DERR-1995-013760 - 0901a068805432dd

DOE ID No.: MS-00004-RS
Property Address: 32 Blue Mountain Drive
SCANNED
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 [ ] 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 the DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
[?] [ 1 [ 1
[y] [ ] [ 1
[Xl [ 1 [ 1
[» [ ] I 1
[ ] [ 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 gamma
exposure rates that do not exceed 30 percent above normal background.
llllllllll Ililllllllll
SFCERTIFED SFMS-00004
DOE ID No.: MS-00004-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 the concurrence of
the U.S. Nuclear Regulatory Commission because supplemental
standards were applied per 40 CFR 192.21.
/anda SyBusby Date
Manager, Monticello Programs
Rust Geotech
DOE EVALUATION
[>0 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.
Cerafication Official * Date
U.S. Department of Energy
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
DOE ID NO.: MS-00004-RS
ADDRESS: 32 BLUE MOUNTAIN DRIVE
MONTICELLO, UTAH 84535
FEBRUARY 1995
Prepared for
U.S. Department of Energy
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
Wanjefa 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.
i r
TABLE OF CONTENTS
Sectipn 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-00004-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 the EPA standards and the
DOE hot spot criteria by the DOE Inclusion Survey Contractor. The DOE
reviewed these evaluation results and determined that the property
contained mill tailings (residual radioactive material) exceeding the DOE
hot spot criteria. The Remedial Action Contractor was notified of the
inclusion of this property into the MVP Project and was authorized by the
DOE to conduct remedial action as required to bring the property into
conformance with the EPA standards and the 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-00004-RS
MS-00004-RS
Location No. M-389; all of Lot 3, Blue
Mountain Heights Subdivision, City of
Monticello, County of San Juan, State of
Utah
32 Blue Mountain Drive
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
August 30, 1991
Rust Geotech
Not applicable; streamlined remediation
procedures were followed
Mountain Region Corporation
117 29 3/4 Road
Grand Junction, Colorado
August 24, 1993
September 17, 1993
Interior: 0 cubic yards
Exterior: 2.1 cubic yards
8.4 square meters (m2)
February 1995
2
DOE ID No.: MS-00004-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 approximately 1.6 cubic yards of
contamination, ranging from 6 inches to 12 inches deep, within the
property. The remedial action process included the removal of
approximately 2.1 cubic yards of residual radioactive material, ranging
from 6 inches 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-00004-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 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).
Additionally, a soil sample was collected in an unremediated area
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 //R/h to 25 //R/h (Appendix
Figure 2.1). The result of analysis for radium-226 in one
composite soil sample was 1.0 picocuries per gram (pCi/g), as
indicated in Appendix Table 3.1. The soil sample result for
radium-226 in the unremediated area with elevated exposure rates
was 1.8 pCi/g (Appendix Table 3.2).
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 3.3. Appendix Figure 2.1 shows the measurement location
on the ground floor (the lowest habitable level of the structure).
4
DOE ID No.: MS-00004-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by the EPA standards (40 CFR 192.12, 192.20-23)
and the DOE hot spot criteria, as indicated in the Certification Data
Summary below.
Therefore, the property located at 32 Blue Mountain Drive, in
Monticello, Utah, is recommended for certification as required by the
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 10 //R/h to
12//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 backgroundf 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.
Soil sample result was
1.8 pCi/g.*
Soil sample result was
1.0 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-00004-RS
4.0 APPENDIX
Appendix Tables:
Table 3.1 Post-Excavation Sample/Measurement Results
Table 3.2 Radium Measurement Results for an Unremediated Area
with Elevated Gamma Exposure Rates
Table 3.3 Radon Decay-Product Concentration
Measurement Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
DAG:01-30-95
MS-00004.RS WP51
REV053193
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00004-RS
Address: 32 Blue Mountain Drive, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (//R/h) Ticket No. Method* (pCi/g)
V-l 13 - 18 NCD 661 OCS 1.0
See Appendix Figure 2.1 for the verification area.
*OCS = Opposed Crystal System
7
Table 3.2
Radium Measurement Results for an Unremediated Area
with Elevated Gamma Exposure Rates
DOE ID No.: MS-00004-RS
Address: 32 Blue Mountain Drive, Monticello, Utah
Meas.
Loc. Grid Meas. Depth Radium-226
Coord. Method* (inches) (pCi/g)
150265 OCS 00 - 06 1.8
*OCS = Opposed Crystal System
8
Table 3.3
Radon Decay-Product Concentration Measurement Results
DOE ID No.: MS-00004-RS
Address: 32 Blue Mountain Drive, Monticello, Utah
Instrument Type: Terradex Radtrak® Detector
Radon
Detector Tracks Per Concentration Working
Number Start Date End Date mm2 (pCi/L) Level
3839359 01-04-94 12-08-94
3839291 01-04-94 12-08-94
3853843 01-04-94 12-08-94
8.2 0.93 0.0047
8.0 0.91 0.0046
7.8 0.90 0.0045
Annual Average: 0.0046
See Appendix Figure 2.1 for the measurement location.
9
10 12
30
14 16 18 20 22 24 26 28 30 32 34 36 38 40
28
26
24
13-18
>2
17-25
METAL
SHED
12-14
22 -
ONE STORY
BRICK HOUSE
10-12
20 -
13-16
18
16
14 l_.
9 12XA
V-1
13-18
OD
13-16
rn
O
z
73
*
12
Y
10
10
20 10
X
I
12
SCALE IN FEET
0 20
I I I I
40 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.
14 1 6 18 20 22 24 26 28
®
rv.-.vj
12-15
12
V-1
16-17
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
POST-REMEDIAL ACTION RADON DECAY-PRODUCT
CONCENTRATION MEASUREMENT LOCATION
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
RESIDENCE-NO. Of OCCUPANTS
NON-RESIDENCE-WAN-HRS./WK.
INSTRUMENT NO.
SURVEY OATE
CK. A.E. APP. BY CK. A.C. APP.
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE, COLORADO
32 BLUE MOUNTAIN DRIVE
MONTICELLO, UTAH
GEOTECH INC
DATE APPROVAL DOE
OOEIDNO. MS-00004-RS
DWB.NO. 3-B00004-V1 SHT 1 „. 1
30 32 34 36 38 40
OAK RIDGE NATIONAL LABORATORY
MANAGED BY MARTIN MARIETTA ENERGY SYSTEMS. INC.
GRAND JUNCTION OFFICE
RO. BOX 2567
GRAND JUNCTION, COLORADO 81502
AUG 3 1 1995
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.
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
MS00004-RS
32 Blue Mountain Drive
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
32 BLUE MOUNTAIN DRIVE
MONTICELLO, UTAH MS00004-RS
M. K. Jensen
August 1995
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY SYSTEMS, INC.
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-84OR21400
CONTENTS
LIST OF TABLES v
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 32 Blue Mountain Drive,
Monticello, Utah (MS00004-RS) 5
v
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 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
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 1993, RUST
Geotech, the remedial action contractor designated by DOE, performed remedial action on
the vicinity property at 32 Blue Mountain 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 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 32 BLUE MOUNTAIN DRIVE
MONTICELLO, UTAH (MS00004-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 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-AC05-84OR21400 with Lockheed Martin Energy Systems, Inc.
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 32 Blue Mountain 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 1995).
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 32 Blue
Mountain 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 (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1995)
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 using streamlined remedial action procedures, based on a memo to the
folio dated, August 9, 1995.
The pre-remedial-action survey performed by Geotech identified 1.6 yd3 of mill
tailings 6 to 12 inches deep. However, during the actual removal process, a total of 2.1
yd3 of contaniinated earth and uranium mill tailings, 6 to 9 inches deep were removed from
a 8.4 m2 area.
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 ofthe structure, a surface scan of the exterior, and soil sampling. Samples
representative 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
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 12 ptR/h. Exterior surface gamma measurements taken from
the excavated areas prior to backfilling ranged from 13 to 18 fjR/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 shows a ^Ra concentration of 1.0 pCi/g. ORNL ETS
obtained this sample and performed a confirmatory analysis which showed a 226Ra
concentration 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
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 one year (from 1/4/94 to 12/8/94). 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 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 and resolved as discussed in a meeting between Geotech and ORNL
on March 22, 1995. 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
(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)
5
Table 2. Results of ORNL analysis of Geotech soil samples
from 32 Blue Mountain Drive, Monticello Utah (MS00004-RS)
226Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No." No.* (cm)
MS00004X1 NCD 661 >15 1.5 1.0
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 ofthe verification areas.
REFERENCES
Geotech 1995, Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00004-RS, Address: 32 Blue Mountain Drive, Monticello,
Utah 84535, Geotech, Grand Junction, Colorado, February 1995.
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.
ORNL, 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
DOE ID No.: MS-00024-RS
Property Address: 480 South First West 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 the DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
I ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
I 1 [ ]
[XI [ ] [ 1
[ 1 [XI U
[)(][] [ 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.
I1I1P1I11IH HIPlllllll
SFCERTIFED
SFMS-09005
DOE ID No.: MS-00024-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 the concurrence of
the U.S. Nuclear Regulatory Commission because supplemental
standards were applied per 40 CFR 192.21.
[/] 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
DOE EVALUATION
Date
U.S. Department of Energy
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00024-RS
ADDRESS: 480 SOUTH FIRST WEST STREET
MONTICELLO, UTAH 84535
APRIL 1995
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
DOE ID No.: MS-00024-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 the EPA standards and the
DOE hot spot criteria by the DOE Inclusion Survey Contractor. The DOE
reviewed these evaluation results and determined that the property
contained mill tailings (residual radioactive material) exceeding the EPA
standards. The Remedial Action Contractor was notified of the inclusion
of this property into the MVP Project and was authorized by the DOE to
conduct remedial action as required to bring the property into conformance
with the EPA standards and the DOE hot spot criteria.
1
DOE ID No.: MS-00024-RS
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
MS-00024-RS
Location No. M-23-C; beginning at the SE corner of Lot 1, Block 5, Monticello
Townsite Survey; north 89 degrees 21 minutes west 97 feet, north 00 degrees
42 minutes east 165 feet, south 89 degrees 21 minutes east 97 feet, south
00 degrees 42 minutes west 165 feet to the point of beginning, 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:
480 South First West Street
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
April 3, 1990
Rust Geotech
November 18, 1992
Sonderegger Inc.
