Colorado, Projects Office.
In 1983 remedial actions for vicinity properties were separated from MRAP with establishment
of the Monticello Vicinity Properties (MVP) Project (U.S. DOE 1990b).
The verification of remedial action was performed by members of the Environmental
Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory
under DOE contract DE-AC05-96OR22464 with Lockheed Martin Energy Research Corp.
2
During 1995, RUST Geotech Inc. (Geotech), the remedial action contractor (RAC)
designated by DOE, performed remedial action on the vicinity property that is the subject of this
report, a private residence located at 349 Abajo Drive, Monticello, Utah. The remedial action
plan required excavation of all exterior contamination, backfilling with uncontaminated material,
and restoration to a condition comparable to that which existed prior to remedial action (Geotech
1996). When the excavation stage was completed, the property was resurveyed, including soil
sampling, by Geotech and by an independent contractor to verify the data supporting the ade-
quacy of remedial action and to confirm the site's compliance with DOE guidelines. The Envi-
ronmental Technology Section (ETS) of Oak Ridge National Laboratory (ORNL) has been
designated the Independent Verification Contractor for the 349 Abajo Drive site. This report
describes the methods and results of the verification surveys.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available documentation
adequately and accurately describes the post-remedial-action radiological conditions of the entire
property that is to be certified and (2) that the remedial action reduced contamination to below
applicable DOE guidelines (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1996) indicates
the property was remediated as evaluated by DOE on the basis of Environmental Protection
Agency standards (DOE 1990a) and that excess residual radioactive materials were present.
Thus it was appropriate to designate this property for remedial action
This property was assessed as part of Group 18, therefore the amount of contamination on
this property was not identified. During the actual removal process, a total of 71 yd3 of
contaminated earth and uranium mill tailings, 6 to 15 inches deep, were removed from a
290 m2 area.
A post-excavation survey was performed by Geotech prior to backfilling the excavated
areas. This survey consisted of gamma scans with a scintillometer of the ground-level of the
house, a surface scan of the exterior, and soil sampling. Samples representative of the bottom
15-cm (6-in.) soil layers of four excavated verification areas were collected and blended to form
representative composite soil samples.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation levels
have not been subtracted. Similarly, background concentrations have not been subtracted from
radionuclide concentrations in soil samples. Applicable DOE guidelines for protection against
radiation are given in Table 1.
GEOTECH SURVEY RESULTS
Gamma Measurements
Gamma exposure rate measurements taken by Geotech over the ground-level of the
residence ranged from 13 to IS uR/h. Exterior surface gamma measurements taken from the
excavated areas prior to backfilling ranged from 14 to 20 uR/h.
Soil Sample Analysis
Prior to backfilling, Geotech collected soil samples representative of the excavated areas
from the bottom 15-cm (6-in.) soil layers. These samples were blended to form composite soil
samples representative of an average over the four exterior verification areas. Geotech's analysis
of these samples showed ^Ra concentrations ranging from 1.3 to 1.8 pCi/g in the composite
sample. ORNL ETS obtained a percentage of these samples and performed a confirmatory anal-
ysis which showed 226Ra concentrations ranging from 1.3 to 2.6 pCi/g. These values are below
the EPA standard value of 15 pCi/g for soil layers >15 cm below the surface (Table 1). Gamma
ranges and/or soil sample results demonstrate compliance to the DOE Hot Spot Guideline for
areas < 25 m2 (Table 1). Results of Geotech and ORNL soil sample analyses are given in
Table 2.
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were determined by
the alpha-track method. To monitor radon levels, Geotech placed three Alpha-track detectors
on the ground floor of the residence located on this property for a period of approximately three
months (from March 6, 1995 to June 6, 1995). The IVC was not present during placement or
retrieval of the detectors to verify the RDC measurements. The average annual working level
(WL) of radon progeny concentration, as determined by the Tech./Ops-Landauer Corporation,
was 0.0020, which is well below the 0.03-WL guideline given in Table 1. The procedures and
methods used to obtain the annual average WL are deemed adequate and the results accurate by
the rVC
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of 226Ra in soil
above background levels,
averaged over a 100-m2 area
5 pCi/g averaged over the
first IS cm of soil below the
surface; 15 pCi/g when
averaged over 15-cm-thick
soil layers more than 15 cm
below the surface.
Radionuclide con-
centrations in soil
for Hot Spot areas
Exposure to 222Rn
progeny
Maximum permissible con-
centration of 226Ra in soil
above background level,
for areas less than 25m2.
Average annual radon proge-
ny concentration (including
background).
Ra concentration, in any
surface or subsurface area
less than 25 m2, is below the
guideline of (100/Af,
where A is the area of the
elevated region.
0.03 WL
(DOE 1990a)
5
Table 2. Results of ORNL and Geotech analyses of soil samples
from 349 Abajo Drive, Monticello, Utah (MS00861-RS)
^Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth
No." No.* (cm) Confirmatory* ORNL Geotech
Xla,Vlrf NCK 644 >15
X2a NCK 592 >15
X3fl NCK 591 >15
V4d NCK 590 >15
2.6 1.7 1.8
1.6 1.5
1.3 1.3
1.7 1.2
" An X-type sample is a split of the sample taken by the remedial action contractor.
6 Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated areas
were taken by RUST Geotech Inc., and these samples were blended to form composite soil
samples, which represent an average over verification areas.
c ORNL performed analysis on aliquots of the composite samples taken by Geotech
(confirmatory).
d Composite samples collected by ORNL from approximately the same excavated locations
sampled by Geotech.
6
ORNL SURVEY RESULTS
Gamma Measurements
Measurements taken by ORNL over the ground surface in the excavated areas prior to
backfilling ranged from 13 to 17 uR/h (Figure 1).
Soil Sample Analysis
ORNL sampled two of the excavated areas prior to backfilling, collecting aliquots repre-
sentative of those areas from the bottom 15-cm (6-in.) soil layers. These samples were blended
to form composite soil samples representative of an average over the exterior verification areas.
ORNL's analysis of these composite samples showed 226Ra concentrations of 1.7 and 1.2 pCi/g.
These values are below the DOE guideline value of 15 pCi/g for soil layers >15 cm below the
surface (Table 1). Results of ORNL sample analyses are given in Table 2.
CONCLUSION
The results of all Geotech and ORNL soil sample analyses show that radionuclide concen-
trations are within applicable DOE guidelines. Based upon the results of the post-remedial-
action data, which are confirmed by the verification assessment data, these radiological measure-
ments fall below the limits prescribed by DOE guidelines. It is concluded that the site success-
fully meets the DOE remedial action objectives.
ABAJO DRIVE
SHE
r Lu
> X or o
V1 4 DRIVE 1—STORY
FRAME
HOUSE V1
V 13 V2 to <4"
V1 <
V2
V3
V1 Hi V1 V4
SHEDS V4
- j
130 FT.
EXPLANATION
m Concrete
Assessed
contamination
Assessed area
not found
.RDC)
"v7
yA Excavated
area
Remaining
contamination
RDC
Measurement
Area identifier Sc
Composite sample
Identifier of
averaged area Sc
Biased sample
13-17 yLiR/h
13-15 /iR/h
13-15 /*R/h
13-15 /iR/h
AT.
A
i
FEET
10 20
3 6
METERS
30
8
Figure 1. Property Map
MS00861
349 ABAJO DRIVE
MONTICELLO, UTAH
8
REFERENCES
Geotech 1996. Property Completion Report for Monticello Vicinity Property Remedial Action
for DOE ID NO: MS00861-RS, Address: 349 Abajo Drive, Monticello, Utah 84535, Geotech,
Grand Junction, Colorado, April, 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment Group)
Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National Laboratory, Grand
Junction, Colorado.
U.S. DOE 1990a. Verification and Certification Protocol for the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination and
Decommissioning Program, Revision 3, November 1990. U.S. Department of Energy,
Washington, D.C.
U. S. DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision and
Record of Decision Summary. U.S. Department of Energy, Grand Junction Projects Office,
Grand Junction, Colorado.
DOE ID No.: MS-00867-VL
Property Address: Parcel No. A33230364800, Uranium Drive
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech of Energy (DQE)
Ra-226 is s 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [ ]
Ra-226 is s 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2.
In-situ [ ] Lab [X]
Interior gamma is * 20 //R/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is £ 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21.
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2. March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[ ] [ ] [X]
(Vacant Lot)
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
l*] I ]
[ ] [ ]
[ I
[>1
[ ] [ ] IX] [ ] [ ] [*
(Vacant Lot)
[ ] I 1
YA [ 1 [ 1
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the ranoe
of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
IIIIHIHIIIIIHIHRlMMIIII^HMHVUHIIIII
HIIIIIIIIIII Ililllllllll
SFCERTIFED SFMS-82867
DOE ID No.: MS-00867-VL
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
;.>flusby Date
Manager, Monticello Programs
Rust Geotech
DOE EVALUATION
ry"] Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Certification Official" Date
U.S. Department of Energy
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00867-VL
ADDRESS: PARCEL NO. A33230364800
URANIUM DRIVE
MONTICELLO, UTAH 84535
FEBRUARY 1996
Prepared for
U.S. Department of Energy
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
by
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
Wanda"S. BusLfy
Manager, Monticello Programs
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
DOE ID No.: MS-00867-VL
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Inclusion Survey Contractor. DOE reviewed
these evaluation results and determined that the property contained mill
tailings (residual radioactive material) exceeding EPA standards and DOE
hot spot criteria. The Remedial Action Contractor was notified of the
inclusion of this property into the MVP Project and was authorized by DOE
to conduct remedial action as required to bring the property into
conformance with EPA standards and DOE hot spot criteria.
1
DOE ID No.: MS-00867-VL
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
Property Address:
Property Owners:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
MS-00867-VL
Beginning north 00 degrees 02 minutes
east 1,822.65 feet and north 88 degrees
18 minutes west 253.11 feet from the
S4 corner of Section 36, T33S., R23E., Salt
Lake Base Meridian; north 00 degrees
02 minutes east 602.35 feet, west
560.89 feet, southeasterly 599.41 feet to a
point which is north 88 degrees 18 minutes
west 484.35 feet from the beginning, south
88 degrees 18 minutes east 484.35 feet to
the beginning, City of Monticello, County of
San Juan, State of Utah
Parcel No. A33230364800
Uranium Drive
Monticello, Utah 84535

Vacant Lot (VL)
Oak Ridge National Laboratory
August 30, 1991
Rust Geotech
June 4, 1993
Diamond Back Services, Inc.
9861 Titan Park Circle
Littleton, Colorado
June 20, 1994
September 1, 1994
Interior: 0 cubic yards
Exterior: 72 cubic yards
241 square meters (m2)
February 1996
2
DOE ID No.: MS-00867-VL
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of exterior residual radioactive
material (Appendix Figure 2.1). Once excavation was complete, the
affected areas were resurveyed for possible remaining residual radioactive
material and, upon attaining satisfactory results, were backfilled with
uncontaminated material. The property was restored to a physical
condition comparable to that which existed prior to remedial action
activities.
2.2 Previously Unidentified Contamination
The radiological assessment identified contamination, ranging from 6 to
12 inches deep, within the property. The quantity of contamination for
this property was not specified because it was assessed with
MS-00879-VL. The remedial action process included the removal of
approximately 72 cubic yards of residual radioactive material, ranging
from 6 to 36 inches deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID No.: MS-00867-VL
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by the Remedial Action
Contractor during June and November 1992, as described in the
final REA dated June 1993. Appendix Figure 2.1 shows the
extent of assessed contamination and identifies the areas
recommended to undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the excavation were
collected.
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 12 to 17 microroentgens per
hour (//R/h), as indicated on Appendix Figure 2.1. The results of
analyses for radium-226 in six composite soil samples ranged from
1.4 to 2.7 picocuries per gram (pCi/g), as indicated in Appendix
Table 3.1.
4
DOE ID No.: MS-00867-VL
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at Parcel No. A33230364800, Uranium
Drive, in Monticello, Utah, is recommended for certification as required
by DOE guidelines, and the appropriate records should be documented.
Certification Data Summary
Applicability Standards Survey Results
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 20 //R/h
above background.
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Shall not exceed 5 pCi/g
above background* in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background* in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
Not applicable: vacant
lot.
Not applicable: vacant
lot.
< 5 pCi/g above
background.
Soil sample results
ranged from 1.4 to
2.7 pCi/g/
*The background radium-226 concentration is approximately 2.0 pCi/g.
The hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-00867-VL
4.0 APPENDIX
Appendix Table:
Table 3.1 Post-Excavation Sample/Measurement Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
JEK:09-14-95
MS-00867.VL WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00867-VL
Address: Parcel No. A33230364800, Uranium Drive, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range UvR/h) Ticket No. Method" (pCi/g)
V-1 12-17 NAZ 449 OCS 1.4
V-2 13-17 NAZ 450 OCS 1.7
V-3 13-17 NAZ 451 OCS 2.7
V-4 14-16 NAZ 452 OCS 2.5
V-5 13-17 NAZ 453 OCS 1.5
V-6 13-15 NAZ 454 OCS 2.6
See Appendix Figure 2.1 for the verification areas.
"OCS = Opposed Crystal System
7
36
34
32
30
28
26
24
22
20
18
16
14
12
10
12 14 16
T
18 20 22 24 26 28 30 32 34 36 38 40 42 46 48 5(
DETAIL A
L
SCALE IN FEET
20 10 0 20 40
M:\fM\033\W03\.»MO0«S7V 09/U/9S 3.4*pm TS07BO
I I I I I I l_
NORTH
URANIUM DRIVE
V-2 V-5 v-2
SEE DETAIL 8 /7\(e
BELOW WV!
FOR V-3 AREAS (Kill
13-17 13-17 13-17 V-l
12-17
LLL r
HW<=0
O o N X 6
A X 6 6X0
6 X B
® in ro i V-2 V-5
3-17 13-17
2> fpYe V-5
J(6 6 X G 13-17
L:i>a
12-17
12-15
V-4 a S X 6
14-16
V-3
V-6
36 13-17
13-15
Ll
V-3
13-17
12-15
V-3
13-17
DETAIL B
V-3 AREAS
1-
12-15 DETAIL B
DETAIL A
12-15
d>
12-15
12
v-i
16-17
NOT TO SCALE
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN /iR/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST—REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE-RATE RANGE
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY ANO ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT, UTILITY LOCATION PLAT, OR OTHER IMPROVEMENT SURVEY
PLAT ANO IS NOT TO SE RELIEO UPON FOR THE ESTABLISHMENT
OF FENCE. BUILOING. OR OTHER FUTURE IMPROVEMENT LINES.
MMM4 V KCVMOTS
)'MMIMt-MM-m /W.
U.S. DEPARTMENT OF ENERGY
CRAMO JUNCTION MtOJCCTS Office. COLORADO
:•> PARCEL NO. A33230364800
URANIUM DRIVE
MONTICELLO, UTAH
RUST Rust 0*ot«ch MS-00B67-VL
3-C00867-V1 ,
12 14 16 18 20 22 24 26 28 30 32 34 36 38 40 42 44 46 48 5l
OAK RIDGE NATIONAL LABORATORY PHONE: [phone]
FAX: [phone] MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
FOR THE U.S. DEPARTMENT OF ENERGY
POST OFFICE BOX 2567
GRAND JUNCTION, COLORADO 61502 JUN 2 8 1996
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by the
U.S. Department of Energy for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program (FUSRAP) and Remote Surplus Facilities Management Program
Sites (SFMP) [Revision 2, March 1987]. This evaluation is based on an independent
verification review of the Remedial Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment of
the ^Ra concentration in the soil.
Therefore, this property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/TVC Project Manager
Environmental Assessment Group
Location Number:
Location Address:
MS00867-VL
Parcel No. A33230364800. Uranium Drive
Monticello. Utah 84535

Property Owner:
Owner Address:
Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
PARCEL NO. A33230364800, URANIUM DRIVE
MONTICELLO, UTAH (MS00867-VL)
S. M. Smith
June 1996
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 3
REFERENCES 6
iii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 4
2. Results of ORNL analysis of Geotech soil samples from Parcel No. A33230364800,
Uranium Drive, Monticello, Utah (MS00867-VL) 5
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site
Decommissioning Projects, U.S. Department of Energy. The author wishes to
acknowledge M. K. Jensen for analysis of soil samples and technical review and
A. R. Jones for technical review.
vii
ABSTRACT
In 1980 the site of a vanadium and uranium mill at Monticello, Utah, was accepted
into the U.S. Department of Energy's (DOE's) Surplus Facilities Management Program,
with the objectives of restoring the government-owned mill site to safe levels of radio-
activity, disposing of or contaiiiing the tailings in an environmentally safe manner, and
performing remedial actions on off-site (vicinity) properties that had been contaminated
by radioactive material resulting from mill operations. During 1994, RUST Geotech, the
remedial action contractor designated by DOE, performed remedial action on the vicinity
property at Parcel No. 33230364800, Uranium Drive, Monticello, Utah. The Environ-
mental Technology Section (ETS) of Oak Ridge National Laboratory was assigned the
responsibility of verifying the data supporting the adequacy of remedial action and con-
firming the site's compliance with DOE guidelines. The ETS found that the site success-
fully meets the DOE remedial action objectives. Procedures used by the ETS are de-
scribed in the Environmental Technology Section Procedures Manual (ORNL 1993).
ix
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT PARCEL NO. A33230364800, URANIUM DRIVE
MONTICELLO, UTAH (MS00867-VL)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the U.S. government through the
Defense Plant Corporation to provide vanadium during World War U. Various govern-
ment agencies operated the mill until 1947. In 1948 the Atomic Energy Commission
(AEC) obtained the mill and operated it under contract through 1959 to provide both
uranium and vanadium. Mill operations were terminated on January 1, 1960. In 1961 the
mill tailings piles were leveled and graded, covered with rock and soil, and seeded with na-
tive grasses. During 1974 and 1975, the ore stockpiles were removed from the site, and
the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city
of Monticello, in San Juan County, Utah. The site is bordered on the south and southeast
by land held by the U.S. Bureau of Land Management. Other boundaries are the city of
Monticello and private property.
During the AEC era, the mill processed approximately one million tons of uranium
ore. Vanadium and uranium were the only substances extracted in the nulling process.
Other constituents of the ore remained in the tailings and were not separated prior to dis-
posal. During the years of active mill operation, the mill tailings were normally moist, so
erosion was minimal. However, throughout the mill's operating period, area residents
used these tailings as fill material and as aggregate in mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy
(DOE) initiated the Surplus Facilities Management Program (SFMP) in 1978 to ensure
the safe caretaking and decommissioning of government facilities that had been retired
from service but still had radioactive contamination. In 1980 the mill site at Monticello
was accepted into the SFMP, and the Monticello Remedial Action Project (MRAP) was
established to restore the government-owned mill site to safe levels of radioactivity, to
dispose of or contain the tailings in an environmentally safe manner, and to perform reme-
dial actions on off-site (vicinity) properties that had been contaminated by radioactive ma-
terial resulting from mill operations. The Monticello mill site and the tailings remain in the
custody of the DOE Grand Junction, Colorado, Projects Office. In 1983 remedial actions
for vicinity properties were separated from MRAP with establishment of the Monticello
Vicinity Properties (MVP) Project (U.S. DOE 1990b).
*The verification of remedial action was performed by members of the Environmental Assessment Group in the
Environmental Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE
contract DE-AC05-96OR22464 with Lockheed Martin Energy Research Corporation.
During 1994, RUST Geotech Inc. (Geotech), the remedial action contractor (RAC)
designated by DOE, performed remedial action on the vicinity property that is the subject
of this report, a vacant lot located at Parcel No. A33230364800, Uranium Drive, Monti-
cello, Utah. The remedial action plan required excavation of all exterior contamination.
When the excavation was completed, the property was resurveyed, including soil sam-
pling, to ensure the removal of all contamination, backfilled with uncontaminated material,
and restored to a condition comparable to that which existed prior to remedial action
(Geotech 1996).
The DOE adopted a policy to assign an independent contractor to verify the data
supporting the adequacy of remedial action and to confirm the site's compliance with DOE
guidelines. The Environmental Technology Section (ETS) of Oak Ridge National Labora-
tory (ORNL) has been assigned the responsibility of this task at Parcel No. A33230364800,
Uranium Drive site. This report describes the methods and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available docu-
mentation adequately and accurately describes the post-remedial-action radiological
conditions of the entire property that is to be certified and (2) that the remedial action
reduced contamination to below applicable DOE guidelines (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1996) in-
dicates the property was remediated as evaluated by DOE on the basis of Environmental
Protection Agency standards and the DOE guidelines (DOE 1990a). Excess residual
radioactive materials were present, thus it was appropriate to designate this property for
remedial action.
This property was assessed as part of MS00879-VL, therefore, the quantity of ma-
terial assessed is not available. During the actual removal process, a total of 72 yd3 of
contaminated earth and uranium mill tailings, 6 to 36 inches deep, were removed from a
241 m2 area.
A post-excavation survey was performed by Geotech prior to backfilling the exca-
vated areas. This survey consisted of gamma scans with a scintillometer of the exterior
and soil sampling. Samples representative of the bottom 15-cm (6-in.) soil layers of six
excavated verification areas were collected and blended to form representative composite
soil samples for each verification area.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation
levels have not been subtracted. Similarly, background concentrations have not been sub-
tracted from radionuclide concentrations in soil samples. Applicable DOE guidelines for
protection against radiation are given in Table 1.
Gamma Measurements
Exterior surface gamma exposure rate measurements taken by Geotech from the
excavated areas prior to backfilling ranged from 12 to 17 uR/h.
Soil Sample Analysis
Prior to backfilling, Geotech collected soil samples representative of the excavated
areas from the bottom 15-cm (6-in.) soil layers. These samples were blended to form com-
posite soil samples representative of an average over the six exterior verification areas.
Geotech's analysis of these samples showed ^Ra concentrations ranging from 1.4 to 2.7
pCi/g in the composite sample. ORNL ETS obtained a percentage of these samples and
performed a confirmatory analysis which showed 22*Ra concentrations ranging from 1.6 to
1.8 pCi/g. These values are below the EPA standard value of 15 pCi/g for soil layers > 15
cm below the surface. Gamma ranges and/or soil sample results demonstrate compliance to
the DOE Hot Spot Guidelines for areas <25 m2 (Table 1). Results of Geotech and ORNL
soil sample analyses are given in Table 2.
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were not deter-
mined as this property is a vacant lot.
CONCLUSION
Results of Geotech soil sample analysis and confirmatory split soil sample analysis by
ORNL show that radionuclide concentrations are within applicable DOE guidelines. Based
on the results of the post-remedial-action data, which are confirmed by the verification
assessment data, these radiological measurements fall below the limits prescribed by DOE
guidelines. It is concluded that the site successfully meets the DOE remedial action objec-
tives.
4
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of ^Ra in soil
above background levels,
averaged over a 100-m2 area
5 pCi/g averaged over the
first 15 cm of soil below the
surface; 15 pCi/g when ave-
raged over 15-cm-thick soil
layers more than 15 cm
below the surface
Radionuclide con-
centrations in soil for
Hot Spot areas
Exposure to 222Rn
progeny
Maximum Permissible con-
centration of Ra226 in soil
above background level, for
areas less than 25 m2
Average annual radon proge-
ny concentration (including
background)
Ra226 concentrations, in any
surface or subsurface area
less than 25 m2, is below the
guideline by a factor of
(lOO/A)*, where A is the
area of the elevated region
0.03 WL
(DOE 1990a)
5
Table 2. Results of ORNL analysis of Geotech soil samples from
Parcel No. A33230364800, Uranium Drive, Monticello Utah (MS00867-VL)
^Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No." No^ (cm)
XI NAZ 449 >15 1.6 1.4
X5 NAZ 453 >15 1.8 1.5
" An X-type sample is a split of the sample taken by the remedial action contractor.
* Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated areas
were taken by Geotech, and these samples were blended to form a composite soil
sample, which represents an average over one of the verification areas.
6
REFERENCES
Geotech 1996. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00867-VL, Address: Parcel No. A33230364800, Uranium
Drive, Monticello, Utah 84535, Geotech, Grand Junction, Colorado, February 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
U.S. DOE 1990a. Verification and Certification Protocol for the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination
and Decommissioning Program, Revision 3, November 1990. U.S. Department of
Energy, Washington, D.C.
U.S. DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision
and Record of Decision Summary. U.S. Department of Energy, Grand Junction Projects
Office, Grand Junction, Colorado.
DOE TD No(s).: MS-00876-RS
Property Address(es): 265 Lower Uranium Drive
Vicinity Property Certification Summary and Recommendation
Summary Evaluation
Certification Criteria MACTEC-ERS
U.S. Department
of Energy (DOE)
Yes No Not Taken Yes No Not Taken
Ra-226 is <. 5 pCi/g above background
in top 15-cm-thick layer of soil
averaged over 100 m2
In situ [X] Lab [ ]
Ra-226 is s 15 pCi/g above
background in any 15-cm-thick layer of
soil more than 15 cm below the
surface averaged over 100 m2.
In situ [ ]Lab[X]
Interior gamma is <. 20 uR/h above
background in any occupied or
habitable structure.
The radon decay-product
concentration in any occupied or
habitable structure is <. 0.02 WL or, at
most, 0.03 WL.
Supplemental standards were applied
in accordance with EPA standard
40 CFR 192.21.
Hot-spot criteria met as outlined by
DOE guidelines for FUSRAP (Rev.2,
March 1987)
[X]a [ ] [ 1 W [ 1 [ ]
[X] [ ]
[X] [ ]
[X] [ ]
[ 1 [X]
[X] [ 1
[ 1
[ ]
[ 1
[ ]
[ ]
DO [ 1
M I ]
[A] [ ]
[ ] IA
Dt] [ 1
[ ]
[ 1
[ 1
[ ]
[ 1
"The excavations were backfilled with materials that were measured at the source indicating that the Ra-226
concentrations are in the range of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
SFCERTIFED
llllli
SFMS-00876
lof2
DOE TD No(s). : MS-00876-RS
MACTEC-ERS Recommendation
On the basis of the MACTEC-ERS evaluation, this property is recommended for
[X] Certification by DOE.
[ ] Certification by DOE with the concurrence ofthe U. S. Nuclear Regulatory Commission
because supplemental standards were applied according to 40 CFR 192.21.
10)1/fit?
Date / /
DOE Evaluation
On the basis of the MACTEC-ERS recommendation, this property
[X] Should be certified by DOE.
[ ] Should be certified by DOE with the concurrence of the TJ. S. Nuclear Regulatory
Commission because supplemental standards were applied according to 40 CFR 192.21.
d yifs 97-
Date
Work performed under DOE Contract No. DE-AC13-95GJ87335, Task Order No. 96-05.02.14.001
Michael C. Butherus
Manager, Monticello Programs
MACTEC-ERS
Certification Official
U.S. Department of Energy
2 of 2
Monticello Vicinity Properties Project
Property Completion Report
for
Monticello
Vicinity Property Remedial Action
for
DOE ID No(s).: MS-00876-RS
Address(es): 265 Lower Uranium Drive
Monticello, Utah 84535
October 1996
Prepared for
U.S. Department of Energy
Albuquerque Operations Office
Grand Junction Projects Office
Prepared by
MACTEC-ERS*
Grand Junction, Colorado
Michael C. Butherus
Manager, Monticello Programs
Work performed under DOE Contract No. DE-AC13-95GJ87335
Task Order No. 96-05.02.001
•MACTEC-ERS has been granted authorization to conduct remedial action by the U.S. Department of Energy.
Remedial action was done in accordance with the U.S. Environmental Protection Agency "Standards for Cleanup of
Land and Buildings Contaminated with Residual Radioactive Materials from Inactive Uranium Processing Sites,"
40 CFR 192, Subpart B; and "Implementation," in 40 CFR 192, Subpart C, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot-spot criteria.
DOE ID No.: MS-O0876-RS
Contents
Page
1.0 Summary 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Remedial Action Summary 2
2.0 Operations Summary 3
2.1 Remedial Action Plan 3
2.2 Assessed and Remediated Contamination 3
3.0 Verification Summary 4
3.1 Radiological Survey Data 4
3.1.1 Preremedial Action Survey 4
3.1.2 Postexcavation Survey 4
3.1.3 Radon Decay-Product Concentration Measurements 4
3.2 Recommendation for Certification 5
Table
Table 1. Certification Data Summary 5
Appendix
Appendix A. Radiological Conditions A-1
DOE/Grand Junction Projects Office
October 1996
MVP Property Completion Report
Pageii
DOE JD No.: MS-00876-RS
1.0 Summary
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce potential hazards to
the public resulting from long-term exposure to low-level radioactivity associated with the off-site
mill tailings derived from the former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States Government through its agent,
the Defense Plant Corporation, to provide additional sources of vanadium needed during World
War TJ. Various government agencies operated the mill until 1947. The AEC obtained the mill in
1948 and operated it through 1959 under cost-type contracts to process uranium and vanadium
ore. Mill operations were terminated on January 1, 1960.
The mill processed approximately one million tons of ore during AEC operations. Throughout the
operating period, mill tailings were removed from the Monticello millsite and used for
construction-related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for Remedial Actions at Inactive
Uranium Processing Sites" (40 CFR Part 192) for all cleanup activities under the MVP Project.
These standards were prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and open lands. Cleanup
activities also were conducted to meet the hot-spot criteria established by radiological protection
guidelines in the DOE Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management Program Sites
(Revision 2, March 1987).
This vicinity property was evaluated on the basis of EPA standards and DOE hot-spot criteria and
determined to contain mill tailings (radioactive material) exceeding EPA standards and/or DOE
hot-spot criteria. The Remedial Action Contractor was notified of the inclusion of this property
into the MVP Project and was authorized by DOE to conduct remedial action as required to bring
the property into conformance with EPA standards and DOE hot-spot criteria.
DOE/Grand Junction Projects Office
October 1996
MVP Property Completion Report
Page 1
DOE ID No.: MS-00876-RS
1.3 Remedial Action Summary
DOE TD No(s).:
Legal Description:
MS-00876-RS
Beginning north 89 degrees 21 minutes west 467.45 feet and south 00 degrees 42 minutes west
132.5 feet from the center of Section 36, T33S., R23E., Salt Lake Base Meridian; north
89 degrees 21 minutes west 83.5 feet, south 00 degrees 42 minutes west 82.5 feet, south
89 degrees 21 minutes east 83.5 feet, north 00 degrees 42 minutes east 82.5 feet to the beginning,
City of Monticello, County of San Juan, State of Utah
Property Address(es):
Property Owner(s):
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological and Engineering Assessment (REA):
Construction Subcontractor:
Preconstruction Conference Record:
Notice of Final Completion Inspection:
Volume of Material Removed in Cubic Yards (yd3):
Area Cleaned Up in Square Meters (m2):
Property Completion Report Submitted:
265 Lower Uranium Drive
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
Grand Junction Office
February 21, 1991
MACTEC-ERS
April 7, 1994
Crowley Construction, Inc.
September 14, 1994
October 3, 1994
Exterior: 3
Interior: 0
15
October 1996
DOE/Grand Junction Projects Office
October 1996
MVP Property Completion Report
Page 2
DOE ID No.: MS-00876-RS
2.0 Operations Summary
2.1 Remedial Action Plan
The remedial action plan specified removal of radioactive material. Once excavation was
completed, the effected area(s) were resurveyed for possible remaining radioactive material and,
upon attaining satisfactory results, were backfilled with uncontaminated material. The property
was restored to a physical condition comparable to that which existed before remedial action
activities.
2.2 Assessed and Remediated Contamination
The radiological assessment identified 3 yd3 of contamination, ranging from 6 to 12 inches (in.)
deep, within the property boundary. The remedial action process included removal of
approximately 3 yd3 of radioactive material, ranging from 6 to 12 in. deep. The areas of assessed
and excavated contamination are shown in Figure A-1.
DOE/Grand Junction Projects Office
October 1996
MVP Property Completion Report
Page 3
DOE ED No.: MS-00876-RS
3.0 Verification Summary
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Preremedial Action Survey
The Remedial Action Contractor conducted a radiological survey during June 1992, as described
in the final REA. Figure A-1 shows the extent of assessed contamination and identifies the area(s)
recommended for remedial action.
3.1.2 Postexcavation Survey
A scintillometer was used to perform a surface gamma scan after removal of radioactive material
and before backfilling. Following the gamma scan, soil samples representative of the 6-m-thick
soil layer at the bottom of the excavation were collected. The results of gamma scans and analysis
for radium-226 are presented in Table A-1.
3.1.3 Radon Decay-Product Concentration Measurement
Radon decay-product concentration (RDC) measurements were taken on the lowest habitable
level ofthe house, as shown on Figure A-1. The measurement results are indicated in Table A-2.
DOE/Grand Junction Projects Office
October 1996
MVP Property Completion Report
Page4
DOE ED No.: MS-00876-RS
3.2 Recommendation for Certification
Radioactive materials have been removed from this property to the extent required by EPA
standards (40 CFR 192, Subparts B and C) and DOE hot-spot criteria, as presented in the
Certification Data Summary (Table 1). Therefore, the property located at 265 Lower Uranium
Drive, in Monticello, Utah, is recommended for certification as required by DOE guidelines.
Table 1. Certification Data Summary
Applicability Standard Survey Results
Radium-226
Concentration in
Surface Soil
Radium-226
Concentration in
Subsurface Soil
Exposure Rate
< 5 pCi/g above background on the
basis of gamma exposure rates that do
not exceed 30 percent above normal
background."
Soil sample result was 4.4 pCi/g.b
Land
Shall not exceed 5 pCi/g above
background" in the 15-cm-thick
surface layer, averaged over
100 m2.
Shall not exceed 15 pCi/g
above background3 in any
15-cm-thick soil layer more than
15 cm below the surface,
averaged over 100 m2.
Habitable Structures
Shall not exceed 20 uR/h above Range for the ground floor was 12 to
background.0 15 pR/h.
Radon Decay-
Product
Concentration
Annual average shall not
exceed 0.02 WL, to the extent
practicable, and shall in no
case exceed 0.03 WL.
Average was 0.0018 WL, on the basis
of the DOE-approved abbreviated-
measurement method.
Key: cm = centimeters; m* = square meters; pCi/g = picocuries per gram; uR/h = microroentgens per hour
•The background radium-226 concentration for Monticello Vicinity Properties is approximately 2.0 pCi/g.
n"he hot-spot criteria were met based on gamma scans and/or soil sample results.
°The background exposure rate for this property is approximately 12 uR/h.
DOE/Grand Junction Projects Office
October 1996
MVP Property Completion Report
Page 5
DOE ID No.: MS-00876-RS
Appendix A
Radiological Conditions
Table A-1. Postexcavation Survey Results
Table A-2. Radon Decay-Product Concentration Measurement Results
Figure A-1. Radiological As-Built
DOE ED No.: MS-00876-RS
Table A-1. Postexcavation Survey Results
Verification
Area*
Gamma
Exposure Rate
Range (uR/h)
Soil Sample
Ticket No.
Measurement
Method
Radium-226
Concentration
(pCi/g)
V-1 16-20 NCA 965 OCS 4.4
Key: OCS = opposed crystal system; pCi/g = picocuries per gram; uR/h = microroentgens per hour;
V = verification area
"See Figure A-1 for location of verification area.
DOE/Grand Junction Projects Office
October 10,1996
UMTRA Property Completion Report
Page A-2
DOE ED No.: MS-00876-RS
Table A-2. Radon Decay-Product Concentration Measurement Results*
Detector"
Number Start Date End Date
Radon
Concentration
(pCi/L) WL
3851619
3851594
3851589
10-27-94
10-27-94
10-27-94
09-28-95
09-28-95
09-28-95
0.29
0.35
0.42
Average:
0.0015
0.0018
0.0021
0.0018
Key: pCi/L = picocuries per liter; WL = working level
aSee Figure A-1 for measurement locations.
"Terradex Radtrak Detector.
DOE/Grand Junction Projects Office
October 10,1996
UMTRA Property Completion Report
Page A-3
10
' 30
12
1—r
14 16 18
i—i—i—r
20 22 24
i—i—i—T
26 28 30 32
i—r
34
T"
36 38 40
30
28
26
24
22
20
18
LOWER URANIUM DRIVE 12_15 |
JJJ LLL
V-1
12-15
6 X A
RDC
0- I
V-1 ONE STORY
FRAME HOUSE
W/ ATTACHED GARAGE
12-15
<
12-15 o
®
<D
rv.vTi
LY.VJ
12-15
12
V-10
LEGEND
ALL DEPTHS/HEIGHTS IN INCHES
ALL EXPOSURE RATES IN /xR/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION AREA IDENTIFIER
RADON DECAY-PRODUCT CONCENTRATION
MEASUREMENT LOCATION
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
28
26
24
22
20
18
16 16
14
12 -
NORTH
20 10
SCALE IN FEET
20
10
M:\FAS\033\0003\RM00876V 10/11/96 09:43om S50730
~T * i i i i i
40 THIS 0RAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT, UTILITY LOCATION PLAT. OR OTHER IMPROVEMENT SURVEY
PLAT AND IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE. BUILDING. OR OTHER FUTURE IMPROVEMENT LINES.
J I I L J L
fWJUILBUm
265 LOWER URANIUM
DRIVE
MONTICELLO, UTAH
•mea
U.S. DEPARTMENT OF ENERGY
GRANO JUNCTION PROJECTS OFFICE. COLORADO
COMPLETION REPORTS MONTICELLO VICINITY PROPERTIES
FIGURE A-1
RADIOLOGICAL AS-BUILT
MS-00876-RS
3-B00876-V1 1 1
14
12
10
10 12 14 16 18 20 22 24 26 28 30 32 34 36 38 40
OAK RIDGE NATIONAL LABORATORY
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
FOR THE U.S. DEPARTMENT OF ENERGY
PHONE: [phone]
FAX: [phone]
2597 By- Road
GRAND JUNCTION, COLORADO 81503
m 31 mi
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by the U.S.
Department of Energy for Residual Radioactive Material at Formerly Utilized Sites Remedial Action
Program (FUSRAP) and Remote Surplus Facilities Management Program Sites (SFMP) [Revision
2, March 1987]. This evaluation is based on an independent verification review of the Remedial
Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment ofthe ^Ra
concentration in the soil, indoor radon daughter concentration, and indoor and outdoor gamma
exposure rates at this property.
This property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
MS00876-RS
265 Lower Uranium Drive
Monticello. Utah 84535

Location Number:
Location Address:
Property Owner:
Owner Address:
Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
265 LOWER URANIUM DRIVE
MONTICELLO, UTAH (MS00876-RS)
M. K. Jensen
January 1997
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81503
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 3
REFERENCES 6
iii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 4
2. Results of ORNL analysis of the RAC soil samples from 265 Lower Uranium Drive,
Monticello, Utah (MS00876-RS) 5
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site Decommissioning
Projects, U.S. Department of Energy. The author wishes to acknowledge M. J. Wilson-Nichols and
A. R. Jones for technical reviews.
vii
ABSTRACT
In 1980, the site of a vanadium and uranium mill at Monticello, Utah, was accepted into the U.S.
Department of Energy (DOE) Surplus Facilities Management Program, with the objectives of
restoring the government-owned mill site to safe levels of radioactivity, disposing of or containing
the tailings in an environmentally safe manner, and performing remedial actions on off-site (vicinity)
properties that had been contaminated by radioactive material resulting from mill operations. During
1994, the Remedial Action Contractor (RAC) designated by DOE, performed remedial action on the
vicinity property at 265 Lower Uranium Drive, Monticello, Utah. The Environmental Technology
Section (ETS) of Oak Ridge National Laboratory was assigned the responsibility of verifying the data
supporting the adequacy of remedial action and confirming the site's compliance with DOE guidelines.
The ETS found that the site successfully meets the DOE remedial action objectives. Procedures used
by the ETS are described in the Environmental Technology Section Procedures Manual (ORNL
1993).
ix
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 265 LOWER URANIUM DRIVE
MONTICELLO, UTAH (MS00876-RS)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the United States (U.S.) government through
the Defense Plant Corporation to provide vanadium during World War II. Various government
agencies operated the mill until 1947. In 1948, the Atomic Energy Commission (AEC) obtained the
mill and operated it under contract through 1959 to provide both uranium and vanadium. Mill
operations were terminated on January 1, 1960. In 1961, the mill tailings piles were leveled and
graded, covered with rock and soil, and seeded with native grasses. During 1974 and 1975, the ore
stockpiles were removed from the site and the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city of
Monticello, in San Juan County, Utah. The site is bordered on the south and southeast by land held
by the U.S. Bureau of Land Management. Other boundaries are the city of Monticello and private
property.
During the AEC era, the mill processed approximately one million tons of uranium ore. Vana-
dium and uranium were the only substances extracted in the milling process. Other constituents of
the ore remained in the tailings and were not separated prior to disposal. During the years of active
mill operation, the mill tailings were normally moist, so erosion was minimal. However, throughout
the mill's operating period, area residents used these tailings as fill material and as aggregate in mortar
and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy (DOE) initiated
the Surplus Facilities Management Program (SFMP) in 1978 to ensure the safe caretaking and de-
commissioning of government facilities that had been retired from service but still had radioactive
contamination. In 1980, the mill site at Monticello was accepted into the SFMP, and the Monticello
Remedial Action Project (MRAP) was established to restore the government-owned mill site to safe
levels of radioactivity, to dispose of or contain the tailings in an environmentally safe manner, and to
perform remedial actions on off-site (vicinity) properties that had been contaminated by radioactive
material resulting from mill operations. The Monticello mill site and the tailings remain in the custody
of the DOE Grand Junction, Colorado, Projects Office. In 1983, remedial actions for vicinity
properties were separated from MRAP with establishment of the Monticello Vicinity Properties
(MVP) Project (US DOE 1990b).
*The verification of remedial action was performed by members ofthe Environmental Assessment Group in the Environmental
Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE contract DE-AC05-
960R22464 with Lockheed Martin Energy Research Corporation.
2
During 1994, the Remedial Action Contractor (RAC) designated by DOE, performed remedial
action on the vicinity property that is the subject of this report, a single family residence located at
265 Lower Uranium Drive, Monticello, Utah. The remedial action plan required excavation of all
exterior contamination. When the excavation was completed, the property was resurveyed, including
soil sampling, to ensure the removal of all contamination, backfilled with uncontaminated material,
and restored to a condition comparable to that which existed prior to remedial action (MACTEC-
ERS 1996).
DOE adopted a policy to assign an independent contractor to verify the data supporting the
adequacy of remedial action and to confirm the site's compliance with DOE guidelines. The Environ-
mental Technology Section (ETS) of Oak Ridge National Laboratory (ORNL) has been assigned the
responsibility of this task at the 265 Lower Uranium Drive site. This report describes the methods
and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available documentation
adequately and accurately describes the post-remedial-action radiological conditions of the entire
property that is to be certified and (2) that the remedial action reduced contamination to below
applicable DOE guidelines (US DOE 1990a).
Document Reviews
Review of the RAC property completion report (MACTEC-ERS 1996) indicates the property
was remediated as evaluated by DOE on the basis of U.S. Environmental Protection Agency
standards and the DOE guidelines (US DOE 1990a). Excess residual radioactive materials were
present, thus it was appropriate to designate this property for remedial action.
The pre-remedial-action survey performed by the RAC identified 3 yd3 of mill tailings 6 to 12
inches deep. During the actual removal process, a total of 3 yd3 of contaminated earth and uranium
mill tailings, 6 to 12 inches deep, were removed from a 15 m2 area.
The RAC performed a post-excavation survey prior to backfilling the excavated area. This
survey consisted of gamma scans with a scintillometer of the ground level of the structure, a surface
scan ofthe exterior, and soil sampling. Samples representative of the bottom 15-cm (6-in.) soil layers
ofthe excavated verification area were collected and blended to form a representative composite soil
sample.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation levels have
not been subtracted. Similarly, background concentrations have not been subtracted from radionu-
clide concentrations in soil samples. Applicable DOE guidelines for protection against radiation are
given in Table 1.
Gamma Measurements
Gamma exposure rate measurements taken by the RAC at the ground-level of the residence
ranged from 12 to 15 uR/h. Exterior surface gamma measurements taken from the excavated areas
prior to backfilling ranged from 16 to 20 uR/h.
Soil Sample Analysis
Prior to backfilling, the RAC collected soil samples representative of the excavated area from
the bottom 15-cm (6-in.) soil layers. These samples were blended to form a composite soil sample
representative of an average over the exterior verification area. The RAC's analysis of this sample
showed a 226Ra concentration of 4.4 pCi/g. ORNL ETS obtained this sample and performed a
confirmatory analysis which showed a 226Ra concentration of 7.4 pCi/g. These values are below the
DOE guideline value of 15 pCi/g for soil layers > 15 cm below the surface. Gamma ranges and/or
soil sample results demonstrate compliance to the DOE Hot Spot Guidelines for areas <25 m2 (Table
1). Results of the RAC and ORNL soil sample analyses are given in Table 2.
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were determined by the
Alpha-track method. To monitor radon levels, the RAC placed three alpha-track detectors on the
ground floor ofthe residence located on this property for a period of approximately one year (from
October 27, 1994 to September 28, 1995). The average annual working level (WL) of radon
progeny concentration, as determined by the Tech./Ops-Landauer Corporation, was 0.0018, which
is well below the 0.03-WL guideline given in Table 1. It should be noted that this is an annual
measurement not the abbrieviated measurement as stated in the completion report.
CONCLUSION
Results of RAC soil sample analysis and confirmatory split soil sample analysis by ORNL, show
that radionuclide concentrations are within applicable DOE guidelines. Based on the results of the
post-remedial-action data, which are confirmed by the verification assessment data, these radiological
measurements fall below the limits prescribed by DOE guidelines. It is concluded that the site
successfully meets the DOE remedial action objectives.
4
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of 226Ra in soil
above background levels,
averaged over a 100-m2
area
5 pCi/g averaged over the first 15 cm
of soil below the surface; 15 pCi/g
when averaged over 15-cm-thick soil
layers more than 15 cm below the
surface
Radionuclide con-
centrations in soil
for Hot Spot areas
Exposure to 222Rn
progeny
Maximum Permissible con-
centration of Ra226 in soil
above background level,
for areas less than 25 m2
Average annual radon
progeny concentration
(including background)
Ra226 concentrations, in any surface
or subsurface area less than 25 m2,
is below the guideline by a factor of
(1007A)V\ where A is the area of the
elevated region
0.03 WL
(US DOE 1990a)
5
Table 2. Results of ORNL analysis of the RAC soil samples from
265 Lower Uranium Drive, Monticello, Utah (MS00876-RS)
226Ra concentration (pCi/g)
ORNL RAC
sample sample Depth ORNL RAC
No." No_^ • (cm)
XI NCA 965 >15 7.4 4.4
" An X-type sample is a split of the sample taken by the remedial action contractor.
* Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated areas were
taken by the RAC, and these samples were blended to form a composite soil sample, which
represents an average over one of the verification areas.
6
REFERENCES
MACTEC-ERS 1996. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00876-RS, Address: 265 Lower Uranium Drive, Monticello, Utah
84535, MACTEC-ERS, Grand Junction, Colorado, October 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment Group)
Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National Laboratory, Grand
Junction, Colorado.
US DOE 1990a. Verification and Certification Protocol for the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination and
Decommissioning Program. Revision 3, November 1990. U.S. Department of Energy, Washington,
D.C.
US DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision and Record
of Decision Summary. U.S. Department of Energy, Grand Junction Projects Office, Grand Junction,
Colorado.
DOE ID No.: MS-00879-VL
Property Address: Parcel No. A33230364814, Uranium Drive
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech of Energy (DQE)
Ra-226 is s 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [ ]
Ra-226 is ^ 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2.
In-situ [ ] Lab [X]
Interior gamma is £ 20 //R/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is s 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21.
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[ ] [X] I ]
[X] [ ] [ ]
YES NO NOT TAKEN
LX] I 1 I 1
[A [ 1 I 1
[ ] [ ] [X] [ ] [ ] [tf
(Vacant Lot)
[ ] [ ] [X] [ ] [ ] [>i
(Vacant Lot)
[ ] [>] [ ]
[>] [ ] [ ]
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of oamma
exposure rates that do not exceed 30 percent above normal background.
ISSI •I SFCERTIFED SFMS-20867
DOE ID No.: MS-00879-VL
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Wanda S. Busby Date
Manager, Monticello Programs
Rust Geotech
DOE EVALUATION
(Xl Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application
of supplemental standards per 40 CFR 192.21.
Ce
U
ification Official
Department of Energy
± Date 4^
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00879-VL
ADDRESS: PARCEL NO. A33230364814
URANIUM DRIVE
MONTICELLO, UTAH 84535
FEBRUARY 1996
Prepared for
U.S. Department of Energy
by
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
7 Wand^S. Busby
Manager, Monticello Programs
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.2 Recommendation for Certification 5
4.0 APPENDIX , 6
i
DOE ID No.: MS-00879-VL
1.0 SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Inclusion Survey Contractor. DOE reviewed
these evaluation results and determined that the property contained mill
tailings (residual radioactive material) exceeding DOE hot spot criteria.
The Remedial Action Contractor was notified of the inclusion of this
property into the MVP Project and was authorized by DOE to conduct
remedial action as required to bring the property into conformance with
EPA standards and DOE hot spot criteria.
1
DOE ID No.: MS-00879-VL
Summary of Remedial Action
DOE ID No.: MS-00879-VL
Legal Description: Beginning at a point on the east line of the
NE4SW4 of Section 36, T33S., R23E., Salt
Lake Base Meridian which is north
00 degrees 02 minutes east 1,822.65 feet
of the S4 corner of said Section 36; north
88 degrees 18 minutes west 253.11 feet,
north 00 degrees 02 minutes east
602.35 feet, east 253.11 feet to the east
line of said NE4SW4, south 00 degrees
02 minutes 602.35 feet to the beginning,
City of Monticello, County of San Juan,
State of Utah
Property Address: Parcel No. A33230364814
Uranium Drive
Monticello, Utah 84535
Property Owners:

Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Vacant Lot (VL)
Oak Ridge National Laboratory
March 5, 1992
Rust Geotech
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
June 4, 1993
Diamond Back Services, Inc.
9861 Titan Park Circle
Littleton, Colorado
June 20, 1994
September 1, 1994
Interior: 0 cubic yards
Exterior: 10 cubic yards
50 square meters (m2)
Property Completion Report
Submitted: February 1996
DOE ID No.: MS-00879-VL
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of exterior residual radioactive
material (Appendix Figure 2.1). Once excavation was complete, the
affected areas were resurveyed for possible remaining residual radioactive
material and, upon attaining satisfactory results, were backfilled with
uncontaminated material. The property was restored to a physical
condition comparable to that which existed prior to remedial action
activities.
2.2 Previously Unidentified Contamination
The radiological assessment identified contamination, 6 inches deep,
within the property. The quantity of contamination for this property was
not specified because it was assessed with MS-00867-VL. The remedial
action process included the removal of approximately 10 cubic yards of
residual radioactive material, 6 inches deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID No.: MS-00879-VL
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by the Remedial Action
Contractor during June 1992, as described in the final REA dated
June 1993. Appendix Figure 2.1 shows the extent of assessed
contamination and identifies the areas recommended to undergo
remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the excavation were
collected. These samples were blended to form composite
samples representing the verification areas (Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 12 to 17 microroentgens per
hour (//R/h), as indicated on Appendix Figure 2.1. The results of
analyses for radium-226 in two composite soil samples were
0.9 and 1.9 picocuries per gram (pCi/g), as indicated in Appendix
Table 3.1.
4
DOE ID No.: MS-00879-VL
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at Parcel No. A33230364814, Uranium
Drive, in Monticello, Utah, is recommended for certification as required
by DOE guidelines, and the appropriate records should be documented.
Certification Data Summary
Applicability
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Standards
Shall not exceed 20 //R/h
above background.
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Survey Results
Not applicable: vacant
lot.
Not applicable: vacant
lot.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background* in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background* in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
< 5 pCi/g above
background.'
Soil sample results were
0.9 and 1.9 pCi/g.
*The background radium-226 concentration is approximately 2.0 pCi/g.
The hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-00879-VL
4.0 APPENDIX
Appendix Table:
Table 3.1 Post-Excavation Sample/Measurement Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
JEK-.09-14-95
MS-00879.VL WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00879-VL
Address: Parcel No. A33230364814, Uranium Drive, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (//R/h) Ticket No. Method' (pCi/g)
V-1 14-17 NAZ 447 OCS 1.9
V-2 14-16 NAZ 448 OCS 0.9
See Appendix Figure 2.1 for the verification areas.
"OCS = Opposed Crystal System
7
36
34
32
30
28
26
24
22
20
18
16
14
12
10
12 14 16 18 20 22 24 26 28 30 32 34 36 38 40 42 44 46 48 50
T 1 1 1 I I I I I I I I I I 1 1 1 1 1 1 1 1 i 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
t URANIUM DRIVE
—x— —*
r SEE DETAIL A
12-15
. SHED
0^12-13
I z~:5J
L NOT TO SCALE
J L J L
12 14 16 18 20
_J L
22 24
-x-r 1 V-1
14-17
12-15
v-i
14-17
V-2
14-16
v-.v:
V-2
14-16
12-15
DETAIL A
<D
LV.YJ
12-15
20 10
NORTH
SCALE IN FEET
20
LEGENQ
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN /iR/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE —RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE-RATE RANGE
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
12
v-i
16-17
40
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. OEPARTUENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT, UTILITY LOCATION PLAT, OR OTHER IMPROVEMENT SURVEY
PLAT ANO IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE. BUILDING. OR OTHER FUTURE IMPROVEMENT LINEV
26 28 30 32 34 36
I
38
••imoci-iii-M rm.
U.S. DEPARTMENT OF ENERGY
CIUWD JUNCTION HUMECTS orriei. COLOHAOO
3^
PARCEL NO. A33230364814
URANIUM DRIVE
MONTICELLO, UTAH
"»•"• MS-00879-VL
j-rj
40 42 44 46 48 5C
OAK RIDGE NATIONAL LABORATORY PHONE: <970) 2484200
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION FAX: [phone]
FOR THE U.S. DEPARTMENT OF ENERGY
FOOT OFFICE BOX 2587
GRAND JUNCTION. COLORADO 81502 JJJ| £ g jggg
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by the
U.S. Department of Energy for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program (FUSRAP) and Remote Surplus Facilities Management Program
Sites (SFMP) [Revision 2, March 1987]. This evaluation is based on an independent
verification review of the Remedial Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment of
the ^Ra concentration in the soil at this property.
Therefore, this property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
Location Number: MS00879-VL
Location Address: Parcel No. A33230364814, Uranium Drive
Monticello, Utah 84535
Property Owner:

Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
PARCEL NO. A33230364814, URANIUM DRIVE
MONTICELLO, UTAH (MS00879-VL)
S. M. Smith
June 1996
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 3
REFERENCES 6
iii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 4
2. Results of ORNL analysis of Geotech soil samples from Parcel No. A33230364814,
Uranium Drive, Monticello, Utah (MS00879-VL) 5
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site Decom-
missioning Projects, U.S. Department of Energy. The author wishes to acknowledge M.
K. Jensen for analysis of soil samples and technical review and J. R. Sauvage for technical
review.
vii
ABSTRACT
In 1980 the site of a vanadium and uranium mill at Monticello, Utah, was accepted
into the U.S. Department of Energy's (DOE's) Surplus Facilities Management Program,
with the objectives of restoring the government-owned mill site to safe levels of radio-
activity, disposing of or containing the tailings in an environmentally safe manner, and
performing remedial actions on off-site (vicinity) properties that had been contaminated
by radioactive material resulting from mill operations. During 1994, RUST Geotech, the
remedial action contractor designated by DOE, performed remedial action on the vicinity
property at Parcel No. A33230364814, Uranium Drive, Monticello, Utah. The
Environmental Technology Section (ETS) of Oak Ridge National Laboratory was
assigned the responsibility of verifying the data supporting the adequacy of remedial
action and confirming the site's compliance with DOE guidelines. The ETS found that
the site successfully meets the DOE remedial action objectives. Procedures used by the
ETS are described in the Environmental Technology Section Procedures Manual (ORNL
1993). .
ix
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT PARCEL NO. A33230364814, URANIUM DRIVE
MONTICELLO, UTAH (MS00879-VL)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the U.S. government through the
Defense Plant Corporation to provide vanadium during World War II. Various govern-
ment agencies operated the mill until 1947. In 1948 the Atomic Energy Commission
(AEC) obtained the mill and operated it under contract through 1959 to provide both
uranium and vanadium. Mill operations were terminated on January 1,1960. In 1961 the
mill tailings piles were leveled and graded, covered with rock and soil, and seeded with
native grasses. During 1974 and 1975, the ore stockpiles were removed from the site, and
the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city
of Monticello, in San Juan County, Utah. The site is bordered on the south and southeast
by land held by the U.S. Bureau of Land Management. Other boundaries are the city of
Monticello and private property.
During the AEC era, the mill processed approximately one million tons of uranium
ore. Vanadium and uranium were the only substances extracted in the milling process.
Other constituents of the ore remained in the tailings and were not separated prior to dis-
posal. During the years of active mill operation, the mill tailings were normally moist, so
erosion was minimal. However, throughout the mill's operating period, area residents
used these tailings as fill material and as aggregate in mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy
(DOE) initiated the Surplus Facilities Management Program (SFMP) in 1978 to ensure
the safe caretaking and decommissioning of government facilities that had been retired
from service but still had radioactive contamination. In 1980 the mill site at Monticello
was accepted into the SFMP, and the Monticello Remedial Action Project (MRAP) was
established to restore the government-owned mill site to safe levels of radioactivity, to
dispose of or contain the tailings in an environmentally safe manner, and to perform
remedial actions on off-site (vicinity) properties that had been contaminated by
radioactive material resulting from mill operations. The Monticello mill site and the
tailings remain in the custody of the DOE Grand Junction, Colorado, Projects Office. In
1983 remedial actions for vicinity properties were separated from MRAP with
establishment of the Monticello Vicinity Properties (MVP) Project (U.S. DOE 1990b).
*The verification of remedial action was performed by members of the Environmental Assessment Group in the
Environmental Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE
contract DE-AC05-96OR22464 with Lockheed Martin Energy Research Corporation.
2
During 1994, RUST Geotech Inc. (Geotech), the remedial action contractor (RAC)
designated by DOE, performed remedial action on the vicinity property that is the subject
of this report, a vacant lot located at Parcel No. A33230364814, Uranium Drive,
Monticello, Utah. The remedial action plan required excavation of all exterior
contamination. When the excavation was completed, the property was resurveyed,
including soil sampling, to ensure the removal of all contamination, backfilled with
micontaminated material, and restored to a condition comparable to that which existed
prior to remedial action (Geotech 1996).
The DOE adopted a policy to assign an independent contractor to verify the data
supporting the adequacy of remedial action and to confirm the site's compliance with
DOE guidelines. The Environmental Technology Section (ETS) of Oak Ridge National
Laboratory (ORNL) has been assigned the responsibility of this task at Parcel No.
A33230364814, Uranium Drive site. This report describes the methods and results of
that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available docu-
mentation adequately and accurately describes the post-remedial-action radiological
conditions of the entire property that is to be certified and (2) that the remedial action
reduced contamination to below applicable DOE guidelines (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1996) in-
dicates the property was remediated as evaluated by DOE on the basis of Environmental
Protection Agency standards and the DOE guidelines (DOE 1990a). Excess residual
radioactive materials were present, thus it was appropriate to designate this property for
remedial action.
This property was assessed with MS00867-VL, therefore, the quantity of material
assessed is not available. During the actual removal process, a total of 10 yd3 of con-
taminated earth and uranium mill tailings, 6 inches deep, were removed from a 50 m2
area.
A post-excavation survey was performed by Geotech prior to backfilling the exca-
vated areas. This survey consisted of gamma scans with a scintillometer of the exterior
and soil sampling. Samples representative of the bottom 15-cm (6-in.) soil layers of two
excavated verification areas were collected and blended to form representative composite
soil samples for each verification area.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation
levels have not been subtracted. Similarly, background concentrations have not been sub-
tracted from radionuclide concentrations in soil samples. Applicable DOE guidelines for
protection against radiation are given in Table 1.
Gamma Measurements
Exterior surface gamma exposure rate measurements taken by Geotech from the
excavated areas prior to backfilling ranged from 12 to 17 uR/h.
Soil Sample Analysis
Prior to backfilling, Geotech collected soil samples representative of the excavated
areas from the bottom 15-cm (6-in.) soil layers. These samples were blended to form
composite soil samples representative of an average over the two exterior verification
areas. Geotech's analysis of these samples showed 226Ra concentrations ranging from 0.9
to 1.9 pCi/g in the composite samples. ORNL ETS obtained one of these samples and
performed a confirmatory analysis which showed a 2MRa concentration of 1.3 pCi/g.
These values are below the EPA standard value of 15 pCi/g for soil layers > 15 cm below
the surface. Gamma ranges and/or soil sample results demonstrate compliance to the
DOE Hot Spot Guidelines for areas <25 m2 (Table 1). Results of Geotech and ORNL soil
sample analyses are given in Table 2.
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were not taken
as this is a vacant lot.
CONCLUSION
Results of Geotech soil sample analysis and confirmatory split soil sample analysis by
ORNL show that radionuclide concentrations are within applicable DOE guidelines.
Based on the results of the post-remedial-action data, which are confirmed by the
verification assessment data, these radiological measurements fall below the limits
prescribed by DOE guidelines. It is concluded that the site successfully meets the DOE
remedial action objectives.
4
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions
Radionuclide con- Maximum permissible con-
centrations in soil centration of 226Ra in soil
above background levels,
averaged over a 100-m2 area
Radionuclide
concentrations in soil
for Hot Spot areas
Maximum Permissible
concentration of Ra226 in soil
above background level, for
areas less than 25 m2
Guideline value
5 pCi/g averaged over the
first 15 cm of soil below the
surface; 15 pCi/g when ave-
raged over 15-cm-thick soil
layers more than 15 cm
below the surface
Ra226 concentrations, in any
surface or subsurface area
less than 25 m2, is below the
guideline by a factor of
(100/A),/4, where A is the
area of the elevated region
0.03 WL Exposure to 222Rn Average annual radon proge-
progeny ny concentration (including
background)
(DOE 1990a)
5
Table 2. Results of ORNL analysis of Geotech soil samples from
Parcel No. A33230364814, Uranium Drive, Monticello Utah (MS00879-VL)
226Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No." No* (cm)
XI NAZ 447 >15 1.3 1.9
" An X-type sample is a split of the sample taken by the remedial action contractor.
* Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated
areas were taken by Geotech, and these samples were blended to form a composite soil
sample, which represents an average over one of the verification areas.
6
REFERENCES
Geotech 1996. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00879-VL, Address: Parcel No. A33230364814, Monticello,
Utah 84535, Geotech, Grand Junction, Colorado, February 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
U.S. DOE 1990a. Verification and Certification Protocol for the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination
and Decommissioning Program, Revision 3, November 1990. U.S. Department of
Energy, Washington, D.C.
U.S. DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision
and Record of Decision Summary. U.S. Department of Energy, Grand Junction Projects
Office, Grand Junction, Colorado.
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPER i Y REMEDIAL ACiiGhi
FOR
DOE ID NOS.: MS-00154-MR AND MS-00897-VL
ADDRESS: 453 SOUTH MAIN STREET
MONTICELLO, UTAH 84535
MARCH 1996
Prepared for
U.S. Department of Energy
by
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
^ Wand£ S. Bus6y
Manager, Monticello Programs
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
TABLE OF CONTENTS
i .0 SUMMARY i
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 4
2.1 Abstract of Remedial Action Plan 4
2.2 Previously Unidentified Contamination 4
2.3 Unanticipated Items During Remedial Action 4
2.4 Application of Supplemental Standards 4
3.0 VERIFICATION SUMMARY 5
3.1 Radiological Survey Data 5
3.1.1 Pre-Remedial Action Survey 5
3.1.2 Post-Excavation Survey 5
3.1.3 Radon Decay-Product Concentration (RDC) Measurement .... 5
3.2 Recommendation for Certification 6
4.0 APPENDIX 7
i
DOE ID No.: MS-00154-MR
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1342, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
These properties were evaluated on the basis of EPA standards and DOE
hot spot criteria by the DOE Remedial Action Contractor. DOE reviewed
these evaluation results and determined that the properties contained mill
tailings (residual radioactive material) exceeding EPA standards. The
Remedial Action Contractor was notified of the inclusion of these
properties into the MVP Project and was authorized by DOE to conduct
remedial action as required to bring the properties into conformance with
EPA standards and DOE hot spot criteria.
1
DOE ID No.: MS-00154-MR
1.3 Summary of Remedial Action
DOE ID Nos.:
Legal Descriptions:
MS-00154-MR and MS-00897-VL
Parcel No. A33230367808 - Beginning 387.75 feet east and 144.5 feet south
of the SW corner of Lot 2, Block 3, Monticello Townsite Survey, north
89 degrees 24 minutes west 237.32 feet, south 62 feet, west 41.5 feet, south
37.5 feet, west 25 feet, mere or less, to the east boundary of the Highway 121
right of way, southeasterly along said boundary 78 feet, more or less, to a
point 169 feet south and 273.8 feet west of the point of beginning, east
231.8 feet, north 89 feet, east 42 feet, north 80 feet, more or less, to the
beginning; except beginning 387.75 feet east and 144.5 feet south of the
SW corner of Lot 2, Block 3, Monticello Townsite Survey, north 89 degrees
24 minutes west 162.01 feet, south 81.7 feet, east 162 feet, north 80 feet,
more or less, to the beginning, County of San Juan, State of Utah
Parcel No. A33230367806 - Beginning 225.75 feet east and 81 feet south of
the SW corner of Lot 2, Block 3, Monticello Townsite Survey, west 75.31 feet,
south 61.02 feet, south 89 degrees 24 minutes east 75.31 feet, north 61.02
feet, more or less, to the beginning, County of San Juan, State of Utah
Property Address:
Property Owner:
Property Categories:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractors:
453 South Main Street
Monticello, Utah 84535