P.O. Box 713
Monticello, Utah
June 10, 1993
June 22, 1993
Interior:
Exterior:
0 cubic yards
31 cubic yards
38 square meters (m2)
April 1995
2
DOE ID No.: MS-0O024-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 remedial action process included the removal of
approximately 31 cubic yards of residual radioactive material, 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-00024-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 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, 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 microroentgens per hour Gt/R/h)
to 25 /#R/h (Appendix Figure 2.1). The result of analysis for
radium-226 in one composite soil sample was 3.0 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 0.0050 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).
The partial basement was uninhabitable.
4
DOE ID No.: MS-00024-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by the EPA standards (40 CFR 192.12, 192.20-23)
and the DOE hot spot criteria, as indicated in the Certification Data
Summary below.
Therefore, the property located at 480 South First West Street, in
Monticello, Utah, is recommended for certification as required by the
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 //R/h to
13 //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 background1 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
3.0 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-00024-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:03-30-95
MS-00024.RS WP52
REV053193
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00024-RS
Address: 480 South First West Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range U/R/h) Ticket No. Method* (pCi/g)
V-l 15 - 25 NAW 069 OCS 3.0
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-00024-RS
Address: 480 South First West Street, Monticello, Utah
Instrument Type: Terradex Radtrak® Detector
Detector
Number Start Date End Date
Tracks Per
mm2
Radon
Concentration
(pCi/L)
Working
Level
3839381
3853906
3839332
01-04-94
01-04-94
01-04-94
12-08-94
12-08-94
12-08-94
6.9
7.3
12.3
0.78
0.83
1.40
0.0039
0.0042
0.0070
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
T
14 16
T
18 20 22 24 26 28 30 32 34 36 38 40 42 44 46 48 5
i—r
i
±
12-15
I
ONE STORY
FRAME HOUSE
W/UNINHABITABLE
PARTIAL BASEMENT
12-13
12-15
12-15
LU
S
3
o
24 v-i
15-25
-777-
URANIUM DRIVE
0
®
(V.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
POST-REMEDIAL ACTION RADON DECAY-PRODUCT
CONCENTRATION MEASUREMENT LOCATION
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
SCALE IN FEET
20 10 0
12
J L_
14
20
16
40 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.
J I L
18 20 22 24 26
_l L
28
Nm-KMMCff-UM-MS./m.
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE. COLO RAM
5! "480 SOUTH FIRST WEST STREET
MONTICELLO, UTAH
RUST «««~ MS-00024-RS
INC 3-C00024-V1
30 32 34 36 38 40 42 46 48 5C
OAK RIDGE NATIONAL LABORATORY GRAND JUNCTION OFFICE
TO BOX 2567
MANAGED BY MARTIN MARIETTA ENERGY SYSTEMS, INC. GRAND JUNCTION, COLORADO 81502
JUL 2 5 1985
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
MS00024-RS
480 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
480 SOUTH 1ST WEST STREET
MONTICELLO, UTAH (MS00024-RS)
M. K. Jensen
July 1995
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY SYSTEMS, INC.
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-84OR21400
CONTENTS
LIST OF TABLES v
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 480 South 1st West
Street, Monticello, Utah (MS00024-RS) 6
V
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, 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 1993,
RUST Geotech, the remedial action contractor designated by DOE, performed remedial
action on the vicinity property at 480 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. Procedures used by the
ETS are described in the Environmental Technology Section Procedures Manual
(ORNL 1993).
ix
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 480 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 1995).
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 480 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 (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1995)
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 5.9 yd3 of mill
tailings 6 inches deep. However, during the actual removal process, a total of 31 yd3 of
contaniinated earth and uranium mill tailings, 24 inches deep were removed from a 38 m2
area.
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 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 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 fiR/h. Exterior surface gamma measurements taken from
the excavated areas prior to backfilling ranged from 15 to 25 /jR/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 shows a ^Ra concentration of 3.0 pCi/g. ORNL ETS
obtained this sample and performed a confirmatory analysis which showed a 226Ra
concentration of 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). As
a result of a meeting between the RAC and the IVC on May 26, 1994, anomalous gamma
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 before
this procedure change. The IVC observed that 25 uR/h exceeds 30% of the excavation
average of 16 uR/h. The IVC will allow a correlation developed by the RAC to estimate
the 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 22SRa 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.
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 one year (from 1/4/94 to 12/8/94). The average annual working
level (WL) of radon progeny concentration, as determined by the Tech./Ops-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 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.
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
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
(1007A)*, where A is the
area of the elevated region
Exposure to 2"Rn Average annual radon proge- 0.03 WL
progeny ny concentration (including
background)
(DOE 1990a)
Table 2. Results of ORNL analysis of Geotech soil samples
from 480 South 1st West Street, Monticello Utah (MS00024-RS)
226Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No." No* (cm)
MS00024X1 NAW 069 >15 2.6 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.
7
REFERENCES
Geotech 1995, Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00024-RS, Address: 480 South First West Street, Monticello,
Utah 84535, Geotech, Grand Junction, Colorado, April 1995.
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.
ORNL, 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
DOE ID No.: MS-00034-RS
Property Address: 49 South First West Street
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geoterh 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 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 the DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
MM [ J
[*1 [ I [ 1
l*l [ ] [ ]
[X\ I ] [ )
[ ] W [ ]
MM [ 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.
SFCERTIFED SFMS-00034
DOE ID No.: MS-00034-RS
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
I ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Wanda S. Busby
Manager, fvlonticello 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 ' Date
U.S. Department of Energy
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
DOE ID NO.: MS-00034-RS
ADDRESS: 49 SOUTH FIRST WEST STREET
MONTICELLO, UTAH 84535
SEPTEMBER 1995
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
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-00034-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 the EPA standards and the
DOE hot spot criteria by the DOE Inclusion Survey Contractor. The DOE
reviewed these evaluation results and determined that the property
contained mill tailings (residual radioactive material) exceeding the EPA
standards and the DOE hot spot criteria. The Remedial Action Contractor
was notified of the inclusion of this property into the MVP Project and
was authorized by the DOE to conduct remedial action as required to bring
the property into conformance with the EPA standards and the DOE hot
spot criteria.
1
DOE ID No.: MS-00034-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-00034-RS
Location No. M-200; beginning 114.5 feet
south of the NE corner of Lot 13, Block 24,
Monticello Townsite Survey; west
214.5 feet, south 100 feet, east
214.5 feet, north 100 feet to beginning,
County of San Juan, State of Utah
49 South First West Street
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
June 19, 1990
Rust Geotech
Not applicable: streamlined remediation
procedures were followed
Not applicable: streamlined remediation
procedures were followed
August 18, 1992
August 27, 1992
Interior: 0 cubic yards
Exterior: 2.2 cubic yards
10.0 square meters (m2)
September 1995
2
DOE ID No.: MS-00034-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 approximately 1.3 cubic yards of
contamination, 6 inches deep, within the property. The remedial action
process included the removal of approximately 2.2 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-00034-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 December 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, individual soil samples representative
of the 6-inch-thick soil layer at the bottom of the excavation were
collected (Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 11 to 16 microroentgens per
hour (//R/h), as indicated on Appendix Figure 2.1. The results of
analyses for radium-226 in four individual soil samples ranged from
1.6 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 measurements representing an annual average, the RDC
was 0.0028 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-00034-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by the EPA standards (40 CFR 192.12, 192.20-23)
and the DOE hot spot criteria, as indicated in the Certification Data
Summary below.
Therefore, the property located at 49 South First West Street, in
Monticello, Utah, is recommended for certification as required by the
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 11 to 13 //R/h.
Annual average was
0.0028 WL.
< 5 pCi/g above
background.**
Soil sample results
ranged from 1.6 to
4.1 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-00034-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:08-21-95
MS-00034.RS WP61
REV053193
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00034-RS
Address: 49 South First West Street, Monticello, Utah
Exposure Soil Sample Meas. Radium-226
Area Rate (jjR/h) Identifier Method" (pCi/g)
V-1 16 Deposit A OCS 4.1
V-2 16 Deposit B OCS 1.6
V-3 16 Deposit C OCS 2.3
V-4 16 Deposit D OCS 2.7
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-00034-RS
Address: 49 South First West Street, Monticello, Utah
Instrument Type: Terradex Radtrak Detector
Radon
Detector Tracks Per Concentration Working
Number Start Date End Date mm2 (pCi/L) Level
3892134 06-13-94 06-05-95
3892198 06-13-94 06-05-95
3892278 06-13-94 06-05-95
4.6 0.50 0.0025
4.9 0.53 0.0027
6.0 0.65 0.0033
Annual Average: 0.0028
See Appendix Figure 2.1 for the measurement location.
8
12
i—r
14 16 20 22 24 26 28 30
"T~
32 34 36 38 40
i—r
42 46 48
i—r
50
42
40
38
36
mi®©-©
LJ
CE
3
O
Ll
r .v.v.\
6 I 6 X C
12-15 6 A D V-3 V-4
I6uR/h 16M"/fi
V-l
16^R/h
SHED
11-713
TRAILER HOUSE
W/ADDITION
11-13 • V-2
16uR/h
RDC
12-15 ji SHED
11-13 12-15
EH
V-l
16-17
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN fiR/r,
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
POST-REMEDIAL ACTION RAOON DECAY-PRODUCT
CONCENTRATION MEASUREMENT LOCATION
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
34
32
30
28
26
24
22
20
18
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
L
SCALE IN FEET
20 10 0 20 40
U:\FAS\033\0003\ftv00034V 00/26/83 i:4epm T307B0
ft
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.
12 14 16 18 20 22
J L
24 26
J L_
28
U.S. DEPARTMENT OF ENERGY
C4AM0 JUMCTtQM MOJICrt CrTrtCE. COtCHUOO
Si 49 SOUTH FIRST WEST ST.