Major Residential (MR) - MS-00154-MR
Vacant Lot (VL) - MS-00897-VL
Not applicable: spillover inclusion requested
by the Remedial Action Contractor - Both
DOE Nos.
June 26, 1987 - Both DOE Nos.
Rust Geotech
January 6, 1988
1st Remediation
Bayless and Bayless, Inc.
435 East 1st Street
Pueblo, Colorado
2nd Remediation
Crowley Construction, Inc.
East Route HC 63 Box 66
Monticello, Utah
2
DOE ID No.: MS-00154-MR
1.3 Summary of Remedial Action (continued)
Pre-Construction Conference
Record: June 6, 1988 - 1st Remediation
Notice of Final Completion
Inspection: July 1,1988 - 1st Remediation
Completion of 2nd Remediation: September 21,1995
Volume of Material Removed: Interior: 0 cubic yards
Exterior: 1,534 cubic yards
Area Cleaned Up: 2,488 square meters (m2)
Property Completion Report
Submitted: March 1996
AH
DOE ID No.: MS-00154-MR
1.3 Summary of Remedial Action (continued)
Pre-Construction Conference
Record: June 6, 1988 - 1st Remediation
Notice of Final Completion
Inspection: July 1, 1988 - 1st Remediation
Completion cf 2nd Remediation: September 21, 1395
Volume of Material Removed: Interior: 0 cubic yards
Exterior: 1,534 cubic yards
Area Cleaned Up: 2,488 square meters (m2)
Property Completion Report
Submitted: March 1996
3
DOE ID No.: MS-00154-MR
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of exterior residual radioactive
material (Appendix Figure 2.1). Interior assessed Area B (soil in the crawl
space) was excluded from remedial action based on gamma exposure
rates and pre-remedial radon decay-product concentration measurements
that did not exceed EPA standards, as discussed in the REA. Once
excavation was complete, the affected area was resurveyed for possible
remaining residual radioactive material and, upon attaining satisfactory
results, was backfilled with uncontaminated material. The properties were
restored to a physical condition comparable to that which existed prior to
remedial action activities.
2.2 Previously Unidentified Contamination
The radiological assessment (excluding assessed Area B) identified
729 cubic yards of contamination, ranging from 6 to 48 inches deep,
within the properties. The remedial action process included the removal
of approximately 1,534 cubic yards of residual radioactive material,
ranging from 6 to 54 inches deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
A portion of assessed Area A involving a water line (Area V-16) was
remediated under MP-00181-OT.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the properties.
4
DOE ID No.: MS-00154-MR
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by the Remedial Action
Contractor during July 1987, as described in the final REA dated
January 1988. Appendix Figure 2.1 shows the extent of assessed
contamination and identifies the area recommended to undergo
remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the excavation were
collected. These samples were blended to form composite
samples representing the verification areas (Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 14 to 29 microroentgens per
hour (//R/h), as indicated on Appendix Figure 2.1. The results of
analyses for radium-226 in 27 composite soil samples ranged from
1.3 to 10.4 picocuries per gram (pCi/g), as indicated in Appendix
Table 3.1.
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on measurements representing an annual average, the RDC
was 0.0130 working level (WL), as indicated in Appendix
Table 3.2. Appendix Figure 2.1 shows the measurement location
on the ground floor (the lowest habitable level of the structure).
The RDC measurements were completed prior to the second
remediation; however, the RDC is valid because the additional
remediation was not conducted in the interior of the structure.
5
DOE ID No.: MS-00154-MR
3.2 Recommendation for Certification
Residual radioactive materials have been removed from these properties
to the extent required by EPA standards (40 CFR 192.12, 192.20-23)
and DOE hot spot criteria, as indicated in the Certification Data
Summary below.
Therefore, the properties located at 453 South Main Street
(MS-00154-MR and MS-00897-VL), in Monticello, Utah, are
recommended for certificstiop ss required by DOE cjuidoHp.cc, 2Pid th;
appropriate records should be documented.
Certification Data Summary
Applicability
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Standards
Shall not exceed 20 //R/h
above background.*
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Survey Results
Range for the ground
floor was 15 to 21 //R/h.
Annual average was
0.0130 WL.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
< 5 pCi/g above
background.**
Soil sample results
ranged from 1.3 to
10.4 pCi/g.**
*The background exposure rate is approximately 15 //R/h.
The background radium-226 concentration is approximately 2.0 pCi/g.
**The hot spot criteria were met based on gamma scans and/or soil sample results.
6
DOE ID No.: MS-00154-MR
4.0 APPENDIX
Appendix Tables:
Table 3.1 Post-Excavation Sample/Measurement Results
Table 3.2 Radon Decay-Product Concentration Measurement Results
Appendix Figure:
Figure 2.1 Interior and Exterior Extent of Contamination -
RADIOLOGICAL AS-BUILT
MRW: 10-06-95
MS-00154.MR WP61
REV080195
7
Table 3.1
Post-Excavation Sample/Measurement Results
DOE !D Nos.: MS-001 54-MR and MS 00297-VL
Address: 453 South Main Street, Monticello, Utah
The analytical uncertainties in the table are reported at the 95-percent confidence
interval.
Area
Exposure-
Rate Range
(//R/h)
Soil
Sample
Ticket No.
Meas.
Method"
Radium-226
(pCi/g)
Potassium
(pCi/g)
Thorium
(pCi/g)
V-1
V-2
V-3
V-4
V-5
V-6
V-7
V-8
V-9
V-10
V-11
V-12
V-13
V-14
V-15
V-16
V-17
V-18
V-19
V-20
V-21
V-22
V-23
16-18
14 - 16
15- 18
16 - 18
16- 20
16-22
16- 18
15-20
17- 20
17 - 18
19 - 21
18- 22
17 - 19
16 - 18
17 - 21
18-29
15- 20
15 - 16
15 - 16
16- 20
15 - 17
15 - 18
16 - 19
MNK 079
MNK 077
MNK 078
MNQ 701
MNK 080
MNK 081
MNK 082
MNK 083
MNK 084
MNK 085
MNK 086
MNK 087
MNK 088
MNK 089
MNK 090
NCN 907
MNK 092
MNK 093
MNK 094
MNK 095
MNK 096
MNK 097
MNK 098
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
3
1.
1.
4.
4,
4.
2.
2.
7,
8.
10.
8,
4.
1.
2.
4.
6.1
2.7
3,
3.
2.
1.
3.
0.5
0.2
0.3
0.7
0.7
0.7
0.4
0.4
1.1
1.3
1.5
1.2
0.7
0.3
0.4
0.7
0.9
0.5
16.0
16.6
17.7
16.7
18.2
16.3
17.7
_16.1
17.0
17.3
17.1
15.5
14.1
15.3
15.7
22.0
15.6
16.8
15.4
13.6
14.5
17.6
16.9
2.8
3.0
3.1
3.3
3.2
2.9
3.1
2.9
3.0
3.1
3.0
2.9
2.6
2.8
2.8
3.8
2.9
3.0
3.1
3.0
3.1
3.4
3.3
1.0
0.8
1.0
1.0
1.1
0.8
0.7
1.1
0.9
0.8
1.5
0.8
1.0
0.8
1.2
2.6
0.8
0.8
1.1
0.8
0.8
1.0
0.9
0.
0.
0.
0.
0.
0.
0.
0.
0.3
0.3
0.3
0.3
0.3
0.2
0.3
0.6
0.2
0.2
0.3
0.2
0.2
0.3
0.3
"AL = Analytical Laboratory
8
Table 3.1 (continued)
Post-Excavation Sample/Measurement Results
DOF ID Nos.: MS-00154-MR and MS-00897-VL
Address: 453 South Main Street, Monticello, Utah
Exposure- Soil
Rate Range Sample Meas. Radium-226 Potassium Thorium
Area OuR/h) Ticket No. Method0 (pCi/g) (pCi/g) (pCi/g)
V-24 15 - 20 MNK 099 AL 4.1 ± 0.6 15.8 ± 3.2 1.1 ±0.3
V-25 17 - 24 MNK 100 AL 5.0 ± 0.8 14.1 ± 3.0 1.3 ±0.3
V-26 17-19 MNQ 702 AL 2.3 ± 0.4 17.0 ± 3.4 1.1 ±0.3
V-27 19 - 22 MNQ 703 AL 7.5 ±1.1 15.8 ± 3.1 0.9 ± 0.3
See Appendix Figure 2.1 for the verification areas.
"AL = Analytical Laboratory
9
Table 3.2
Radon Decay-Product Concentration Measurement Results
nOP in Mnc • ^/^C-nA1t;4..^l^p pnri MC r»r>oo-7_\/t
Address: 453 South Main Street, Monticello, Utah
Instrument Type: Terradex Track Etch Detector
Radon
Detector Tracks Per Concentration Working
Number Start Date End Date mm2 (pCi/L) Level
526503 01-18-89 01-18-90 20.2 2.65 0.0133
526082a 01-18-89
526463 01-18-89 01-18-90 19.3 2.54 0.0127
Annual Average: 0.0130
See Appendix Figure 2.1 for the measurement location.
aDetector damaged.
10
42
40
33
35
34
32
30
28
26
24
22
20
18
16
1 4
12
10
1 2 1 4
~T
1 6 13 20 22 24 26
"T~
28 30 32 34 36 38 40 42 44 45 43 50
15-17
'mmm
V-2
14-16
rz.0
v.v.v.
SHED
V-7
16-18
V-5
16-22
0
15-16 •:•©•:
'.CRAWL SPACE'.
v-8
15-20 LU
V-5
16-20
V-4
16-18
12
30.
v-i
16-18
36
V-12
18-22
•0
V- 1 1
19-21
<2
V-10
17-18
30.
v-9
17-20
DETAIL A
NOT TO SCALE
(24>
V-15
17-21
ia
V- 1 4
16-18
18
54 17-19
V-19
15-16
{I)
12
18
V-18
15-16
V-17
15-20
36
v-22
15-18 15-21
<5>
DT
ONE STORY
FRAME HOUSE
ROC,
s V-21
15-17
V-20
16-20
SEE
DETAIL
A
S
V-24
15-20
<£>
V-23
16-19 •36:
v-25
17-24
0®
vrfHi) 26
17-19
r
::::.\~-~-
©
(!)
tV.YJ
12-15
12
v-i
16-17
y-27
19-22
36 V-1 6
18-29
LEGENQ
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN /iR/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE —RATE RANGE
BOUNOARY OF EXCAVATION
AVERAGE EXCAVATED OEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE-RATE RANGE
RADON DECAY—PRODUCT CONCENTRATION
MEASUREMENT LOCATION
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEOIAL ACTION
ASSESSED AREA B (SOIL IN CRAWL SPACE)
WAS EXCLUDED FROM REMEDIAL ACTION
AREA V-1 6 WAS REMEDIATED UNDER
MP-00181 -OT
ADDRESSED UNDER MP-00181-OT
RADIOLOGICAL AS-BUILT
FIGURE 2.1
INTERIOR AND EXTERIOR EXTENT OF CONTAMINATION
u
SCALE IN FEET
20 10 0 20 40
u \f*S\033\0OO3\«UOOIJ«V 03/08/94 07:47of T30T80
1 2 1 4 1 6 18
NORTH
I I
20
THIS DRAWING 15 FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY ANO ITS CONTRACTORS IT IS NOT A LANO SURVEY
PLAT. UTILITY LOCATION PLAT. OR OTHER IMPROVEMENT SURVEY
PLAT ANO IS NOT TO BE RELIEO UPON FOR THE ESTABLISHMENT
OF FENCE. BUILDING. OR OTHER FUTURE IMPROVEMENT LINES
U.S. DEPARTMENT OF ENERGY
CUND JUNCTION MQJCCTS QfTlCC. COLO VCD
453 SOUTH MAIN STREET
MONTICELLO, UTAH
RUST
•tuft 0*ot«ch wm MS*0Ot3«-UR.US-OO697-VL
22 24 26 28 30 32 34 35 38 40 42 46
• - 3-C0Q154-V1 ,
48 5
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
453 SOUTH MAIN STREET
MONTICELLO, UTAH (MS00154-MR/MS00897-VL)
A. R. Jones
June 1996
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 4
REFERENCES 7
iii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 5
2. Results of ORNL analysis of Geotech soil samples from 453 South Main Street,
Monticello, Utah (MSOO 154-MR/MS00897-VL) 6
iv
ABSTRACT
In 1980 the site of a vanadium and uranium mill at Monticello, Utah, was accepted into
the U.S. Department of Energy's (DOE's) Surplus Facilities Management Program, with the
objectives of restoring the government-owned mill site to safe levels of radioactivity, dispos-
ing of or containing the tailings in an environmentally safe manner, and performing remedial
actions on off-site (vicinity) properties that had been contaminated by radioactive material
resulting from mill operations. During 1988 and 1995, RUST Geotech, the remedial action
contractor designated by DOE, performed remedial action on the vicinity property at 453
South Main Street, Monticello, Utah. The Environmental Technology Section (ETS) of Oak
Ridge National Laboratory was assigned the responsibility of verifying the data supporting
the adequacy of remedial action and confirming the site's compliance with DOE guidelines.
All deficiencies noted in the initial review have been resolved in the revised completion
report. The ETS found that the site successfully meets the DOE remedial action objectives.
Procedures used by the ETS are described in the Environmental Technology Section
Procedures Manual (ORNL 1993).
ix
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 453 SOUTH MAIN STREET
MONTICELLO, UTAH (MS00154-MR/MS00897-VL)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the U.S. government through the
Defense Plant Corporation to provide vanadium during World War II. Various government
agencies operated the mill until 1947. In 1948 the Atomic Energy Commission (AEC) ob-
tained the mill and operated it under contract through 1959 to provide both uranium and vana-
dium. Mill operations were terminated on January 1, 1960. In 1961 the mill tailings piles
were leveled and graded, covered with rock and soil, and seeded with native grasses. During
1974 and 1975, the ore stockpiles were removed from the site, and the mill foundations were
buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city of
Monticello, in San Juan County, Utah. The site is bordered on the south and southeast by land
held by the U.S. Bureau of Land Management. Other boundaries are the city of Monticello
and private property.
During the AEC era, the mill processed approximately one million tons of uranium ore.
Vanadium and uranium were the only substances extracted in the milling process. Other con-
stituents ofthe ore remained in the tailings and were not separated prior to disposal. During
the years of active mill operation, the mill tailings were normally moist, so erosion was
minimal. However, throughout the mill's operating period, area residents used these tailings as
fill material and as aggregate in mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy (DOE)
initiated the Surplus Facilities Management Program (SFMP) in 1978 to ensure the safe care-
taking and decommissioning of government facilities that had been retired from service but
still had radioactive contamination. In 1980 the mill site at Monticello was accepted into the
SFMP, and the Monticello Remedial Action Project (MRAP) was established to restore the
government-owned mill site to safe levels of radioactivity, to dispose of or contain the tailings
in an environmentally safe manner, and to perform remedial actions on off-site (vicinity)
properties that had been contaminated by radioactive material resulting from mill operations.
The Monticello mill site and the tailings remain in the custody of the DOE Grand Junction,
Colorado, Projects Office. In 1983 remedial actions for vicinity properties were separated
from MRAP with establishment ofthe Monticello Vicinity Properties (MVP) Project (U.S.
DOE 1990b).
The verification of remedial action was performed by members of the Environmental Assessment Group in the
Environmental Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE
contract DE-AC05-96OR22464 with Lockheed Martin Energy Research Corporation.
2
During 1988 and 1995, RUST Geotech Inc. (Geotech), the remedial action contractor
(RAC) designated by DOE, performed remedial action on the vicinity property that is the
subject of this report, a single family residence located at 453 South Main Street, Monticello,
Utah. The remedial action plan required excavation of all exterior contamination. When the
excavation was completed, the property was resurveyed, including soil sampling, to ensure the
removal of all contamination, backfilled with uncontaminated material, and restored to a
condition cornparaHe to that' which existed prior to remedi?.! action (Geotech 1996).
The DOE adopted a policy to assign an independent contractor to verify the data
supporting the adequacy of remedial action and to confirm the site's compliance with DOE
guidelines. The Environmental Technology Section (ETS) of Oak Ridge National Laboratory
(ORNL) has been assigned the responsibility of this task at the 453 South Main Street site.
This report describes the methods and results of that verification.
PROCEDURES
Objectives
The objectives ofthe verification activities were to confirm (1) that available documenta-
tion adequately and accurately describes the post-remedial-action radiological conditions of the
entire property that is to be certified and (2) that the remedial action reduced contamination to
below applicable DOE guidelines (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1996) indicates
the property was remediated as evaluated by DOE on the basis of Environmental Protection
Agency standards and the DOE guidelines (DOE 1990a). Excess residual radioactive
materials were present, thus it was appropriate to designate this property for remedial action.
The pre-remedial-action survey performed by Geotech identified 729 yd3 of mill tailings
6 to 48 inches deep. During the actual removal process, a total of 1534 yd3 of contaminated
earth and uranium mill tailings, 6 to 54 inches deep, was removed from a 2488 m2 area.
A post-excavation survey was performed by Geotech prior to backfilling the excavated
areas. This survey consisted of gamma scans with a scintillometer of the ground level of the
structure, a surface scan ofthe exterior, and soil sampling. Samples representative of the
bottom 15-cm (6-in.) soil layers of 27 excavated verification areas were collected and blended
to form representative composite soil samples for each verification area.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation
levels have not been subtracted. Similarly, background concentrations have not been
subtracted from radionuclide concentrations in soil samples. Applicable DOE guidelines for
protection against radiation are given in Table 1.
Gamma Measurements
Gamma exposure rate measurements taken by Geotech at the ground-level ofthe resi-
dence ranged from 15 to 21 uR/h. Exterior surface gamma measurements taken from the
excavated areas prior to backfilling ranged from 14 to 29 uR/h.
Soil Sample Analysis
Prior to backfilling, Geotech collected soil samples representative of the excavated areas
from the bottom 15-cm (6-in.) soil layers. These samples were blended to form a composite
soil sample representative of an average over the 27 exterior verification areas. Geotech's
analysis of these samples showed 226Ra concentrations ranging from 1.3 to 10.4 pCi/g in the
composite sample. ORNL ETS obtained a percentage of these samples and performed a con-
firmatory analysis which showed 226Ra concentrations ranging from 2.7 to 9.9 pCi/g. These
values are below the EPA standard value of 15 pCi/g for soil layers > 15 cm below the surface.
Results of Geotech and ORNL soil sample analyses are given in Table 2.
As a result of a meeting between the RAC and IVC on May 26, 1994, anomalous read-
ings, defined as > 30% above the average of the excavation, will be investigated to show com-
pliance to the DOE hot spot guideline. The RAC remediated this property before this proce-
_ dure change. The IVC observed that areas V6, V8, VI7, and V25 exceed 30% of the
excavation average. The IVC will allow a correlation developed by the RAC to estimate 226Ra
pCi/g concentrations based on gamma exposure rates. The highest anomalous reading of
24 uR/h in these.areas using the RAC's correlation yields a 226Ra concentration of 4.4 pCi/g.
This value is well below the minimum concentration of 30 pCi/g needed, when assuming the
maximum area under the hot spot guideline of 25 nr, for subsurface samples. Additionally,
gamma readings in area V16 exceed 30% of the excavation average. This area was revisited in
September of 1995, to remove contamination left in place around a water line. A sample from
this area after removal had a 226Ra concentration of 4.8 pCi/g. Gamma ranges and/or soil
sample results demonstrate compliance to the DOE Hot Spot Guidelines for areas <25 nr
(Table 1).
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were determined
by the Alpha-track method. To monitor radon levels, Geotech placed three alpha-track detec-
tors on the ground floor ofthe residence located on this property for a period of approximately
one year (from January 18, 1989 to January 18, 1990). One detector was damaged during the
measurements; therefore only two values were used to calculate the results. The average
annual working level (WL) of radon progeny concentration, as determined by the Tech./Ops-
Landauer Corporation, was 0.0130, which is well below the 0.03-WL guideline given in
Table 1.
4
CONCLUSION
Results of Geotech soil sample analysis and confirmatory split soil sample analysis by
ORNL show that radionuclide concentrations are within applicable DOE guidelines. Based on
the results ofthe post-remedial-action data, which are confirmed bv the verification assessment
data, these radiological measurements fall below the limits prescribed by DOE guidelines. All
deficiencies noted in the initial review have been corrected in the revised completion report as
discussed in a meeting between Geotech and ORNL on May 17, 1996. It is concluded that the
site successfully meets the DOE remedial action objectives.
5
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of 226Ra in soil
above background levels,
averaged over a 100-m2 area
5 pCi/g averaged over the
first 15 cm of soil below the
surface; 15 pCi/g when ave-
raged over 15-cm-thick soil
layers more than 15 cm
below the surface
Radionuclide
concentrations in soil
for Hot Spot areas
Maximum Permissible
concentration of Ra226 in soil
above background level, for
areas less than 25 m2
Ra226 concentrations, in any
surface or subsurface area
less than 25 m2, is below the
guideline by a factor of
(100/A),/!, where A is the
area of the elevated region
Exposure to 222Rn
progeny
Average annual radon proge-
ny concentration (including
background)
0.03 WL
(DOE 1990a)
Table 2. Results of ORNL analysis of Geotech soil samples
from 453 South Main Street, Monticello Utah (MS00154-MR/MS00897-VL)
226Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No." No/ (cm)
X5 MNK 080 >15 4.2 4.6
XI1 MNK 086 >15 9.9 10.4
X20 MNK 095 >15 2.7 3.1
X25 MNK 100 >15 5.4 5.0
4 ^
" An X-type sample is a split of the sample taken by the remedial action contractor.
* Soil samples representative of the bottom 15-cm (6-in.) soil layers ofthe excavated areas
were taken by Geotech, and these samples were blended to form a composite soil sample,
which represents an average over one of the verification areas.
REFERENCES
Geotech 1995. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00154-MR/MS00897-VL, Address: 453 South Main Street,
Monticello, Utah 84535, Geotech, Grand Junction, Colorado, March 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment Group)
Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National Laboratory,
Grand Junction, Colorado.
U.S. DOE 1990a. Verification and Certification Protocol for the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination and
Decommissioning Program, Revision 3, November 1990. U.S. Department of Energy,
Washington, D.C.
U.S. DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision and
Record of Decision Summary. U.S. Department of Energy, Grand Junction Projects Office,
Grand Junction, Colorado.
DOE ID Nos.: MS-00154-MR and MS-00897-VL
Property Address: 453 South Main Street
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
' Rust Geotech of Energy (DOE)
Ra-226 is < 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [ ]
Ra-226 is <, 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2.
In-situ [ ] Lab [X]
Interior gamma is <z 20 //R/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is <; 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21.
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
L>] [ ] [ ]
[*] [ ] [ 1
W [ ] [ 1
W [ ] [ ]
[ ] [XI [ ]
[Yl [ ] [ ]
COMMENTS: *The excavation was backfilled with materials that were measured
at the source showing that the Ra-226 concentrations are in the range of normal
background. Other surface areas were verified on the basis of gamma exposure
rates that do not exceed 30 percent above normal background.
SFCERTIFED SFMS-00154
DOE ID Nos.: MS-00154-MR and MS-00897-VL
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Wanda S. Busby
Manager, Monticello Programs
Rust Geotech
Date
DOE EVALUATION
f>d Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Certification Officiat
U.S. Department of Energy
\1 JJ
Date
DOE ID No.: MS-00917-OT
Property Address: Parcel No. A33240308405, East Highway 666
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech of Energy (DOE)
Ra-226 is <; 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [Xf
Ra-226 is < 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2.
In-situ [ ] Lab [X]
Interior gamma is <; 20 //R/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is < 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21.
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
[>0 [ ] I ]
IX] [ ] I ]
l*l [ ] I ]
IX] [ ] [ 1
[ ] M [ 1
[X] [ ] [ ]
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
tPart of one sample was taken from the top laver. and was lab-analvzed.
lllllillll
SFCERTIFED SFMS-00917
DOE ID No.: MS-00917-OT
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
/anda S. Bus
Manager, Monticello Programs
Rust Geotech
Date
DOE EVALUATION
[X] Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
fication Official
Department of Energy
Cer
U.S
Date
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
DOE ID NO.: MS-00917-OT
ADDRESS: PARpEL NO. A33240308405
EAST HIGHWAY 666
MONTICELLO, UTAH 84535
MARCH 1996
Prepared for
U.S. Department of Energy
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
/ Wanda S. Busby
Manager, Monticello Programs
FOR
by
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.1.3 Radon Decay-Product Concentration (RDC) Measurement .... 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
i
DOE ID No.: MS-00917-OT
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Inclusion Survey Contractor. DOE reviewed
these evaluation results and determined that the property contained mill
tailings (residual radioactive material) exceeding DOE hot spot criteria.
The Remedial Action Contractor was notified of the inclusion of this
property into the MVP Project and was authorized by DOE to conduct
remedial action as required to bring the property into conformance with
EPA standards and DOE hot spot criteria.
1
DOE ID No.: MS-00917-OT
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
MS-00917-OT
Beginning 2,050 feet west and 287 feet north of the SE corner of Section 30,
T33S., R24E., Salt Lake Base Meridian; north 239.5 feet, east 70 feet, north
133.5 feet, west 340 feet, south 641 feet, east 145 feet, north 120 feet,
northeasterly 58.3 feet, north 98 feet, east 95 feet to beginning, City
of Monticello, County of San Juan, State of Utah
Property Address:
Property Owner:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
Parcel No. A33240308405
East Highway 666
Monticello, Utah 84535

Monticello, Utah 84535
Other (OT)
Oak Ridge National Laboratory
November 6, 1992
Rust Geotech
May 3, 1994
Crowley Construction, Inc.
East Route HC 63, Box 66
Monticello, Utah
September 29, 1994
November 14, 1994
Interior:
Exterior:
0 cubic yards
2 cubic yards
7 square meters (m2)
March 1996
2
DOE ID No.: MS-00917-OT
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of exterior residual radioactive
material (Appendix Figure 2.1). Once excavation was complete, the
affected area was resurveyed for possible remaining residual radioactive
material and, upon attaining satisfactory results, was backfilled with
uncontaminated material. The property was restored to a physical
condition comparable to that which existed prior to remedial action
activities.
2.2 Previously Unidentified Contamination
The radiological assessment identified 2 cubic yards of contamination,
ranging from 4 inches deep to 36 inches high, within the property. The
remedial action process included the removal of approximately 2 cubic
yards of residual radioactive material, ranging from 4 inches deep to
36 inches high, within the property.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID No.: MS-00917-OT
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by the Remedial Action
Contractor during July 1993, as described in the final REA dated
May 1994. Appendix Figure 2.1 shows the extent of assessed
contamination and identifies the area recommended to undergo
remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the excavation were
collected. These samples were blended to form a composite
sample representing the verification area (Appendix Figure 2.1).
Interior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 11 to 58 microroentgens per
hour (//R/h) for the ground floor (Appendix Figure 2.1). Elevated
exposure rates were associated with a point source (ore) that was
left in place at the owner's request. Exposure rates for the rest of
the ground floor ranged from 11 to 13 //R/h.
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 12 to 15//R/h (Appendix
Figure 2.1). The result of analysis for radium-226 in one
composite soil sample was 2.8 picocuries per gram (pCi/g), as
indicated in Appendix Table 3.1.
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on the DOE-approved abbreviated-measurement method, the
RDC was 0.0017 working level (WL), as indicated in
Appendix Table 3.2. Appendix Figure 2.1 shows the measurement
location on the ground floor (the lowest habitable level of the
structure).
4
DOE ID No.: MS-00917-OT
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at Parcel No. A33240308405, East
Highway 666, in Monticello, Utah, is recommended for certification as
required by DOE guidelines, and the appropriate records should be
documented.
Applicability
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Certification Data Summary
Standards
Shall not exceed 20 //R/h
above background.*
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Survey Results
Range for the ground
floor was 11 to 58 //R/h.
Average was 0.0017 WL,
based on the DOE-
approved abbreviated-
measurement method.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background** in
the 15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background** in
any 15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
< 5 pCi/g above
background.
Soil sample result was
2.8 pCi/g.*
*The background exposure rate is approximately 13//R/h.
Elevated exposure rates were due to a point source. The rest of the structure ranged
from 11 to 13 //R/h.
**The background radium-226 concentration is approximately 2.0 pCi/g.
§The hot spot criteria were met based on gamma scans and/or soil sample results.
A part of sample V-1 was from the 15-cm surface layer.
5
DOE ID No.: MS-00917-OT
4.0 APPENDIX
Appendix Tables:
Table 3.1 Post-Excavation Sample/Measurement Results
Table 3.2 Radon Decay-Product Concentration Measurement
Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
SJW: 10-25-95
MS-00917.OT WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00917-OT
Address: Parcel No. A33240308405, East Highway 666, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (//R/h) Ticket No. Method* (pCi/g)
V-1 13 - 15 NCG 191 OCS 2.8
See Appendix Figure 2.1 for the verification area.
"OCS = Opposed Crystal System
7
Table 3.2
Radon Decay-Product Concentration Measurement Results
DOE ID No.: MS-00917-OT
Address: Parcel No. A33240308405, East Highway 666, Monticello, Utah
Instrument Type: Landauer Radtrak Detector
Radon
Detector Tracks Per Concentration Working
Number Start Date End Date mm2 (pCi/L) Level
3964234 02-28-95 05-31-95 0.6 0.33 0.0017
3964316 02-28-95 05-31-95 0.8 0.33 0.0017
3964171 02-28-95 05-31-95 0.3 0.33 0.0017
Average: 0.0017
See Appendix Figure 2.1 for the measurement location.
8
.10
30
12 1 4 16 18
i—r
20 22 24 26 28 30 32 34 36 38 40
30
28
26
24
22
20
18
1 6
14
12
Y
10
12-15
SEE DETAIL A
, BARN
12-13
ONE STORY
METAL
BUILDING
11-13
\
RDC r
L1
i
u.
58/zR/h
T
I
UNINHABITABLE
ONE STORY /
METAL BUILDINGS/
12-13
12-15
(
I
I
NINHABITABLE
CINDER BLOCK
BUILDING
13-15
NINHABITABLE
ONE STORY
METAL BUILDING
12-13
"1
5 36 GRANDSTAND
1 1
V-1
13-15
DETAIL A
SCALE IN FEET
20 10 0 20 40
EAST HIGHWAY 666
NOT TO SCALE
M:\FAS\033\0003\RM00917V 03/05/96 3:14pm T50780
" X
I I I I J L
NORTH
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT. UTILITY LOCATION PLAT, OR OTHER IMPROVEMENT SURVEY
PLAT AND IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE, BUILDING, OR OTHER FUTURE IMPROVEMENT LINES.
©
rv.-TTi
LV.VJ
12-15
12
V-1
16-17
RDC)
[12]
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN fiR/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE-RATE RANGE
RADON DECAY-PRODUCT CONCENTRATION
MEASUREMENT LOCATION
HEIGHT IN INCHES OF ASSESSED CONTAMINATED
SANDSTONE REMOVED AND REPLACED
POINT SOURCE (ORE)
28
26
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
RESIOENCE-NO. OF OCCUPANTS
NON—RESIDENCE—UAN—HRS./WK.
INSTRUMENT NO.
SURVEY OATE
BY CK. A.E. APP, CK. A.E. APP.
U.S. DEPARTMENT OF ENERGY
GRANO JUNCTION PROJECTS OFFICE. COLORADO
PARCEL NO. A33240308405
EAST HIGHWAY 666
MONTICELLO, UTAH
Rust Qeotech
APPROVAL DOE
OOEIDNO. MS-00917-OT
owe.NO. 3-B00917-V1 1 or 1
24
22
20
18
1 6
1 4
1 2
10
10 12 1 4 1 6 18 20 22 24 26 28 30 32 34 36 38 40
OAK RIDGE NATIONAL LABORATORY
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
FOR THE U.S. DEPARTMENT OF ENERGY
PHONE: [phone]
FAX' (970)2484220
POST OFFICE BOX 2SS7
GRAND JUNCTION. COLORADO 81502
M 2 8 1996
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by
the U.S. Department of Energy for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program (FUSRAP) and Remote Surplus Facilities Management Program
Sites (SFMP) [Revision 2, March 1987]. This evaluation is based on an independent verifi-
cation review of the Remedial Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment of
the 226Ra concentration in the soil, indoor radon daughter concentration, and indoor gamma
exposure rates at this property.
This property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
Location Number: MS00917- OT
Location Address: Parcel No. A33240308405
East Highway 666
Monticello, Utah 84535
Property Owner:

Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
PARCEL NO. A33240308405, EAST HIGHWAY 666
MONTICELLO, UTAH (MS00917-OT)
M. J. Wilson-Nichols
June 1996
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 3
REFERENCES 6
iii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 4
2. Results of ORNL analysis of Geotech soil samples from Parcel No. A33240308405,
East Highway 666, Monticello, Utah (MS00917-OT) 5
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site
Decommissioning Projects, U.S. Department of Energy. The author wishes to acknow-
ledge M. K. Jensen for analysis of soil samples and N. F. Kirby and A. R. Jones for tech-
nical reviews.
vii
ABSTRACT
In 1980 the site of a vanadium and uranium mill at Monticello, Utah, was accepted
into the U.S. Department of Energy's (DOE's) Surplus Facilities Management Program,
with the objectives of restoring the government-owned mill site to safe levels of radio-
activity, disposing of or containing the tailings in an environmentally safe manner, and
performing remedial actions on off-site (vicinity) properties that had been contaminated
by radioactive material resulting from mill operations. During 1994, RUST Geotech, the
remedial action contractor designated by DOE, performed remedial action on the vicinity
property at Parcel No. A33240308405, East Highway 666, Monticello, Utah. The Envi-
ronmental Technology Section (ETS) of Oak Ridge National Laboratory was assigned
the responsibility of verifying the data supporting the adequacy of remedial action and
confrrming the site's compliance with DOE guidelines. The ETS found that the site suc-
cessfully meets the DOE remedial action objectives. Procedures used by the ETS are
described in the Environmental Technology Section Procedures Manual (ORNL 1993).
ix
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
PARCEL NO. A33240308405, EAST HIGHWAY 666
MONTICELLO, UTAH (MS00917-OT)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the U.S. government through the
Defense Plant Corporation to provide vanadium during World War JJ. Various govern-
ment agencies operated the mill until 1947. In 1948 the Atomic Energy Commission
(AEC) obtained the mill and operated it under contract through 1959 to provide both
uranium and vanadium. Mill operations were terminated on January 1, 1960. In 1961 the
mill tailings piles were leveled and graded, covered with rock and soil, and seeded with na-
tive grasses. During 1974 and 1975, the ore stockpiles were removed from the site, and
the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city
of Monticello, in San Juan County, Utah. The site is bordered on the south and southeast
by land held by the U.S. Bureau of Land Management. Other boundaries are the city of
Monticello and private property.
During the AEC era, the mill processed approximately one million tons of uranium
ore. Vanadium and uranium were the only substances extracted in the milling process.
Other constituents of the ore remained in the tailings and were not separated prior to dis-
posal. During the years of active mill operation, the mill tailings were normally moist, so
erosion was minimal. However, throughout the mill's operating period, area residents
used these tailings as fill material and as aggregate in mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy
(DOE) initiated the Surplus Facilities Management Program (SFMP) in 1978 to ensure
the safe caretaking and decommissioning of government facilities that had been retired
from service but still had radioactive contamination. In 1980 the mill site at Monticello
was accepted into the SFMP, and the Monticello Remedial Action Project (MRAP) was
established to restore the government-owned mill site to safe levels of radioactivity, to
dispose of or contain the tailings in an environmentally safe manner, and to perform reme-
dial actions on off-site (vicinity) properties that had been contaminated by radioactive ma-
terial resulting from mill operations. The Monticello mill site and the tailings remain in the
custody of the DOE Grand Junction, Colorado, Projects Office. In 1983 remedial actions
for vicinity properties were separated from MRAP with establishment of the Monticello
Vicinity Properties (MVP) Project (U.S. DOE 1990b).
*The verification of remedial action was performed by members of the Environmental Assessment Group in the
Environmental Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE
contract DE-AC05-96OR22464 with Lockheed Martin Energy Research Corporation.
2
During 1994, RUST Geotech Inc. (Geotech), the remedial action contractor (RAC)
designated by DOE, performed remedial action on the vicinity property that is the subject
of this report, the San Juan County Fairgrounds located at Parcel No. A33240308405,
East Highway 666, Monticello, Utah. The remedial action plan required excavation of
all exterior contamination. When the excavation was completed, the property was resur-
veyed, including soil sampling, to ensure the removal of all contamination, backfilled with
uncontaminated material, and restored to a condition comparable to that which existed
prior to remedial action (Geotech 1996).
The DOE adopted a policy to assign an independent contractor to verify the data
supporting the adequacy of remedial action and to confirm the site's compliance with
DOE guidelines. The Environmental Technology Section (ETS) of Oak Ridge National
Laboratory (ORNL) has been assigned the responsibility of this task at the Parcel No.
A33240308405, East Highway 666 site. This report describes the methods and results
of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available doc-
umentation adequately and accurately describes the post-remedial-action radiological
conditions of the entire property that is to be certified and (2) that the remedial action
reduced contamination to below applicable DOE guidelines (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1996) in-
dicates the property was remediated as evaluated by DOE on the basis of Environmental
Protection Agency standards and the DOE guidelines (DOE 1990a). Excess residual
radioactive materials were present, thus it was appropriate to designate this property for
remedial action.
The pre-remedial-action survey performed by Geotech identified 2 yd3 of mill tailings
4 inches deep to 36 inches high. During the actual removal process a total of 2 yd3
of contaminated earth and uranium mill tailings, 4 inches deep to 36 inches high, were
removed from a 7 m2 area. This area, shown as VI on Figure 2-1, involved removal
of contaminated mortar from a sandstone drinking fountain and sandstone base.
A post-excavation survey was performed by Geotech prior to backfilling the exca-
vated areas. This survey consisted of gamma scans with a scintillometer of the ground
level of the structure, a surface scan of the exterior, and soil sampling. Samples repre-
sentative of the bottom 15-cm (6-in.) soil layers of one excavated verification area were
collected and blended to form a representative composite soil sample for the verification
area.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation
levels have not been subtracted. Similarly, background concentrations have not been sub-
tracted from radionuclide concentrations in soil samples. Applicable DOE guidelines for
protection against radiation are given in Table 1.
Gamma Measurements
Gamma exposure rate measurements taken by Geotech at the ground-level of the
structure ranged from 11 to 13 uR/h and a point source measuring 58 uR/h. This point
source (ore) was left in place at the owner's request. Exterior surface gamma measure-
ments taken from the excavated areas prior to backfilling ranged from 12 to 15 uR/h.
Soil Sample Analysis
Prior to backfilling, Geotech collected soil samples representative of the excavated
areas from the bottom 15-cm (6-in.) soil layers. These samples were blended to form a
composite soil sample representative of an average over the exterior verification area.
Geotech's analysis of this sample showed a 226Ra concentration of 2.8 pCi/g. ORNL ETS
obtained this sample and performed a confirmatory analysis which showed a ^Ra concen-
tration of 2.4 pCi/g. These values are below the EPA standard value of 15 pCi/g for soil
layers > 15 cm below the surface. Gamma ranges and/or soil sample results demonstrate
compliance to the DOE Hot Spot Guidelines for areas <25 m2 (Table 1).
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were deter-
mined by the Alpha-track method. To monitor radon levels, Geotech placed three alpha-
track detectors on the ground floor of the structure located on this property for a period
of approximately three months (from February 28, 1995 to May 31, 1995). The average
annual working level (WL) of radon progeny concentration, as determined by the Tech-
/Ops-Landauer Corporation, was 0.0017, which is well below the 0.03-WL guideline
given in Table 1.
CONCLUSION
Results of Geotech soil sample analysis and confirmatory split soil sample analysis
by ORNL show that radionuclide concentrations are within applicable DOE guidelines.
Based upon the results of the post-remedial-action data, which are confirmed by the veri-
fication assessment data, these radiological measurements fall below the limits prescribed
by DOE guidelines. It is concluded that the site successfully meets the DOE remedial
action objectives.
4
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of ^Ra in soil
above background levels,
averaged over a 100-m2 area
5 pCi/g averaged over the
first 15 cm of soil below the
surface; 15 pCi/g when ave-
raged over 15-cm-thick soil
layers more than 15 cm
below the surface
Radionuclide
concentrations in soil
for Hot Spot areas
Exposure to 222Rn
progeny
Maximum Permissible con-
centration of Ra226 in soil
above background level, for
areas less than 25 m2
Average annual radon proge-
ny concentration (including
background)
Ra226 concentrations, in any
surface or subsurface area
less than 25 m2, is below the
guideline by a factor of
(lOO/A)*, where A is the
area of the elevated region
0.03 WL
(DOE 1990a)
5
Table 2. Results of ORNL analysis of Geotech soil samples from
Parcel No. A33240308405, East Highway 666, Monticello Utah (MS00917-OT)
226Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No.a No^ (cm)
XI NCG191 >15 2.4 2.8
" An X-type sample is a split of the sample taken by the remedial action contractor.
* Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated areas
were taken by Geotech, and these samples were blended to form a composite soil
sample, which represents an average over one of the verification areas.
6
REFERENCES
Geotech 1996. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS009I7-OT, Address: Parcel No. A33240308405, East
Highway 666, Monticello, Utah 84535, Geotech, Grand Junction, Colorado, March 1996.
ORNL, 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
U.S. DOE 1990a. Verification and Certification Protocolfor the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination
and Decommissioning Program, Revision 3, November 1990. U.S. Department of
Energy, Washington, D.C.
U.S. DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision
and Record of Decision Summary. U.S. Department of Energy, Grand Junction Projects
Office, Grand Junction, Colorado.
DOE ID No.: MS-00946-RS
Property Address: Parcel No. A33240309003, East Highway 666
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech of Energy (DOE)
Ra-226 is z 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [ ]
Ra-226 is s 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2.
In-situ [ ] Lab [X]
Interior gamma is < 20 //R/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is <, 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21,
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
MM [ 1
[V] [ ] [ ]
[y] [ ] [ ]
[V] [ ] [ ]
[ ] [y] [ 1
N [ ] [ 1
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
I111H11PU
SFCERTIFED
SFMS-00946
DOE ID No.: MS-00946-RS
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Wanda Slushy / Date
Manager, Monticello Programs
Rust Geotech
DOE EVALUATION
[y] Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Certification Officfa^ Date
U.S. Department of Energy
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00946-RS
ADDRESS: PARCEL NO. A33240309003
EAST HIGHWAY 666
MONTICELLO, UTAH 84535
MAY 1996
Prepared for
U.S. Department of Energy
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
by
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.1.3 Radon Decay-Product Concentration (RDC) Measurement .... 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
i
1.0 SUMMARY
DOE ID No.: MS-00946-RS
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Inclusion Survey Contractor. DOE reviewed
these evaluation results and determined that the property contained mill
tailings (residual radioactive material) exceeding EPA standards and DOE
hot spot criteria. The Remedial Action Contractor was notified of the
inclusion of this property into the MVP Project and was authorized by DOE
to conduct remedial action as required to bring the property into
conformance with EPA standards and DOE hot spot criteria.
1
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
Property Address:
Property Owner:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
DOE ID No.: MS-00946-RS
MS-00946-RS
Parcel No. A33240309003; beginning at a
point 25 feet north of the SE corner of
Section 30, T33S., R24E., Salt Lake Base
Meridian; north 236.35 feet, west
1,120 feet, south 236.35 feet, east
1,120 feet to the beginning, County of San
Juan, State of Utah
East Highway 666
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
August 30, 1991
Rust Geotech
April 7, 1994
Crowley Construction, Inc.
East Route HC 63 Box 66
Monticello, Utah
September 14, 1994
November 29, 1994
Interior: 0 cubic yards
Exterior: 4 cubic yards
18 square meters (m2)
May 1996
2
2.0 OPERATIONS SUMMARY
DOE ID No.: MS-00946-RS
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of exterior residual radioactive
material (Appendix Figure 2.1). Once excavation was complete, the
affected areas were resurveyed for possible remaining residual radioactive
material and, upon attaining satisfactory results, were backfilled with
uncontaminated material. The property was restored to a physical
condition comparable to that which existed prior to remedial action
activities.
2.2 Previously Unidentified Contamination
The radiological assessment identified 4 cubic yards of contamination,
6 inches deep, within the property. The remedial action process included
the removal of approximately 4 cubic yards of residual radioactive
material, 6 inches deep.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID No.: MS-00946-RS
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by the Remedial Action
Contractor during July 1992, as described in the final REA dated
April 1994. Appendix Figure 2.1 shows the extent of assessed
contamination and identifies the areas recommended to undergo
remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the excavation were
collected. These samples were blended to form a composite
sample representing the verification area (Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 12 to 16 microroentgens per
hour (/;R/h), as indicated on Appendix Figure 2.1. The result of
analysis for radium-226 in one composite soil sample was
3.2 picocuries per gram (pCi/g), as indicated in Appendix
Table 3.1.
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on the DOE-approved abbreviated-measurement method,
the RDC was 0.0019 working level (WL), as indicated in Appendix
Table 3.2. Appendix Figure 2.1 shows the measurement location
on the ground floor (the lowest habitable level of the structure).
4
DOE ID No.: MS-00946-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at Parcel No. A33240309003, East
Highway 666, in Monticello, Utah, is recommended for certification as
required by DOE guidelines, and the appropriate records should be
documented.
Standards Survey Results Applicability
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Certification Data Summary
Shall not exceed 20 //R/h
above background.*
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Shall not exceed 5 pCi/g
above background in the
15-cm surface layer,
averaged over 100 m2.
Range for the ground
floor was 12 to 13 //R/h.
Average was 0.0019 WL,
based on the DOE-
approved abbreviated-
measurement method.
< 5 pCi/g above
background.**
Shall not exceed 15 pCi/g Soil sample result was
above background in any 3.2 pCi/g.**
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
*The background exposure rate is approximately 13 //R/h.
The background radium-226 concentration is approximately 2.0 pCi/g.
**The hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-00946-RS
4.0 APPENDIX
Appendix Tables:
Table 3.1 Post-Excavation Sample/Measurement Results
Table 3.2 Radon Decay-Product Concentration Measurement
Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
SJW:04-29-96
MS-00946.RS WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00946-RS
Address: Parcel No. A33240309003, East Highway 666, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range U/R/h) Ticket No. Method" (pCi/g)
V-1 12-16 NCG 192 OCS 3.2
See Appendix Figure 2.1 for the verification area.
"OCS = Opposed Crystal System
7
Table 3.2
Radon Decay-Product Concentration Measurement Results
DOE ID No.: MS-00946-RS
Address: Parcel No. A33240309003, East Highway 666, Monticello, Utah
Instrument Type: Landauer Radtrak Detector
Detector
Number Start Date End Date
Radon
Concentration
(pCi/L)
Working
Level
3964212
3964306
3964378
03-01-95
03-01-95
03-01-95
06-05-95
06-05-95
06-05-95
0.31 0.0016
0.36 0.0018
0.48 0.0024
J
Average: 0.0019
See Appendix Figure 2.1 for the measurement location.
8
10
30
12 14 16 20 22
nr
24 26 28
T
32 34 56 38 40
30
28
26
24
22
20
13-15
ONE STORY
FRAME HOUSE
12-13
13-15
12-16
(RDC)
V-1
12-16
©
13-15
©
<D
Lv.vj
12-15
1 2
V-1
16-17
(RDC)
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN /iR/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE-RATE RANGE
RADON DECAY-PRODUCT CONCENTRATION
MEASUREMENT LOCATION
28
26
24
22
20
18 1 8
DETAIL A
1 6
1 4
1 2
SHED
1 2/iR/K
13-15
Y
10
10
"777"
SHEDS
12-13
•
SEE
DETAIL A
HIGHWAY 666
NOT TO SCALE
13-15
-777-
SCALE IN FEET
20 10 0 20 40
X M:\FAS\033\0003\RM00946V 05/02/96 09:57am T50780
NORTH
1 2 1 4 1 6 18 20
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT. UTILITY LOCATION PLAT. OR OTHER IMPROVEMENT SURVEY
PLAT AND IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE. BUILDING. OR OTHER FUTURE IMPROVEMENT LINES.
22 24 26 28
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
RESIOENCE-NO. OF OCCUPANTS
NON-RCSIOENCE-MAN-HRS./WK.
INSTRUUENT NO.
SURVEY OATE
VERIFICATION
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE, COLORADO
CHECKED
PRdi. ENGR".
SUBMITTED
CRAI
PARCEL NO. A33240309003
EAST HIGHWAY 666
MONTICELLO, UTAH
Rust Qeotech
OAIE APPROVAL OOC
OOCIONO MS-00946-RS
OOC.NO. 3-B00946-V1 1
1 6
1 4
1 2
1 0
30 32 34 36 38 40
OAK RIDGE NATIONAL LABORATORY
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
FOR THE U.S. DEPARTMENT OF ENERGY
PHONE: [phone]
FAX: [phone]
POST OFFICE BOX 2507
GRANO JUNCTION. COLORADO 81502 we 3 o ms
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by
the U.S. Department of Energy for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program (FUSRAP) and Remote Surplus Facilities Management Program
Sites (SFMP) [Revision 2, March 1987]. This evaluation is based on an independent verifi-
cation review of the Remedial Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment of
the 226Ra concentration in the soil, indoor radon daughter concentration, and indoor gamma
exposure rates at this property.
This property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
Location Number: MS00946
Location Address: Parcel No. A33240309003
East Highway 666
Monticello, Utah 84535
Property Owner:

Tenant Name: Same
Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
PARCEL NO. A33240309003, EAST HIGHWAY 666
MONTICELLO, UTAH (MS00946-RS)
N. F. Kirby
August 1996
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 3
REFERENCES 6
iii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 4
2. Results of ORNL analysis of Geotech soil samples from Parcel No. A33240309O03,
East Highway 666, Monticello, Utah (MS00946-RS) 5
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site
Decommissioning Projects, U.S. Department of Energy. The author wishes to
acknowledge M. K. Jensen for analysis of soil samples and technical reviw and S. M.
Smith for technical review.
vii
ABSTRACT
In 1980 the site of a vanadium and uranium mill at Monticello, Utah, was accepted
into the U.S. Department of Energy's (DOE's) Surplus Facilities Management Program,
with the objectives of restoring the government-owned mill site to safe levels of radio-
activity, disposing of or containing the tailings in an environmentally safe manner, and
performing remedial actions on off-site (vicinity) properties that had been contaminated
by radioactive material resulting from mill operations. During 1994, RUST Geotech, the
remedial action contractor designated by DOE, performed remedial action on the vicinity
property at Parcel No. A33240309003, East Highway 666, Monticello, Utah. The Environ-
mental Technology Section (ETS) of Oak Ridge National Laboratory was assigned the re-
sponsibility of verifying the data supporting the adequacy of remedial action and confirming
the site's compliance with DOE guidelines. The ETS found that the site successfully meets
the DOE remedial action objectives. Procedures used by the ETS are described in the
Environmental Technology Section Procedures Manual (ORNL 1993).
ix
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT PARCEL NO. A33240309003, EAST HIGHWAY 666
MONTICELLO, UTAH (MS00946-RS)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the U.S. government through the
Defense Plant Corporation to provide vanadium during World War II. Various govern-
ment agencies operated the mill until 1947. In 1948 the Atomic Energy Commission
(AEC) obtained the mill and operated it under contract through 1959 to provide both
uranium and vanadium. Mill operations were terminated on January 1, 1960. In 1961 the
mill tailings piles were leveled and graded, covered with rock and soil, and seeded with na-
tive grasses. During 1974 and 1975, the ore stockpiles were removed from the site, and
the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city
of Monticello, in San Juan County, Utah. The site is bordered on the south and southeast
by land held by the U.S. Bureau of Land Management. Other boundaries are the city of
Monticello and private property.
During the AEC era, the mill processed approximately one million tons of uranium
ore. Vanadium and uranium were the only substances extracted in the milling process.
Other constituents of the ore remained in the tailings and were not separated prior to dis-
posal. During the years of active mill operation, the mill tailings were normally moist, so
erosion was minimal. However, throughout the mill's operating period, area residents
used these tailings as fill material and as aggregate in mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy
(DOE) initiated the Surplus Facilities Management Program (SFMP) in 1978 to ensure
the safe caretaking and decommissioning of government facilities that had been retired
from service but still had radioactive contamination. In 1980 the mill site at Monticello
was accepted into the SFMP, and the Monticello Remedial Action Project (MRAP) was
established to restore the government-owned mill site to safe levels of radioactivity, to
dispose of or contain the tailings in an environmentally safe manner, and to perform reme-
dial actions on off-site (vicinity) properties that had been contaminated by radioactive ma-
terial resulting from mill operations. The Monticello mill site and the tailings remain in the
custody of the DOE Grand Junction, Colorado, Projects Office. In 1983 remedial actions
for vicinity properties were separated from MRAP with establishment of the Monticello
Vicinity Properties (MVP) Project (U.S. DOE 1990b).
*The verification of remedial action was performed by members of the Environmental Assessment Group in the
Environmental Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE
contract DE-AC05-96OR22464 with Lockheed Martin Energy Research Corporation.
2
During 1994, RUST Geotech Inc. (Geotech), the remedial action contractor (RAC)
designated by DOE, performed remedial action on the vicinity property that is the subject
of this report, a single family residence located at Parcel No. A33240309003, East High-
way 666, Monticello, Utah. The remedial action plan required excavation of all exterior
contamination. When the excavation was completed, the property was resurveyed, in-
cluding soil sampling, to ensure the removal of all contamination, backfilled with uncon-
taminated material, and restored to a condition comparable to that which existed prior to
remedial action (Geotech 1996).
The DOE adopted a policy to assign an independent contractor to verify the data
supporting the adequacy of remedial action and to confirm the site's compliance with
DOE guidelines. The Environmental Technology Section (ETS) of Oak Ridge National
Laboratory (ORNL) has been assigned the responsibility of this task at the Parcel No.
A33240309003, East Highway 666 site. This report describes the methods and results
of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available doc-
umentation adequately and accurately describes the post-remedial-action radiological
conditions of the entire property that is to be certified and (2) that the remedial action
reduced contamination to below applicable DOE guidelines (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1996) in-
dicates the property was remediated as evaluated by DOE on the basis of Environmental
Protection Agency standards and the DOE guidelines (DOE 1990a). Excess residual
radioactive materials were present, thus it was appropriate to designate this property for
remedial action.
The pre-remedial-action survey performed by Geotech identified 4 yd3 of mill tailings
6 inches deep. During the actual removal process, a total of 4 yd3 of contaminated earth
and uranium mill tailings, 6 inches deep, were removed from an 18 m2 area.
A post-excavation survey was performed by Geotech prior to backfilling the exca-
vated areas. This survey consisted of gamma scans with a scintillometer of the ground
level of the structure, a surface scan of the exterior, and soil sampling. Samples repre-
sentative of the bottom 15-cm (6-in.) soil layers of the excavated verification area were
collected and blended to form a representative composite soil sample.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation
levels have not been subtracted. Similarly, background concentrations have not been sub-
tracted from radionuclide concentrations in soil samples. Applicable DOE guidelines for
protection against radiation are given in Table 1.
Gamma Measurements
Gamma exposure rate measurements taken by Geotech at the ground-level ofthe
residence ranged from 12 to 13 uR/h. Exterior surface gamma measurements taken from
the excavated areas prior to backfilling ranged from 12 to 16 uR/h.
Soil Sample Analysis
Prior to backfilling, Geotech collected soil samples representative of the excavated
area from the bottom 15-cm (6-in.) soil layers. These samples were blended to form a
composite soil sample representative of an average over the exterior verification area.
Geotech's analysis of this sample showed a 226Ra concentration of 3.2 pCi/g. ORNL ETS
obtained this sample and performed a confirmatory analysis which showed a 226Ra con-
centration of 1.6 pCi/g. These values are below the EPA standard value of 15 pCi/g for
soil layers >15 cm below the surface. Gamma ranges and/or soil sample results demon-
strate compliance to the DOE Hot Spot Guidelines for areas <25 m2 (Table 1). Results
of Geotech and ORNL soil sample analyses are given in Table 2.
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were deter-
mined by the Alpha-track method. To monitor radon levels, Geotech placed three alpha-
track detectors on the ground floor of the residence located on this property for a period
of approximately three months (from March 1, 1995 to June 5, 1995). The average an-
nual working level (WL) of radon progeny concentration, as determined by the Tech./Ops-
Landauer Corporation, was 0.0019, which is well below the 0.03-WL guideline given in
Table 1.
CONCLUSION
Results of Geotech soil sample analysis and confirmatory split soil sample analysis by
ORNL show that radionuclide concentrations are within applicable DOE guidelines.
Based on the results of the post-remedial-action data, which are confirmed by the
verification assessment data, these radiological measurements fall below the limits
prescribed by DOE guidelines. It is concluded that the site successfully meets the DOE
remedial action objectives.
4
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of n6Ra in soil
above background levels,
averaged over a 100-m2 area
5 pCi/g averaged over the
first 15 cm of soil below the
surface; 15 pCi/g when ave-
raged over 15-cm-thick soil
layers more than 15 cm
below the surface
Radionuclide con-
centrations in soil
for Hot Spot areas
Exposure to 222Rn
progeny
Maximum Permissible con-
centration of Ra226 in soil
above background level, for
areas less than 25 m2
Average annual radon proge-
ny concentration (including
background)
Ra226 concentrations, in any
surface or subsurface area
less than 25 m2, is below the
guideline by a factor of
(100/A)*, where A is the
area of the elevated region
0.03 WL
(DOE 1990a)
Table 2. Results of ORNL analysis of Geotech soil samples from
Parcel No. A33240309003, East Highway 666, Monticello, Utah (MS00946-RS)
M6Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No." No^ (cm)
XI NCG 192 >15 1.6 3.2
" An X-type sample is a split of the sample taken by the remedial action contractor.
h Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated areas
were taken by Geotech, and these samples were blended to form a composite soil
sample, which represents an average over one of the verification areas.
6
REFERENCES
Geotech 1996. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00946-RS, Address: Parcel No. A33240309003, East
Highway 666, Monticello, Utah 84535, Geotech, Grand Junction, Colorado, May 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
U.S. DOE 1990a. Verification and Certification Protocol for the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination
and Decommissioning Program, Revision 3, November 1990. U.S. Department of
Energy, Washington, D.C.
U.S. DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision
and Record of Decision Summary. U.S. Department of Energy, Grand Junction Projects
Office, Grand Junction, Colorado.
DOE ID No(s).: MS-00952-VL
Property Address(es): Parcel No. A33240310004, East Highway 666
Vicinity Property Certification Summary and Recommendation
Summary Evaluation
Certification Criteria MACTEC-ERS
U.S. Department
of Energy (DOE)
Ra-226 is s 5 pCi/g above background
in top 15-cm-thick layer of soil
averaged over 100 m2
In situ [X] Lab [ ]
Ra-226 is < 15 pCi/g above
background in any 15-cm-thick layer of
soil more than 15 cm below the
surface averaged over 100 m2.
In situ [ ]Lab[X]
Interior gamma is <; 20 uR/h above
background in any occupied or
habitable structure.
The radon decay-product
concentration in any occupied or
habitable structure is <. 0.02 WL or, at
most, 0.03 WL.
Supplemental standards were applied
in accordance with EPA standard
40 CFR 192.21.
Hot spot criteria met as outlined by
DOE guidelines for FUSRAP (Rev.2,
March 1987)
Yes No Not Taken Yes No Not Taken
[X]a [ ]
[X] [ ]
[ ] [ ]
[ ] [ I
[ 1 [X]
[X] [ ]
[ ]
[ ]
[X]b
[X]b
[ ]
[ ]
[>q [ ]
[XI I ]
[ ] [ ]
[ ] [ ]
[ ] [>3
[y] [ ]
[ ]
[ ]
[M
[ ]
[ ]
"The excavations were backfilled with materials that were measured at the source indicating that the Ra-226
concentrations are in the range of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
"Vacant lot.
•M1111IIII
•llllllllll
SFCERTIFED
SFMS-80952
lof2
DOE ID No(s).: MS-00952-VL
MACTEC-ERS Recommendation
On the basis of the MACTEC-ERS evaluation, this property is recommended for
[X] Certification by DOE.
[ ] Certification by DOE with the concurrence ofthe U.S. Nuclear Regulatory Commission
because supplemental standards were applied according to 40 CFR 192.21.
Michael C. Butherus
Manager, Monticello Programs
MACTEC-ERS
Date
DOE Evaluation
On the basis of the MACTEC-ERS recommendation, this property
[ x ] Should be certified by DOE.
[ ] Should be certified by DOE with the concurrence of the U. S. Nuclear Regulatory
Commission because supplemental standards were applied according to 40 CFR 192.21.
Certification Official
U.S. Department of Energy
Date
4>/1>
Work performed under DOE Contract No. DE-AC13-95GJ87335, Task Order No. 96-05.02.14:001
2 Of 2
Monticello Vicinity Properties Project
Property Completion Report
for
Monticello
Vicinity Property Remedial Action
for
DOE ID No(s).: MS-00952-VL
Address(es): Parcel No. A33240310004, East Highway 666
Monticello, Utah 84535
October 1996
Prepared for
U.S. Department of Energy
Albuquerque Operations Office
Grand Junction Projects Office
Prepared by
MACTEC-ERS*
Grand Junction, Colorado
Michael C. Butherus
Manager, Monticello Programs
Work performed under DOE Contract No. DE-AC13-95GJ87335
Task Order No. 96-05.02.14.001
*MACTEC-ERS has been granted authorization to conduct remedial action by the U.S. Department of Energy.
Remedial action was done in accordance with the U.S. Environmental Protection Agency "Standards for Cleanup of
Land and Buildings Contaminated with Residual Radioactive Materials from Inactive Uranium Processing Sites,"
40 CFR 192, Subpart B; and "Implementation," in 40 CFR 192, Subpart C, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
1
DOE ID No.: MS-00952-VL
Contents
Page
1.0 Summary 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Remedial Action Summary 2
2.0 Operations Summary 3
2.1 Remedial Action Plan 3
2.2 Assessed and Remediated Contamination 3
3.0 Verification Summary 4
3.1 Radiological Survey Data 4
3.1.1 Preremedial Action Survey 4
3.1.2 Postexcavation Survey 4
3.2 Recommendation for Certification 5
Table
Table 1. Certification Data Summary 5
Appendix
Appendix A. Radiological Conditions A-1
DOE/Grand Junction Projects Office
October 1996
MVP Property Completion Report
Page ii
DOE ID No.: MS-00952-VL
1.0 Summary
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce potential hazards to
the public resulting from long-term exposure to low-level radioactivity associated with the off-site
mill tailings derived from the former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States Government through its agent,
the Defense Plant Corporation, to provide additional sources of vanadium needed during World
War JJ. Various government agencies operated the mill until 1947. The AEC obtained the mill in
1948 and operated it through 1959 under cost-type contracts to process uranium and vanadium
ore. Mill operations were terminated on January 1, 1960.
The mill processed approximately one million tons of ore during AEC operations. Throughout the
operating period, mill tailings were removed from the Monticello millsite and used for
construction-related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for Remedial Actions at Inactive
Uranium Processing Sites" (40 CFR Part 192) for all cleanup activities under the MVP Project.
These standards were prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and open lands. Cleanup
activities also were conducted to meet the hot spot criteria established by radiological protection
guidelines in the DOE Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management Program Sites
(Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot-spot criteria and
determined to contain mill tailings (radioactive material) exceeding EPA standards and/or DOE
hot-spot criteria. The Remedial Action Contractor was notified of the inclusion of this property
into the MVP Project and was authorized by DOE to conduct remedial action as required to bring
the property into conformance with EPA standards and DOE hot-spot criteria.
DOE/Grand Junction Projects Office
October 1996
MVP Property Completion Report
Page 1
DOE ID No.: MS-00952-VL
1.3 Remedial Action Summary
DOE ID No(s).:
Legal Description:
MS-00952-VL
Beginning 58 feet south and 1,320 feet west of the NE comer of Section 31, T33S., R24E.,
Salt Lake Base Meridian; south 1,902 feet, west 220 feet, north 640 feet, west 114 feet, north
1,262 feet, east 334 feet to beginning, County of San Juan, State of Utah
Property Address(es):
Property Owner(s):
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological and Engineering Assessment (REA):
Construction Subcontractor:
Preconstruction Conference Record:
Notice of Final Completion Inspection:
Volume of Material Removed in Cubic Yards (yd3):
Area Cleaned Up in Square Meters (m2):
Property Completion Report Submitted:
Parcel No. A33240310004,
East Highway 666
Monticello, Utah 84535

Vacant Lot (VL)
Rust Geotech
November 2, 1993
MACTEC-ERS
July 25, 1994
Diamond Back Services, Inc.
August 21, 1995
September 18, 1995
Exterior: 277
Interior: 0
1,372
October 1996
DOE/Grand Junction Projects Office
October 1996
MVP Property Completion Report
Page 2
DOE ID No.: MS-O0952-VL
2.0 Operations Summary
2.1 Remedial Action Plan
The remedial action plan specified removal of radioactive material. Once excavation was
completed, the effected area(s) were resurveyed for possible remaining radioactive material and,
upon attaining satisfactory results, were backfilled with uncontaminated material. The property
was restored to a physical condition comparable to that which existed before remedial action
activities.
2.2 Assessed and Remediated Contamination
The radiological assessment identified 280 yd3 of contamination, 6 inches (in.) deep, within the
property boundary. The remedial action process included removal of approximately 277 yd3 of
radioactive material, ranging from 6 to 12 in. deep. The areas of assessed and excavated
contamination are shown on Figure A-1.
DOE/Grand Junction Projects Office
October 1996
MVP Property Completion Report
Page 3
DOE TD No.: MS-00952-VL
3.0 Verification Summary
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Preremedial Action Survey
The Remedial Action Contractor conducted a radiological survey during May and
November 1993, as described in the final REA. Figure A-1 shows the area(s) and depth(s) of
assessed contamination that are recommended for remedial action.
3.1.2 Postexcavation Survey
A scintillometer was used to perform a surface gamma scan after removal of radioactive material
and before backfilling. Following the gamma scan, soil samples representative of the 6-in.-thick
soil layer at the bottom of the excavation were collected. The results of gamma scans and analyses
for radium-226 are presented in Table A-1.
DOE/Grand Junction Projects Office
October 1996
MVP Property Completion Report
Page 4
DOE ID No.: MS-00952-VL
3.2 Recommendation for Certification
Radioactive materials have been removed from this property to the extent required by EPA
standards (40 CFR 192, Subparts B and C) and DOE hot-spot criteria, as indicated in the
Certification Data Summary (Table 1). Therefore, the property located at Parcel
No. A33240310004, East Highway 666, in Monticello, Utah, is recommended for certification as
required by DOE guidelines.
Table 1. Certification Data Summary
Applicability Standard Survey Results
Radium-226
Concentration in
Surface Soil
Radium-226
Concentration in
Subsurface Soil
Exposure Rate
Land
Shall not exceed 5 pCi/g above
background8 in the 15-cm-thick
surface layer, averaged over
100 m2.
Shall not exceed 15 pCi/g
above background8 in any
15-cm-thick soil layer more than
15 cm below the surface,
averaged over 100 m2.
Habitable Structures
< 5 pCi/g above background on the
basis of gamma exposure rates that do
not exceed 30 percent above normal
background."
Soil sample results ranged from < 1.0
to 6.4 pCi/g.b
Shall not exceed 20 uR/h above
background.
Not applicable; vacant lot.
Radon Decay- Annual average shall not Not applicable; vacant lot.
Product exceed 0.02 WL, to the extent
Concentration practicable, and shall in no
case exceed 0.03 WL.
Key: cm = centimeters; m2 = square meters; pCi/g = picocuries per gram; uR/h = microroentgens per hour
aThe background radium-226 concentration for Monticello Vicinity Properties is approximately 2.0 pCi/g.
'The hot-spot criteria were met based on gamma scans and/or soil sample results.
DOE/Grand Junction Projects Office
October 1996
MVP Property Completion Report
Page 5
DOE ID No.: MS-00952-VL
Appendix A
Radiological Conditions
Table A-1. Postexcavation Survey Results
Figure A-1. Radiological As-Built
DOE ID No.: MS-00952-VL
Table A-1. Postexcavation Survey Results
Verification
Area*
Gamma
Exposure Rate
Range (pR/h)
Soil Sample
Ticket No.
Measurement
Method
Radium-226
Concentration
(pCi/g)
V-1
V-2
V-3
V-4
V-5
V-6
V-7
V-8
V-9
V-10
V-11
V-12
V-13
V-14
V-15
V-16
V-17
V-18
16-19
14-15
14-16
14-16
14-17
13-14
13- 15
14- 16
14-15
13- 15
14- 17
13- 15
14- 17
13-15
13-15
13- 15
14- 16
13-16
NCL 762
NCL 732
NCL 733
NCL 734
NCL 735
NCL 736
NCN 639
NCN 640
NCN 641
NCN 642
NCN 643
NCN 644
NCN 645
NCN 646
NCN 647
NCN 648
NCN 649
NCN 650
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
6.4
2.9
1.0
3.5
1.4
2.7
< 1.0
1.3
1.9
1.7
3.2
3.0
3.2
1.9
< 1.0
2.1
2.2
2.1
Key: OCS = opposed crystal system; pCi/g = picocuries per gram; uR/h = microroentgens per hour;
V = verification area
"See Figure A-1 for location of verification areas.
DOE/Grand Junction Projects Oftice
October 4, 1996
UMTRA Property Completion Report
Page A-2
56
54
52
50
48
46
44
42
40
36
36
34
32
30
28
26
24
22
20
18
16
14
12
10
T—i—i—i—i—i—i—i—r
22 24
"l 1 1 r-"i i i i r
36
T—r-
40
1 r-
44 46
"I 1 1 1-
48
T-
50
T" T—i—r
54
-T-
56
1—i—i—r
66
-i—r
70
1—r i—r 1—r
777 777—|
EAST HIGHWAY 666 , •
_ /// __ ///A I
SEE DETAIL B
L
I I I I I I I
NOT TC SCALE
I I I I I
EAST HIGHWAY 666
•HD
12-16
©\ \
V-1B
SHED
12-13
© 6 K6AC
B ra
7 m ra ra ra v-i
© ra 6 (6 IB
ra ra 12-16
© © ra ra ra
SCALE IN FEET
I I ' I t L ' I
20 10 0
I t I t I I
©
Lv_l
12-15
| v-10
IFGFNO
ALL OEPTHS/HEICHTS IM INCHES
ALL EXPOSURE RATES IN pR/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
EXPOSURE-RATE RANGE
BOUNOARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION AREA IDENTIFIER
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
THIS DRAWING tS TOR TH£ SOLE USC Or THE U S DEPARTMENT
OE ENERGY 'NO TS CONTRACTORS. IT IS NOT A LANQ SURVEY
PLAT, UTILITY LOCATION PLAT. ON OTHER lUPROvEWENT SURVEY
PLAT ANO IS NOT TO IE REuEO UPON roR THE ESTABLISHMENT
Of TENCE. BUiLCiNC. OR OTHER FUTURE IMPROVEMENT LINES
I I I I • III
PARCEL A3J2.03I0004
EAST KWY 666
MONTICELLO, UTAH
U.S. DEPARTMENT OF ENERGY
OPA.HD JUNCTION PROJECrs OFFICE. COLOR AO 0
COMPLETION REPORTS UONTiCEU.0 VICINITY PROPERTIES
FIGURE A-1
RADIOLOGICAL AS-BUILT
US-00952-VL
1 1
OAK RIDGE NATIONAL LABORATORY PHONE: [phone]
FAX: (970) 248-S220 MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
FOR THE U.S. DEPARTMENT OF ENERGY
2597 B'/A Road
GRAND JUNCTION, COLORADO 81503 ffB 2 8 mi
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by the U.S.
Department of Energy for Residual Radioactive Material at Formerly Utilized Sites Remedial
Action Program (FUSRAP) and Remote Surplus Facilities Management Program Sites (SFMP)
[Revision 2, March 1987]. This evaluation is based on an independent verification review of the
Remedial Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment of the
226Ra concentration in the soil.
This property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
Location Number:
Location Address:
MS00952-VT.
Parcel No. A33240310004. East Highway 666
Monticello. Utah 84535

Vacant lot
Property Owner:
Owner Address:
Tenant Name:
Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
PARCEL NO. A33240310004, EAST HIGHWAY 666
MONTICELLO, UTAH (MS00952-VL)
M.K. Jensen
February 1997
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81503
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS , vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 3
REFERENCES 6
iii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 4
2. Results of ORNL analysis ofthe RAC soil samples from Parcel No. A33240310004, East
Highway 666, Monticello, Utah (MS00952-VL) 5
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site Decommissioning
Projects, U.S. Department of Energy. The author wishes to acknowledge A. D. Laase and A. R.
Jones for technical reviews.
vii
ABSTRACT
In 1980, the site of a vanadium and uranium mill at Monticello, Utah, was accepted into the U.S.
Department of Energy (DOE) Surplus Facilities Management Program, with the objectives of
restoring the government-owned mill site to safe levels of radioactivity, disposing of or containing
the tailings in an environmentally safe manner, and performing remedial actions on off-site (vicinity)
properties that had been contaminated by radioactive material resulting from mill operations. During
1995, the Remedial Action Contractor (RAC) designated by DOE, performed remedial action on the
vicinity property at Parcel No. A33240310004, East Highway 666, Monticello, Utah. The
Environmental Technology Section (ETS) of Oak Ridge National Laboratory was assigned the
responsibility of verifying the data supporting the adequacy of remedial action and confirming the
site's compliance with DOE guidelines. The ETS found that the site successfully meets the DOE
remedial action objectives. Procedures used by the ETS are described in the Environmental
Technology Section Procedures Manual (ORNL 1993).
IX
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT PARCEL NO. A33240310004, EAST HIGHWAY 666
MONTICELLO, UTAH (MS00952-VL)*
INTRODUCTION
The rnill at Monticello, Utah, was built in 1942 by the United States (U.S.) government through
the Defense Plant Corporation to provide vanadium during World War II. Various government
agencies operated the mill until 1947. In 1948, the Atomic Energy Commission (AEC) obtained the
mill and operated it under contract through 1959 to provide both uranium and vanadium. Mill
operations were terminated on January 1, 1960. In 1961, the mill tailings piles were leveled and
graded, covered with rock and soil, and seeded with native grasses. During 1974 and 1975, the ore
stockpiles were removed from the site and the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city of
Monticello, in San Juan County, Utah. The site is bordered on the south and southeast by land held
by the U.S. Bureau of Land Management. Other boundaries are the city of Monticello and private
property.
During the AEC era, the mill processed approximately one million tons of uranium ore. Vana-
dium and uranium were the only substances extracted in the milling process. Other constituents of
the ore remained in the tailings and were not separated prior to disposal. During the years of active
mill operation, the mill tailings were normally moist, so erosion was minimal. However, throughout
the mill's operating period, area residents used these tailings as fill material and as aggregate in mortar
and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy (DOE) initiated
the Surplus Facilities Management Program (SFMP) in 1978 to ensure the safe caretaking and de-
commissioning of government facilities that had been retired from service but still had radioactive
contamination. In 1980, the mill site at Monticello was accepted into the SFMP, and the Monticello
Remedial Action Project (MRAP) was established to restore the government-owned mill site to safe
levels of radioactivity, to dispose of or contain the tailings in an environmentally safe manner, and to
perform remedial actions on off-site (vicinity) properties that had been contaminated by radioactive
material resulting from mill operations. The Monticello mill site and the tailings remain in the custody
ofthe DOE Grand Junction, Colorado, Projects Office. In 1983, remedial actions for vicinity
properties were separated from MRAP with establishment of the Monticello Vicinity Properties
(MVP) Project (US DOE 1990b).
*The verification of remedial action was performed by members ofthe Environmental Assessment Group in the Environmental
Technology Section ofthe Health Sciences Research Division at Oak Ridge National Laboratory under DOE contract DE-AC05-
960R22464 with Lockheed Martin Energy Research Corporation.
2
During 1995, the Remedial Action Contractor (RAC) designated by DOE, performed remedial
action on the vicinity property that is the subject of this report, a vacant lot located at Parcel No.
A33240310004, East Highway 666, Monticello, Utah. The remedial action plan required excavation
of all exterior contamination. When the excavation was completed, the property was resurveyed,
including soil sampling, to ensure the removal of all contamination, backfilled with uncontaminated
material, and restored to a condition comparable to that which existed prior to remedial action
(MACTEC-ERS 1996).
DOE adopted a policy to assign an independent contractor to verify the data supporting the
adequacy of remedial action and to confirm the site's compliance with DOE guidelines. The Environ-
mental Technology Section (ETS) of Oak Ridge National Laboratory (ORNL) has been assigned the
responsibility of this task at Parcel No. A33240310004, East Highway 666 site. This report describes
the methods and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available documentation
adequately and accurately describes the post-remedial-action radiological conditions of the entire
property that is to be certified and (2) that the remedial action reduced contamination to below
applicable DOE guidelines (US DOE 1990a).
Document Reviews
Review of the RAC property completion report (MACTEC-ERS 1996) indicates the property
was remediated as evaluated by DOE on the basis of U.S. Environmental Protection Agency
standards and the DOE guidelines (US DOE 1990a). Excess residual radioactive materials were
present, thus it was appropriate to designate this property for remedial action.
The pre-remedial-action survey performed by the RAC identified 230 yd3 of mill tailings 6 inches
deep. During the actual removal process, a total of 277 yd3 of contaminated earth and uranium mill
tailings, 6 to 12 inches deep, were removed from a 1,372 nr area.
The RAC performed a post-excavation survey prior to backfilling the excavated areas. This
survey consisted of gamma scans with a scintillometer of the exterior, and soil sampling. Samples
representative ofthe bottom 15-cm (6-in.) soil layers of eighteen excavated verification areas were
collected and blended to form representative composite soil samples for each verification area.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation levels have
not been subtracted. Similarly, background concentrations have not been subtracted from radionu-
clide concentrations in soil samples. Applicable DOE guidelines for protection against radiation are
given in Table 1.
Gamma Measurements
Exterior surface gamma exposure rate measurements taken by the RAC from the excavated areas
prior to backfilling ranged from 13 to 19 uR/h.
Soil Sample Analysis
Prior to backfilling, the RAC collected soil samples representative of the excavated areas from
the bottom 15-cm (6-in.) soil layers. These samples were blended to form composite soil samples
representative of an average over the eighteen exterior verification areas. The RAC's analysis of these
samples showed 226Ra concentrations ranging from <1.0 to 6.4 pCi/g in the composite samples.
ORNL ETS obtained a percentage of these samples and performed a confirmatory analysis which
showed 226Ra concentrations ranging from 1.3 to 5.8 pCi/g. These values are below the DOE
guideline value of 15 pCi/g for soil layers > 15 cm below the surface. Gamma ranges and/or soil
sample results demonstrate compliance to the DOE Hot Spot Guidelines for areas <25 m2 (Table 1).
Results of the RAC and ORNL soil sample analyses are given in Table 2.
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were not taken as this
property has no habitable structures.
CONCLUSION
Results of RAC soil sample analysis and confirmatory split soil sample analysis by ORNL, show
that radionuclide concentrations are within applicable DOE guidelines. Based on the results of the
post-remedial-action data, which are confirmed by the verification assessment data, these radiological
measurements fall below the limits prescribed by DOE guidelines. It is concluded that the site
successfully meets the DOE remedial action objectives.
4
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of 226Ra in soil
above background levels,
averaged over a 100-m2
area
5 pCi/g averaged over the first 15 cm
of soil below the surface; 15 pCi/g
when averaged over 15-cm-thick soil
layers more than 15 cm below the
surface
Radionuclide con-
centrations in soil
for Hot Spot areas
Exposure to 222Rn
progeny
Maximum Permissible con-
centration of Ra226 in soil
above background level,
for areas less than 25 m2
Average annual radon
progeny concentration
(including background)
Ra226 concentrations, in any surface
or subsurface area less than 25 m2,
is below the guideline by a factor of
(100/A)'71, where A is the area of the
elevated region
0.03 WL
(US DOE 1990a)
5
Table 2. Results of ORNL analysis of the RAC soil samples from
Parcel No. A33240310004, East Highway 666, Monticello, Utah (MS00952-VL)
'Ra concentration (pCi/g)
ORNL RAC
sample sample Depth ORNL RAC
No.a No_^ (cm)
XI NCL 762 >15 5.8 6.4
X6 NCL 736 >15 1.6 2.7
X8 NCL 640 >15 1.3 1.3
X12 NCN 644 >15 1.8 3.0
X15 NCN 647 >15 1.5 <1.0
X17 NCN 649 >15 1.4 2.2
" An X-type sample is a split of the sample taken by the remedial action contractor.
* Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated areas were
taken by the RAC, and these samples were blended to form a composite soil sample, which
represents an average over one of the verification areas.
6
REFERENCES
MACTEC-ERS 1996. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00952-VL, Address: Parcel No. A33240310004, East Highway 666,
Monticello, Utah 84535, MACTEC-ERS, Grand Junction, Colorado, October 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment Group)
Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National Laboratory, Grand
Junction, Colorado.
US DOE 1990a. Verification and Certification Protocol for the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination and
Decommissioning Program. Revision 3, November 1990. U.S. Department of Energy, Washington,
D.C.
US DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision and Record
of Decision Summary. U.S. Department of Energy, Grand Junction Projects Office, Grand Junction,
Colorado.
DOE ID No.: MS-00958-RS
Property Address: Parcel No. A33240310002, East Highway 666
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust flflotech of Energy (DQE)
Ra-226 is s 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [X]T
Ra-226 is <; 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2.
In-situ [ ] Lab [X]
Interior gamma is £ 20 //R/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is <; 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21.
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] 11
[X] [ ] [ ]
I ] [ ] [X]**
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
Mil i 1
IX I 1 11
MM M
I 1 [>] I ]
[XI [ 1 I ]
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of oamma
exposure rates that do not exceed 30 percent above normal background.
fPart of one sample was from the top layer, and was lab-analyzed.
**Trailer house.
•iiiiiiiiiii iniiiiiiiiHi
SFCERTIFED SFMS-00958
DOE ID No.: MS-00958-RS
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Wanda s: Busby Date
Manager, Monticello Programs
Rust Geotech
DOE EVALUATION
be] Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Ceijpfication Official
U.S. Department of Energy
Date
2^L
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00958-RS
ADDRESS: PARCEL NO. A33240310002
EAST HIGHWAY 666
MONTICELLO, UTAH 84535
AUGUST 1996
Prepared for
U.S. Department of Energy
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
by
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
Manager, Monticello Programs
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.1.3 Radon Decay-Product Concentration (RDC) Measurement .... 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
DOE ID No.: MS-00958-RS
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Inclusion Survey Contractor. DOE reviewed
these evaluation results and determined that the property contained mill
tailings (residual radioactive material) exceeding DOE hot spot criteria.
The Remedial Action Contractor was notified of the inclusion of this
property into the MVP Project and was authorized by DOE to conduct
remedial action as required to bring the property into conformance with
EPA standards and DOE hot spot criteria.
1
DOE ID No.: MS-00958-RS
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
Property Address:
Property Owners:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
MS-00958-RS
Beginning 55 feet south and 276 feet west
of the NE corner of Section 31, T33S.,
R24E., Salt Lake Base Meridian; south
286 feet, east 236 feet, south 979 feet,
west 620 feet, north 1,263.5 feet, east
384 feet to beginning, County of San Juan,
State of Utah
Parcel No. A33240310002
East Highway 666
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
March 5, 1992
Rust Geotech
February 9, 1995
Diamond Back Services, Inc.
9861 Titan Park Circle
Littleton, Colorado
September 8, 1995
September 18, 1995
Interior:
Exterior:
0 cubic yards
11 cubic yards
79 square meters (m2)
August 1996
2
DOE ID No.: MS-00958-RS
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of exterior residual radioactive
material (Appendix Figure 2.1). Once excavation was complete, the
affected areas were resurveyed for possible remaining residual radioactive
material and, upon attaining satisfactory results, were backfilled with
uncontaminated material. The property was restored to a physical
condition comparable to that which existed prior to remedial action
activities.
2.2 Previously Unidentified Contamination
The radiological assessment identified 13 cubic yards of contamination,
6 inches deep, within the property. The remedial action process included
the removal of approximately 11 cubic yards of residual radioactive
material, ranging from 1 to 6 inches deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
Assessed Area C (55-gallon drum) and Area D (mining equipment) were
removed prior to remedial action. Assessed Area J (mining equipment)
was cleaned and relocated, and underlying unassessed contaminated soil
was remediated.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID No.: MS-00958-RS
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by the Remedial Action
Contractor during August 1992, as described in the final REA
dated February 1995. Appendix Figure 2.1 shows the extent of
assessed contamination and identifies the areas recommended to
undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the excavation were
collected. These samples were blended to form composite
samples representing the verification areas (Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 12 to 17 microroentgens per
hour OvR/h), as indicated on Appendix Figure 2.1. The results of
analyses for radium-226 in two composite soil samples were
1.7 and 2.6 picocuries per gram (pCi/g), as indicated in Appendix
Table 3.1.
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
RDC measurements were not taken in the trailer house due to
excessive ventilation caused by no permanent foundation.
4
DOE ID No.: MS-00958-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at Parcel No. A33240310002,
East Highway 666, in Monticello, Utah, is recommended for
certification as required by DOE guidelines, and the appropriate records
should be documented.
Certification Data Summary
Applicability
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Standards
Shall not exceed 20 //R/h
above background.*
Annual average shall not
exceed 0.02 working
level (WL), to the extent
practicable, and in no
case shall exceed
0.03 WL.
Survey Results
Range for the ground
floor was 12 to 13 //R/h.
Not applicable: trailer
house.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
< 5 pCi/g above
background.**
Soil sample results were
1.7 and 2.6 pCi/g.
*The background exposure rate is approximately 14 yR/h.
The background radium-226 concentration is approximately 2.0 pCi/g.
**A part of sample V-2 was from the 15-cm surface layer.
The hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-00958-RS
4.0 APPENDIX
Appendix Table:
Table 3.1 Post-Excavation Sample/Measurement Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
RKJ:07-17-96
MS-00958.RS WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00958-RS
Address: Parcel No. A33240310002, East Highway 666, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range OtvR/h) Ticket No. Method" (pCi/g)
V-1 13-17 NCN 651 OCS 2.6
V-2 13-17 NCN 652 OCS 1.7
See Appendix Figure 2.1 for the verification areas.
"OCS = Opposed Crystal System
7
42
40
38
36
34
32
30
28
26
24
22
20
18
16
1 4
12
10
12 14 16 18 20 22 24 26
1 F
HsXDE
V-1
13-17
TRAILER HOUSE
12-13
S4P
V-2
13-17
V-1
13-17 KX6 6
mm
13-15
V-2
13-17
28 30 32 34 36
D r
14-16
LU--
E X 6 v-i
13-17
O CD
SHED
12-13
v-i
13-17 SHED
12-13
v-2
13-17
/::::
SHED -12MR/h
12fiR/h-
SHED
<4
DETAIL A
14-15
L
DETAIL B
U:\FAS\033\0003\RU00938V 07/22/96 t:46pm 150^80
_1 L
12
13-15
Y-I
13-17
DETAIL C
20 10
NORTH
SCALE IN FEET
20
38 40 42
US HIGHWAY 666
46 48 50
©
<D
Lv.vj
12-15
12
v-i
16-17
-K-K-
13-15
Jg- DETAIL C
I DETAIL B
I
DETAIL A
13-15 1
13-15 J
KEY MAP
NOT TO SCALE
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN ^R/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE-RATE RANGE
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
ASSESSED AREA C (DRUM) AND AREA 0 (MINING
EQUIPMENT) WERE REMOVED PRIOR TO REMEDIAL
ACTION
ASSESSED AREA J (MINING EOUIPMENT) WAS
CLEANED AND RELOCATED. AND UNASSESSEO
CONTAMINATED SOIL WAS REMEDIATED
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
40
THIS DRAWING IS TOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT, UTILITY LOCATION PLAT. OR OTHER IMPROVEMENT SURVEY
PLAT ANO IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE, BUILDING. OR OTHER FUTURE IMPROVEMENT LINES.
• -•CMWCI-MM-HHI /WK.
VfJUrCAIIOM
U.S. DEPARTMENT OF ENERGY
MANO .UNCTION PROJCCTS OFFICE, COLOMOO
PARCEL NO. A33240310002
EAST HIGHWAY 666
MONTICELLO. UTAH
l^fftj RustCteotMh MS-00958-RS
14 16 18 20 22 24 26 28 30 32 34 36 38 40 42 44 46 48 5'
OAK RIDGE NATIONAL LABORATORY
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
FOR THE U.S. DEPARTMENT OF ENERGY
PHONE: [phone]
FAX: [phone]
2597 B*/4 Road
GRAND JUNCTION, COLORADO 81503
M 31 mi
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by the U.S.
Department of Energy for Residual Radioactive Material at Formerly Utilized Sites Remedial
Action Program (FUSRAP) and Remote Surplus Facilities Management Program Sites (SFMP)
[Revision 2, March 1987]. This evaluation is based on an independent verification review of the
Remedial Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment ofthe
226Ra concentration in the soil and indoor gamma exposure rates at this property.
This property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
MS0Q958-RS
Parcel No. A33240310002
East Highway 666
Monticello. Utah 84535

Location Number :
Location Address:
Property Owner:
Owner Address:
Tenant Name:
Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 401)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
PARCEL NO. A33240310002, EAST HIGHWAY 666
MONTICELLO, UTAH (MS00958-RS)
A. R. Jones
January 1997
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81503
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION • 3
REFERENCES 6
iii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 4
2. Results of ORNL analysis ofthe RAC soil samples from Parcel No. A33240310002, East
Highway 666, Monticello, Utah (MS00958-RS) 5
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site Decommissioning
Projects, U.S. Department of Energy. The author wishes to acknowledge M. K. Jensen for analysis
of soil samples and S. M. Smith and T. L. Meyer for technical reviews.
vii
ABSTRACT
In 1980, the site of a vanadium and uranium mill at Monticello, Utah, was accepted into the
U.S. Department of Energy (DOE) Surplus Facilities Management Program, with the objectives of
restoring the government-owned mill site to safe levels of radioactivity, disposing of or containing
the tailings in an environmentally safe manner, and performing remedial actions on off-site (vicinity)
properties that had been contaminated by radioactive material resulting from mill operations. During
1995, the Remedial Action Contractor (RAC) designated by DOE, performed remedial action on the
vicinity property at Parcel No. A33240310002, East Highway 666, Monticello, Utah. The Environ-
mental Technology Section (ETS) of Oak Ridge National Laboratory was assigned the responsibility
of verifying the data supporting the adequacy of remedial action and confuming the site's compliance
with DOE guidelines. The ETS found that the site successfully meets the DOE remedial action
objectives. Procedures used by the ETS are described in the Environmental Technology Section
Procedures Manual (ORNL 1993).
ix
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT PARCEL NO. A33240310002, EAST HIGHWAY 666
MONTICELLO, UTAH (MS00958-RS)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the United States (U.S.) government through
the Defense Plant Corporation to provide vanadium during World War II. Various government
agencies operated the mill until 1947. In 1948, the Atomic Energy Commission (AEC) obtained the
mill and operated it under contract through 1959 to provide both uranium and vanadium. Mill
operations were terminated on January 1, 1960. In 1961, the mill tailings piles were leveled and
graded, covered with rock and soil, and seeded with native grasses. During 1974 and 1975, the ore
stockpiles were removed from the site and the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city of
Monticello, in San Juan County, Utah. The site is bordered on the south and southeast by land held
by the U.S. Bureau of Land Management. Other boundaries are the city of Monticello and private
property.
During the AEC era, the mill processed approximately one million tons of uranium ore. Vana-
dium and uranium were the only substances extracted in the milling process. Other constituents of
the ore remained in the tailings and were not separated prior to disposal. During the years of active
mill operation, the mill tailings were normally moist, so erosion was minimal. However, throughout
the mill's operating period, area residents used these tailings as fill material and as aggregate in
mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy (DOE) initiated
the Surplus Facilities Management Program (SFMP) in 1978 to ensure the safe caretaking and de-
commissioning of government facilities that had been retired from service but still had radioactive
contamination. In 1980, the mill site at Monticello was accepted into the SFMP, and the Monticello
Remedial Action Project (MRAP) was established to restore the government-owned mill site to safe
levels of radioactivity, to dispose of or contain the tailings in an environmentally safe manner, and
to perform remedial actions on off-site (vicinity) properties that had been contaminated by radio-
active material resulting from mill operations. The Monticello mill site and the tailings remain in
the custody of the DOE Grand Junction, Colorado, Projects Office. In 1983, remedial actions for
vicinity properties were separated from MRAP with establishment of the Monticello Vicinity Proper-
ties (MVP) Project (US DOE 1990b).
•The verification of remedial action was performed by members of the Environmental Assessment Group in the Environmental
Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE contract DE-AC05-
960R22464 with Lockheed Martin Energy Research Corporation.
2
During 1995, the Remedial Action Contractor (RAC) designated by DOE, performed remedial
action on the vicinity property that is the subject of this report, a single family residence located at
Parcel No. A33240310002, East Highway 666, Monticello, Utah. The remedial action plan required
excavation of all exterior contamination. When the excavation was completed, the property was
resurveyed, including soil sampling, to ensure the removal of all contamination, backfilled with
uncontaminated material, and restored to a condition comparable to that which existed prior to
remedial action (Geotech 1996).
DOE adopted a policy to assign an independent contractor to verify the data supporting the
adequacy of remedial action and to confirm the site's compliance with DOE guidelines. The
Environmental Technology Section (ETS) of Oak Ridge National Laboratory (ORNL) has been
assigned the responsibility of this task at the Parcel No. A33240310002, East Highway 666 site.
This report describes the methods and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available documentation
adequately and accurately describes the post-remedial-action radiological conditions ofthe entire
property that is to be certified and (2) that the remedial action reduced contamination to below
applicable DOE guidelines (US DOE 1990a).
Document Reviews
Review of the RAC property completion report (Geotech 1996) indicates the property was reme-
diated as evaluated by DOE on the basis of U.S. Environmental Protection Agency standards and
the DOE guidelines (US DOE 1990a). Excess residual radioactive materials were present, thus it
was appropriate to designate this property for remedial action.
The pre-remedial-action survey performed by the RAC identified 13 yd3 of contamination 6
inches deep. During the actual removal process, a total of 11 yd3 of contaniinated earth and uranium
mill tailings, 1 to 6 inches deep, were removed from a 79 m2 area.
The RAC performed a post-excavation survey prior to backfilling the excavated areas. This
survey consisted of gamma scans with a scintillometer of the ground level of the structure, a surface
scan of the exterior, and soil sampling. Samples representative of the bottom 15-cm (6-in.) soil
layers of two excavated verification areas were collected and blended to form representative
composite soil samples for each verification area.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation levels have
not been subtracted. Similarly, background concentrations have not been subtracted from radionu-
clide concentrations in soil samples. Applicable DOE guidelines for protection against radiation are
given in Table 1.
Gamma Measurements
Gamma exposure rate measurements taken by the RAC at the ground-level of the residence
ranged from 12 to 13 uR/h. Exterior surface gamma measurements taken from the excavated areas
prior to backfilling ranged from 13 to 17 uR/h.
Soil Sample Analysis
Prior to backfilling, the RAC collected soil samples representative of the excavated areas from
the surface and subsurface 15-cm (6-in.) soil layers. These samples were blended to form a
composite soil sample representative of an average over the two exterior verification areas. The
RAC's analysis of these samples showed 226Ra concentrations to range from 1.7 to 2.6 pCi/g in the
composite sample. ORNL ETS obtained these samples and performed a confirmatory analysis that
showed 226Ra concentrations ranging from 1.6 to 3.0 pCi/g. The sample for V2 contains soil from
the surface soil interval. These values are below the DOE guideline value of 5 pCi/g for soil layers
<15 cm and 15 pCi/g for soil layers >15 cm below the surface. Gamma ranges and/or soil sample
results demonstrate compliance to the DOE Hot Spot Guidelines for areas <25 m2 (Table 1). Results
of the RAC and ORNL soil sample analyses are given in Table 2.
Radon Measurement Results
Radon measurements were not collected on this property due to excessive ventilation in the
trailer house.
CONCLUSION
Results of RAC soil sample analysis and confirmatory split soil sample analysis by ORNL,
show that radionuclide concentrations are within applicable DOE guidelines. Based on the results
of the post-remedial-action data, which are confirmed by the verification assessment data, these
radiological measurements fall below the limits prescribed by DOE guidelines. It is concluded that
the site successfully meets the DOE remedial action objectives.
4
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of 226Ra in soil
above background levels,
averaged over a 100-m2
area
5 pCi/g averaged over the first 15 cm
of soil below the surface; 15 pCi/g
when averaged over 15-cm-thick soil
layers more than 15 cm below the
surface
Radionuclide con-
centrations in soil
for Hot Spot areas
Exposure to 222Rn
progeny
Maximum Permissible con-
centration of Ra226 in soil
above background level,
for areas less than 25 m2
Average annual radon
progeny concentration
(including background)
Ra226 concentrations, in any surface
or subsurface area less than 25 m2,
is below the guideline by a factor of
(100/A)'/j, where A is the area of the
elevated region
0.03 WL
(US DOE 1990a)
5
Table 2. Results of ORNL analysis of the RAC soil samples from
Parcel No. A33240310002, East Highway 666, Monticello, Utah (MS00958-RS)
^Ra concentration (pCi/g)
ORNL RAC
sample sample Depth ORNL RAC
No." Nol {£21}
XI NCN651 >15 1.6 2.6
X2 NCN652 < 15 3.0 1.7
" An X-type sample is a split of the sample taken by the remedial action contractor.
* Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated areas were taken by
the RAC, and these samples were blended to form a composite soil sample, which represents an average
over one of the verification areas.
6
REFERENCES
Geotech 1996. Property Completion Report for Monticello Vicinity Property Remedial Action for
DOE ID NO: MS00958-RS, Parcel No. A33240310002, East Highway 666, Monticello, Utah 84535,
RUST Geotech, Grand Junction, Colorado, August 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment Group)
Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National Laboratory, Grand
Junction, Colorado.
US DOE 1990a. Verification and Certification Protocolfor the Office of Environmental Restoration,
Formerly Utilized Sites Remedial Action Programs and Decontamination and Decommissioning
Program. Revision 3, November 1990. U.S. Department of Energy, Washington, D.C.
US DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision and Record
of Decision Summary. U.S. Department of Energy, Grand Junction Projects Office, Grand Junction,
Colorado.
DOE ID No.: MS-01002-VL
Property Address: Parcel No. 33S24E324801, East Clay Hill Drive
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Gpotech of Energy (DOE)—
YES NO NOT TAKEN YES NO NOT TAKEN
Ra-226 is & 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2. [X]* [ ] [ ] [*l [ ] [ ]
In-situ [X] Lab [ ]
Ra-226 is s 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2. [X] [ ] [ ] [A \ \ I 1
In-situ [ ] Lab [X]
Interior gamma is a 20 //R/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is s 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21.
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987). [X] [ ] [ ] M [ ] [ ]
COMMENTS: »The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
Ililllllllll Ililllllllll
SFCERTIFED SFMS-01001
[ ] [ ] IX] I ] [ ] lx]
(Vacant Lot)
[ ] I ] IX] [ ] [ ] [A
(Vacant Lot)
[ ] [X] [ ] [ ] m [ ]
DOE ID No.: MS-01002-VL
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Wanda S. Btrsby Date
Manager, Monticello Programs
Rust Geotech
DOE EVALUATION
\A Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Certification Official Date
U.S. Department of Energy
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-01002-VL
ADDRESS: PARCEL NO. 33S24E324801
EAST CLAY HILL DRIVE
MONTICELLO, UTAH 84535
FEBRUARY 1996
Prepared for
U.S. Department of Energy
by
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
Wanda S. Busby
Manager, Monticello Programs
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
•iiiiiiiiiii minimi
SFOCPLRPTS SFMS-01001
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
DOE ID No.: MS-01002-VL
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Inclusion Survey Contractor. DOE reviewed
these evaluation results and determined that the property contained mill
tailings (residual radioactive material) exceeding DOE hot spot criteria.
The Remedial Action Contractor was notified of the inclusion of this
property into the MVP Project and was authorized by DOE to conduct
remedial action as required to bring the property into conformance with
EPA standards and DOE hot spot criteria.
1
DOE ID No.: MS-01002-VL
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
Property Address:
Property Owner:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
MS-01002-VL
NE4NE4SW4 of Section 32, T33S., R24E.,
Salt Lake Base Meridian, City of Monticello,
County of San Juan, State of Utah
Parcel No. 33S24E324801
East Clay Hill Drive
Monticello, Utah 84535

Vacant Lot (VL)
Oak Ridge National Laboratory
September 12, 1991
Rust Geotech
February 24, 1994
Crowley Construction, Inc.
East Route HC 63 Box 66
Monticello, Utah
October 12, 1994
November 15, 1994
Interior: 0 cubic yards
Exterior: 30 cubic yards
150 square meters (m2)
February 1996
2
DOE ID No.: MS-01002-VL
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of exterior residual radioactive
material (Appendix Figure 2.1). Once excavation was complete, the
affected areas were resurveyed for possible remaining residual radioactive
material and, upon attaining satisfactory results, were backfilled with
uncontaminated material. The property was restored to a physical
condition comparable to that which existed prior to remedial action
activities.
2.2 Previously Unidentified Contamination
The radiological assessment identified contamination, 6 inches deep,
within the property. The quantity of contamination for this property was
not specified because it was assessed with MS-01001-RS. The remedial
action process included the removal of approximately 30 cubic yards of
residual radioactive material, 6 inches deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID No.: MS-01002-VL
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by the Remedial Action
Contractor during July 1993, as described in the final REA dated
February 1994. Appendix Figure 2.1 shows the extent of
assessed contamination and identifies the areas recommended to
undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the excavation were
collected. These samples were blended to form composite
samples representing the verification areas (Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 13 to 19 microroentgens per
hour (//R/h), as indicated on Appendix Figure 2.1. The results of
analyses for radium-226 in two composite soil samples were
3.9 and 5.1 picocuries per gram (pCi/g), as indicated in Appendix
Table 3.1.
4
DOE ID No.: MS-01002-VL
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
" below.
Therefore, the property located at Parcel No. 33S24E324801, East Clay
Hill Drive, in Monticello, Utah, is recommended for certification as
required by DOE guidelines, and the appropriate records should be
documented.
Certification Data Summary
Applicability
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Standards
Shall not exceed 20 //R/h
above background.
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Survey Results
Not applicable: vacant
lot.
Not applicable: vacant
lot.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background* in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background* in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
< 5 pCi/g above
background.
Soil sample results were
3.9 and 5.1 pCi/g.
*The background radium-226 concentration is approximately 2.0 pCi/g.
The hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-01002-VL
4.0 APPENDIX
Appendix Table:
Table 3.1 Post-Excavation Sample/Measurement Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
JEK: 10-27-95
MS-01002.VL WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-01002-VL
Address: Parcel No. 33S24E324801, East Clay Hill Drive, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (jjR/h) Ticket No. Method" (pCi/g)
V-1 13-19 NCH 231 OCS 3.9
V-2 13-16 NCH 232 OCS 5.1
See Appendix Figure 2.1 for the verification areas.
"OCS = Opposed Crystal System
7
40
38
36
34
32
30
28
26
24
22
20
18
16
14
12
10
1
ob 38 40 42 44 46 48 5(
I I I I
V-l
13-19
EAST CLAY HILL DRIVE
13-19
EAST CLAY HILL DRIVE
DETAIL B
DETAIL A
13-16 V-2
3-16
t.^.v.-.-..V
V-2
13-16
V-2
13-18
DETAIL D
13-16
DETAIL C
L
SCALE IN FEET
20 10 0 20 40
U.\r«S\0»\0003\IHI010aiV 11/01/N* 07:3*1 n\ T507B0
I I I I I I I
ft
NORTH
J I L
13-16
13-16
13-16
SEE DETAIL D
"1 -v I I
13-16
SEE DETAIL A SEE DETAIL B SEE DETAIL C
EAST CLAY HILL DRIVE
NOT TO SCALE
©
rr-.\vt
Lv.vj
12-15
12
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN i*R/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE-RATE RANGE
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
v-i
16-17
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY AND ITS CONTRACTORS. IT IS HOT A LAND SURVEY
PLAT, UTILITY LOCATION PLAT. OR OTHER IMPROVEMENT SURVEY
PLAT ANO IS NOT TO BE RELIEO UPON FOR THE ESTABLISHMENT
OF FENCE. BUILDING. OR OTHER FUTURE IMPROVEMENT UNES.
U.S. OEPARTUENT Of ENERGY
awMO JUNCTION rtwtxn OFFICE, coumtfo
"rr <t
PARCEL N0/33S24E324801
EAST CLAY HILL DRIVE
MONTICELLO, UTAH
«••"» MS-01002-VL I
»•» 3-C01002-V1 _ 1 .. 1
12 14 16 18 20 22 24 26 28 30 32 34 36 38 40 42 44 46 48 51
OAK RIDGE NATIONAL LABORATORY
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
FOR THE U.S. DEPARTMENT OF ENERGY
PHONE: [phone]
FAX: (970)24*4220
POST OFFICE BOX 2587
GRAND JUNCTION, COLORADO 81502 ftp J 6 im
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by the U.S.
Department of Energy for Residual Radioactive Material at Formerly Utilized Sites Remedial Action
Program (FUSRAP) and Remote Surplus Facilities Management Program Sites (SFMP) [Revision
2, March 1987]. This evaluation is based on an independent verification review of the Remedial
Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment ofthe 226Ra
concentration in the soil.
This property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
Location Number: MS01002-VL
Location Address: Parcel No. 33S24E324801
East Clav Hill Drive
Monticello. Utah 84535
Property Owner:

Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
PARCEL NO. 33S24E324801, EAST CLAY HELL DRIVE
MONTICELLO, UTAH (MS01002-VL)
M. K. Jensen
August 1996
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 3
REFERENCES 6
iii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 4
2. Results of ORNL analysis of Geotech soil samples from Parcel No. 33S24E324801,
East Clay Hill Drive, Monticello, Utah (MS01002-VL) 5
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site
Decommissioning Projects, U.S. Department of Energy. The author wishes to acknowledge
S. M. Smith and A. R. Jones for technical reviews.
vii
ABSTRACT
In 1980 the site of a vanadium and uranium mill at Monticello, Utah, was accepted into
the U.S. Department of Energy's (DOE's) Surplus Facilities Management Program, with the
objectives of restoring the government-owned mill site to safe levels of radioactivity, dis-
posing of or containing the tailings in an environmentally safe manner, and performing
remedial actions on off-site (vicinity) properties that had been contaminated by radioactive
material resulting from mill operations. During 1994, RUST Geotech, the remedial action
contractor designated by DOE, performed remedial action on the vicinity property at Parcel
No. 33S24E324801, East Clay Hill Drive, Monticello, Utah. The Environmental Technology
Section (ETS) of Oak Ridge National Laboratory was assigned the responsibility of verifying
the data supporting the adequacy of remedial action and confirming the site's compliance with
DOE guidelines. The ETS found that the site successfully meets the DOE remedial action
objectives. Procedures used by the ETS are described in the Environmental Technology
Section Procedures Manual (ORNL 1993).
ix
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT PARCEL NO. 33S24E324801, EAST CLAY HTLL DRIVE
MONTICELLO, UTAH (MS01002-VL)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the U.S. government through the
Defense Plant Corporation to provide vanadium during World War JJ. Various government
agencies operated the mill until 1947. In 1948 the Atomic Energy Commission (AEC)
obtained the mill and operated it under contract through 1959 to provide both uranium and
vanadium. Mill operations were terminated on January 1,1960. In 1961 the mill tailings piles
were leveled and graded, covered with rock and soil, and seeded with native grasses. During
1974 and 1975, the ore stockpiles were removed from the site, and the mill foundations were
buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city of
Monticello, in San Juan County, Utah. The site is bordered on the south and southeast by
land held by the U.S. Bureau of Land Management. Other boundaries are the city of
Monticello and private property.
During the AEC era, the mill processed approximately one million tons of uranium ore.
Vanadium and uranium were the only substances extracted in the milling process. Other
constituents of the ore remained in the tailings and were not separated prior to disposal.
During the years of active mill operation, the mill tailings were normally moist, so erosion was
minimal. However, throughout the mill's operating period, area residents used these tailings
as fill material and as aggregate in mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy (DOE)
initiated the Surplus Facilities Management Program (SFMP) in 1978 to ensure the safe
caretaking and decommissioning of government facilities that had been retired from service
but still had radioactive contamination. In 1980 the mill site at Monticello was accepted into
the SFMP, and the Monticello Remedial Action Project (MRAP) was established to restore
the government-owned mill site to safe levels of radioactivity, to dispose of or contain the
tailings in an environmentally safe manner, and to perform remedial actions on off-site
(vicinity) properties that had been contaminated by radioactive material resulting from mill
operations. The Monticello mill site and the tailings remain in the custody of the DOE Grand
Junction, Colorado, Projects Office. In 1983 remedial actions for vicinity properties were
separated from MRAP with establishment of the Monticello Vicinity Properties (MVP)
Project (U.S. DOE 1990b).
*The verification of remedial action was performed by members of the Environmental Assessment Group in the
Environmental Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE
contract DE-AC05-96OR22464 with Lockheed Martin Energy Research Corporation.
2
During 1994, RUST Geotech Inc. (Geotech), the remedial action contractor (RAC)
designated by DOE, performed remedial action on the vicinity property that is the subject of
this report, a vacant lot located at Parcel No. 33S24E324801, East Clay Hill Drive,
Monticello, Utah. The remedial action plan required excavation of all exterior containination.
When the excavation was completed, the property was resurveyed, including soil sampling,
to ensure the removal of all contamination, backfilled with uncontaminated material, and
restored to a condition comparable to that which existed prior to remedial action (Geotech
1996).
The DOE adopted a policy to assign an independent contractor to verify the data
supporting the adequacy of remedial action and to confirm the site's compliance with DOE
guidelines. The Environmental Technology Section (ETS) of Oak Ridge National Laboratory
(ORNL) has been assigned the responsibility of this task at Parcel No. 33S24E324801, East
Clay Hill Drive site. This report describes the methods and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available documenta-
tion adequately and accurately describes the post-remedial-action radiological conditions of
the entire property that is to be certified and (2) that the remedial action reduced contamina-
tion to below applicable DOE guidelines (DOE 1990a).
Document Reviews
Review ofthe property completion report prepared by Geotech (Geotech 1996) indicates
the property was remediated as evaluated by DOE on the basis of Environmental Protection
Agency standards and the DOE guidelines (DOE 1990a). Excess residual radioactive materi-
als were present, thus it was appropriate to designate this property for remedial action.
This property was assessed with MSO1001-RS, therefore, the quantity of material
assessed is not available. During the actual removal process, a total of 30 yd3 of contaminated
earth and uranium mill tailings, 6 inches deep, were removed from a 150 m2 area.
A post-excavation survey was performed by Geotech prior to backfilling the excavated
areas. This survey consisted of a surface gamma scan with a scintillometer and soil sampling.
Samples representative ofthe bottom 15-cm (6-in.) soil layers of two excavated verification
areas were collected and blended to form representative composite soil samples.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation
levels have not been subtracted. Similarly, background concentrations have not been sub-
tracted from radionuclide concentrations in soil samples. Applicable DOE guidelines for
protection against radiation are given in Table 1.
Gamma Measurements
Exterior surface gamma exposure rate measurements taken by Geotech from the exca-
vated areas prior to backfilling ranged from 13 to 19 uR/h.
Soil Sample Analysis
Prior to backfilling, Geotech collected soil samples representative of the excavated areas
from the bottom 15-cm (6-in.) soil layers. These samples were blended to form composite
soil samples representative of an average over the two exterior verification areas. Geotech's
analysis of these samples showed ^Ra concentrations ranging from 3.9 to 5.1 pCi/g in the
composite sample. ORNL ETS obtained one of these samples and performed a confirmatory
analysis which showed a ^^Ra concentration of 1.9 pCi/g. These values are below the EPA
standard value of 15 pCi/g for soil layers > 15 cm below the surface. Results of Geotech and
ORNL soil sample analyses are given in Table 2. Gamma ranges and/or soil sample results
demonstrate compliance to the DOE Hot Spot Guidelines for areas <25 m2 (Table 1).
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were not deter-
mined as this property is a vacant lot.
CONCLUSION
Results of Geotech soil sample analysis and confirmatory split soil sample analysis by
ORNL show that radionuclide concentrations are within applicable DOE guidelines. Based
on the results of the post-remedial-action data, which are confirmed by the verification
assessment data, these radiological measurements fall below the limits prescribed by DOE
guidelines. It is concluded that the site successfully meets the DOE remedial action objec-
tives.
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of ^Ra in soil
above background levels,
averaged over a 100-m2 area
5 pCi/g averaged over the
first 15 cm of soil below the
surface; 15 pCi/g when ave-
raged over 15-cm-thick soil
layers more than 15 cm
below the surface
Radionuclide con-
centrations in soil
for Hot Spot areas
Exposure to 222Rn
progeny
Maximum Permissible con-
centration of Ra226 in soil
above background level, for
areas less than 25 m2
Average annual radon proge-
ny concentration (including
background)
Ra226 concentrations, in any
surface or subsurface area
less than 25 m2, is below the
guideline by a factor of
(lOO/A)*4, where A is the
area of the elevated region
0.03 WL
(DOE 1990a)
5
Table 2. Results of ORNL analysis of Geotech soil samples from
Parcel No. 33S24E324801, East Clay Hill Drive, Monticello, Utah (MS01002-VL)
^Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No." No^ (cm)
XI NCH 231 >15 1.9 3.9
" An X-type sample is a split of the sample taken by the remedial action contractor.
* Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated areas
were taken by Geotech, and these samples were blended to form a composite soil
sample, which represents an average over one of the verification areas.
6
REFERENCES
Geotech 1996. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS01002-VL, Address: Parcel No. 33S24E324801MS01002-VL,
East Clay Hill Drive, Monticello, Utah 84535, Geotech, Grand Junction, Colorado, February
1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment Group)
Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National Laboratory,
Grand Junction, Colorado.
U.S. DOE 1990a. Verification and Certification Protocolfor the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination and
Decommissioning Program, Revision 3, November 1990. U.S. Department of Energy,
Washington, D.C.
U.S. DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision and
Record of Decision Summary. U.S. Department of Energy, Grand Junction Projects Office,
Grand Junction, Colorado.
DOE ID No.: MS-01037-CS
Property Address: Parcel No. A34240063001, South Highway 191
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech of Energy (DQE)
Ra-226 is ^ 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [ ]
Ra-226 is < 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2.
In-situ [ ] Lab [X]
Interior gamma is ^ 20 //R/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is < 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21.
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
[XI [ ] [ ]
[/] [ ] [ 1
[XI [ 1 [ 1
[X] [ ] [ 1
[ ] [)4 t 1
[X] I ] [ ]
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
•llllllllll 11111111111
SFCERTIFED SFMS-81037
i r
DOE ID No.: MS-01037-CS
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
^/^y£i~ /A, At
Wanda S.yBusby Date
Manager/Monticello Programs
Rust Geotech
DOE EVALUATION
[Xl Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Certification Official
U.S. Department of Energy
7r *4f
Date
I t
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-01037-CS
ADDRESS: PARCEL NO. A34240063001
SOUTH HIGHWAY 191
MONTICELLO, UTAH 84535
AUGUST 1996
Prepared for
U.S. Department of Energy
by
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
Wanj2ra S. Busby
Manager, Monticello Programs
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.1.3 Radon Decay-Product Concentration (RDC) Measurement .... 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
DOE ID No.: MS-01037-CS
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Inclusion Survey Contractor. DOE reviewed
these evaluation results and determined that the property contained mill
tailings (residual radioactive material) exceeding DOE hot spot criteria.
The Remedial Action Contractor was notified of the inclusion of this
property into the MVP Project and was authorized by DOE to conduct
remedial action as required to bring the property into conformance with
EPA standards and DOE hot spot criteria.
1
DOE ID No.: MS-01037-CS
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
MS-01037-CS
Beginning at the NW corner of Section 6, T34S., R24E., Salt Lake Base
Meridian; east 208 feet, south 208 feet, west 208 feet, north 208 feet to the
beginning; except beginning at the NW corner of said Section 6, south
41.69 feet to the true point of beginning, being a point on the easterly right of
way of Highway 191, southeasterly, more or less, along a curve to a point
208 feet south and 37.14 feet east of the NW corner of said Section 6, west
37.14 feet, north 166.31 feet to the true point of beginning, City of Monticello,
County of San Juan, State of Utah
Property Address:
Property Owner:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
Parcel No. A34240063001
South Highway 191
Monticello, Utah 84535

Commercial Structure (CS)
Oak Ridge National Laboratory
March 5, 1992
Rust Geotech
February 24, 1994
Diamond Back Services, Inc.
9861 Titan Park Circle
Littleton, Colorado
April 18, 1995
August 8, 1995
Interior:
Exterior:
0 cubic yards
113 cubic yards
197 square meters (m2)
August 1996
2
DOE ID No.: MS-01037-CS
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of exterior residual radioactive
material (Appendix Figure 2.1). Once excavation was complete, the
affected areas were resurveyed for possible remaining residual radioactive
material and, upon attaining satisfactory results, were backfilled with
uncontaminated material. The property was restored to a physical
condition comparable to that which existed prior to remedial action
activities.
2.2 Previously Unidentified Contamination
The radiological assessment identified contamination, ranging from 6 to
24 inches deep, within the property. The quantity of contamination for
this property was not specified because it was assessed as part of
Group 1. The remedial action process included the removal of
approximately 113 cubic yards of residual radioactive material, ranging
from 6 to 48 inches deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID No.: MS-01037-CS
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by the Remedial Action
Contractor during August 1992, as described in the final REA
dated February 1994. Appendix Figure 2.1 shows the extent of
assessed contamination and identifies the areas recommended to
undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the excavation were
collected. These samples were blended to form composite
samples representing the verification areas (Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 12 to 27 microroentgens per
hour (//R/h), as indicated on Appendix Figure 2.1. The results of
analyses for radium-226 in three composite soil samples ranged
from 0.9 to 3.9 picocuries per gram (pCi/g), as indicated in
Appendix Table 3.1.
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on the DOE-approved abbreviated-measurement method,
the RDC was 0.0052 working level (WL), as indicated in Appendix
Table 3.2. Appendix Figure 2.1 shows the measurement location
on the ground floor (the lowest habitable level of the structure).
The RDC measurements were started prior to remediation of the
property.
4
DOE ID No.: MS-01037-CS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at Parcel A34240063001, South
Highway 191, in Monticello, Utah, is recommended for certification as
required by DOE guidelines, and the appropriate records should be
documented.
Certification Data Summary
Applicability
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Standards
Shall not exceed 20 //R/h
above background.*
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Survey Results
Range for the ground
floor was 12 to 14//R/h.
Average was 0.0052 WL,
based on the DOE-
approved abbreviated-
measurement method.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
< 5 pCi/g above
background.**
Soil sample results
ranged from 0.9 to
3.9 pCi/g.**
*The background exposure rate is approximately 13 //R/h.
The background radium-226 concentration is approximately 2.0 pCi/g.
**The hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-01037-CS
4.0 APPENDIX
Appendix Tables:
Table 3.1 Post-Excavation Sample/Measurement Results
Table 3.2 Radon Decay-Product Concentration Measurement
Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
MRW:06-21-96
MS-01037.CS WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-01037-CS
Address: Parcel No. A34240063001, South Highway 191, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range U/R/h) Ticket No. Method" (pCi/g)
V-1 15-19 NCI 507 OCS 0.9
V-2 15-21 NCI 508 OCS 3.9
V-3 16-27 NCH 858 OCS 3.6
See Appendix Figure 2.1 for the verification areas.
"OCS = Opposed Crystal System
7
Table 3.2
Radon Decay-Product Concentration Measurement Results
DOE ID No.: MS-01037-CS
Address: Parcel No. A34240063001, South Highway 191, Monticello, Utah
Instrument Type: Landauer Radtrak Detector
Detector
Number Start Date End Date
Radon
Concentration
(pCi/L)
Working
Level
3964301
3964307
3964336
02-28-95
02-28-95
02-28-95
05-31-95
05-31-95
05-31-95
0.82
0.98
1.32
0.0041
0.0049
0.0066
Average: 0.0052
See Appendix Figure 2.1 for the measurement location.
8
42
40
36
36
34
32
30
28
26
24
22
20
18
16
14
12
10
12 14 16 18 20 22 24 26 28 30 32 34 36 38
T—i—i—i—i—i—i—i—i—i—i—i—i—i—i—i—i—i—i—i—i—i—i—i—i—T
40 42 4* 46 48
T—i—i—i—i—i—i—i—i 1—r
12-16
RDC
L
w
V I \ l
I \ 1
V
CT I f\
\ w
—21.—
ONE STORY
METAL BUILDING
12-14
12-16
4XB) U3 24 32
48
V-2
15-21
V-3
16-27
12-16
V-
15-19
20
12-16
12-16
<D
•7=-??i
LY.YJ
12-15
12
v-i
16-17
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN /iR/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST —REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE-RATE RANGE
RADON DECAY-PRODUCT CONCENTRATION
MEASUREMENT LOCATION
.1L
L
SCALE IN FEET
20 10 0 20 40
M:\FA5\OJJ\OOOJ\RM010J7V 0«/0»/»« 2:37pm 150780
12 14 16 18
NORTH
20 22 24 26 28
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT, UTILITY LOCATION PLAT. OR OTHER IMPROVEMENT SURVEY
PLAT AND IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE. BUILDING. OR OTHER FUTURE IMPROVEMENT LINES.
KBBCMCt-iM. tH 0CCU..HT1
mtmnnjn aa.
30 32 34 36 38 40
>. U.S. DEPARTMENT OF ENERGY
\ Sfc»ND JUNCTtOK FHOJCCTS OFFI«. COIOKACO
Si tu5 ft
PARCEL NO. A34240063001
SOUTH HIGHWAY 191
MONTICELLO. UTAH
I Ml |»»MU.Mf
Rust Ovotoch «*•- MS-01037-CS
42 44 46
' - 3-C01O37-V1,
48 51
OAK RIDGE NATIONAL LABORATORY
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
FOR THE US. DEPARTMENT OF ENERGY
PHONE: [phone]
FAX: [phone]
2597 WA Road
GRAND JUNCTION. COLORADO 81503 FEB 2 8 mi
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by the U.S.
Department of Energy for Residual Radioactive Material at Formerly Utilized Sites Remedial Action
Program (FUSRAP) and Remote Surplus Facilities Management Program Sites (SFMP) [Revision
2, March 1987]. This evaluation is based on an independent verification review of the Remedial
Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment of the 226Ra
concentration in the soil, indoor radon daughter concentration, and indoor gamma exposure rates at
this property.
This property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
Location Number:
Location Address:
Property Owner:
Owner Address:
MS01037-CS
Parcel No. A34240063001. South Highway 191
Monticello. Utah 84535

Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
PARCEL NO. A34240063001, SOUTH HIGHWAY 191
MONTICELLO, UTAH (MS01037-CS)
M. K. Jensen
February 1997
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81503
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 4
REFERENCES 7
iii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 5
2. Results of ORNL analysis ofthe RAC soil samples from Parcel No. A34240063001, South
Highway 191, Monticello, Utah (MS01037-CS) 6
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site Decommissioning
Projects, U.S. Department of Energy. The author wishes to acknowledge A. R. Jones and T. L.
Meyer for technical reviews.
vii
ABSTRACT
In 1980, the site of a vanadium and uranium mill at Monticello, Utah, was accepted into the U.S.
Department of Energy (DOE) Surplus Facilities Management Program, with the objectives of
restoring the government-owned mill site to safe levels of radioactivity, disposing of or containing
the tailings in an environmentally safe manner, and performing remedial actions on off-site (vicinity)
properties that had been contaminated by radioactive material resulting from mill operations. During
1995, the Remedial Action Contractor (RAC) designated by DOE, performed remedial action on the
vicinity property at Parcel No. A34240063001, South Highway 191, Monticello, Utah. The
Environmental Technology Section (ETS) of Oak Ridge National Laboratory was assigned the
responsibility of verifying the data supporting the adequacy of remedial action and confirming the
site's compliance with DOE guidelines. The ETS found that the site successfully meets the DOE
remedial action objectives. Procedures used by the ETS are described in the Environmental
Technology Section Procedures Manual (ORNL 1993).
ix
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT PARCEL NO. A34240063001, SOUTH HIGHWAY 191
MONTICELLO, UTAH (MS01037-CS)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the United States (U.S.) government through
the Defense Plant Corporation to provide vanadium during World War II. Various government
agencies operated the mill until 1947. In 1948, the Atomic Energy Commission (AEC) obtained the
mill and operated it under contract through 1959 to provide both uranium and vanadium. Mill
operations were terminated on January 1, 1960. In 1961, the mill tailings piles were leveled and
graded, covered with rock and soil, and seeded with native grasses. During 1974 and 1975, the ore
stockpiles were removed from the site and the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city of
Monticello, in San Juan County, Utah. The site is bordered on the south and southeast by land held
by the U.S. Bureau of Land Management. Other boundaries are the city of Monticello and private
property.
During the AEC era, the mill processed approximately one million tons of uranium ore. Vana-
dium and uranium were the only substances extracted in the milling process. Other constituents of
the ore remained in the tailings and were not separated prior to disposal. During the years of active
mill operation, the mill tailings were normally moist, so erosion was minimal. However, throughout
the mill's operating period, area residents used these tailings as fill material and as aggregate in mortar
and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy (DOE) initiated
the Surplus Facilities Management Program (SFMP) in 1978 to ensure the safe caretaking and de-
commissioning of government facilities that had been retired from service but still had radioactive
contamination. In 1980, the mill site at Monticello was accepted into the SFMP, and the Monticello
Remedial Action Project (MRAP) was established to restore the government-owned mill site to safe
levels of radioactivity, to dispose of or contain the tailings in an environmentally safe manner, and to
perform remedial actions on off-site (vicinity) properties that had been contaminated by radioactive
material resulting from mill operations. The Monticello mill site and the tailings remain in the custody
ofthe DOE Grand Junction, Colorado, Projects Office. In 1983, remedial actions for vicinity
properties were separated from MRAP with establishment of the Monticello Vicinity Properties
(MVP) Project (US DOE 1990b).
*The verification of remedial action was performed by members ofthe Environmental Assessment Group in the Environmental
Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE contract DE-AC05-
960R22464 with Lockheed Martin Energy Research Corporation.
2
During 1995, the Remedial Action Contractor (RAC) designated by DOE, performed remedial
action on the vicinity property that is the subject of this report, a commercial structure located at
Parcel No. A34240063001, South Highway 191, Monticello, Utah. The remedial action plan re-
quired excavation of all exterior contamination. When the excavation was completed, the property
was resurveyed, including soil sampling, to ensure the removal of all contamination, backfilled with
uncontaminated material, and restored to a condition comparable to that which existed prior to
remedial action (Geotech 1996).
DOE adopted a policy to assign an independent contractor to verify the data supporting the
adequacy of remedial action and to confirm the site's compliance with DOE guidelines. The
Environmental Technology Section (ETS) of Oak Ridge National Laboratory (ORNL) has been
assigned the responsibility of this task at Parcel No. A34240063001, South Highway 191 site. This
report describes the methods and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available documentation
adequately and accurately describes the post-remedial-action radiological conditions ofthe entire
property that is to be certified and (2) that the remedial action reduced contamination to below
applicable DOE guidelines (US DOE 1990a).
Document Reviews
Review of the RAC property completion report (Geotech 1996) indicates the property was reme-
diated as evaluated by DOE on the basis of U.S. Environmental Protection Agency standards and
the DOE guidelines (US DOE 1990a). Excess residual radioactive materials were present, thus it
was appropriate to designate this property for remedial action.
This property was assessed as part of Group 1, therefore, the quantity of material assessed is not
available. During the actual removal process, a total of 113 yd3 of contaminated earth and residual
radioactive material, 6 to 48 inches deep, were removed from a 197 m2 area.
The RAC performed a post-excavation survey prior to backfilling the excavated areas. This
survey consisted of gamma scans with a scintillometer of the ground level of the structure, a surface
scan of the exterior, and soil sampling. Samples representative of the bottom 15-cm (6-in.) soil
layers of three excavated verification areas were collected and blended to form representative
composite soil samples for each verification area.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation levels have
not been subtracted. Similarly, background concentrations have not been subtracted from radionu-
clide concentrations in soil samples. Applicable DOE guidelines for protection against radiation are
given in Table 1.
Gamma Measurements
Gamma exposure rate measurements taken by the RAC at the ground-level of the building
ranged from 12 to 14 uR/h. Exterior surface gamma measurements taken from the excavated areas
prior to backfilling ranged from 15 to 27 uR/h.
Soil Sample Analysis
Prior to backfilling, the RAC collected soil samples representative of the excavated areas from
the bottom 15-cm (6-in.) soil layers. These samples were blended to form a composite soil sample
representative of an average over the three exterior verification areas. The RAC's analysis of these
samples showed 226Ra concentrations ranging from 0.9 to 3.9 pCi/g in the composite sample. ORNL
ETS obtained these samples and performed a confirmatory analysis which showed 226Ra
concentrations ranging from 2.1 to 4.0 pCi/g. These values are below the DOE guideline value of
15 pCi/g for soil layers > 15 cm below the surface. Results ofthe RAC and ORNL soil sample
analyses are given in Table 2.
As a result of a meeting between the RAC and IVC on May 26, 1994, anomalous readings,
defined as > 30% above the average of the excavation, will be investigated to show compliance to
the DOE hot spot guideline. This property was remediated after this procedure change. The IVC
observed that 27 uR/h exceeds 30% of the excavation average of 20 pR/h. The IVC will allow a
correlation developed by the RAC to estimate ^Ra pCi/g concentrations based on gamma exposure
rates. The anomalous reading of 27 uR/h on this property using the RAC's correlation yields a 226Ra
concentration of 8.1 pCi/g. This value is well below the minimum concentration of 30 pCi/g needed,
when assuming the maximum area under the hot spot guideline of 25 m2, for subsurface samples.
Gamma ranges and/or soil sample results demonstrate compliance to the DOE Hot Spot Guidelines
for areas <25 m2 (Table 1).
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were determined by the
Alpha-track method before remediation of this property. To monitor radon levels, the RAC placed
three alpha-track detectors on the ground floor of the structure located on this property for a period
of approximately three months (from February 28, 1995 to May 31, 1995). The average annual
working level (WL) of radon progeny concentration, as determined by the Tech./Ops-Landauer
Corporation, was 0.0052, which is well below the 0.03-WL guideline given in Table 1.
4
CONCLUSION
Results of RAC soil sample analysis and confirmatory split soil sample analysis by ORNL, show
that radionuclide concentrations are within applicable DOE guidelines. Based on the results of the
post-remedial-action data, which are confirmed by the verification assessment data, these radiological
measurements fall below the limits prescribed by DOE guidelines. It is concluded that the site
successfully meets the DOE remedial action objectives.
5
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of 226Ra in soil
above background levels,
averaged over a 100-m2
area
5 pCi/g averaged over the first 15 cm
of soil below the surface; 15 pCi/g
when averaged over 15-cm-thick soil
layers more than 15 cm below the
surface
Radionuclide con-
centrations in soil
for Hot Spot areas
Exposure to ^Rn
progeny
Maximum Permissible con-
centration of Ra226 in soil
above background level,
for areas less than 25 m2
Average annual radon
progeny concentration
(including background)
Ra226 concentrations, in any surface
or subsurface area less than 25 m2,
is below the guideline by a factor of
(lOO/A)*, where A is the area ofthe
elevated region
0.03 WL
(US DOE 1990a)
6
Table 2. Results of ORNL analysis of the RAC soil samples from
Parcel No. A34240063001, South Highway 191, Monticello, Utah (MS01037-CS)
226Ra concentration (pCi/g)
ORNL RAC
sample sample Depth ORNL RAC
No." No^ (cm)
XI NCI 507 >15 2.1 0.9
X2 NCI 508 >15 3.6 3.9
X3 NCH 858 >15 4.0 3.6
* An X-type sample is a split of the sample taken by the remedial action contractor.
* Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated areas were
taken by the RAC, and these samples were blended to form a composite soil sample, which
represents an average over one of the verification areas.
7
REFERENCES
Geotech 1996. Property Completion Report for Monticello Vicinity Property Remedial Action for
DOE ID NO: MS01037-CS, Address: Parcel No. A34240063001, South Highway 191, Monticello,
Utah 84535, RUST Geotech, Grand Junction, Colorado, August 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment Group)
Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National Laboratory, Grand
Junction, Colorado.
US DOE 1990a. Verification and Certification Protocol for the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination and
Decommissioning Program. Revision 3, November 1990. U.S. Department of Energy, Washington,
D.C.
US DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision and Record
of Decision Summary. U.S. Department of Energy, Grand Junction Projects Office, Grand Junction,
Colorado.
DOE ID No.: MS-01039-RS
Property Address: Parcel No. A34240063000, South Highway 191
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech of Energy (DQE)
Ra-226 is ^ 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [ ]
Ra-226 is * 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2.
In-situ [ ] Lab [X]
Interior gamma is * 20jL/R/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is <; 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21.
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
[XI I ] I 1
[X] [ ] [ ]
[X] [ ] [ ]
[>] [ ] [ 1
[ 1 [A [ 1
[*]•[] [ 1
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
llllllillll Illlllflffl
SFCERTIFED SFMS-01037
DOE ID No.: MS-01039-RS
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Wanda S^usby Date
Manager, Monticello Programs
Rust Geotech
DOE EVALUATION
[X] Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Certification Official
U.S. Department of Energy
3 A?/ rr
Date
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-01039-RS
ADDRESS: PARCEL NO. A34240063000
SOUTH HIGHWAY 191
MONTICELLO, UTAH 84535
AUGUST 1996
Prepared for
U.S. Department of Energy
by
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
Warida^S. Busby '
Manager, Monticello Programs
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.1.3 Radon Decay-Product Concentration (RDC) Measurement .... 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
i
DOE ID No.: MS-01039-RS
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192j
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Inclusion Survey Contractor. DOE reviewed
these evaluation results and determined that the property contained mill
tailings (residual radioactive material) exceeding EPA standards. The
Remedial Action Contractor was notified of the inclusion of this property
into the MVP Project and was authorized by DOE to conduct remedial
action as required to bring the property into conformance with EPA
standards and DOE hot spot criteria.
1
DOE ID No.: MS-01039-RS
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
MS-01039-RS
Beginning 208 feet east and 208 feet south of the NW corner of Lot 4,
Section 6, T34S., R24E., Salt Lake Base Meridian; east 208 feet, north
208 feet, east 170.66 feet, south 416 feet, west 520 feet, more or less, to the
east boundary of the Highway 191 right-of-way, northerly to a point 208 feet
south and 37.14 feet east of the NW corner of said Lot 4, east 170.86 feet,
more or less, to the beginning, City of Monticello, County of San Juan, State of
Utah
Property Address:
Property Owners:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
Parcel No. A34240063000
South Highway 191
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
January 31, 1992
Rust Geotech
February 24, 1994
Diamond Back Services, Inc.
9861 Titan Park Circle
Littleton, Colorado
April 18, 1995
August 8, 1995
Interior: 0 cubic yards
Exterior: 2,863 cubic yards
10,994 square meters (m2)
August 1996
2
DOE ID No.: MS-01039-RS
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of exterior residual radioactive
material (Appendix Figure 2.1). Once excavation was complete, the
affected area was resurveyed for possible remaining residual radioactive
material and, upon attaining satisfactory results, was backfilled with
uncontaminated material. The property was restored to a physical
condition comparable to that which existed prior to remedial action
activities.
2.2 Previously Unidentified Contamination
The radiological assessment identified contamination, 6 inches deep,
within the property. The quantity of contamination for this property was
not specified because it was assessed as part of Group 1. The remedial
action process included the removal of approximately 2,863 cubic yards
of residual radioactive material, ranging from 6 to 50 inches deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID No.: MS-01039-RS
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by the Remedial Action
Contractor during August 1992, as described in the final REA
dated February 1994. Appendix Figure 2.1 shows the extent of
assessed contamination and identifies the area recommended to
undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the excavation were
collected. Soil samples were collected at the highest exposure-
rate location within each 30- by 30-foot section of the excavation.
These samples were blended to form composite samples
representing the verification areas (Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 13 to 23 microroentgens per
hour (//R/h), as indicated on Appendix Figure 2.1. The results of
analyses for radium-226 in 13 composite soil samples ranged from
1.1 to 5.8 picocuries per gram (pCi/g), as indicated in Appendix
Table 3.1.
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on the DOE-approved abbreviated-measurement method,
the RDC was 0.0068 working level (WL), as indicated in Appendix
Table 3.2. Appendix Figure 2.1 shows the measurement location
on the ground floor (the lowest habitable level of the structure).
The RDC measurements were completed prior to remediation of
the property.
4
DOE ID No.: MS-01039-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at Parcel No. A34240063000, South
Highway 191, in Monticello, Utah, is recommended for certification as
required by DOE guidelines, and the appropriate records should be
documented.
Certification Data Summary
Applicability
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Land.
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Standards
Shall not exceed 20 //R/h
above background.*
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Shall not exceed 5 pCi/g
above background in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
Survey Results
Range for the ground
floor was 12 to 13//R/h.
Average was 0.0068 WL,
based on the DOE-
approved abbreviated-
measurement method.
< 5 pCi/g above
background.**
Soil sample results
ranged from 1.1 to
5.8 pCi/g.**
*The background exposure rate is approximately 14//R/h.
The background radium-226 concentration is approximately 2.0 pCi/g.
**The hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-01039-RS
4.0 APPENDIX
Appendix Tables:
Table 3.1 Post-Excavation Sample/Measurement Results
Table 3.2 Radon Decay-Product Concentration Measurement Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
MRW:06-24-96
MS-01039.RS WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-01039-RS
Address: Parcel No. A34240063000, South Highway 191, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range O^R/h) Ticket No. Method" (pCi/g)
V-1 13-15 NCJ 551 OCS 3.9
V-2 13-15 NCJ 552 OCS 1.2
V-3 13-18 NCJ 553 OCS 1.1
V-4 13-16 NCJ 554 OCS 3.1
V-5 13-17 NCJ 555 OCS 1.9
V-6 14-18 NCJ 556 OCS 1.4
V-7 14-16 OCS 1.6b
V-8 14-17 NCJ 559 OCS 3.2
V-9 14-23 NCJ 560 OCS 3.1
V-10 14-18 NCJ 561 OCS 3.9
V-11 14-20 NCJ 562 OCS 2.5
V-12 14-20 NCJ 566 OCS 4.0
V-13 14-20 NCJ 567 OCS 5.8
See Appendix Figure 2.1 for the verification areas.
"OCS = Opposed Crystal System
This result is the weighted average of the results of analysis of soil sample NCJ 557
(6 aliquots, 1.8 pCi/g) and NCJ 558 (3 aliquots, 1.2 pCi/g).
7
Table 3.2
Radon Decay-Product Concentration Measurement Results
DOE ID No.: MS-01039-RS
Address: Parcel No. A34240063000, South Highway 191, Monticello, Utah
Instrument Type: Landauer Radtrak Detector
Radon
Detector Concentration Working
Number Start Date End Date (pCi/L) Level
3964322 03-02-95 06-01-95 1.65 0.0083
3964201 03-02-95 06-01-95 1.36 0.0068
3964110 03-02-95 06-01-95 1.05 0.0053
Average: 0.0068
See Appendix Figure 2.1 for the measurement location.
8
©
<•>
iv.vj
12-15
V-I
H-17
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN ^R/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
JOENRTA^NKATED 0EPTH F0R THE DEPOSIT OF
MEASUR^EiE^-LOC^AT/oN ^^^^"A^'ON
2*
TM(S OWWINC IS fOR THE SOLE WE OF THE U.S. OEPARTUENT
Of ENERCr ANO ITS CONTRACTORS, it tS «OI A LANO SURVEY
PUT. UTILITY LOCATION PLAT, OR OTHCR IMPROVEMENT SURVEY
PL»T ANO 1$ WT TO BC «L«D UPON tO* THC ESTABLISHMENT
OF fENCE. «UILD"NC. OR OTHER FUTURE IMPROVEMENT LMCS.
RADIOLOGICAL AS-BUILT
FIGURE ?1
EXTERIOR EXTENT OF CONTAMINATION
WQ. OAIE REVISIONS
*CT.OCtKt-«0 OT OCCUMNT!
MSIflUMtHI M
CK. A.E. APP
U.S. DEPARTMENT OF ENERGY
CtyHD JUNCTION PROJECTS OFFICE. COLOMOO
P«Oj CMCfl •
tUtMITIft'-
PARCEL NO. A3424006J000
SOUTH HIGHWAY 191
MONTICELLO. UTAH
OAK RIDGE NATIONAL LABORATORY
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
FOR THE U.S. DEPARTMENT OF ENERGY
PHONE: (970) 244V-6200
FAX: [phone]
2597 BV. Road
GRAND JUNCTION, COLORADO 81503
FEB 2 8 1M7
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by the U.S.
Department of Energy for Residual Radioactive Material at Formerly Utilized Sites Remedial Action
Program (FUSRAP) and Remote Surplus Facilities Management Program Sites (SFMP) [Revision
2, March 1987]. This evaluation is based on an independent verification review of the Remedial
Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment ofthe ^Ra
concentration in the soil, indoor radon daughter concentration, and indoor gamma exposure rates at
this property.
This property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
Location Number: MS01039-RS
Location Address: Parcel No. A34240063000. South Highway 191
Monticello. Utah 84535
Property Owner:

Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
PARCEL NO. A34240063000, SOUTH HIGHWAY 191
MONTICELLO, UTAH (MS01039-RS)
M. K. Jensen
February 1997
Work, performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81503
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 3
REFERENCES 6
iii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 4
2. Results of ORNL analysis ofthe RAC soil samples from Parcel No. A34240063000, South
Highway 191, Monticello, Utah (MS01039-RS) 5
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site Decommissioning
Projects, U.S. Department of Energy. The author wishes to acknowledge A. R. Jones and P. D.
Roundtree for technical reviews.
vii
ABSTRACT
In 1980, the site of a vanadium and uranium mill at Monticello, Utah, was accepted into the U.S.
Department of Energy (DOE) Surplus Facilities Management Program, with the objectives of
restoring the government-owned mill site to safe levels of radioactivity, disposing of or containing
the tailings in an environmentally safe manner, and performing remedial actions on off-site (vicinity)
properties that had been contaminated by radioactive material resulting from mill operations. During
1995, the Remedial Action Contractor (RAC) designated by DOE, performed remedial action on the
vicinity property at Parcel No. A34240063000, South Highway 191, Monticello, Utah. The
Environmental Technology Section (ETS) of Oak Ridge National Laboratory was assigned the
responsibility of verifying the data supporting the adequacy of remedial action and confirming the
site's compliance with DOE guidelines. The ETS found that the site successfully meets the DOE
remedial action objectives. Procedures used by the ETS are described in the Environmental
Technology Section Procedures Manual (ORNL 1993).
ix
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT PARCEL NO. A34240063000, SOUTH HIGHWAY 191
MONTICELLO, UTAH (MSOT039-RS)*
INTRODUCTION
The rnill at Monticello, Utah, was built in 1942 by the United States (U.S.) government through
the Defense Plant Corporation to provide vanadium during World War II. Various government
agencies operated the mill until 1947. In 1948, the Atomic Energy Commission (AEC) obtained the
mill and operated it under contract through 1959 to provide both uranium and vanadium. Mill
operations were terminated on January 1, 1960. In 1961, the mill tailings piles were leveled and
graded, covered with rock and soil, and seeded with native grasses. During 1974 and 1975, the ore
stockpiles were removed from the site and the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city of
Monticello, in San Juan County, Utah. The site is bordered on the south and southeast by land held
by the U.S. Bureau of Land Management. Other boundaries are the city of Monticello and private
property.
During the AEC era, the mill processed approximately one million tons of uranium ore. Vana-
dium and uranium were the only substances extracted in the milling process. Other constituents of
the ore remained in the tailings and were not separated prior to disposal. During the years of active
mill operation, the mill tailings were normally moist, so erosion was minimal. However, throughout
the mill's operating period, area residents used these tailings as fill material and as aggregate in mortar
and concrete.
Under the authority ofthe Atomic Energy Act, the U.S. Department of Energy (DOE) initiated
the Surplus Facilities Management Program (SFMP) in 1978 to ensure the safe caretaking and de-
commissioning of government facilities that had been retired from service but still had radioactive
contamination. In 1980, the mill site at Monticello was accepted into the SFMP, and the Monticello
Remedial Action Project (MRAP) was established to restore the government-owned mill site to safe
levels of radioactivity, to dispose of or contain the tailings in an environmentally safe manner, and to
perform remedial actions on off-site (vicinity) properties that had been contaminated by radioactive
material resulting from mill operations. The Monticello mill site and the tailings remain in the custody
of the DOE Grand Junction, Colorado, Projects Office. In 1983, remedial actions for vicinity
properties were separated from MRAP with establishment of the Monticello Vicinity Properties
(MVP) Project (US DOE 1990b).
•The verification of remedial action was performed by members of the Environmental Assessment Group in the Environmental
Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE contract DE-AC05-
960R22464 with Lockheed Martin Energy Research Corporation.
2
During 1995, the Remedial Action Contractor (RAC) designated by DOE, performed remedial
action on the vicinity property that is the subject of this report, a single famliy residence located at
Parcel No. A34240063000, South Highway 191, Monticello, Utah. The remedial action plan re-
quired excavation of all exterior contamination. When the excavation was completed, the property
was resurveyed, including soil sampling, to ensure the removal of all contamination, backfilled with
uncontaminated material, and restored to a condition comparable to that which existed prior to
remedial action (Geotech 1996).
DOE adopted a policy to assign an independent contractor to verify the data supporting the
adequacy of remedial action and to confirm the site's compliance with DOE guidelines. The
Environmental Technology Section (ETS) of Oak Ridge National Laboratory (ORNL) has been
assigned the responsibility of this task at Parcel No. A34240063000, South Highway 191 site. This
report describes the methods and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available documentation
adequately and accurately describes the post-remedial-action radiological conditions of the entire
property that is to be certified and (2) that the remedial action reduced contamination to below
applicable DOE guidelines (US DOE 1990a).
Document Reviews
Review of the RAC property completion report (Geotech 1996) indicates the property was reme-
diated as evaluated by DOE on the basis of U.S. Environmental Protection Agency standards and
the DOE guidelines (US DOE 1990a). Excess residual radioactive materials were present, thus it
was appropriate to designate this property for remedial action.
This property was assessed as part of Group 1, therefore, the quantity of material assessed is not
available. During the actual removal process, a total of 2,863 yd3 of contaniinated earth and residual
radioactive material, 6 to 50 inches deep, were removed from a 10,994 m2 area.
The RAC performed a post-excavation survey prior to backfilling the excavated areas. This
survey consisted of gamma scans with a scintillometer of the ground level of the structure, a surface
scan ofthe exterior, and soil sampling. Samples representative of the bottom 15-cm (6-in.) soil
layers of thirteen excavated verification areas were collected and blended to form representative
composite soil samples. Large area verification procedures were implemented on this property. The
composite sample consisted of soil samples collected at the highest exposure rate within each 30-
by 30-foot section in each verification area.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation levels have
not been subtracted. Similarly, background concentrations have not been subtracted from radionu-
clide concentrations in soil samples. Applicable DOE guidelines for protection against radiation are
given in Table 1.
Gamma Measurements
Gamma exposure rate measurements taken by the RAC at the ground-level of the residence
ranged from 12 to 13 uR/h. Exterior surface gamma measurements taken from the excavated areas
prior to backfilling ranged from 13 to 23 uR/h.
Soil Sample Analysis
Prior to backfilling, the RAC collected soil samples representative of the excavated areas from
the bottom 15-cm (6-in.) soil layers. Each sample was taken at the highest exposure rate within each
30- by 30-foot section. These samples were blended to form a composite soil sample representative
of an average over the thirteen exterior verification areas. The RAC's analysis of these samples
showed 226Ra concentrations ranging from 1.1 to 5.8 pCi/g in the composite sample. ORNL ETS
obtained a percentage of these samples and performed a confirmatory analysis which showed W6Ra
concentrations ranging from 1.4 to 5.7 pCi/g. These values are below the DOE guideline value of
15 pCi/g for soil layers >15 cm below the surface. Results ofthe RAC and ORNL soil sample
analyses are given in Table 2.
In addition, five individual soil samples were taken at the highest exposure rate in areas
exceeding 30% of the excavation average. The RAC's analysis of these samples showed ^Ra
concentrations ranging from 7.3 to 13.8 pCi/g. Gamma ranges and/or soil sample results demonstrate
compliance to the DOE Hot Spot Guidelines for areas <25 m2 (Table 1).
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were determined by the
Alpha-track method prior to remediation. To monitor radon levels, the RAC placed three alpha-track
detectors on the ground floor of the residence located on this property for a period of approximately
three months (from March 2, 1995 to June 1, 1995). The average annual working level (WL) of
radon progeny concentration, as determined by the Tech./Ops-Landauer Corporation, was 0.0068,
which is well below the 0.03-WL guideline given in Table 1.
CONCLUSION
Results of RAC soil sample analysis and confirmatory Split soil sample analysis by ORNL, show
that radionuclide concentrations are within applicable DOE guidelines. Based on the results of the
post-remedial-action data, which are confirmed by the verification assessment data, these radiological
measurements fall below the limits prescribed by DOE guidelines. It is concluded that the site
successfully meets the DOE remedial action objectives.
4
4
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of 226Ra in soil
above background levels,
averaged over a 100-m2
area
5 pCi/g averaged over the first 15 cm
of soil below the surface; 15 pCi/g
when averaged over 15-cm-thick soil
layers more than 15 cm below the
surface
Radionuclide con-
centrations in soil
for Hot Spot areas
Exposure to 222Rn
progeny
Maximum Permissible con-
centration of Ra226 in soil
above background level,
for areas less than 25 m2
Average annual radon
progeny concentration
(including background)
Ra226 concentrations, in any surface
or subsurface area less than 25 m2,
is below the guideline by a factor of
(100/A)'71, where A is the area of the
elevated region
0.03 WL
(US DOE 1990a)
5
Table 2. Results of ORNL analysis of the RAC soil samples from
Parcel No. A34240063000, South Highway 191, Monticello, Utah (MS01039-RS)
226Ra concentration (pCi/g)
ORNL RAC
sample sample Depth ORNL RAC
No." No^ (cm}
X3 NCJ 553 >15 1.4 1.1
X6 NCJ 556 >15 2.7 1.4
X10 NCJ 561 >15 4.1 3.9
X13 NCJ 567 >15 5.7 5.8
° An X-type sample is a split of the sample taken by the remedial action contractor.
* Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated areas were
taken by the RAC, and these samples were blended to form a composite soil sample, which
represents an average over one of the verification areas.
6
REFERENCES
Geotech 1996. Property Completion Report for Monticello Vicinity Property Remedial Action for
DOE ID NO: MS01039-RS, Address: Parcel No. A34240063000, South Highway 191, Monticello,
Utah 84535, RUST Geotech, Grand Junction, Colorado, August 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment Group)
Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National Laboratory, Grand
Junction, Colorado.
US DOE 1990a. Verification and Certification Protocol for the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination and
Decommissioning Program. Revision 3, November 1990. U.S. Department of Energy, Washington,
D.C.
US DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision and Record
of Decision Summary. U.S. Department of Energy, Grand Junction Projects Office, Grand Junction,
Colorado.
DOE ID No.: MS-01064-CS
Property Address: Parcel No. A33230254800, North Main Street
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
Ra-226 is <. 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [ ]
Ra-226 is ^ 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2.
In-situ [ ] Lab [X]
Interior gamma is <. 20 //R/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is <. 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21.
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
Rust Geotech
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[ 1 [X] [ ]
[X] [ ] [ ]
U.S. Department
of Energy (DOE)
YES NO NOT TAKEN
M [ ] [ 1
[ 1 [ ] [X] [ ] [ ] \y\
(Vacant Lot)
[ ] [ ] [X] [ ] [ 1 [ ^
(Vacant Lot)
[ 1 \Y\ [ 1
[ ] [ 1
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of oamma
exposure rates that do not exceed 30 percent above normal background.
•IIIIIIIIIN 11111111111
SFCERTIFED SFMS-00748
DOE ID No.: MS-01064-CS
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with the concurrence
of the U.S. Nuclear Regulatory Commission because supplemental
standards were applied per 40 CFR 192.21.
[X] Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with the
concurrence of the U.S. Nuclear Regulatory Commission because
supplemental standards were applied per 40 CFR 192.21.
Date
Manager, Monticello Programs
Rust Geotech
DOE EVALUATION
Date
U.S. Department of Energy
PROPERTY COMPLETION REPORT
DOE ID NO.: MS-01064-CS
ADDRESS: PARCEL NO. A33230254800
NORTH MAIN STREET
MONTICELLO, UTAH 84535
AUGUST 1996
Prepared for
U.S. Department of Energy
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
by
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
Manager, Monticello Programs
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 4
2.1 Abstract of Remedial Action Plan 4
2.2 Previously Unidentified Contamination 4
2.3 Unanticipated Items During Remedial Action 4
2.4 Application of Supplemental Standards 4
3.0 VERIFICATION SUMMARY 5
3.1 Radiological Survey Data 5
3.1.1 Pre-Remedial Action Survey 5
3.1.2 Post-Excavation Survey 5
3.2 Recommendation for Certification 6
4.0 APPENDIX 7
i
DOE ID No.: MS-01064-CS
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Inclusion Survey Contractor. DOE reviewed
these evaluation results and determined that the property contained mill
tailings (residual radioactive material) exceeding EPA standards and DOE
hot spot criteria. The Remedial Action Contractor was notified of the
inclusion of this property into the MVP Project and was authorized by DOE
to conduct remedial action as required to bring the property into
conformance with EPA standards and DOE hot spot criteria.
1
DOE ID No.: MS-01064-CS
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
MS-01064-CS
Beginning 1325.09 feet north and 1320.29 feet east of the SW corner of
Section 25, T33S., R23E., Salt Lake Base Meridian; north 00 degrees
02 minutes 55 seconds east 1,294.25 feet, north 89 degrees 16 minutes
45 seconds east 639.48 feet, east 718.47 feet, north 03 degrees 40 minutes
35 seconds west 8.64 feet, north 02 degrees 10 minutes 07 seconds west
1,127.05 feet, north 180.57 feet, north 89 degrees 33 minutes 04 seconds
east 821.88 feet to the west right of way of Highway 191, south 03 degrees
54 minutes 23 seconds east 361.84 feet, south 00 degrees 34 minutes
56 seconds east 613.90 feet, south 88 degrees 50 minutes 57 seconds west
213.21 feet, south 00 degrees 34 minutes 56 seconds east 386.14 feet, north
88 degrees 50 minutes 57 seconds east 213.21 feet to west side of said right
of way, south 00 degrees 34 minutes 56 seconds east 224.44 feet, south
89 degrees 40 minutes 12 seconds west 250.95 feet, south 293.88 feet, west
185 feet, south 30 feet, west 120 feet, south 30 feet, south 24 degrees
15 minutes west 150 feet, south 550.99 feet, north 89 degrees 47 minutes
6 seconds west 360.75 feet, south 05 degrees 18 minutes 41 seconds west
8.89 feet, north 89 degrees 24 minutes 56 seconds west 1,195.68 feet to the
beginning [including that portion of the property deeded to the City of
Monticello for public roads as described in Book 721, Page 346]; except for the
north 800 feet, more or less, as described in Book 708, Page 14, and also
except that parcel described in Book 708, Page 12; and also except that parcel
described in Book 719, Page 850, records of the San Juan County clerk and
recorder, City of Monticello, County of San Juan, State of Utah
Property Address:
Property Owner:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Parcel No. A33230254800
North Main Street
Monticello, Utah 84535