MONTICELLO. UTAH
j un limAsmt p
|»^pfpp Rust Osotoch MS-000J4-RS
30 32 34 36 38 40 42 44 46
3-C00034-V1 r 1 |
48 50
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 F-& 2 3 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 verifica-
tion 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:
MS00034
49 South 1st West 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
49 SOUTH 1ST WEST STREET
MONTICELLO, UTAH (MS00034-RS)
N. F. Lewis
February 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
LIST OF TABLES
Applicable guidelines for protection against radiation
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 M. K. Jensen for technical reviews.
vii
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 49 SOUTH 1ST WEST STREET
MONTICELLO, UTAH (MS00034-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 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 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 49 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 1995).
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 49 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 (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1995)
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 1.3 yd3 of mill tail-
ings 6 inches deep. However, during the actual removal process, a total of 2.2 yd3 of
contaminated earth and uranium mill tailings, 6 to 12 inches deep were removed from a
10 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 ofthe structure, a surface scan of the exterior, and soil sampling. Individual
samples representative of the bottom 15-cm (6-in.) soil layers of 4 excavated verification
areas were collected. The RAC is unable to locate or has 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 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 11 to 13 uR/h. Exterior surface gamma measurements taken from
the excavated areas prior to backfilling were 16 uR/h.
Soil Sample Analysis
Prior to backfilling, Geotech collected individual soil samples representative of the
excavated areas from the bottom 15-cm (6-in.) soil layers. These samples are representa-
tive ofthe 4 exterior verification areas. Geotech's analysis of these samples showed 226Ra
concentrations ranging from 1.6 to 4.1 pCi/g. ORNL ETS was unable to obtain samples
for confirmatory analysis. 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 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 detectors on the ground floor of the residence located on this property for a
period of approximately one year (from 06/13/94 to 06/05/95). The average annual
working level (WL) of radon progeny concentration, as determined by the Tech./Ops-
Landauer Corporation, was 0.0028, 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
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 nr, is below the
guideline by a factor of
(1007A)14, 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
REFERENCES
Geotech 1995. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00034-RS, Address: 49 South First West Street, Monticello,
Utah 84535, Geotech, Grand Junction, Colorado, September 1995.
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.
ORNL, 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
DOE ID No.: MS-00044-RS
Property Address: 364 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 < 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 the DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
YES NO NOT TAKEN
LX] [ ] [ 1
[X] [ ] [ ] [X] [ ]
[ ] [ 1 [X] [ ] [ ]
(Trailer Houses Removed)
[ ] [ ] [X] [ ] [ ]
(Trailer Houses Removed)
[ ] [X] [ 1 [ ] [y]
[ ]
[vi
[y]
[ 1
[X] [ ] [ ] I*] 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.
Illlllll
SFCERTIFED •111 SFMS-09007
}
DOE ID No.: MS-00044-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 the concurrence of
the U.S. Nuclear Regulatory Commission because supplemental
standards were applied per 40 CFR 192.21.
[¥\ 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
Date
U.S. Department of Energy
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00044-RS
ADDRESS: 364 SOUTH MAIN STREET
MONTICELLO, UTAH 84535
JUNE 1995
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
Wan0a 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-00044-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 the EPA standards and the
DOE hot spot criteria by the DOE Inclusion Survey Contractor. The DOE
reviewed these evaluation results and determined that the property
contained mill tailings (residual radioactive material) exceeding the EPA
standards and the DOE hot spot criteria. The Remedial Action Contractor
was notified of the inclusion of this property into the MVP Project and was
authorized by the DOE to conduct remedial action as required to bring the
property into conformance with the EPA standards and the DOE hot spot
criteria.
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-00044-RS
MS-00044-RS
Location No. M-44; Lot 4, Block 7,
Monticello Townsite Survey, beginning at a
point 107.25 feet south of the NE corner of
Lot 4, west 107.25 feet, north
107.25 feet, west 107.25 feet, south
214.5 feet, east 214.5 feet, north
107.25 feet to point of beginning, County
of San Juan, State of Utah
364 South Main Street
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
January 31, 1991
Rust Geotech
May 26, 1992
DLB Unlimited Inc.
P.O. Box 740
Dove Creek, Colorado
September 16, 1992
October 7, 1992
Interior: 0 cubic yards
Exterior: 38 cubic yards
100 square meters (m2)
June 1995
2
DOE ID No.: MS-00044-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 remedial action process included the removal of
approximately 38 cubic yards of residual radioactive material, ranging from
8 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
3.0 VERIFICATION SUMMARY
DOE ID No.: MS-00044-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 1991, as described in the final REA
dated 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 a composite
sample representing the verification areas (Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 11 to 25 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
5.8 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 houses because
they were removed prior to placement of RDC detectors; therefore,
the trailer houses were verified according to exterior standards.
4
1 '
DOE ID No.: MS-00044-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by the EPA standards (40 CFR 192.12, 192.20-23)
and the DOE hot spot criteria, as indicated in the Certification Data
Summary below.
Therefore, the property located at 364 South Main Street, in Monticello,
Utah, is recommended for certification as required by the 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: trailer
houses removed.
Not applicable: trailer
houses removed.
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
5.8 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-00044-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
DAG:04-27-95
MS-00044.RS WP52
REV053193
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00044-RS
Address: 364 South Main Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range U/R/h) Ticket No. Method' (pCi/g)
V-l 13 - 25 NAX 733 OCS 5.8
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 14 16
~i—i—r
18 20 22 24
~T—i 1—r
26 28 30 32 34 36 38
i—T
40 42 44 46 48 5'
ii r
WEST THIRD SOUTH STREET
n
V-1
13-25
TRAILER.. J
HOUSE"*"!
11-14
I 1
HED*"!
11-14
L.
L
12-15
TRAILER..
HOUSE
12-13 1
13-25
12-15
| SHED*" I
I 1114 I
I L
J L
o
©
<D
iv.-.vj
12-15
12
v-i
16-17
<
2
3
O
to
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN itR/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
STRUCTURES WERE REMOVED AFTER REMEDIAL
ACTION
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
L
SCALE IN FEET
20 10 0 20 40
U:\FA5\033\0003\RU00044V 06/01/95 09:57om TS0780
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 14 16 18 20 22
_l L
24
RCMCKCC-M. OT U.S. DEPARTMENT OF ENERGY
GRANO JUNCTION PROJECTS OFFICE. COLORADO
-rag
364 SOUTH MAIN STREET
MONTICELLO, UTAH
MS-00044-RS
3-C00044-V1 ,
26 28 30 32 34 36 38 40 42 44 46 48 50
OAK RIDGE NATIONAL LABORATORY
MANAGED BY MARTIN MARIETTA ENERGY SYSTEMS, INC.
GRAND JUNCTION OFFICE
RO. BOX 2567
GRAND JUNCTION. COLORADO 81502
JUL 2 5 1995
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 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: MS00044-RS
Location Address: 364 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
364 SOUTH MAIN STREET
MONTICELLO, UTAH (MS00044-RS)
M. K. Jensen
July 1995
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY SYSTEMS, INC.
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-84OR21400
CONTENTS
LIST OF TABLES v
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 T. . 4
2 Results of ORNL analysis of Geotech soil samples from 364 South Main Street,
Monticello, Utah (MS00044-RS) 5
v
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, 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 364 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
RESULTS OF THE INDEPENDENT VERD7ICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 364 SOUTH MAIN STREET
MONTICELLO, UTAH (MS00044-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 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
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).
*Thc 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-AC05-84OR21400 with Lockheed Martin Energy Systems, Inc.
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, several private residences located at 364 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
1995).
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 364 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 (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1995)
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 16 yd3 of mill tailings
6 inches deep. However, during the actual removal process, a total of 38 yd3 of
contaminated earth and uranium mill tailings, 8 to 12 inches deep were removed from a
100 m2 area.
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 of the structures, a surface scan 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.
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 Trailer
#1 ranged from 11-14 uR/h and 12-13 yuR/h in Trailer #2. Exterior surface gamma
measurements taken from the excavated areas prior to backfilling ranged from 13 to 25
fiR/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 5.8 pCi/g. ORNL ETS
obtained this sample and performed a confirmatory analysis which showed a 226Ra
concentration of 8.4 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).
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 all of the structures were removed from the property after 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.
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)*, 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 364 South Main Street, Monticeiio, Utah (MS00044-RS)
^Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No." No^ (cm)
MS00044X1 NAX 733 >15 8.4 5.8
" 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 1995, Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00044-RS, Address: 364 South Main Street, Monticello, Utah
84535, Geotech, Grand Junction, Colorado, June 1995.
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.
ORNL, 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
DOE ID No.: MS-00045-RS
Property Address: 80 West Fourth South Street
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech of Enerc-v (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 the DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[ 1 [ ] [X]
(Trailer House
Removed)
[ ] [ ] [X]
(Trailer House
Removed)
[ ] [X] [ 1
YES NO NOT TAKEN
[*] [ 1 [ 1
[X] [ ]
[ ] [ ]
[ ] [ ]
[ 1 [Xl
[ 1
[y]
[ 1
[X] [ ] [ ] [Y] [ ] 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.
illllilllV - I1IH111IIII
SFCERTIFED SFMS-09007
DOE ID No.: MS-00045-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 the concurrence of
the U.S. Nuclear Regulatory Commission because supplemental
standards were applied per 40 CFR 192.21.
[/] 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
DOE EVALUATION
Date
U.S. Department of Energy
PROPERTY COMPLETION REPORT
DOE ID NO.: MS-00045-RS
ADDRESS: 80 WEST FOURTH SOUTH STREET
MONTICELLO, UTAH 84535
JULY 1995
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 Paoe
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-00045-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 the EPA standards and the
DOE hot spot criteria by the DOE Inclusion Survey Contractor. The DOE
reviewed these evaluation results and determined that the property
contained mill tailings (residual radioactive material) exceeding the EPA
standards and the DOE hot spot criteria. The Remedial Action Contractor
was notified of the inclusion of this property into the MVP Project and was
authorized by the DOE to conduct remedial action as required to bring the
property into conformance with the EPA standards and the DOE hot spot
criteria.
1
DOE ID No.: MS-00045-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-00045-RS
Location No. M-39-1; beginning at a point
8 feet west of SE corner of Lot 2, Block 7,
Monticello Townsite Survey, north
144.5 feet, east 8 feet, north 70 feet to the
NE corner of Lot 2, west 88 feet, south
214.5 feet, east 80 feet to point of
beginning, County of San Juan, State of
Utah
80 West Fourth South Street
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
January 23, 1991
Rust Geotech
May 26, 1992
DLB Unlimited Inc.
P.O. Box 740
Dove Creek, Colorado
September 16, 1992
September 29, 1992
Interior: 0 cubic yards
Exterior: 7 cubic yards
26 square meters (m2)
July 1995
2
2.0 OPERATIONS SUMMARY
DOE ID No.: MS-00045-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 contamination, 6 inches deep,
within the property. The remedial action process included the removal of
approximately 7 cubic yards of residual radioactive material, 8 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-00045-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 October 1991, as described in the final REA
dated 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 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 20 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
3.7 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 because it
was removed prior to placement of RDC detectors.
4
DOE ID No.: MS-00045-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by the EPA standards (40 CFR 192.12, 192.20-23)
and the DOE hot spot criteria, as indicated in the Certification Data
Summary below.
Therefore, the property located at 80 West Fourth South Street, in
Monticello, Utah, is recommended for certification as required by the
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: trailer
house removed.
Not applicable: trailer
house removed.
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.1
Soil sample result was
3.7 pCi/g.f
*The background radium-226 concentration is approximately 2.0 pCi/g.
fThe hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-00045-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
DAG:04-26-95
MS-00045.RS WP52
REV053193
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00045-RS
Address: 80 West Fourth South Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (//R/h) Ticket No. Method" (pCi/g)
V-l 15-20 NAW 403 OCS 3.7
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 14 16 18 20 22 24 26 28 30 32 34 36 38 40 42 44 46 48 5
SHED
ADDRESSED
UNDER
MS-00232-RS
SHED
ADDRESSED
UNDER
MS-00233-RS
=r
12-15
' SHED
12-14
0
12-15
IS
oo .
J TRAILER
-I HOUSE
J WITH
I ADDITION"*-*"
12-14
w_.—•
— L
0
<D
iv.-.vj
12-15
12
v-1
16-17
-X-*
8 K6XC V-1
15-20
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
ASSESSED AREA B (METAL PIPES) WAS REMOVED
TRAILER HOUSE WAS REMOVED PRIOR TO PLACEMENT
OF RDC DETECTORS
SCALE IN FEET
12
20 10 0
14
"777 777-
WEST FOURTH SOUTH STREET
20 40 NORTH
16 18 20 22 24
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
J I I
WWDOtCC-NO. OF OCCUMHTS
MM-miorjKC-«M-HM./m.
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE, COLORADO
80 WEST FOURTH SOUTH ST.
MONTICELLO, UTAH
I kit |«MMLBU
MS-00045-RS
nc w 3-C00045-V1 ,
26 28 30 32 34 36 38 40 42 44 46 48 50
OAK RIDGE NATIONAL LABORATORY
MANAGED BY MARTIN MARIETTA ENERGY SYSTEMS, INC.
GRAND JUNCTION OFFICE
RO. BOX 2567
GRAND JUNCTION. COLORADO 81502
Awn 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.
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:
Property Owner:
Owner Address:
Tenant Name:
MS00045-RS
80 West 4th South 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
80 WEST 4TH SOUTH STREET
MONTICELLO, UTAH (MS00045-RS)
N. F. Lewis
August 1995
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY SYSTEMS, INC.
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-84OR21400
CONTENTS
LIST OF TABLES v
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 80 West 4th South Street,
Monticello, Utah (MS00045-RS) 5
v
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 D. S. List for analysis of soil samples and A. R. Jones 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
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 1992, RUST
Geotech, the remedial action contractor designated by DOE, performed remedial action on
the vicinity property at 80 West 4th 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 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 WEST 4TH SOUTH STREET
MONTICELLO, UTAH (MS00045-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
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 ofthe Environmental Assessment Group in the
Environmental Technology Section of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE contract
DE-AC05-84OR21400 with Lockheed Martin Energy Systems, Inc.
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 80 West 4th 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 1995).
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 West 4th
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 (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1995)
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 mill tailings 6 inches
deep. During the actual removal process, a total of 7 yd3 of contaminated earth and
uranium mill tailings, 8 inches deep were removed from a 26 m2 area.
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 of the structure, a surface scan 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
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 12 to 14 /iR/h. Exterior surface gamma measurements taken from
the excavated area prior to backfilling ranged from 15 to 20 jjR/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 shows a ^Ra concentration of 3.7 pCi/g. ORNL ETS
obtained this sample and performed a confirmatory analysis which showed a ^Ra
concentration of 2.5 pCi/g. 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 before this procedure change. The IVC observed that area VI exceeds 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 anomalous
reading of 20 uR/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. 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
in the trailer house because it was removed prior to placement of RDC detectors.
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 2. Results of ORNL analysis of Geotech soil samples
from 80 WEST 4TH SOUTH STREET, Monticello Utah (MS00045-RS)
^Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No." No/; (cm)
XI NAW 403 >15 2.5 3.7
" 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.
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 pCVg 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)14, where A is the
area of the elevated region.
Average annual radon proge- 0.03 WL
ny concentration (including
background).
(DOE 1990a)
Exposure to Rn
progeny
REFERENCES
Geotech 1995, Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00045-RS, Address: 80 West 4th South Street, Monticello,
Utah 84535, Geotech, Grand Junction, Colorado, July 1995.
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.
ORNL, 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
DOE ID No.: MS-00064-RS
Property Address: 333 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 [ ] 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 the DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
IX] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ 1 [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
[Xl [ 1 [ 1
m [ 1 [ 1
M t ] [ 1
[V] [ ] I ]
[Yl [ 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.
llllllllll llllllllll
SFCERTIFED SFMS-00064
DOE ID No.: MS-00064-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 the concurrence of
the U.S. Nuclear Regulatory Commission because supplemental
standards were applied per 40 CFR 192.21.
[xT] 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
Date
U.S. Department of Energy
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00064-RS
ADDRESS: 333 SOUTH MAIN STREET
MONTICELLO, UTAH 84535
FEBRUARY 1995
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
3.1.3 Radon Decay-Product Concentration (RDC) Measurement .... 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
i
DOE ID No.: MS-00064-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 the EPA standards and the
DOE hot spot criteria by the DOE Remedial Action Contractor. The DOE
reviewed these evaluation results and determined that the property
contained mill tailings (residual radioactive material) exceeding the DOE
hot spot criteria. The Remedial Action Contractor was notified of the
inclusion of this property into the MVP Project and was authorized by the
DOE to conduct remedial action as required to bring the property into
conformance with the EPA standards and the DOE hot spot criteria.
1
DOE ID No.: MS-00064-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-00064-RS
Location No. M-51; south 1/3 of Lot 3,
Block 8, Plat A, Monticello Townsite
Survey, County of San Juan, State of Utah
333 South Main Street
Monticello, Utah 84535

Residential Simple (RS)
Not applicable: inclusion requested by the
Remedial Action Contractor
December 7, 1992
Rust Geotech
Not applicable: streamlined remediation
procedures were followed
Mountain Region Corporation
117 29 3/4 Road
Grand Junction, Colorado
November 11, 1993
November 19, 1993
Interior: 0 cubic yards
Exterior: 0.4 cubic yards
1.9 square meters (m2)
February 1995
2
DOE ID No.: MS-00064-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, 6 inches deep,
within the property. The remedial action process included the removal of
approximately 0.4 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
3.0 VERIFICATION SUMMARY
DOE ID No.: MS-00064-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 April 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, individual soil samples representative
of the 6-inch-thick soil layer at the bottom of the excavation were
collected for the verification areas (Appendix Figure 2.1).
Additionally, a soil sample was collected in an unremediated area
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 //R/h to 19 //R/h (Appendix
Figure 2.1). The results of analyses for radium-226 in two
individual soil samples were 1.7 picocuries per gram (pCi/g) and
4.9 pCi/g (Appendix Table 3.1). The soil sample result for
radium-226 in the unremediated area with elevated exposure rates
was 3.6 pCi/g (Appendix Table 3.2).
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on measurements representing an annual average, the RDC
was 0.0032 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).
4
DOE ID No.: MS-00064-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by the EPA standards (40 CFR 192.12, 192.20-23)
and the DOE hot spot criteria, as indicated in the Certification Data
Summary below.
Therefore, the property located at 333 South Main Street, in Monticello,
Utah, is recommended for certification as required by the 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 //R/h to
13//R/h.
Annual average was
0.0032 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 background1 in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
Soil sample result was
3.6 pCi/g.*
Soil sample results were
1.7 pCi/g and 4.9 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-00064-RS
4.0 APPENDIX
Appendix Tables:
Table 3.1 Post-Excavation Sample/Measurement Results
Table 3.2 Radium Measurement Results for an Unremediated Area
with Elevated Gamma Exposure Rates
Table 3.3 Radon Decay-Product Concentration
Measurement Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
DAG:01-25-95
MS-00064.RS WP51
REV053193
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00064-RS
Address: 333 South Main Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (/yR/h) Ticket No. Method* (pCi/g)
V-l 16 - 17 NAO 939 OCS 4.9
V-2 13 - 15 NAO 928 OCS 1.7
See Appendix Figure 2.1 for the verification areas.
*OCS = Opposed Crystal System
7
Table 3.2
Radium Measurement Results for an Unremediated Area
with Elevated Gamma Exposure Rates
DOE ID No.: MS-00064-RS
Address: 333 South Main Street, Monticello, Utah
Meas.
Loc. Grid Meas. Depth Radium-226
Coord. Method* (inches) (pCi/g)
181195 OCS 00 - 06 3.6
*OCS = Opposed Crystal System
8
Table 3.3
Radon Decay-Product Concentration Measurement Results
DOE ID No.: MS-00064-RS
Address: 333 South Main Street, Monticello, Utah
Instrument Type: Terradex Radtrak® Detector
Radon
Detector Tracks Per Concentration Working
Number Start Date End Date mm2 (pCi/L) Level
3854001 01-04-94 12-08-94
3839370 01-04-94 12-08-94
3853827 01-04-94 12-08-94
5.6 0.64 0.0032
6.3 0.71 0.0036
4.9 0.56 0.0028
Annual Average: 0.0032
See Appendix Figure 2.1 for the measurement location.