Commercial Simple (CS)
Oak Ridge National Laboratory
February 11, 1992
Rust Geotech
February 3, 1994
2
DOE ID No.: MS-01064-CS
Summary of Remedial Action (continued)
Construction Subcontractor: 1st Remediation
Bayless and Bayless, Inc.
435 East 1st
Pueblo, Colorado
2nd Remediation
Diamond Back Services, Inc.
9861 Titan Park Circle
Littleton, Colorado
Completion of 1st Remediation: July 29, 1992
Pre-Construction Conference
Record: July 6, 1994- 2nd Remediation
Notice of Final Completion
Inspection: September 8, 1994 - 2nd remediation
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
Interior: 0 cubic yards
Exterior: 106 cubic yards
499 square meters (m2)
August 1996
DOE ID No.: MS-01064-CS
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of exterior residual radioactive
material (Appendix Figure 2.1). Once excavation was complete, the
affected areas were resurveyed for possible remaining residual radioactive
material and, upon attaining satisfactory results, were backfilled with
uncontaminated material. The property was restored to a physical
condition comparable to that which existed prior to remedial action
activities.
2.2 Previously Unidentified Contamination
The radiological assessment identified 118 cubic yards of contamination,
ranging from 6 to 12 inches deep, within the property. The remedial
action process included the removal of approximately 106 cubic yards of
residual radioactive material, ranging from 6 to 48 inches deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
A portion of this property (Area V-8) was remediated in July 1992 prior to
the release of the REA to facilitate the property owner's construction
schedule.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
4
DOE ID No.: MS-01064-CS
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by the Remedial Action
Contractor during July 1992, as described in the final REA dated
February 1994. Appendix Figure 2.1 shows the extent of
assessed contamination and identifies the areas recommended to
undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the excavation were
collected. These samples were blended to form composite
samples representing the verification areas (Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 12 to 19 microroentgens per
hour OwR/h), as indicated on Appendix Figure 2.1. The results of
analyses for radium-226 in eight composite soil samples ranged
from less than 1.0 to 2.6 picocuries per gram (pCi/g), as indicated
in Appendix Table 3.1. The composite sample representing
Area V-8 included soil samples collected from MS-00748-CS
(Area V-1).
5
DOE ID No.: MS-01064-CS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at Parcel No. A33230254800,
North Main Street, in Monticello, Utah, is recommended for certification
as required by DOE guidelines, and the appropriate records should be
documented.
Certification Data Summary
Applicability
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Standards
Shall not exceed 20 //R/h
above background.
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Survey Results
Not applicable: vacant
lot.
Not applicable: vacant
lot.
Land.
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background* in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background* in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
< 5 pCi/g above
background.
Soil sample results
ranged from < 1.0 to
2.6 pCi/g.f
*The background radium-226 concentration is approximately 2.0 pCi/g.
The hot spot criteria were met based on gamma scans and/or soil sample results.
6
DOE ID No.: MS-01064-CS
4.0 APPENDIX
Appendix Table:
Table 3.1 Post-Excavation Sample/Measurement Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
MRW: 10-2-95
MS-01064.CS WP61
REV080195
7
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-01064-CS
Address: Parcel No. A33230254800, North Main Street, Monticello, Utah
A less-than sign (<) indicates that the minimum detection limit based on Compton
background was reached.
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (//R/h) Ticket No. Method' (pCi/g)
V-1 15-19 NCB 912 OCS 2.6
V-2 13-17 NCB 913 OCS 2.0
V-3 13-16 NCB 914 OCS 2.2
V-4 14-16 NCB 915 OCS 1.2
V-5 14-17 NCB 916 OCS < 1.0
V-6 13-15 NCB 917 OCS 2.0
V-7 14-18 NCB 918 OCS 1.8
V-8 13-16 NAT 337 OCS 1.5
See Appendix Figure 2.1 for the verification areas.
"OCS = Opposed Crystal System
8
40
38
36
34
32
30
28
26
24
22
20
13
16
14
12
10
1
i I I I i—r i—r
4<;
T—r
46 48 5(
V-7 V-7
14-ta 14-18
48
18
12-16
. LJ.
r~"
L.
L
42
V-7
14-18
12-16
DETAIL C
12-16
DETAIL B
DETAIL D
SCALE IN FEET
20 10 0 20 40
U:\fAS\033\O003\RU01064V 0S/16/96 10:26am T50780
ft
NORTH
12-16 V-4
14-16
0
®
0 0 V- 1
V-6 15-9
13-15
12-16
V-5
14-17
1
V-7
14-18
36
J L
12 14 16 18 20 22
_l L
24
12-16
6 X A
v-e
13-16
12-16
12
DETAIL A
SEE DETAIL A
SEE DETAIL B
12-16
12-16
THIS DRAWING IS FOB THE SOLE USE OF THE U.S. OEPARTUENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT, UTILITY LOCATION PLAT, OR OTHER IMPROVEMENT 5UPVEY
PLAT AND IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE. BUILDING. OR OTHER FUTURE IMPROVEMENT LINES
I 12-16 -'J
SEE OETAIL 0
lEP^i. i
a
I—
in
z < z
X \~ or O z
Tt3 r -i
L j-
UNIMPROVED/) I
CITY STREETS |
! •
i
SEE DETAIL cj
12-16
NOT TO SCALE
<D rv.vn
LV.7J
12-15
EH
V-l
16-17
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN /iR/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE-RATE RANGE
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
U.S. DEPARTMENT OF ENERGY
ClUMO JUNCTIOX MMCCfS OfHCC. COU«AOO
3L
ilST s
PARCEL NO. A33230254800
NORTH MAIN STREET
MONTICELLO, UTAH
Hull OMtech «*•- MS-0I064-CS
26 28 30 32 34 36 38 40 42 44 46 48 5i
OAK RIDGE NATIONAL LABORATORY
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
FOR THE U.S. DEPARTMENT OF ENERGY
PHONE: [phone]
FAX: [phone]
2597 BK Road
GRAND JUNCTION, COLORADO 81503
m 2 g
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by the U.S.
Department of Energy for Residual Radioactive Material at Formerly Utilized Sites Remedial
Action Program (FUSRAP) and Remote Surplus Facilities Management Program Sites (SFMP)
[Revision 2, March 1987]. This evaluation is based on an independent verification review of the
Remedial Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment of the
^Ra concentration in the soil.
This property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
MS01064-CS
Parcel No. A33230254800
North Main Street
Monticello. Utah 84535

Location Number:
Location Address:
Property Owner:
Owner Address:
Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
PARCEL NO. A33230254800, NORTH MAIN STREET
MONTICELLO, UTAH (MS01064-CS)
A. R. Jones
March 1997
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81503
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 3
REFERENCES 6
iii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 4
2. Results of ORNL analysis ofthe RAC soil samples from Parcel No. A33230254800,
North Main Street, Monticello, Utah (MS01064-CS) 5
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site Decommissioning
Projects, U.S. Department of Energy. The author wishes to acknowledge M. K. Jensen for analysis
of soil samples and technical review and S. M. Smith for technical review.
vii
ABSTRACT
In 1980, the site of a vanadium and uranium mill at Monticello, Utah, was accepted into the
U.S. Department of Energy (DOE) Surplus Facilities Management Program, with the objectives of
restoring the government-owned mill site to safe levels of radioactivity, disposing of or containing
the tailings in an environmentally safe manner, and performing remedial actions on off-site (vicinity)
properties that had been contaminated by radioactive material resulting from mill operations. During
1992 and 1994, the Remedial Action Contractor (RAC) designated by DOE, performed remedial
action on the vicinity property at Parcel No. A33230254800, North Main Street, Monticello, Utah.
The Environmental Technology Section (ETS) of Oak Ridge National Laboratory was assigned the
responsibility of verifying the data supporting the adequacy of remedial action and confirming the
site's compliance with DOE guidelines. The ETS found that the site successfully meets the DOE
remedial action objectives. All deficiencies noted in the initial review have been resolved with the
data in the revised completion report. Procedures used by the ETS are described in the Environmen-
tal Technology Section Procedures Manual (ORNL 1993).
ix
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT PARCEL NO. A33230254800, NORTH MAIN STREET
MONTICELLO, UTAH (MS01064-CS)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the United States (U.S.) government through
the Defense Plant Corporation to provide vanadium during World War II. Various government
agencies operated the mill until 1947. In 1948, the Atomic Energy Commission (AEC) obtained the
mill and operated it under contract through 1959 to provide both uranium and vanadium. Mill
operations were terminated on January 1, 1960. In 1961, the mill tailings piles were leveled and
graded, covered with rock and soil, and seeded with native grasses. During 1974 and 1975, the ore
stockpiles were removed from the site and the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city of
Monticello, in San Juan County, Utah. The site is bordered on the south and southeast by land held
by the U.S. Bureau of Land Management. Other boundaries are the city of Monticello and private
property.
During the AEC era, the mill processed approximately one million tons of uranium ore. Vana-
dium and uranium were the only substances extracted in the milling process. Other constituents of
the ore remained in the tailings and were not separated prior to disposal. During the years of active
mill operation, the mill tailings were normally moist, so erosion was minimal. However, throughout
the mill's operating period, area residents used these tailings as fill material and as aggregate in mortar
and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy (DOE) initiated
the Surplus Facilities Management Program (SFMP) in 1978 to ensure the safe caretaking and de-
commissioning of government facilities that had been retired from service but still had radioactive
contamination. In 1980, the mill site at Monticello was accepted into the SFMP, and the Monticello
Remedial Action Project (MRAP) was established to restore the government-owned mill site to safe
levels of radioactivity, to dispose of or contain the tailings in an environmentally safe manner, and to
perform remedial actions on off-site (vicinity) properties that had been contaminated by radioactive
material resulting from mill operations. The Monticello mill site and the tailings remain in the custody
of the DOE Grand Junction, Colorado, Projects Office. In 1983, remedial actions for vicinity
properties were separated from MRAP with establishment of the Monticello Vicinity Properties
(MVP) Project (US DOE 1990b).
*The verification of remedial action was performed by members ofthe Environmental Assessment Group in the Environmental
Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE contract DE-AC05-
960R22464 with Lockheed Martin Energy Research Corporation.
2
During 1992 and 1994, the Remedial Action Contractor (RAC) designated by DOE, performed
remedial action on the vicinity property that is the subject of this report, vacant land located at Parcel
No. A33230254800, North Main Street, Monticello, Utah. The remedial action plan required excava-
tion of all exterior contamination. When the excavation was completed, the property was resurveyed,
including soil sampling, to ensure the removal of all contamination, backfilled with uncontaminated
material, and restored to a condition comparable to that which existed prior to remedial action
(Geotech 1996).
DOE adopted a policy to assign an independent contractor to verify the data supporting the
adequacy of remedial action and to confirm the site's compliance with DOE guidelines. The Environ-
mental Technology Section (ETS) of Oak Ridge National Laboratory (ORNL) has been assigned the
responsibility of this task at the Parcel No. A33230254800, North Main Street site. This report
describes the methods and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available documentation
adequately and accurately describes the post-remedial-action radiological conditions of the entire
property that is to be certified and (2) that the remedial action reduced contamination to below
applicable DOE guidelines (US DOE 1990a).
Document Reviews
Review of the RAC property completion report (Geotech 1996) indicates the property was reme-
diated as evaluated by DOE on the basis of U.S. Environmental Protection Agency standards and the
DOE guidelines (US DOE 1990a). Excess residual radioactive materials were present, thus it was
appropriate to designate this property for remedial action.
This property, MS01064, and the adjacent property, MS00748, overlay historical property
MSOO 136. The historical property was remediated in 1986 and certified by DOE in 1991. During
the assessments of MS00748 and MS01064, it was discovered that the area remediated under
MSOO 136 was recontaminated. The completion reports for MS00748 and MS01064 reflect the final
radiological status of these properties.
The pre-remedial-action survey performed by the RAC identified 118 yd3 of mill tailings 6 to 12
inches deep. During the actual removal process, a total of 106 yd3 of contaminated earth and uranium
mill tailings, 6 to 48 inches deep, were removed from a 499 m2 area.
The RAC performed a post-excavation survey prior to backfilling the excavated areas. This
survey consisted of surface gamma scans with a scintillometer of the of the exterior, and soil
sampling. Samples representative of the bottom 15-cm (6-in.) soil layers of 8 excavated verification
areas were collected and blended to form representative composite soil samples for each verification
area.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation levels have
not been subtracted. Similarly, background concentrations have not been subtracted from radionu-
clide concentrations in soil samples. Applicable DOE guidelines for protection against radiation are
given in Table 1.
Gamma Measurements
Exterior surface gamma exposure rate measurements taken by the RAC from the excavated areas
prior to backfilling ranged from 13 to 19 uR/h.
Soil Sample Analysis
Prior to backfilling, the RAC collected soil samples representative of the excavated areas from
the bottom 15-cm (6-in.) soil layers. These samples were blended to form composite soil samples
representative of an average over the 8 exterior verification areas. The RAC's analysis of these
samples showed 226Ra concentrations ranging from <1.0 to 2.6 pCi/g in the composite sample.
ORNL ETS obtained a percentage of these samples and performed a confirmatory analysis which
showed 226Ra concentrations ranging from 1.7 to 1.9 pCi/g. These values are below the DOE
guideline value of 15 pCi/g for soil layers > 15 cm below the surface. Results of the RAC and ORNL
soil sample analyses are given in Table 2. Gamma ranges and/or soil sample results demonstrate
compliance to the DOE Hot Spot Guidelines for areas <25 m2 (Table 1).
Radon Measurement Results
Radon decay-product concentration measurements were not collected for this site, since it is
vacant land.
CONCLUSION
Results of RAC soil sample analysis and confirmatory split soil sample analysis by ORNL, show
that radionuclide concentrations are within applicable DOE guidelines. Based on the results ofthe
post-remedial-action data, which are confirmed by the verification assessment data, these radiological
measurements fall below the limits prescribed by DOE guidelines. All deficiencies noted in the initial
review have been identified by the RAC as discussed in a meeting between the RAC and ORNL on
January 15, 1997, and corrected in the revised completion report. It is concluded that the site
successfully meets the DOE remedial action objectives.
4
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of 226Ra in soil
above background levels,
averaged over a 100-m2
area
5 pCi/g averaged over the first 15 cm
of soil below the surface; 15 pCi/g
when averaged over 15-cm-thick soil
layers more than 15 cm below the
surface
Radionuclide con-
centrations in soil
for Hot Spot areas
Exposure to 222Rn
progeny
Maximum Permissible con-
centration of Ra226 in soil
above background level,
for areas less than 25 m2
Average annual radon
progeny concentration
(including background)
Ra226 concentrations, in any surface
or subsurface area less than 25 m2,
is below the guideline by a factor of
(10G7A)'/j, where A is the area of the
elevated region
0.03 WL
(US DOE 1990a)
5
Table 2. Results of ORNL analysis of the RAC soil samples from
Parcel No. A33230254800, North Main Street, Monticello, Utah (MS01064-CS)
^Ra concentration
ORNL RAC (pCi/g)
sample sample Depth
No.a No.* (cm) ORNL
RAC
X2 NCB 913 >15 1.9 2.0
X5 NCB 916 >15 1.7 <1.0
" An X-type sample is a split of the sample taken by the remedial action contractor.
* Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated areas were
taken by the RAC, and these samples were blended to form a composite soil sample, which
represents an average over one of the verification areas.
6
REFERENCES
Geotech 1996. Property Completion Report for Monticello Vicinity Property Remedial Action for
DOE ID NO: MS01064-CS, Address: Parcel No. A33230254800, North Main Street, Monticello,
Utah 84535, RUST Geotech, Grand Junction, Colorado, August 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment Group)
Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National Laboratory, Grand
Junction, Colorado.
US DOE 1990a. Verification and Certification Protocol for the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination and
Decommissioning Program. Revision 3, November 1990. U.S. Department of Energy, Washington,
D.C.
US DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision and Record
of Decision Summary. U.S. Department of Energy, Grand Junction Projects Office, Grand Junction,
Colorado.
DOE ID No.: MS-01069-VL
Property Address: Parcel No. A34240063003, South Highway 191
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech of Energy (DOE)
Ra-226 is s 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [ ]
Ra-226 is * 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2.
In-situ [ ] Lab [X]
Interior gamma is * 20 //R/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is <. 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21.
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[ ] [ ] [X]
(Vacant Lot)
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
[/] [ ] I 1
W t 1
[ ] [ 1
[ ]
MM [X] [ ] [ ] [tf
(Vacant Lot)
[ ] [7<l [ ]
[xl [ ] [ ]
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
•llllllllll 11111111111
SFCERTIFED SFMS-01037
1 ' <
DOE ID No.: MS-01069-VL
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
-Wanda S. B*fs /anda S. Bdsby Date
Manager, Monticello Programs
Rust Geotech
DOE EVALUATION
[X] Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Certification Official ' Date
U.S. Department of Energy'
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-01069-VL
ADDRESS: PARCEL NO. A34240063003
SOUTH HIGHWAY 191
MONTICELLO, UTAH 84535
AUGUST 1996
Prepared for
U.S. Department of Energy
by
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
Wands' S. Busby'
Manager, Monticello Programs
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
i
DOE ID No.: MS-01069-VL
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Inclusion Survey Contractor. DOE reviewed
these evaluation results and determined that the property contained mill
tailings (residual radioactive material) exceeding EPA standards. The
Remedial Action Contractor was notified of the inclusion of this property
into the MVP Project and was authorized by DOE to conduct remedial
action as required to bring the property into conformance with EPA
standards and DOE hot spot criteria.
1
DOE ID No.: MS-01069-VL
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
Property Address:
Property Owner:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
MS-01069-VL
Beginning 208 feet, more or less, east of
the NW corner of the NW4 of Section 6,
T34S., R24E., Salt Lake Base Meridian;
east 208 feet, south 208 feet, west
208 feet, north 208 feet, more or less, to
the beginning, City of Monticello, County of
San Juan, State of Utah
Parcel No. A34240063003
South Highway 191
Monticello, Utah 84535

Vacant Lot (VL)
Oak Ridge National Laboratory
March 5, 1992
Rust Geotech
February 24, 1994
Diamond Back Services, Inc.
9861 Titan Park Circle
Littleton, Colorado
April 18, 1995
August 8, 1995
Interior: 0 cubic yards
Exterior: 916 cubic yards
3,370 square meters (m2)
August 1996
2
DOE ID No.: MS-01069-VL
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of exterior residual radioactive
material (Appendix Figure 2.1). Once excavation was complete, the
affected area was resurveyed for possible remaining residual radioactive
material and, upon attaining satisfactory results, was backfilled with
uncontaminated material. The property was restored to a physical
condition comparable to that which existed prior to remedial action
activities.
2.2 Previously Unidentified Contamination
The radiological assessment identified contamination, 6 inches deep,
within the property. The quantity of contamination for this property was
not specified because it was assessed as part of Group 1. The remedial
action process included the removal of approximately 916 cubic yards of
residual radioactive material, ranging from 6 to 24 inches deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID No.: MS-01069-VL
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by the Remedial Action
Contractor during August 1992, as described in the final REA
dated February 1994. Appendix Figure 2.1 shows the extent of
assessed contamination and identifies the area recommended to
undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the excavation were
collected. Soil samples were collected at the highest exposure-
rate location within each 30- by 30-foot section of the excavation.
These samples were blended to form composite samples
representing the verification areas (Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 13 to 18 microroentgens per
hour (//R/h), as indicated on Appendix Figure 2.1. The results of
analyses for radium-226 in four composite soil samples ranged
from 2.6 to 3.4 picocuries per gram (pCi/g), as indicated in
Appendix Table 3.1.
4
DOE ID No.: MS-01069-VL
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at Parcel No. A34240063003, South
Highway 191, in Monticello, Utah, is recommended for certification as
required by DOE guidelines, and the appropriate records should be
documented.
Certification Data Summary
Applicability Standards Survey Results
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 20 //R/h
above background.
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Shall not exceed 5 pCi/g
above background* in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background* in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
Not applicable: vacant
lot.
Not applicable: vacant
lot.
< 5 pCi/g above
background.
Soil sample results
ranged from 2.6 to
3.4 pCi/g.T
*The background radium-226 concentration is approximately 2.0 pCi/g.
The hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-01069-VL
4.0 APPENDIX
Appendix Table:
Table 3.1 Post-Excavation Sample/Measurement Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
MRW:06-20-96
MS-01069.VL WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-01069-VL
Address: Parcel No. A34240063003, South Highway 191, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range Ct/R/h) Ticket No. Method" (pCi/g)
V-1 13-18 NCJ 570 OCS 2.6
V-2 13-17 NCJ 571 OCS 3.4
V-3 13-18 NCJ 572 OCS 2.6
V-4 13-18 NCJ 573 OCS 3.0
See Appendix Figure 2.1 for the verification areas.
"OCS = Opposed Crystal System
7
42
40
38
36
34
32
30
28
26
24
22
20
18
16
14
12
10
1
12 14 16 18
T
20 22 24 26 28 30 32 34 36 38 40 42 44 46 48 5(
_ SOUTH
HIGHWAY 191
®
Vm
© © © © / f.
12 24
•v.
V-* V-3
13-18 13-16
©
©
V-2
13-17
s E
LU © V-l
13-18
14-16
on ©
14-16
L
SCALE IN FEET
20 10 0 20 40
M:\FAS\0JJ\000J\RM0I089V 08/09/98 2:32pm T50780 NORTH
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. OEPARTUENT
OF ENERGY ANO ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT. UTILITY LOCATION PLAT. OR OTHER IMPROVEMENT SURVEY
PLAT ANO IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE, BUILDING. OR OTHER FUTURE IMPROVEMENT LINE!:.
12 14 16 18 20 22
J I L
24
©
©
Cv.vTI
tv.vj
12-15
12
v-i
16-17
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN jtR/h
ASSESSEO AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE —RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE-RATE RANGE
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
Mtm*cf-«o. w OCCUMMTI U.S. DEPARTMENT OF ENERGY
GAAMD JUNCTION MMJCTt OFFICE. COLOM0O
PARCEL NO. A34240063003
SOUTH HIGHWAY 191
MONTICELLO, UTAH
•bniQMUch M.S-01069-VL
T"l lall IMJUIIW
26 28 30 32 34 36 38 40 42 44 46 48 51
OAK RIDGE NATIONAL LABORATORY PHONE: [phone]
FAX: [phone] MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
FOR THE U.S. DEPARTMENT OF ENERGY
2597 B* Road
GRAND JUNCTION, COLORADO 81503 MAR 1 i m
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by the U.S.
Department of Energy for Residual Radioactive Material at Formerly Utilized Sites Remedial
Action Program (FUSRAP) and Remote Surplus Facilities Management Program Sites (SFMP)
[Revision 2, March 1987]. This evaluation is based on an independent verification review of the
Remedial Action Contractor's completion report and independent field verification.
This recommendation is based upon the Independent Verification Contractor's assessment of the
226Ra concentration in the soil.
This property is recommended for certification by the U.S. Department of Energy.
Location Number: MS01069-VL ;
Location Address: Parcel No. A34240063003. South Highway 191
Monticello. Utah 84535
Property Owner:

Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE B INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
PARCEL NO. A34240063003, SOUTH HIGHWAY 191
MONTICELLO, UTAH (MS01069-VL)
M. K. Jensen
March 1997
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81503
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES v
UST OF FIGURES v
ACKNOWLEDGMENTS vii
ABSTRACT viii
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
THE RAC SURVEY RESULTS 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
ORNL SURVEY RESULTS 6
Gamma Measurements 6
Soil Sample Analysis 6
CONCLUSION 6
REFERENCES 8
ii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 4
2. Results of ORNL and the RAC analyses of soil samples from Parcel No. A34240063003,
South Highway 191, Monticello, Utah (MSO1069-VL) 5
LIST OF FIGURES
I. Property Map 7
v
ACKNOWLEDGMENTS
Research for this project was sponsored by the U.S. Department of Energy, Office of Environ-
mental Restoration, Southwestern Area Programs. The author wishes to acknowledge A. R. Jones
and T. L. Meyer for technical reviews.
vii
ABSTRACT
In 1980, the site of a vanadium and uranium mill at Monticello, Utah, was accepted into the
U.S. Department of Energy (DOE) Surplus Facilities Management Program, with the objectives of
restoring the government-owned mill site to safe levels of radioactivity, disposing of or containing
the tailings in an environmentally safe manner, and rx^rforming remedial actions on off-site (vicinity)
properties that had been contaminated by radioactive material resulting from mill operations. During
1995, the Remedial Action Contractor (RAC) designated by DOE, performed remedial action on the
vicinity property at Parcel No. A34240063003, South Highway 191, Monticello, Utah. The
Environmental Technology Section (ETS) of Oak Ridge National Laboratory was assigned the
responsibility of verifying the data supporting the adequacy of remedial action and confirming the
site's compliance with DOE guidelines. ETS performed an independent field verification at this site.
The ETS found that the site successfully meets the DOE remedial action objectives. Procedures used
by ETS are described in the Environmental Technology Section Procedures Manual (ORNL 1993).
viii
1
RESULTS OF THE TYPE B INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT PARCEL NO. A34240063003, SOUTH HIGHWAY 191
MONTICELLO, UTAH (MS01069-VL)*
INTRODUCTION
The null at Monticello, Utah, was built in 1942 by the United States (U.S.) government through
the Defense Plant Corporation to provide vanadium during World War U. Various government
agencies operated the mill until 1947. In 1948, the Atomic Energy Commission (AEC) obtained the
mill and operated it under contract through 1959 to provide both uranium and vanadium. Mill
operations were terminated on January 1, 1960. In 1961, the mill tailings piles were leveled and
graded, covered with rock and soil, and seeded with native grasses. During 1974 and 1975, the ore
stockpiles were removed from the site and the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city of
Monticello, in San Juan County, Utah. The site is bordered on the south and southeast by land held
by the U.S. Bureau of Land Management. Other boundaries are the city of Monticello and private
property.
During the AEC era, the mill processed approximately one million tons of uranium ore.
Vanadium and uranium were the only substances extracted in the milling process. Other constituents
of the ore remained in the tailings and were not separated prior to disposal. During the years of
active mill operation, the mill tailings were normally moist, so erosion was minimal. However,
throughout the mill's operating period, area residents used these tailings as fill material and as
aggregate in mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy (DOE) initiated
the Surplus Facilities Management Program (SFMP) in 1978 to ensure the safe caretaking and
decommissioning of government facilities that had been retired from service but still had radioactive
contamination. In 1980, the mill site at Monticello was accepted into the SFMP, and the Monticello
Remedial Action Project (MRAP) was established to restore the government-owned mill site to safe
levels of radioactivity, to dispose of or contain the tailings in an environmentally safe manner, and
to perform remedial actions on off-site (vicinity) properties that had been contaminated by
radioactive material resulting from mill operations. The Monticello mill site and the tailings remain
in the custody of the DOE Grand Junction, Colorado, Projects Office. In 1983, remedial actions for
vicinity properties were separated from MRAP with establishment of the Monticello Vicinity
Properties (MVP) Project (US DOE 1990b).
* The verification of remedial action was performed by members of tne Environmental Technology Section of the Health Sciences Research
Division at Oak Ridge National Laboratory under DOE contract DE-AC05-96OR22464 with Lockheed Martin Energy Research Corp.
2
During 1995, the Remedial Action Contractor (RAC) designated by DOE, performed remedial
action on the vicinity property that is the subject of this report, a vacant lot located at Parcel No.
A34240063003, South Highway 191, Monticello, Utah. The remedial action plan required
excavation of all exterior contamination, backfilling with uncontaminated material, and restoration
to a condition comparable to that which existed prior to remedial action (Geotech 1996). When the
excavation stage was completed the property was resurveyed, including soil sampling, by the RAC
and by an independent contractor to verily the data supporting the adequacy of remedial action and
to confirm the site's compliance with DOE guidelines.
The Environmental Technology Section (ETS) of Oak Ridge National Laboratory (ORNL) has
been designated the Independent Verification Contractor for the Parcel No. A34240063003, South
Highway 191 she. ORNL conducts independent Type B field verifications on 10% of the Monticello
vicinity properties. This site was selected for Type B verification. This report describes the methods
and results of the verification surveys.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available documentation
adequately and accurately describes the post-remedial-action radiological conditions of the entire
property that is to be certified and (2) that the remedial action reduced contamination to below
applicable DOE guidelines (US DOE 1990a).
Document Reviews
Review of the RAC property completion report (Geotech 1996) indicates the property was
remediated as evaluated by DOE on the basis of U.S. Environmental Protection Agency standards
(US DOE 1990a) and that excess residual radioactive materials were present. Thus it was
appropriate to designate this property for remedial action
This property was assessed as part of Group 1, therefore the quantity of material assessed is not
available. During the actual removal process, a total of 916 yd3 of contaminated earth and radioactive
material, 6 to 24 inches deep, were removed from a 3,370 m2 area.
The RAC performed a post-excavation survey prior to backfilling the excavated areas. This
survey consisted of surface gamma scans with a scintillometer of the exterior and soil sampling.
Samples representative of the bottom 15-cm (6-in.) soil layers were collected at the highest exposure
rate location within each 30- by 30-foot section of the excavation and blended to form a
representative composite soil sample for each of the four verification areas.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation levels have
not been subtracted. Similarly, background concentrations have not been subtracted from radionu-
clide concentrations in soil samples. Applicable DOE guidelines for protection against radiation are
given in Table 1.
THE RAC SURVEY RESULTS
Gamma Measurements
Exterior surface gamma exposure rate measurements taken by the RAC from the excavated
areas prior to backfilling ranged from 13 to 18 uR/h.
Soil Sample Analysis
Prior to backfilling, the RAC collected soil samples representative of the excavated areas from
the bottom 15-cm (6-in.) soil layers at the highest exposure rate location within each 30- by 30-foot
section. These samples were blended to form composite soil samples representative of an average
over the four large exterior verification areas. The RAC's analysis of these samples showed 226Ra
concentrations ranging from 2.6 to 3.4 pCi/g in the composite sample. ORNL ETS obtained these
samples and performed a confirmatory analysis which showed ^^a concentrations ranging from 2.1
to 4.7 pCi/g. These values are below the DOE guideline values of 15 pCi/g for soil layers >15 cm
below the surface (Table 1). Gamma ranges and/or soil sample results demonstrate compliance to
the DOE Hot Spot Guideline for areas < 25 m2 (Table 1). Results of the RAC and ORNL soil
sample analyses are given in Table 2.
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were not determined as
this property is a vacant lot.
4
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of 226Ra in soil
above background levels,
averaged over a 100-m2 area
5 pCi/g averaged over the first 15 cm
of soil below the surface; 15 pCi/g
when averaged over 15-cm-thick soil
layers more than 15 cm below the
surface.
Radionuclide con-
centrations in soil
for Hot Spot areas
Exposure to 222Rn
progeny
Maximum permissible con-
centration of ^Ra in soil
above background level,
for areas less than 25m2.
Average annual radon proge-
ny concentration (including
background).
Ra226 concentration, in any surface or
subsurface area less than 25 m2, is
below the guideline of (100/A)H, where
A is the area of the elevated region.
0.03 WL
(US DOE 1990a)
5
Table 2. Results of ORNL and the RAC analyses of soil samples
from Parcel No. A34240063003, South Highway 191, Monticello, Utah (MS01069-VL)
^Ra concentration (pCi/g)
ORNL RAC
sample sample Depth
No. No." (cm) Confirmatory ORNL Geotech
Xlfc NCJ 570 >15 2.4 2.6
X2" NCJ 571 >15 2.1 3.4
X3" NCJ 572 >15 2.9 2.6
X4b NCJ 573 >15 4.7 3.0
V2AHC >15 2.0
V2J3HC >15 1.1
V2CHC >15 1.5
V2DHC >15 1.6
V2EHC >15 2.2
V2FHC >15 4.1
V2GHC >15 10.0
V2HHC >15 3.0
V2IHC >15 1.8
V2JHe >15 2.9
V2KHe >15 6.3
V2C NCJ 571 >15 3.5 3.4
° Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated areas were
taken by the RAC. These samples were blended to form composite soil samples which
represent an average over verification areas.
b An X-type sample is a split of the sample taken by the RAC. ORNL performed a confirmatory
analysis of these samples.
c Individual samples collected by ORNL from the highest outdoor gamma in each 30- by 30-foot
section of the verification area.
d Composite of individual high outdoor gamma samples taken by ORNL.
ORNL SURVEY RESULTS
Gamma Measurements
Gamma exposure rate measurements taken by ORNL over the ground surface in the excavated
areas prior to backfilling ranged from 13 to 17 uR/h (Figure 1).
Soil Sample Analysis
ORNL sampled one of the excavated areas prior to backfilling, collecting aliquots at the highest
exposure rate in each 30- by 30-foot section from the bottom 15-cm (6-in.) soil layers. Individual
aliquots were analyzed to show compliance to the DOE Hot Spot Guideline. Equal amounts of each
of these aliquots were then blended to form a composite soil sample representative of an average
over the exterior verification area (V2). ORNL's analysis of these individual samples ranged from
1.1 to 10 pCi/g. The composite sample showed a 226Ra concentration of 3.6 pCi/g. These values are
below the DOE guideline values of 15 pCi/g for soil layers >15 cm below the surface (Table 1).
Results of ORNL sample analyses are given in Table 2.
CONCLUSION
The results of RAC and ORNL soil sample analyses show that radionuclide concentrations are
within applicable DOE guidelines. Based upon the results of the post-remedial-action data, which
are confirmed by the verification assessment data, these radiological measurements fall below the
limits prescribed by DOE guidelines. It is concluded that the site successfully meets the DOE
remedial action objectives.
7
7
E3 V3
i
oo
CM
V2 2
V1
208 FT
x
V2
V3
V4
13-16 MR/h
13- 17 yitR/h
14- 17 /ttR/h
14-17 /LtR/h
0
• 3
RET
« SO 40
EXPLANATION
Assessed
contamination
• f * w*
\f * f f
area
Excavated
ED Area identifier ie
Composite sample
Location of
HOG sample
MS01069
PARCEL NO. A34240063003
SOUTH HIGHWAY 191
MONTICELLO, UTAH
Figure 1. Property Map
8
REFERENCES
Geotech 1996, Property Completion Report for Monticello Vicinity Property Remedial Action
for DOE ID NO: MS01069-VL, Address: Parcel No. A34240063003, South Highway 191,
Monticello, Utah 84535, Rust Geotech, Grand Junction, Colorado, August, 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment Group)
Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National Laboratory, Grand
Junction, Colorado.
US DOE 1990a. Verification and Certification Protocolfor the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination and
Decommissioning Program. Revision 3, November 1990. U.S. Department of Energy,
Washington, D.C.
US DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision and
Record of Decision Summary. U.S. Department of Energy, Grand Junction Projects Office,
Grand Junction, Colorado.
DOE ID No.: MS-01073-RS
Property Address: 381 South First West Street
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech of Energy (DOE)
YES NO NOT TAKEN YES NO NOT TAKEN
Ra-226 is s 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2.
In-situ [X] Lab [ ]
[X]* [ ] [ ] tA] I ] [ ]
Ra-226 is < 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2. [X] [ ] [ ] [ j] [ ] [ ]
In-situ [ ] Lab [X]
Interior gamma is <. 20 //R/h
above background in any
occupied or habitable
structure. [X] [ ] [ ] [>] [ ] [ ]
The radon decay-product
concentration in any
occupied or habitable
structure is <; 0.02
working level or, at
most, 0.03 working level. [ ] [ ] [X] [ ] [ ] [ y\
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21. [ ]
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987). [X]
(Trailer House)
[X] [ ] n ix\ [ ]
[ ] 11 l/X] [ ] [ 1
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of oamma
exposure rates that do not exceed 30 percent above normal background.
•llllllllll Ililllllllll
SFCERTIFED SFMS-00233
DOE ID No.: MS-01073-RS
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
K^C
/anda S.Jsusby ' Date
Manager, Tvlonticello Programs
Rust Geotech
DOE EVALUATION
[<] Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Cpftificatrbn Official Date
U.S. Department of Energy
04%
PROPERTY COMPLETION REPORT
DOE ID NO.: MS-01073-RS
ADDRESS: 381 SOUTH FIRST WEST STREET
MONTICELLO, UTAH 84535
MAY 1996
Prepared for
U.S. Department of Energy
Rust Geotech has been granted authorization to conduct remedial action by the
U.S. Department of Energy. Remedial action was done in accordance with the
U.S. Environmental Protection Agency "Standards for Cleanup of Land and Buildings
Contaminated with Residual Radioactive Materials from Inactive Uranium Processing
Sites," 40 CFR 192.12, 192.20-23, and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria.
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
by
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
•llllllllll 1111111111
SFOCPLRPTS SFMS-00233
(MS-01073)
TABLE OF CONTENTS
section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.1.3 Radon Decay-Product Concentration (RDC) Measurement .... 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
i
DOE ID No.: MS-01073-RS
SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce
the potential hazard to the public due to long-term exposure to low-level
radioactivity associated with the offsite mill tailings derived from the
former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States
Government through its agent, the Defense Plant Corporation, to provide
additional sources of vanadium needed during World War II. Various
government agencies operated the mill until 1947. The AEC obtained the
mill in 1948 and operated it through 1959 under cost-type contracts to
provide both uranium and vanadium. Mill operations were terminated on
January 1, 1960.
The mill processed approximately one million tons of ore during the AEC
operations. Throughout the operating period, mill tailings from the
Monticello millsite were removed from the site and used for construction-
related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for
Remedial Actions at Inactive Uranium Processing Sites" (40 CFR Part 192)
for all cleanup activities under the MVP Project. These standards were
prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and
open lands. Cleanup activities also were conducted to meet the hot spot
criteria established by radiological protection guidelines in the DOE
"Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Management
Program Sites" (Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot
spot criteria by the DOE Remedial Action Contractor. DOE reviewed these
evaluation results and determined that the property contained mill tailings
(residual radioactive material) exceeding DOE hot spot criteria. The
Remedial Action Contractor was notified of the inclusion of this property
into the MVP Project and was authorized by DOE to conduct remedial
action as required to bring the property into conformance with EPA
standards and DOE hot spot criteria.
1
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
Property Address:
Property Owner:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
DOE ID No.: MS-01073-RS
MS-01073-RS
Beginning 54.5 feet north of the SW corner
of Lot 2, Block 7, Monticello Townsite
Survey; east 110 feet, north 80 feet, west
110 feet, south 80 feet to beginning,
County of San Juan, State of Utah
381 South First West Street
Monticello, Utah 84535