9
10
30
12 1 4 16 18 20 22 24 26 28
1 T
30 32 34 36 38 40
28
26
24
22
20
18
1 6
1 4
12 -
cr
I—
CO
<
X
o
CO
©
<D
iTv.vl
12-15
12
v-1
16-17
(RDC)
10
r o
SHED
12-13
0 ONE STORY
FRAME HOUSE
12-13
RDC
13-17
•D o
3-7
o 17-19
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
POST-REMEDIAL ACTION RADON DECAY-PRODUCT
CONCENTRATION MEASUREMENT LOCATION
20 10
NORTH
SCALE IN FEET
20
I
V-2
13-15
V-1
16-17
- 26
- 24
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
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.
RESIDENCE-NO. OF OCCUPANTS
NON-RESIDENCE-UAN-HRS./«K.
INSTRUMENT NO.
SURVEY OATC
BY CK. A.C. APP. NO. DATE BV CK. A.E. APP.
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE, COLORADO
3$s 333 SOUTH MAIN STREET
MONTICELLO, UTAH
GBOIBCH INC
DATE I APPROVAL bAt
DOEIDNO. MS-00064-RS
OWO.NO. 3-B0QQ64-V1 M1M1
10 12 1 4 16 18 20 22 24 26 28 30 32 34 36 38 40
OAK RIDGE NATIONAL LABORATORY
MANAGED BY MARTIN MARIETTA ENERGY SYSTEMS, INC.
GRAND JUNCTION OFFICE
RO. 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, 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
MS00064-RS
333 South Main Street
Monticello. Utah 84535
Leroy and Pricilla Romero

Same
ApR 2 7 1895
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
333 SOUTH MAIN STREET
MONTICELLO, UTAH MS00064-RS
M. K. Jensen
April 1995
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
MARTIN MARIETTA ENERGY SYSTEMS, INC.
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-84OR21400
CONTENTS
LIST OF TABLES v
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
vii
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 G. A. Pierce for technical reviews.
viii
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 1993, RUST
Geotech, the remedial action contractor designated by DOE, performed remedial action on
the vicinity property at 333 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
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 333 SOUTH MAIN STREET
MONTICELLO, UTAH (MS00064-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 of the
Monticello Vicinity Properties (MVP) Project (Abramiuk 1989).
*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-AC05-84OR21400 with Martin Marietta Energy Systems, Inc.
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 333 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 1995).
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 333 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 (DOE 1990).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1995)
indicates the property was remediated as evaluated by DOE on the basis of Environmental
Protection Agency standards and the DOE guidelines (DOE 1990). 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 mill tailings 6 inches
deep. During the actual removal process, a total of 0.4 yd3 of contaminated earth and
uranium mill tailings, 6 inches deep were removed from a 1.9 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 structures and a suface 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. A sample was also taken in an unremediated area with slightly elevated
gamma readings to show compliance with DOE guidelines.
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 12 to 13 //R/h. Exterior surface gamma measurements taken from
the excavated areas prior to backfilling ranged from 13 to 17 yuR/h.
Soil Sample Analysis
Prior to backfilling, Geotech collected individual soil samples representative of the
excavated areas from the bottom 15-cm (6-in.) soil layers. Geotech's analysis of these
samples showed ^Ra concentrations ranging from 1.7 to 4.9 pCi/g. ORNL ETS was
unable to obtain samples for confirmatory analysis. These values are below the EPA
standard value of 15 pCi/g for soil layers >15 cm below the surface. A surface (0-15 cm)
soil sample, collected from an area with gamma reading >30% of background, was also
analyzed with a ^Ra of 3.6 pCi/g. This value is below the EPA standard value of 5 pCi/g
for surface soil layers 0-15 cm. 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 detectors on the ground floor of the residence located on this property for a
period of approximately one year (from 1/4/94 to 12/8/94). The average annual working
level (WL) of radon progeny concentration, as determined by the TechVOps-Landauer
Corporation was 0.0032, 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
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 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
Radionuclide
concentrations in soil
for Hot Spot areas
Maximum Permissible
concentration of Ra226 in soil
above background level, for
areas less than 25 m2.
Ra concentrations, m any
surface or subsurface area
less than 25 m2, is below the
guideline by a factor of
(100/A)H, where A is the
area of the elevated region.
Average annual radon proge- 0.03 WL
ny concentration (including
background)
(DOE 1990)
Exposure to 222Rn
progeny
5
REFERENCES
Abramiuk I. N.et al. 1989. Monticello Remedial Action Project Site Analysis Report, GJ-
10, prepared by Bendix Field Engineering Corporation, Grand Junction, Colorado, for the
U.S. Department of Energy, Surplus Facilities Management Program, Richland,
Washington.
Geotech 1995, Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00064-RS, Address: 333 South Main Street, Monticello, Utah
84535, Geotech, Grand Junction, Colorado, February 1995.
U.S. DOE 1990. 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.
ORNL, 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
DOE ID No.: MS-00106-RS
Property Address: 332 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 [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 the DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
[Vi [ ] [ ]
[X] I 1 [ 1
MM I ]
W [ 1 [ 1
[ ] [V] [ ]
M [ 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.
llllllill lIHllll
SFCERTIFED SFMS-09030
DOE ID No.: MS-00106-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 the concurrence of
the U.S. Nuclear Regulatory Commission because supplemental
standards were applied per 40 CFR 192.21.
[/] 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
DOE EVALUATION
Date
U.S. Department of Energy
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
DOE ID NO.: MS-00106-RS
ADDRESS: 332 EAST CENTER STREET
MONTICELLO, UTAH 84535
APRIL 1995
Prepared for
U.S. Department of Energy
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
' VVanid/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-00106-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 the EPA standards and the
DOE hot spot criteria by the DOE Inclusion Survey Contractor. The DOE
reviewed these evaluation results and determined that the property
contained mill tailings (residual radioactive material) exceeding the EPA
standards. The Remedial Action Contractor was notified of the inclusion
of this property into the MVP Project and was authorized by the DOE to
conduct remedial action as required to bring the property into conformance
with the EPA standards and the DOE hot spot criteria.
1
DOE ID No.: MS-00106-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-00106-RS
Location No. M-229-1; beginning 27 feet
south of the NE corner of Block E,
Monticello Townsite Survey; south
105 feet, west 60 feet, north to a point
south 87 degrees 17 minutes west 60 feet
from the point of beginning, north
87 degrees 17 minutes east 60 feet to the
point of beginning, County of San Juan,
State of Utah
332 East Center Street
Monticello, Utah 84535

Monticello, Utah 84535
Residential Simple (RS)
Oak Ridge National Laboratory
June 19, 1990
Rust Geotech
July 27, 1992
Crowley Construction, Inc.
East Route HC 63 Box 66
Monticello, Utah
June 2, 1993
July 22, 1993
Interior: 0 cubic yards
Exterior: 26 cubic yards
95 square meters (m2)
April 1995
2
2.0 OPERATIONS SUMMARY
DOE ID No.: MS-00106-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 contamination, ranging from
6 inches to 9 inches deep, within the property. The remedial action
process included the removal of approximately 26 cubic yards of residual
radioactive material, ranging from 6 inches 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
1
DOE ID No.: MS-00106-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 1991, as described in the final REA dated
July 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 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 microroentgens per hour (j/R/h)
to 23 //R/h (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. The
composite sample representing Area V-1 included soil removed
from MS-00247-RS (Area V-2).
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on measurements representing an annual average, the RDC
was 0.0036 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-00106-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by the EPA standards (40 CFR 192.12, 192.20-23)
and the DOE hot spot criteria, as indicated in the Certification Data
Summary below.
Therefore, the property located at 332 East Center Street, in Monticello,
Utah, is recommended for certification as required by the 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 //R/h to
13 //R/h.
Annual average was
0.0036 WL.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above backgroundT 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
3.2 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-00106-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
DAG :03-14-95
MS-00106.RS WP52
REV053193
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00106-RS
Address: 332 East Center Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range U/R/h) Ticket No. Method* (pCi/g)
V-l 13 - 23 NAW 445 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-00106-RS
Address: 332 East Center Street, Monticello, Utah
Instrument Type: Terradex Radtrak® Detector
Radon
Detector Tracks Per Concentration Working
Number Start Date End Date mm2 (pCi/L) Level
3853810 01-04-94 12-08-94
3839353 01-04-94 12-08-94
3839299 01-04-94 12-08-94
7.7 0.88 0.0044
5.2 0.59 0.0030
5.9 0.67 0.0034
Annual Average: 0.0036
See Appendix Figure 2.1 for the measurement location.
8
0
30
28
12 14 16 8 20 22 24 26 28 30 32 34 36 38 40
26
24
22
20 -
18 -
1 6
14
12
Y
10
Ld
Ld cr
I—
CO
cr
Ld
o
I—
CO
<
Ld
20 10
V-1
13-23
12-16
V-1
13-23
CT
A X 6 10
SCALE IN FEET
0 20 40
ONE
STORY
FRAME
HOUSE
v-1
13-23
RDC
12-16
...J
r- THIS DRAWING IS FOR THE SOLE USE OF THE U.S. DEPARTMENT
CT OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
O PLAT. UTILITY LOCATION PLAT, OR OTHER IMPROVEMENT SURVEY
2 PLAT AND IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE, BUILDING, OR OTHER FUTURE IMPROVEMENT LINES.
©
<D
rv.-.vi
LV.-.vj
12-15
12
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
POST-REMEDIAL ACTION RADON DECAY-PRODUCT
CONCENTRATION MEASUREMENT LOCATION
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
- 26
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
ncsn>cNce-No. or OCCUPANTS
NON-RESIDENCE-MAN-HRS./WK.
INSTRUMENT NO.
CK. A.E. APP. NO. DATE CK. A.E. APP.
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE, COLORADO
332 EAST CENTER STREET
MONTICELLO, UTAH
APPROVAL
GEOTECH INC
APPROVAL DOE TSATE-
DOEIONO. MS-00106-RS
MKi.NO. 3-B00106-V1 SHT, 1 „ 1
10 12 14 1 6 18 20 22 24 26 28 30 32 34 36 38 40
OAK RIDGE NATIONAL LABORATORY
MANAGED BY MARTIN MARIETTA ENERGY SYSTEMS, INC.
GRAND JUNCTION OFFICE
RO. BOX 2567
GRAND JUNCTION, COLORADO 81502
JUL 2 S 1995
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, 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, 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: MS00106-RS
Location Address: 332 East 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 VERD7ICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
332 EAST CENTER STREET
MONTICELLO, UTAH (MS00106-RS)
M. K. Jensen
July 1995
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY SYSTEMS, INC.
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-84OR21400
CONTENTS
LIST OF TABLES v
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 332 East Center Street,
Monticello, Utah (MS00106-RS) 6
v
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 and N. F. Lewis 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 remedial actions on off-site (vicinity) properties that had been
contaminated by radioactive material resulting from mill operations. During 1993,
RUST Geotech, the remedial action contractor designated by DOE, performed remedial
action on the vicinity property at 332 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 332 EAST CENTER STREET
MONTICELLO, UTAH (MS00106-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
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-AC05-84OR21400 with Lockheed Martin Energy Systems, Inc.
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 332 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 1995).
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 332 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
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 1995)
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 mill tailings 6 to 9
inches deep. During the actual removal process, a total of 26 yd3 of contaminated earth
and uranium mill tailings, 6 to 10 inches deep were removed from a 95 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 and a surface scan ofthe exterior and soil sampling. Soil
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.
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
house 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, 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 of the exterior verification area.
Geotech's analysis of this sample shows a ^Ra concentration of 3.2 pCi/g. ORNL ETS
obtained this sample and performed a confirmatory analysis which showed a ^Ra
concentration of 2.6 pCi/g. 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
the IVC on May 26, 1994, anomalous gamma 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 before this procedure change. The IVC
observed that 23 uR/h exceeds 30% ofthe excavation average of 17 uR/h. The IVC will
allow a correlation developed by the RAC to estimate 22SRa. Concentrations in pCi/g are
based on gamma exposure rates. The anomalous reading of 23 uR/h on this property
using the RAC's correlation yields a 226Ra concentration of 5.0 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 m5 for subsurface samples. 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
determined by the Alpha-track method. To monitor radon levels, Geotech placed three
alpha-track detectors on the ground floor of the house located on this property for a
period of approximately one year (from 01/04/94 to 12/08/94). The average annual
working level (WL) of radon progeny concentration, as determined by the Tech./Ops-
Landauer Corporation, was 0.0036, 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
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 ^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
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)H, where A is the
area of the elevated region
Average annual radon proge- 0.03 WL
ny concentration (including
background)
(DOE 1990a)
Exposure to 222Rn
progeny
6
Table 2. Results of ORNL analysis of Geotech soil samples
from 332 East Center Street, Monticello Utah (MS00106-RS)
226Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No." No* (cm) ___
MS00106X1 NAW-445 >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 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.
7
REFERENCES
Geotech 1995. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00106-RS, Address: 332 East Center Street, Monticello, Utah
84535, Geotech, Grand Junction, Colorado, April 1995.
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.
ORNL, 1993. Environmental Technology Section (Formerly Pollutant Assessments
Group) Procedures Manual, ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
PROPERTY COMPLETION REPORT
FOR*
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
DOE ID NO.: MS-00147-RS
ADDRESS: 180 EAST FOURTH SOUTH STREET
MONTICELLO, UTAH 84535
JULY 1995
Prepared for
U.S. Department of Energy
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
FOR
by
Rust Geojech 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 Paoe
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-00147-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 ll. 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 the EPA standards by the
DOE, which determined that the property contained mill tailings (residual
radioactive material) exceeding the EPA standards. The Remedial Action
Contractor was notified of the inclusion of this property into the MVP
Project and was authorized by the DOE to conduct remedial action as
required to bring the property into conformance with the EPA standards
and the 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-00147-RS
MS-00147-RS
Location No. M-8; Block 2, Monticello
Townsite Survey, County of San Juan,
State of Utah
180 East Fourth South Street
Monticello, Utah 84535

Residential Simple (RS)
Not applicable: historical inclusion by the
DOE
June 8, 1984
Rust Geotech
November 20, 1985
Sonderegger Inc.
P.O. Box 713
Monticello, Utah
September 29, 1987
November 12, 1987
Interior: 0 cubic yards
Exterior: 1,066 cubic yards
1,776 square meters (m2)
July 1995
2
DOE ID No.: MS-00147-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 819 cubic yards of contamination,
ranging from 12 inches to 42 inches deep, within the property. The
remedial action process included the removal of approximately
1,066 cubic yards of residual radioactive material, ranging from 9 inches
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-00147-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 Bendix Field Engineering
Corporation during October 1984 and February 1985, as described
in the final REA dated November 1985. 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-22.
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 15 microroentgens per hour Ot/R/h)
to 126 /vR/h (Appendix Figure 2.1). Elevated exposure rates in
Area V-16 were associated with material along the edge of the
excavation that met the hot spot criteria. Residual radioactive
material was left in place in Area V-22 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 17.7 picocuries per
gram (pCi/g). The 100 m2 area average was 7.8 pCi/g (Appendix
Table 3.1). Area V-22 also met the hot spot Criteria, as indicated
in Appendix Table 3.2. The results of analyses for radium-226 in
21 composite soil samples ranged from 0.5 pCi/g to 17.0 pCi/g
(Appendix Table 3.3).
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on measurements representing an annual average, the RDC
was 0.0132 working level (WL), as indicated in Appendix
Table 3.4. Appendix Figure 2.1 shows the measurement location
in the basement (the lowest habitable level of the structure).
4
DOE ID No.: MS-00147-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by the EPA standards (40 CFR 192.12, 192.20-23)
and the DOE hot spot criteria, as indicated in the Certification Data
Summary below.
Therefore, the property located at 180 East Fourth South Street, in
Monticello, Utah, is recommended for certification as required by the
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 basement
was 13 //R/h to 14 //R/h.
Annual average was
0.0132 WL.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above backgroundf 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 0.5 pCi/g to
17.0-pCi/g.* Another soil
sample result, averaged
over a 100 m2 area, was
7.8 pCi/g.
*The background exposure rate is approximately 16 //R/h.
*The background radium-226 concentration is approximately 2.0 pCi/g.
*The hot spot criteria were met based on gamma scans, delta scintillometer
measurements, and soil sample results.
5
DOE ID No.: MS-00147-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
JEK:04-13-95
MS-00147.RS WP51
REV053193
6
>
Table 3.1
Calculation of Average Radium Concentration over a 100 m1 Area
DOE ID No.: MS-00147-RS
Address: 180 East Fourth South Street, Monticello, Utah
_ (CpXAp) + [Cr x (1,076 - Ap)l
Cav9 = 1,076
Where:
Cava = Radium-226 concentration in pCi/g averaged over a 100 m2
a (1,076 ft2) area.
Cp = Radium-226 concentration in pCi/g of the residual radioactive
material left in place.
Ap = Area in ft2 of the residual radioactive material left in place.
Cr = Radium-226 concentration in pCi/g for the remainder of the
100 m2 area, including excavated and unexcavated areas.
1,076 = Total area in ft2 over which the EPA guideline is applied.
Cp Ap Cr C EPA
Meas. Depth Standard
Area Method* (inches) (pCi/g) (ft2) (pCi/g) (pCi/g) (pCi/g)
V-22 OCS 15 - 21 17.7 95 6.8f 7.8 15.0*
Therefore, the averaged radium-226 concentration does not exceed the EPA
standard.
*OCS = Opposed Crystal System
tRadium-226 concentration of Area V-18.
*The DOE-implemented standard used for OCS measurements taken after
December 7, 1990, does not include the background radium-226 concentration.
7
1 1 >
Table 3.2
Hot Spot Calculation Results
DOE ID No.: MS-00147-RS
Address: 180 East Fourth South Street, Monticello, Utah
Shg = [Sgx(100/A)1/2] + Bkg
Where:
Shg = Hot Spot Limit of radium-226 concentration in pCi/g.
Sg = Authorized Limit of radium-226 concentration in pCi/g
(Sg = 5.0 pCi/g for surface soil and 15.0 pCi/g for subsurface soils).
100 = Total area,in m2 over which the Hot Spot Limit guideline is applied.
A = Area in nr of the hot spot.
Bkg = Background radium-226 concentration in pCi/g (Bkg = 2.0 pCi/g for
Monticello).
A SQ ShQ Radium-226 in
Meas. Depth y Hot Spot Area
Area Method* (inches) (m2) (pCi/g) (pCi/g) (pCi/g)
V-22 OCS 15 - 21 8.8 15.0 52.6 , ~ 17.7
Therefore, the radium-226 concentration in the hot spot area does not exceed the
Hot Spot Limit.
*OCS = Opposed Crystal System
8
Table 3.3
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00147-RS
Address: 180 East Fourth South 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.
Area
Exposure- Soil
Rate Range Sample
U/R/h) Ticket No.