Residential Simple (RS)
Not applicable: inclusion requested by the
Remedial Action Contractor
May 20, 1994
Rust Geotech
September 13, 1994
Diamond Back Services, Inc.
9861 Titan Park Circle
Littleton, Colorado
May 1, 1995
May 22, 1995
Interior: 0 cubic yards
Exterior: 7 cubic yards
30 square meters (m2)
May 1996
2
DOE ID No.: MS-01073-RS
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of exterior residual radioactive
material (Appendix Figure 2.1). Once excavation was complete, the
affected areas were resurveyed for possible remaining residual radioactive
material and, upon attaining satisfactory results, were backfilled with
uncontaminated material. The property was restored to a physical
condition comparable to that which existed prior to remedial action
activities.
2.2 Previously Unidentified Contamination
The radiological assessment identified contamination, 6 inches deep,
within the property. The quantity of contamination for this property was
not specified because it was assessed as part of a larger property
(MS-00233-MR) that was subsequently divided into two smaller, separate
properties. The remedial action process included the removal of
approximately 7 cubic yards of residual radioactive material, ranging from
6 to 15 inches deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
3.0 VERIFICATION SUMMARY
DOE ID No.: MS-01073-RS
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by the Remedial Action
Contractor during October and December 1991 and May and
October 1993, as described in the final REA dated September
1994. Appendix Figure 2.1 shows the extent of assessed
contamination and identifies the areas recommended to undergo
remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted after
the removal of residual radioactive material and prior to backfilling.
Following the gamma scan, soil samples representative of the
6-inch-thick soil layer at the bottom of the excavation were
collected. These samples were blended to form a composite
sample representing the verification area (Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 12 to 21 microroentgens per
hour (//R/h), as indicated on Appendix Figure 2.1. The result of
analysis for radium-226 in one composite soil sample was
4.3 picocuries per gram (pCi/g), as indicated in Appendix
Table 3.1.
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
RDC measurements were not taken in the trailer house due to
excessive ventilation caused by no permanent foundation.
4
DOE ID No.: MS-01073-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by EPA standards (40 CFR 192.12, 192.20-23) and
DOE hot spot criteria, as indicated in the Certification Data Summary
below.
Therefore, the property located at 381 South First West Street, in
Monticello, Utah, is recommended for certification as required by DOE
guidelines, and the appropriate records should be documented.
Certification Data Summary
Applicability
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Standards
Shall not exceed 20 //R/h
above background.*
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Survey Results
Range for the ground
floor was 12 to 13 //R/h.
Not taken in the trailer
house due to no
permanent foundation.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above background in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
< 5 pCi/g above
background.**
Soil sample result was
4.3 pCi/g.**
*The background exposure rate is approximately 14 //R/h.
The background radium-226 concentration is approximately 2.0 pCi/g.
* *The hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-01073-RS
4.0 APPENDIX
Appendix Table:
Table 3.1 Post-Excavation Sample/Measurement Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
SJW:05-03-96
MS-01073.RS WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-01073-RS
Address: 381 South First West Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (//R/h) Ticket No. Method" (pCi/g)
V-1 16-21 NCL 477 OCS 4.3
See Appendix Figure 2.1 for the verification area.
"OCS = Opposed Crystal System
7
30
28
26
24
22
20
18
16
14
12
2b
Ld
UJ tr
r-
CO
CO
CO
or
3
o
CO
V-1
16-21
SHED
12-13 C X 6 6
3
15
6 6
rh 13-16 J
TRAILER
HOUSE
12-13
13-16 G
Y
SCALE IN FEET
20 10 0 20 40
M:\FAS\033\0003\RM01073V 05/02/96 10:23am T50780
NORTH
28
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT, UTILITY LOCATION PLAT, OR OTHER IMPROVEMENT SURVEY
PLAT AND IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE, BUILDING, OR OTHER FUTURE IMPROVEMENT LINES.
10
10 12 14 16 18 20 22 24 26 28
30
®
F7.-"vl
Lv.vj
12-15
12
V-1
16-17
32 34 36 38
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN //R/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE-RATE RANGE
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
40
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
RESIDENCE-NO. OF OCCUPANTS
NON—RESIDENCE—HAN—HRS./WK.
INSTRUMENT NO.
SURVEY DATE
VERIFICATION
CK. A.E. APP. NO. OATE CK. A.E. APP.
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE. COLORADO
SD DEStGNE
DRAW
Safe P CHECKED
PROJ. ENG
381 SOUTH FIRST WEST STREET
MONTICELLO, UTAH
SUBMITTED
Rust Qeotech
AHMttKMxRiCaiM*
DATE I APPROVAL DOE DATE
OOEIONO. MS-01073-RS
OWO.NO. 3-B01073-V1 1 „, 1 snTi if
30
28
26
24
22
20
18
16
14
12
10
30 32 34 36 38 40
OAK RIDGE NATIONAL LABORATORY
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
FOR THE US. DEPARTMENT OF ENERGY
PHONE: [phone]
FAX [phone]
POST OFFICE BOX 2567
GRAND JUNCTION, COLORADO 81502
Me 30 m
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by
the U.S. Department of Energy for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program (FUSRAP) and Remote Surplus Facilities Management Program
Sites (SFMP) [Revision 2, March 1987]. This evaluation is based on an independent verifi-
cation review of the Remedial Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment of
the 226Ra concentration in the soil and indoor gamma exposure rates at this property.
This property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
Location Number: MS01073-RS
Location Address: 381 South 1st West Street
Monticello, Utah 84535
Property Owner:

Attachments
HEALTH SCIENCES RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
381 SOUTH 1ST WEST STREET
MONTICELLO, UTAH (MS01073-RS)
M. J. Wilson-Nichols
August 1996
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO SI502
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 3
REFERENCES 5
iii
LIST OF TABLES
Applicable guidelines for protection against radiation
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site
Deconmiissioning Projects, U.S. Department of Energy. The author wishes to
acknowledge M. K. Jensen for analysis of soil samples and N. F. Kirby and A. R.
Jones for technical reviews.
vii
ABSTRACT
In 1980 the site of a vanadium and uranium mill at Monticello, Utah, was accepted
into the U.S. Department of Energy's (DOE's) Surplus Facilities Management Program,
with the objectives of restoring the government-owned mill site to safe levels of radio-
activity, disposing of or containing the tailings in an environmentally safe manner, and
performing remedial actions on off-site (vicinity) properties that had been contaminated
by radioactive material resulting from mill operations. During 1995, RUST Geotech, the
remedial action contractor designated by DOE, performed remedial action on the vicinity
property at 381 South 1st West Street, Monticello, Utah. The Environmental Technology
Section (ETS) of Oak Ridge National Laboratory was assigned the responsibility of veri-
fying the data supporting the adequacy of remedial action and confirming the site's compli-
ance with DOE guidelines. The ETS found that the site successfully meets the DOE re-
medial action objectives. Procedures used by the ETS are described in the Environmental
Technology Section Procedures Manual (ORNL 1993).
ix
1
RESULTS OF THE INDEPENDENT VERD7ICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 381 SOUTH 1ST WEST STREET
MONTICELLO, UTAH (MS01073-RS)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the U.S. government through the
Defense Plant Corporation to provide vanadium during World War II. Various govern-
ment agencies operated the mill until 1947. In 1948 the Atomic Energy Commission
(AEC) obtained the mill and operated it under contract through 1959 to provide both
uranium and vanadium. Mill operations were terminated on January 1, 1960. In 1961 the
mill tailings piles were leveled and graded, covered with rock and soil, and seeded with na-
tive grasses. During 1974 and 1975, the ore stockpiles were removed from the site, and
the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city
of Monticello, in San Juan County, Utah. The site is bordered on the south and southeast
by land held by the U.S. Bureau of Land Management. Other boundaries are the city of
Monticello and private property.
During the AEC era, the mill processed approximately one million tons of uranium
ore. Vanadium and uranium were the only substances extracted in the milling process.
Other constituents of the ore remained in the tailings and were not separated prior to dis-
posal. During the years of active mill operation, the mill tailings were normally moist, so
erosion was minimal. However, throughout the mill's operating period, area residents
used these tailings as fill material and as aggregate in mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy
(DOE) initiated the Surplus Facilities Management Program (SFMP) in 1978 to ensure
the safe caretaking and decommissioning of government facilities that had been retired
from service but still had radioactive contamination. In 1980 the mill site at Monticello
was accepted into the SFMP, and the Monticello Remedial Action Project (MRAP) was
established to restore the government-owned mill site to safe levels of radioactivity, to
dispose of or contain the tailings in an environmentally safe manner, and to perform reme-
dial actions on off-site (vicinity) properties that had been contaniinated by radioactive ma-
terial resulting from mill operations. The Monticello mill site and the tailings remain in the
custody of the DOE Grand Junction, Colorado, Projects Office. In 1983 remedial actions
for vicinity properties were separated from MRAP with establishment of the Monticello
Vicinity Properties (MVP) Project (U.S. DOE 1990b).
*The verification of remedial action was performed by members of the Environmental Assessment Group in the
Environmental Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE
contract DE-AC05-96OR22464 with Lockheed Martin Energy Research Corporation.
2
During 1995, RUST Geotech Inc. (Geotech), the remedial action contractor (RAC)
designated by DOE, performed remedial action on the vicinity property that is the subject
of this report, a single family residence located at 381 South 1st West Street, Monticello,
Utah. The remedial action plan required excavation of all exterior contamination. When
the excavation was completed, the property was resurveyed, including soil sampling, to
ensure the removal of all contamination, backfilled with uncontaminated material, and
restored to a condition comparable to that which existed prior to remedial action (Geotech
1996).
The DOE adopted a policy to assign an independent contractor to verify the data
supporting the adequacy of remedial action and to confirm the site's compliance with DOE
guidelines. The Environmental Technology Section (ETS) of Oak Ridge National Labor-
atory (ORNL) has been assigned the responsibility of this task at the 381 South 1st West
Street site. This report describes the methods and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available doc-
umentation adequately and accurately describes the post-remedial-action radiological
conditions of the entire property that is to be certified and (2) that the remedial action
reduced contamination to below applicable DOE guidelines (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1996) in-
dicates the property was remediated as evaluated by DOE on the basis of Environmental
Protection Agency standards and the DOE guidelines (DOE 1990a). Excess residual
radioactive materials were present, thus it was appropriate to designate this property for
remedial action.
This property was assessed as part of MS00233-MR, therefore, the quantity of
material assessed is not available. During the actual removal process, a total of 7 yd3 of
contaminated earth and uranium mill tailings, 6 to 15 inches deep, were removed from a
30 m2 area.
A post-excavation survey was performed by Geotech prior to backfilling the exca-
vated areas. This survey consisted of gamma scans with a scintillometer of the ground
level ofthe structure, a surface scan of the exterior, and soil sampling. Samples repre-
sentative ofthe bottom 15-cm (6-in.) soil layers of the excavated verification area were
collected and blended to form a representative composite soil sample. The RAC is unable
to locate or inadvertently disposed of the sample requested for ORNL confirmatory
analysis.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation
levels have not been subtracted. Similarly, background concentrations have not been sub-
tracted from radionuclide concentrations in soil samples. Applicable DOE guidelines for
protection against radiation are given in Table 1.
Gamma Measurements
Gamma exposure rate measurements taken by Geotech at the ground-level of the
residence ranged from 12 to 13 uR/h. Exterior surface gamma measurements taken from
the excavated areas prior to backfilling ranged from 16 to 21 uR/h.
Soil Sample Analysis
Prior to backfilling, Geotech collected soil samples representative of the excavated
areas from the bottom 15-cm (6-in.) soil layers. These samples were blended to form a
composite soil sample representative of an average over the exterior verification area.
Geotech's analysis of this sample showed a ^Ra concentration of 4.3 pCi/g. ORNL ETS
was unable to obtain this sample for confirmatory analysis. The value of Geotech's sam-
ple is below the EPA standard value of 15 pCi/g for soil layers > 15 cm below the surface.
Gamma ranges and/or soil sample results demonstrate compliance to the DOE Hot Spot
Guidelines for areas <25 m2 (Table 1).
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were not taken
at this property because the structure is a trailer house with no permanent foundation.
CONCLUSION
Results of Geotech soil sample analysis show that radionuclide concentrations are
within applicable DOE guidelines. Based on the results of the post-remedial-action data,
which are confirmed by the verification assessment data, these radiological measurements
fall below the limits prescribed by DOE guidelines. It is concluded that the site success-
fully meets the DOE remedial action objectives.
4
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Radionuclide con-
centrations in soil
for Hot Spot areas
Exposure to 222Rn
progeny
Maximum permissible con-
centration of ^Ra in soil
above background levels,
averaged over a 100-m2 area
Maximum Permissible con-
centration of Ra226 in soil
above background level for
areas less than 25 m2
Average annual radon proge-
ny concentration (including
background)
5 pCi/g averaged over the
first 15 cm of soil below the
surface; 15 pCi/g when ave-
raged over 15-cm-thick soil
layers more than 15 cm
below the surface
Ra226 concentrations, in any
surface or subsurface area
less than 25 m2, is below the
guideline by a factor of
(100/A)M, where A is the
area of the elevated region
0.03 WL
(DOE 1990a)
5
REFERENCES
Geotech 1996. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS01073-RS, Address: 381 South First West Street,
Monticello, Utah 84535, Geotech, Grand Junction, Colorado, May 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
U.S. DOE 1990a. Verification and Certification Protocolfor the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination
and Decommissioning Program, Revision 3, November 1990. U.S. Department of
Energy, Washington, D.C.
U.S. DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision
and Record of Decision Summary. U.S. Department of Energy, Grand Junction Projects
Office, Grand Junction, Colorado.
DOE ID No.: MS-01076-RS
Property Address: 1057 North Main Street
Vicinity Property Certification Summary and Recommendation
Summary Evaluation
Certification Criteria MACTEC-ERS
U.S. Department
of Energy (DOE)
Ra-226 is < 5 pCi/g above background
in top 15-cm-thick layer of soil
averaged over 100 m2
In situ [X] Lab [ ]
Ra-226 is < 15 pCi/g above
background in any 15-cm-thick layer of
soil more than 15 cm below the
surface averaged over 100 m2.
In situ [ ]Lab[X]
Interior gamma is < 20 uR/h above
background in any occupied or
habitable structure.
The radon decay-product
concentration in any occupied or
habitable structure is < 0.02 WL or, at
most, 0.03 WL.
Supplemental standards were applied
in accordance with EPA standard
40 CFR 192.21.
Hot spot criteria met as outlined by
DOE guidelines for FUSRAP (Rev.2,
March 1987)
Yes No Not Taken Yes No Not Taken
[X]a [ ]
[X] [ ]
[X] [ ]
[X] [ ]
[ ] [X]
[X] [ ]
[ ]
[ ]
[ ]
[ ]
[ ]
[ ]
in i ]
[X] [ ]
[yj [ ]
LX] [ ]
[ ] [X
lyi [ i
[ ]
[ ]
[ ]
[ ]
[ ]
[ ]
aThe excavations were backfilled with materials that were measured at the source indicating that the Ra-226
concentrations are in the range of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
•lilllilll llIHIlIfflU
SFCERTIFED SFMS-00726
1 of 2
DOE ID No.: MS-01076-RS
MACTEC-ERS Recommendation
On the basis of the Property Completion Report evaluation, this property is recommended for
[X] Certification by DOE.
[ ] Certification by DOE with the concurrence of the U. S. Nuclear Regulatory Commission
because supplemental standards were applied according to 40 CFR 192.21.
Manager, Monticello Programs
MACTEC-ERS
DOE Evaluation
On the basis of the Property Completion Report recommendation, this property
[ VJ Should be certified by DOE.
[ ] Should be certified by DOE with the concurrence of the U.S. Nuclear Regulatory
Commission because supplemental standards were applied according to 40 CFR 192.21.
Date
U.S. Department of Energy
Work performed under DOE Contract No. DE-AC 13-96GJ87335, Task Order No. 96-05.02.14
2 Of 2
Monticello Vicinity Properties Project
Property Completion Report
for
Monticello
Vicinity Property Remedial Action
for
DOE H) No.: MS-01076-RS
Address: 1057 North Main Street
Monticello, Utah 84535
November 1996
Prepared for
U.S. Department of Energy
Albuquerque Operations Office
Grand Junction Office
Prepared by
MACTEC-ERS*
Grand Junction, Colorado
Michael C. Butherus ^
Manager, Monticello Programs
Work performed under DOE Contract No. DE-AC 13-96GJ87335
Task Order No. 96-05.02.14
"MACTEC-ERS has been granted authorization to conduct remedial action by the U.S. Department of Energy.
Remedial action was performed in accordance with the U.S. Environmental Protection Agency "Standards for Cleanup
of Land and Buildings Contaminated with Residual Radioactive Materials from Inactive Uranium Processing Sites,"
40 CFR 192, Subpart B; and "Implementation," in 40 CFR 192, Subpart C. and the U.S. Department of Energy Formerly
Utilized Sites Remedial Action Program hot spot criteria
DOE ID No.: MS-01076-RS
Contents
Page
1.0 Summary 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Remedial Action Summary 2
2.0 Operations Summary 3
2.1 Remedial Action Plan 3
2.2 Assessed and Remediated Contamination 3
3.0 Verification Summary 4
3.1 Radiological Survey Data 4
3.1.1 Preremedial Action Survey 4
3.1.2 Postexcavation Survey 4
3.1.3 Radon Decay-Product Concentration Measurements 4
3.2 Recommendation for Certification 5
Table
Table 1. Certification Data Summary . 5
Appendix
Appendix A. Radiological Conditions A-1
]X)i;/Graiiel Junction Oliice MVP Property Completion Report
November 1996 Page ii
DOE ID No.: MS-01076-RS
1.0 Summary
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) Project was established to reduce the potential hazard
to the public due to long-term exposure to low-level radioactivity associated with the offsite mill
tailings derived from the former U.S. Atomic Energy Commission (AEC) uranium mill.
The original mill, built in 1942, was financed by the United States Government through its agent,
the Defense Plant Corporation, to provide additional sources of vanadium needed during World
War II. Various government agencies operated the mill until 1947. The AEC obtained the mill in
1948 and operated it through 1959 under cost-type contracts to process uranium and vanadium
ore. Mill operations were terminated on January 1, 1960.
The mill processed approximately one million tons of ore during the AEC operations. Throughout
the operating period, mill tailings from the Monticello millsite were removed from the site and
used for construction-related activities in the vicinity.
1.2 Criteria for Remedial Action
The U.S. Department of Energy (DOE) adopted the "Standards for Remedial Actions at Inactive
Uranium Processing Sites" (40 CFR Part 192) for all cleanup activities under the MVP Project.
These standards were prepared by the U.S. Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of buildings and open lands. Cleanup
activities also were conducted to meet the hot spot criteria established by radiological protection
guidelines in the DOE Guidelines for Residual Radioactive Material at Formerly Utilized Sites
Remedial Action Program and Remote Surplus Facilities Managemenl Program Sites
(Revision 2, March 1987).
This property was evaluated on the basis of EPA standards and DOE hot spot criteria and
determined to contain mill tailings (radioactive material) exceeding EPA standards and/or DOE
hot spot criteria. The Remedial Action Contractor was notified of the inclusion of this property
into the MVP Project and was authorized by DOE to conduct remedial action as required to bring
the property into conformance with EPA standards and DOE hot spot criteria.
DOH'Orand Junction Office
November 19%
MVP Properly Completion Report
Page 1
DOE ID No.: MS-01076-RS
1.3 Remedial Action Summary
DOE D3 No.:
Legal Description:
Property Address:
Property Owners:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological and Engineering Assessment (REA):
Construction Subcontractor:
Preconstruction Conference Record:
Notice of Final Completion Inspection:
Volume of Material Removed in Cubic Yards (yd3):
Area Cleaned Up in Square Meters (m2):
Property Completion Report Submitted:
MS-01076-RS
Beginning 1,040 feet south and
644 feet east of the N4 corner of
Section 25, T33S., R23E., Salt Lake
Base Meridian; north 165 feet,
easterly 163 feet, south 165 feet, west
163 feet to the beginning, City of
Monticello, County of San Juan, State
of Utah
1057 North Main Street
Monticello, Utah 84535

Residential Simple (RS)
MACTEC-ERS
November 2, 1993
MACTEC-ERS
June 23, 1994
Diamond Back Services, Inc.
July 18, 1995
August 14, 1995
Exterior: 69
Interior: 0
221
November 1996
DOli/Grand Junction Office
November 19%
MVP Property Completion Report
Page 2
DOE ID No.: MS-01076-RS
2.0 Operations Summary
2.1 Remedial Action Plan
The remedial action plan specified removal of radioactive material. Once excavation was
completed, the affected areas were resurveyed for possible remaining radioactive material and,
upon attaining satisfactory results, were backfilled with uncontaminated material. The property
was restored to a physical condition comparable to that which existed before remedial action
activities.
2.2 Assessed and Remediated Contamination
The radiological assessment identified contamination, ranging from 6 to 18 inches (in.) deep,
within the property boundary. The quantity of contamination for this property was not specified
because it was assessed as part of Group 17. The remedial action process included removal of
approximately 69 yd3 of radioactive material, ranging from 6 to 30 in. deep. The areas of assessed
and excavated contamination are shown on Figure A-1.
lX)H/Orand Junction Office
November 19%
MV1' Property Completion Report
Page 3
DOE ID No.: MS-01076-RS
3.0 Verification Summary
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Preremedial Action Survey
The Remedial Action Contractor conducted a radiological survey during October 1992, as
described in the final REA. Figure A-1 shows the extent of assessed contamination and identifies
the areas recommended for remedial action.
3.1.2 Postexcavation Survey
A scintillometer was used to perform a surface gamma scan after the removal of radioactive
material and before backfilling. Following the gamma scan, soil samples representative of the
6-in.-thick soil layer at the bottom of the excavation were collected. An individual soil sample was
collected for Area V-4. The remaining samples were blended to form composite samples
representing the other verification areas. These samples, representing the verification areas, were
analyzed for radium-226. The results of the gamma scan and analyses for radium-226 are
presented in Table A-1.
3.1.3 Radon Decay-Product Concentration Measurements
Radon decay-product concentration (RDC) measurements were taken on the lowest habitable
level of the house, as shown on Figure A-1. The measurement results are presented in Table A-2.
IX)1- Grand Junction Office
November 1990
MVP Property Completion Report
Page 4
DOE ID No.: MS-01076-RS
3.2 Recommendation for Certification
Radioactive materials have been removed from this property to the extent required by EPA
standards (40 CFR 192, Subparts B and C) and DOE hot spot criteria, as indicated in the
Certification Data Summary (Table 1). Therefore, the property located at 1057 North Main
Street, in Monticello, Utah, is recommended for certification as required by DOE guidelines.
Table 1. Certification Data Summary
Applicability Standard Survey Results
Radium-226
Concentration in
Surface Soil
Radium-226
Concentration in
Subsurface Soil
Land
Shall not exceed 5 pCi/g above
background3 in the 15-cm-thick
surface layer, averaged over
100 m2.
Shall not exceed 15 pCi/g
above background3 in any
15-cm-thick soil layer more than
15 cm below the surface,
averaged over 100 m2.
Habitable Structures
< 5 pCi/g above background on the
basis of gamma exposure rates that do
not exceed 30 percent above normal
background.11
Soil sample results ranged from 1.6 to
3.9 pCi/g.b
Exposure Rate Shall not exceed 20 uR/h above
background.0
Range for the ground floor was 12 to
15 pR/h.
Radon Decay-
Product
Concentration
Annual average shall not
exceed 0.02 WL, to the extent
practicable, and shall in no
case exceed 0.03 WL.
Average was 0.0128 WL, on the basis
of the DOE-approved abbreviated-
measurement method.
Key: cm = centimeters; m2 = square meters; pCi/g = picocuries per gram; uR/h = microroentgens per hour
WL = working level
aThe background radium-226 concentration for Monticello Vicinity Properties is approximately 2.0 pCi/g.
The hot spot criteria were met based on gamma scans and/or soil sample results.
cThe background exposure rate for this property is approximately 15 uR/h.
DOM/Grand Junction Office
November 1996
MVP Property Completion Report
Page 5
DOE ID No.: MS-01076-RS
Appendix A
Radiological Conditions
Table A-1. Postexcavation Survey Results
Table A-2. Radon Decay-Product Concentration Measurement Results
Figure A-1. Radiological As-Built
DOE ID No.: MS-01076-RS
Table A-1. Postexcavation Survey Results
Gamma Radium-226
Verification Exposure Rate Soil Sample Measurement Concentration
Area3 Range (uR/h) Ticket No. Method (pCi/g)
V-1 15-18 NCH 077 OCS 2.9
V-2 14-23 NCH 078 OCS 3.9
V-3 15-29 NCH 079 OCS 1.6
V-4 20-23 NCH 080 OCS 3.7
Key: OCS = opposed crystal system; pCi/g = picocuries per gram; uR/h = microroentgens per hour
V = verification area
'See Figure A-1 for location of verification areas.
OOH/Grand JunetionOfliee
November 1990
MVP Property Completion Report
Page A -2
DOE ID No.: MS-01076-RS
Table A-2. Radon Decay-Product Concentration Measurement Results3
Detector6
Number Start Date End Date
Radon
Concentration
(pCi/L) WL
3973925
3973998
3973966
03-09-95
03-09-95
03-09-95
06-07-95
06-07-95
06-07-95
2.39
2.68
2.60
Average:
0.0120
0.0134
0.0130
0.0128
Key: pCi/L = picocuries per liter; WL = working level
aSee Figure A-1 for measurement location.
bTerradex Radtrak Detector.
DOI- Grand JunctionOllkc
November 19%
MVP Property Completion Report
Page A 3
10
30
12 14 16 18 20 22 24 26 28
~T~
30 32 34 36 38 40
30
28
26
24
22
20
18
16
1 4
1 2
Y
0
1 13-15
o 12, 73 73
O X 13-15 •7-
rn ^
O 7)
V-3
\ v\ GARAG
®
V-4
12-15 30
v
<
2
13-15 V-10
STO RY \
FRAM OU V-3 RDC
1 2
DC
E X 6 1 2
30
13-15 \< 6 X D V-1
1 2 B X 6 V-3 1 2
12
V-3
I
M:\FAS\033\0003\RM01076V 11/13/96 1 0:09am M5031 2
—— X
_J I I I I I
NORTH
SCALE IN FEET
- 28
26
20 10 0 20 40
24
LEGEND
ALL DEPTHS/HEIGHTS IN INCHES
ALL EXPOSURE RATES IN //R/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH OF ASSESSED CONTAMINATION "
AREA OF ASSESSED CONTAMINATION
EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION AREA IDENTIFIER
RADON DECAY-PRODUCT CONCENTRATION
MEASUREMENT LOCATION
ASSESSED CONTAMINATION NOT FOUND AT TIME _
OF REMEDIAL ACTION
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT, UTILITY LOCATION PLAT. OR OTHER IMPROVEMENT SURVEY
PLAT AND IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE. BUILDING, OR OTHER FUTURE IMPROVEMENT LINES.
22
20
18
1 6
1 4
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION OFFICE, COLORADO
1057 NORTH
MAIN STREET
MONTICELLO, UTAH
COMPLETION REPORTS MONTICELLO VICINITY PROPERTIES
1 2
FIGURE A-1
RADIOLOGICAL AS-BUILT
MS-01076-RS
10 12 1 4 1 6 18 20 22 24 26 28 30 32 34
3-B01076-V1
36
1 1
1 0
38 40
OAK RIDGE NATIONAL LABORATORY
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
FOR THE U.S. DEPARTMENT OF ENERGY
PHONE: [phone]
FAX: [phone]
2597 B'/. Road
GRAND JUNCTION, COLORADO 81503
APR 1 6 1997
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, Colorado 81502
Dear Ms. Rondinella:
Radiation levels at the property identified below do not exceed the guidelines specified by the U.S.
Department of Energy for Residual Radioactive Material at Formerly Utilized Sites Remedial Action
Program (FUSRAP) and Remote Surplus Facilities Management Program Sites (SFMP) [Revision
2, March 1987]. This evaluation is based on an independent verification review of the Remedial
Action Contractor's completion report.
This recommendation is based upon the Independent Verification Contractor's assessment of the 226Ra
concentration in the soil, indoor radon daughter concentration, and indoor gamma exposure rates at
this property.
This property is recommended for certification by the U.S. Department of Energy.
Sincerely,
Gretchen A. Pierce
MVP/IVC Project Manager
Environmental Assessment Group
MS01076-RS
1057 North Main Street
Monticello. Utah 84535

Location Number:
Location Address:
Property Owner:
Owner Address:
Attachments
LIFE SCIENCES DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
1057 NORTH MAIN STREET
MONTICELLO, UTAH (MS01076-RS)
M. K. Jensen
April 1997
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81503
managed by
LOCKHEED MARTIN ENERGY RESEARCH CORPORATION
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-96OR22464
CONTENTS
LIST OF TABLES iv
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
Radon Measurement Results 3
CONCLUSION 4
REFERENCES 7
iii
LIST OF TABLES
1. Applicable guidelines for protection against radiation 5
2. Results of ORNL analysis of the RAC soil samples from 1057 North Main Street,
Monticello, Utah (MS01076-RS) 6
iv
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site Decommissioning
Projects, U.S. Department of Energy. The author wishes to acknowledge A. R. Jones and S. M.
Smith for technical reviews.
vii
ABSTRACT
In 1980, the site of a vanadium and uranium mill at Monticello, Utah, was accepted into the U.S.
Department of Energy (DOE) Surplus Facilities Management Program, with the objectives of
restoring the government-owned mill site to safe levels of radioactivity, disposing of or containing
the tailings in an environmentally safe manner, and performing remedial actions on off-site (vicinity)
properties that had been contaminated by radioactive material resulting from mill operations. During
1995, the Remedial Action Contractor (RAC) designated by DOE, performed remedial action on the
vicinity property at 1057 North Main Street, Monticello, Utah. The Environmental Technology
Section (ETS) of Oak Ridge National Laboratory was assigned the responsibility of verifying the data
supporting the adequacy of remedial action and confirming the site's compliance with DOE guidelines.
The ETS found that the site successfully meets the DOE remedial action objectives. Procedures used
by the ETS are described in the Environmental Technology Section Procedures Manual (ORNL
1993).
ix
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 1057 NORTH MAIN STREET
MONTICELLO, UTAH (MS01076-RS)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the United States (U.S.) government through
the Defense Plant Corporation to provide vanadium during World War U. Various government
agencies operated the mill until 1947. In 1948, the Atomic Energy Commission (AEC) obtained the
mill and operated it under contract through 1959 to provide both uranium and vanadium. Mill
operations were terminated on January 1, 1960. In 1961, the mill tailings piles were leveled and
graded, covered with rock and soil, and seeded with native grasses. During 1974 and 1975, the ore
stockpiles were removed from the site and the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city of
Monticello, in San Juan County, Utah. The site is bordered on the south and southeast by land held
by the U.S. Bureau of Land Management. Other boundaries are the city of Monticello and private
property.
During the AEC era, the mill processed approximately one million tons of uranium ore. Vana-
dium and uranium were the only substances extracted in the milling process. Other constituents of
the ore remained in the tailings and were not separated prior to disposal. During the years of active
mill operation, the mill tailings were normally moist, so erosion was minimal. However, throughout
the mill's operating period, area residents used these tailings as fill material and as aggregate in
mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy (DOE) initiated
the Surplus Facilities Management Program (SFMP) in 1978 to ensure the safe caretaking and de-
commissioning of government facilities that had been retired from service but still had radioactive
contamination. In 1980, the mill site at Monticello was accepted into the SFMP, and the Monticello
Remedial Action Project (MRAP) was established to restore the government-owned mill site to safe
levels of radioactivity, to dispose of or contain the tailings in an environmentally safe manner, and
to perform remedial actions on off-site (vicinity) properties that had been contaminated by radio-
active material resulting from mill operations. The Monticello mill site and the tailings remain in
the custody of the DOE Grand Junction, Colorado, Projects Office. In 1983, remedial actions for
vicinity properties were separated from MRAP with establishment of the Monticello Vicinity Proper-
ties (MVP) Project (US DOE 1990b).
*The verification of remedial action was performed by members of the Environmental Assessment Group in the Environmental
Technology Section of the Life Sciences Division at Oak Ridge National Laboratory under DOE contract DE-AC05-96OR22464
with Lockheed Martin Energy Research Corporation.
2
During 1995, the Remedial Action Contractor (RAC) designated by DOE, performed remedial
action on the vicinity property that is the subject of this report, a single family residence located at
1057 North Main Street, Monticello, Utah. The remedial action plan required excavation of all
exterior contamination. When the excavation was completed, the property was resurveyed, including
soil sampling, to ensure the removal of all contamination, backfilled with uncontaminated material,
and restored to a condition comparable to that which existed prior to remedial action (MACTEC-
ERS 1996).
DOE adopted a policy to assign an independent contractor to verify the data supporting the
adequacy of remedial action and to confirm the site's compliance with DOE guidelines. The
Environmental Technology Section (ETS) of Oak Ridge National Laboratory (ORNL) has been
assigned the responsibility of this task at the 1057 North Main Street site. This report describes the
methods and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available documentation
adequately and accurately describes the post-remedial-action radiological conditions of the entire
property that is to be certified and (2) that the remedial action reduced contamination to below
applicable DOE guidelines (US DOE 1990a).
Document Reviews
Review of the RAC property completion report (MACTEC-ERS 1996) indicates the property
was remediated as evaluated by DOE on the basis of U.S. Environmental Protection Agency
standards and the DOE guidelines (US DOE 1990a). Excess residual radioactive materials were
present, thus it was appropriate to designate this property for remedial action.
This property was assessed as part of Group 17, therefore, the quantity of material assessed is
not available. During the actual removal process, a total of 69 yd3 of contaminated earth and residual
radioactive material, 6 to 30 inches deep, were removed from a 221 m2 area.
The RAC performed a post-excavation survey prior to backfilling the excavated areas. This
survey consisted of gamma scans with a scintillometer of the ground level of the structure, a surface
scan of the exterior, and soil sampling. Samples representative of the bottom 15-cm (6-in.) soil
layers of four excavated verification areas were collected and blended to form representative
composite soil samples for each verification area.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation levels have
not been subtracted. Similarly, background concentrations have not been subtracted from radionu-
clide concentrations in soil samples. Applicable DOE guidelines for protection against radiation are
given in Table 1.
Gamma Measurements
Gamma exposure rate measurements taken by the RAC at the ground-level of the residence
ranged from 12 to 15 pR/h. Exterior surface gamma measurements taken from the excavated areas
prior to backfilling ranged from 14 to 29 uR/h.
Soil Sample Analysis
Prior to backfilling, the RAC collected soil samples representative of the excavated areas from
the bottom 15-cm (6-in.) soil layers. These samples were blended to form composite soil samples
representative of an average over the four exterior verification areas. The RAC's analysis of these
samples showed 226Ra concentrations ranging from 1.6 to 3.9 pCi/g in the composite sample. ORNL
ETS obtained these samples and performed a confirmatory analysis which showed 226Ra
concentrations ranging from 2.3 to 4.2 pCi/g. These values are below the DOE guideline value of
15 pCi/g for soil layers >15 cm below the surface. Results of the RAC and ORNL soil sample
analyses are given in Table 2.2.
As a result of a meeting between the RAC and IVC on May 26, 1994, anomalous readings,
defined as >30% above the average of the excavation, will be investigated to show compliance to
the DOE Hot Spot Guideline. This property was remediated after this procedure change. The RAC
collected an excavation control sample at the highest gamma measurement in area V3 to show
compliance, however, additional excavation control samples in areas V2 and V3 exceeding 30% of
the excavation average were not taken. The IVC observed that 25 uR/h exceeds 30% of the
excavation average of 20 uR/h. The IVC will allow a correlation developed by the RAC to estimate
226Ra pCi/g concentrations based on gamma exposure rates. The anomalous reading of 25 uR/h on
this property using the RAC's correlation yields a 226Ra concentration of 4.4 pCi/g. This value is
well below the minimum concentration of 30 pCi/g needed, when assuming the maximum area under
the hot spot guideline of 25 m2, for subsurface samples. Gamma ranges and/or soil sample results
demonstrate compliance to the DOE Hot Spot Guidelines for areas <25 m2 (Table 1).
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were determined prior
to remediation by the Alpha-track method. To monitor radon levels, the RAC placed three alpha-
track detectors on the ground floor of the residence located on this property for a period of
approximately three months (from March 9, 1995 to June 7, 1995). The average annual working
level (WL) of radon progeny concentration, as determined by the TechVOps-Landauer Corporation,
was 0.0128, which is below the 0.03-WL guideline given in Table 1.
4
CONCLUSION
Results of RAC soil sample analysis and confirmatory split soil sample analysis by ORNL, show
that radionuclide concentrations are within applicable DOE guidelines. Based on the results of the
post-remedial-action data, which are confirmed by the verification assessment data, these radiological
measurements fall below the limits prescribed by DOE guidelines. It is concluded that the site
successfully meets the DOE remedial action objectives.
5
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of 226Ra in soil
above background levels,
averaged over a 100-m2
area
5 pCi/g averaged over the first 15 cm
of soil below the surface; 15 pCi/g
when averaged over 15-cm-thick soil
layers more than 15 cm below the
surface
Radionuclide con-
centrations in soil
for Hot Spot areas
Exposure to 222Rn
progeny
Maximum Permissible con-
centration of Ra226 in soil
above background level,
for areas less than 25 m2
Average annual radon
progeny concentration
(including background)
Ra226 concentrations, in any surface
or subsurface area less than 25 m2,
is below the guideline by a factor of
(lOO/A)'7', where A is the area of the
elevated region
0.03 WL
(US DOE 1990a)
6
Table 2. Results of ORNL analysis of the RAC soil samples from
1057 North Main Street, Monticello, Utah (MS01076-RS)
226Ra concentration (pCi/g)
ORNL RAC
sample sample Depth ORNL RAC
No.g No^ (cm}
XI NCH 077 >15 4.2 2.9
X2 NCH 078 >15 3.1 3.9
X3 NCH 079 >15 2.3 1.6
X4 NCH 080 >15 2.8 3.7
" An X-type sample is a split of the sample taken by the remedial action contractor.
* Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated areas were
taken by the RAC, and these samples were blended to form a composite soil sample, which
represents an average over one of the verification areas.
7
REFERENCES
MACTEC-ERS 1996. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS01076-RS, Address: 1057 North Main Street, Monticello, Utah 84535,
MACTEC-ERS, Grand Junction, Colorado, November 1996.
ORNL 1993. Environmental Technology Section (Formerly Pollutant Assessment Group)
Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National Laboratory, Grand
Junction, Colorado.
US DOE 1990a. Verification and Certification Protocol for the Office of Environmental
Restoration, Formerly Utilized Sites Remedial Action Programs and Decontamination and
Decommissioning Program. Revision 3, November 1990. U.S. Department of Energy, Washington,
D.C.
US DOE 1990b. Monticello Mill Tailings Site Declaration for the Record of Decision and Record
of Decision Summary. U.S. Department of Energy, Grand Junction Projects Office, Grand Junction,
Colorado.