Meas. Radium-226 Potassium Thorium
Method* (pCi/g) (pCi/g) (pCi/g)
V-l
V-2
V-3
V-4
V-5
V-6
V-7
V-8
V-9
V-10
V-ll
V-12
V-13
V-14
V-15
V-16
V-17
V-18
V-19
V-20
V-21
V-22
17
17
17
17
19
18
18
19
21
16
18
18
18
18
17
18
18
16
16
18
18
15
21
23
25
23
25
25
. 25
26
27
21
21
21
20
21
25
126
21
21
25
21
21
25
MNH 401
MNH 402
MNH 403
MNH 404
MNH 405
MNH 406
MNH 407
MNH 408
MNH 409
MNH 410
MNH 411
MNH 412
MNH 413
MNH 414
MNH 415
MNH 416
MNH 417
MNH 418
MNH 419
MNH 420
MNH 421
NAR 076
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
OCS
6.1
7.0
9.5
9.8
3.7
5.0
4.9
8.7
17.0
3.2
5.2
8.4
3.5
3.1
5.2
0.5
5.2
6.8
16.9
1.6
8.3
17.7
0.9
1.1
1.5
1.5
0.6
0.8
0.8
16.5 ± 3.9 < 0.2
1.2
0.5
0.5
0.7
0.2
0.7
1.0
2.8
0.3
1.2
15.5
11.3
15.9
15.2
14.3
15.8
16.4,
18.4
12.4
14.2
14.6
13.1
12.3
15.3
12.5
17.7
16.0
16.5
15.4
16.4
3.9
3.8
4.0
4.1
4.0
4.0
4.1
4.2
3.1
3.2
3.2
3.1
3.1
3.2
3.0
3.5
3.3
3.9
3.3
3.4
1.3
0.3
0.2
0.3
0.2
0.2
0.3
0.3
1.4
0.9
0.9
0.6
0.2
0.8
0.8
0.6
0.7
1.3
1.0
0.9
± 0.3
0.3
0.3
0.3
0.2
0.2
0.2
0.2
0.2
0.4
0.3
0.3
See Appendix Figure 2.1 for the verification areas.
*AL = Analytical Laboratory; OCS = Opposed Crystal System
9
Table 3.4
Radon Decay-Product Concentration Measurement Results
DOE ID No.: MS-00147-RS
Address: 180 East Fourth South Street, Monticello, Utah
Instrument Type: Terradex Track Etch® Detector
Detector
Number Start Date End Date
Tracks Per
mm2
Radon
Concentration
(pCi/L)
Working
Level
639336
639002
639307
12-21-87
12-21-87
12-21-87
01-18-89
01-18-89
01-18-89
24.8
23.6
27.5
2.58
2.46
2.86
0.0129
0.0123
0.0143
Annual Average: 0.0132
See Appendix Figure 2.1 for the measurement location.
10
42
40
38
36
34
32
30
28
26
24
22
20
18
16
14
12
10
1 2 1 4 16 20 22 24 25
~T~
28 30 32
T
34 36 38 40 42 44 46 48
i—T
50
15 V-2 V- 1
I7-2J 7-21
SHED
Worn © 15 V-3 Lt2] V-21 V-1 6 17-25
V-10 V-9 I'.7 V-13
0
18-21 18-126
21-27 SEE 16-21 18-20
DETAIL A 30
\© <3> 48
© DX21
•fr
<2J> 48 v-1 * 33 v-a V-20
Slit
V-4 18-21 V- 1 1 19-26
18-21 /33YT1 ^ 17-23 18-21
V-17
18-21
©-© 36 39
© ^30] 0>
:© 30 0X12 V-19 V-18 V-15 V-12 12 V-7
16-25 17-25 V-S 16-21 18-21
dm 18-25 ® 18-25 •V 15
V-5 V-22 SOUTH SECONO" EAST STREET
36 19-25 15-25
UJ or
t— co
I
h—
Z> o
o
®
rv.-.vi
LV.VJ
12-15
EH
V-1
16-17
(ROC)
ffl!!
ONE STORY
FRAME HOUSE
WITH BASEMENT
13-14
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
L
SCALE IN FEET
20 10 0 20 40
O:\DRAWINCS\OJA0003\RHOOM7V 03/2*/« 10:2Jom TS0780
X
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, BUILDING. OR OTHER FUTURE IMPROVEMENT LINES.
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
(SMXMCI-MO O* OCC**wtl U.S. DEPARTMENT OF ENERGY
CRAMS JUNCTION pmuccra orncc. COLOMAOO
180 EAST FOURTH SOUTH ST.
MONTICELLO, UTAH
RtMt <«0>RCll ««•-• MS-00147-RS
3-C00147-V1 „ 1 , 1
12 14 16 18 20 22 24 26 28 30 32 34 36 38 40 42 44 46 48 50
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 EAST 4TH SOUTH STREET
MONTICELLO, UTAH (MS00147-RS)
A. R. Jones
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 SYSTEMS, INC.
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-84OR21400
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. K. Jensen 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
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 1987, RUST
Geotech, the remedial action contractor designated by DOE, performed remedial action
on the vicinity property at 180 East 4th 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. All deficiencies noted
during an earlier review were corrected 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).
be
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 180 EAST 4TH SOUTH STREET
MONTICELLO, UTAH (MS00147-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.
•t
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 contarnination. 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-AC05-84OR21400 with Lockheed Martin Energy Systems, Inc.
2
During 1987, 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 180 East 4th 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 .
1995).
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 East 4th
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 ofthe 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 (peotech 1995)
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 819 yd3 of mill
tailings 12 to 42 inches deep. However, during the actual removal process, a total of
1,066 yd3 of contaminated earth and uranium mill tailings, 9 to 48 inches deep were
removed from a 1,776 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 ofthe structure, a surface scan of the exterior, and soil sampling. Samples
representative ofthe bottom 15-cm (6-in.) soil layers of 21 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
V-22 was collected to document contamination left in place around a mature tree. The
RAC is unable to locate or inadvertently disposed of the samples requested by ORNL for
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.
Gamma Measurements
Gamma exposure rate measurements taken by Geotech at the ground-level ofthe
residence ranged from 13 to 14 uR/h. Exterior surface gamma measurements taken from
the excavated areas prior to backfilling ranged from 15 to 126 uR/h.
Soil Sample Analysis
Prior to backfilling, Geotech collected 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 21 exterior verification areas.
Geotech's analysis of these samples showed 226Ra concentrations ranging from 0.5 to 17.0
pCi/g in the composite sample. An individual soil sample was taken from area V-22 and
is representative of contamination left in place around a mature tree. This sample
exceeded hot spot criteria. Geotech revisited the property, removed the top 6 inch layer
of soil, and resampled area V-22. A sample taken at the high outdoor gamma yielded a
226Ra concentration of 17.7 pCi/g. Calculations included in the property completion
report show compliance to guidelines in area average and hot spot vajues. ORNL ETS
was unable to obtain samples for confirmatory analysis. These values are below the EPA
standard value of 15 pCi/g for soil layers > 15 cm below the surface. Elevated gamma
exposure rates associated with area VI6 were investigated, and documented in the
property folio to indicate compliance with the DOE hot spot guideline. 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 detectors on the ground floor of the residence located on this property for a
period of approximately one year (from 12/21/87 to 01/18/89). The average annual
working level (WL) of radon progeny concentration, as determined 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 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 an earlier
review have been identified by the RAC as the result of a meeting August 8, 1995,
between the RAC and ORNL. These were resolved as provided in the letter dated August
31,1995 from R. K. Johnson to G. A. Pierce, MS-00147-RS, Comments Resolution, and
have been corrected in the completion report. 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
(lOO/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)
REFERENCES
Geotech 1995, Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MSQ0147-RS, Address: 180 East Fourth South Street,
Monticello, Utah 84535, Geotech, Grand Junction, Colorado, July 1995 .
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-00147-RS
Property Address: 180 East 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 [ ]
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 the DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
[/] [ ] I 1
[54 [ ] [ ]
[X] [ ] [ ]
[ ] [M [ 1
[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.
SFCERTIFED SFMS-80147
DOE ID No.: MS-00147-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
[><[ 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-00162-MR
ADDRESSES: 217 AND 249 EAST THIRD SOUTH STREET
MONTICELLO, UTAH 84535
AUGUST 1995
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-00162-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 the EPA standards and the
DOE hot spot criteria by the DOE Remedial Action Contractor. The DOE
reviewed these evaluation results and determined that the property
contained mill tailings (residual radioactive material) exceeding the EPA
standards. The Remedial Action Contractor was notified of the inclusion
of this property into the MVP Project and was authorized by the DOE to
conduct remedial action as required to bring the property into conformance
with the EPA standards and the DOE hot spot criteria.
1
DOE ID No.: MS-00162-MR
.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:
MS-00162-MR
Location No. M-70-1; in the S2 of Lot 2,
Block 11, Monticello Townsite Survey,
County of San Juan, State of Utah
217 and 249 East Third South Street
Monticello, Utah 84535

Major Residential (MR)
Not applicable: spillover inclusion requested
by the Remedial Action Contractor
June 26, 1987
Rust Geotech
November 24, 1987
Crowley Construction, Inc.
East Route HC 63 Box 66
Monticello, Utah
August 18, 1988
September 30, 1988
Interior: 12 cubic yards
Exterior: 506 cubic yards
1,622 square meters (m2)
August 1995
DOE ID No.: MS-00162-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). Exterior assessed Area J (front
stoop) was verified according to interior standards. 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 357 cubic yards of contamination,
ranging from 15 inches deep to 30 inches high, within the property. The
remedial action process included the removal of approximately 518 cubic
yards of residual radioactive material, ranging from 48 inches deep to
30 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-00162-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
November 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. Individual soil samples were collected for Areas
V-6 and V-25. The remaining samples were blended to form
composite samples representing the other exterior verification
areas (Appendix Figure 2.1).
Interior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 15 to 18 microroentgens per
hour (//R/h) for the remediated portion of the crawl space, 14 to
32 //R/h for the remediated portions of the attached garage, 15 to
23 //R/h for the remediated portion of the ground floor, 12 to
14 //R/h for the rest of the attached garage, and 12 to 22 //R/h for
the rest of the ground floor (Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 12 to 28 //R/h (Appendix
Figure 2.1). Residual radioactive material was left in place in
Areas V-6 and V-25 to avoid causing permanent damage to mature
bushes. The results of analyses for radium-226 in individual soil
samples of these areas were 23.3 and 6.0 picocuries per
gram (pCi/g), respectively. The 100 m2 area averages were 2.5
and 2.1 pCi/g (Appendix Table 3.1). Areas V-6 and V-25 also met
the hot spot criteria, as indicated in Appendix Table 3.2. The
results of analyses for radium-226 in 20 composite soil samples
ranged from 1.4 to 6.4 pCi/g (Appendix Table 3.3).
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on measurements representing an annual average, the RDC
was 0.0156 working level (WL), as indicated in Appendix
Table 3.4. Appendix Figure 2.1 shows the measurement location
on the ground floor (the lowest habitable level of the structure).
4
DOE ID No.: MS-00162-MR
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by the EPA standards (40 CFR 192.12, 192.20-23)
and the DOE hot spot criteria, as indicated in the Certification Data
Summary below.
Therefore, the property located at 217 and 249 East Third South Street,
in Monticello, Utah, is recommended for certification as required by the
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 15 to
18 //R/h for the
remediated portion of the
crawl space, 14 to
32 //R/h for the
remediated portions of
the attached garage, 15
to 23 //R/h for the
remediated portion of the
ground floor, 12 to
14 //R/h for the rest of
the attached garage, and
12 to 22 //R/h for the rest
of the ground floor.
Annual average was
0.0156 WL.
Land
Radium-226 Concentration
in Surface Soil:
Shall not exceed 5 pCi/g
above background* in the
15-cm surface layer,
averaged over 100 m2.
Soil sample results,
averaged over 100 m2
areas, were 2.1 and
2.5 pCi/g.**
Radium-226 Concentration Shall not exceed 15 pCi/g Soil sample results ranged
in Subsurface Soils: above background1 in any from 1.4 to 6.4 pCi/g.**
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
•The background exposure rate is approximately 14 //R/h.
fThe 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-00162-MR
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 Interior and Exterior Extent of Contamination -
RADIOLOGICAL AS-BUILT
JEK:06-21-95
MS-00162.MR WP52
REV053193
6
Table 3.1
Calculations of Average Radium Concentrations over 100 m2 Areas
Where:
DOE ID No.: MS-00162-MR
Addresses: 217 and 249 East Third South Street, Monticello, Utah
(CpXAp) + [Crx (1,076-Ap)]
Cav9 = 1,076
Cava = Radium-226 concentration in pCi/g averaged over a 100 m2
a (1,076 ft2) area.
Cp = Radium-226 concentration in pCi/g of the residual radioactive
material left in place.
Ap = Area in ft2 of the residual radioactive material left in place.
Cr = Radium-226 concentration in pCi/g for the remainder of the
100 m2 area, including excavated and unexcavated areas.
1,076 = Total area in ft2 over which the EPA guideline is applied.
Cp Ap Cr Cavg EPA
Meas. Depth y Standard
Area Method4 (inches) (pCi/g) (ft2) (pCi/g) (pCi/g) (pCi/g)
V-6 OCS 00 - 06 23.3 25 2.0b 2.5 5.0C
V-25 OCS 00 - 06 6.0 40 2.0b 2.1 5.0C
Therefore, the averaged radium-226 concentrations do 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-00162-MR
Addresses: 217 and 249 East Third South Street, Monticello, Utah
Shg = [Sg x (100 / A)54] + Bkg
Hot Spot Limit of radium-226 concentration in pCi/g.
Authorized Limit of radium-226 concentration in pCi/g
(Sg = 5.0 pCi/g for surface soil and 15.0 pCi/g for subsurface soils).
Total area,in m2 over which the Hot Spot Limit guideline is applied.
Area in nr of the hot spot.
Background radium-226 concentration in pCi/g (Bkg = 2.0 pCi/g for
Monticello).
A SQ ShQ Radium-226 in
Meas. Depth a Hot Spot Area
Area Method" (inches) (m2) (pCi/g) (pCi/g) (pCi/g)
V-6 OCS 00 - 06 2.3 5.0 35.0 "23.3
V-25 OCS 00 - 06 3.7 5.0 28.0 6.0
Therefore, the radium-226 concentrations in the hot spot areas do not exceed the
Hot Spot Limit.
"OCS = Opposed Crystal System
Where:
100
A
Bkg
8
Table 3.3
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00162-MR
Addresses: 217 and 249 East Third South Street, Monticello, Utah
The analytical uncertainties in the table are reported at the 95-percent confidence
interval.
Area
Exposure- Soil
Rate Range Sample Meas.
(//R/h) Ticket No. Method'
Radium-226
(pCi/g)
Potassium
(pCi/g)
Thorium
(pCi/g)
EXTERIOR
V-l
V-2
V-3
V-4
V-5
V-6
V-7
V-8
V-9
V-10
V-ll
V-12
V-13
V-14
V-15
V-16
V-17
V-18
V-19
V-20
V-21
V-25
14
14
14
14
14
19
14
15
13
14
15
15
15
15
14
15
15
15
14
13
14
18
17
18
18
22
24
18
24
16
16
16
18
28
16
16
20
18
20
16
18
20
19
MNK 633
MNK 634
MNK 635
MNK 636
MNK 637
NCG 194
MNK 639
MNK 640
MNK 641
MNK 644
MNK 645
MNK 646
MNK 647
MNK 648
MNK 649
MNK 650
MNK 151
MNK 152
MNK 153
MNK 154
MNK 155
NCG 197
AL
AL
AL
AL
AL
OCS
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
OCS
1.4
1.8
2.0
1.9
2.7
23.3
1.8
5.0
1.6
1.8
3.0
3.9
4.3
2.7
4.2
4.2
5.2
6.
3.
4.
4.
± 0.3
± 0.3
± 0.3
± 0.3
± 0.5
0.3
0.8
0.3
0.3
0.5
0.6
0.7
0.4
0.7
0.6
0.8
1.0
0.5
0.7
0.6
14.1 ± 3.0
14.7 ± 3.0
14.1 ± 2.9
16.0 ± 3.2
15.5 ± 3.2
16.5
15.9
13.8
18.2
16.2
14.6
17.2
14.4
14.3
15.6
13.9
16.2
14.1
17.3
16.6
3.3
3.2
2.9
3.4
3.2
3.0
3.3
3.0
3.0
3.2
3.1
3.3
3.0
3.9
3.9
1.0
1.0
1.0
0.9
1.1
1.1
0.9
0.9
1.1
0.8
1.0
0.8
1.1
1.0
1.0
1.1
1.0
0.9
0.7
1.1
± 0.3
± 0.2
± 0.3
± 0.2
± 0.3
0.3
0.2
0.3
0.3
0.3
0.3
0.3
0.3
6.0
"AL = Analytical Laboratory; OCS = Opposed Crystal System
9
Table 3.3 (continued)
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00162-MR
Addresses: 217 and 249 East Third South Street, Monticello, Utah
Exposure- Soil
Rate Range Sample Meas. Radium-226 Potassium Thorium
Area OvR/h) Ticket No. Method (pCi/g) (pCi/g) (pCi/g)
INTERIOR
V-22 15 - 18 Not applicable
V-23 14 - 32 Not applicable
V-24 15 - 23 Not applicable
See Appendix Figure 2.1 for the verification areas.
10
Table 3.4
Radon Decay-Product Concentration Measurement Results
DOE ID No.: MS-00162-MR
Addresses: 217 and 249 East Third South Street, Monticello, Utah
Instrument Type: Terradex Radtrak® Detector
Detector
Number Start Date End Date
Tracks Per
mm2
Radon
Concentration
(pCi/L)
Working
Level
3071118
3078139
3078182
03-13-90
03-13-90
03-13-90
03-11-91
03-11-91
03-11-91
24.8
25.0
25.8
3.02
3.04
3.27
0.0151
0.0152
0.0164
Annual Average: 0.0156
See Appendix Figure 2.1 for the measurement location.
11
40
38
36
34
32
30
28
26
24
22
20
16
16
14
12
10
1
i i "i—i—i—i 1 r
or
h-
</l >—
in <
UJ
Q
Z
o
UJ
3
O
V-20
13-IS
/0 V- 19
14-16 14-16 v-25
IB."
RDC
V-15 V- 18 V-21
14-16 15-20 14-20
ONE STORY FRAME
HOUSE W/CRAWL SPACE
SEE DETAIL A
12-22 -a 1, mm UK v-s WMM-V-5 GREEN 19-2* v-i 7 HOUSE M-22
V-1 6 GREEN V-14
15-20 HOUS 15-16 V-l
mmm I4-1R
12-16
GREEN
HOUSE v-3 12-16
V-4 I4-1S V-2 13-15 14-18
I 4- 1 6 14-17
V-13
15-28
® V-10
14-1
V-12
48 15-18
V-l 1
V-21 15-16
14-20
V-7
14-1
E V-9 V-8 V-10
U-16 14-16 15-24
14-16 [it
6 > I v-23 v-22
H) "-32
17
15-18
• 6
©00 GARAGE
12-14
24 !** \ CRAWL SPACE
.\ ^-GROUND FLOOR
DETAIL A
NOT TO SCALE
12 (Jl^Ol
V-24
15-23
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN /iR/h
ASSESSE0 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
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
©
<D
rr.-n
LV.-.vj
12-15
EE
V-1
16-17
[12] HEIGHT IN INCHES OF ASSESSED CONTAMINATED
CONCRETE STOOPS REMOVED ANO REPLACED
EAST THIRD SOUTH STREET
L
SCALE IN FEET
20 10 0 20 40
u \r<s\ojj\oooJ\»uooi«;v oe/li/a jjTpm rjo7ao
12 16 18
NORTH
20 22 24 26 28 30
THIS DRAWING IS TOR 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
32 34 36 38
RADIOLOGICAL AS-BUILT
FIGURE 2.1
INTERIOR AND EXTERIOR EXTENT OF CONTAMINATION
ffr c*. »l.
U.S. DEPARTMENT OF ENERGY
HAND JUNCTION MOJtCTS OftKt. COlOftAOO
8$r
217 AND 249 EAST THIRD
SOUTH STREET
MONTICELLO. UTAH
Ruat tooted! "»*•» MS-00162-MR
40 42 44 46
3-C0Q162-V1 „, 1 ,
48 51
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
217 AND 249 EAST 3RD SOUTH STREET
MONTICELLO, UTAH (MS00162-MR)
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 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 217 and 249 East 3rd
South Street, Monticello, Utah (MS00162-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.
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 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, RUST Geotech,
the remedial action contractor designated by DOE, performed remedial action on the
vicinity property at 217 and 249 East 3rd South Street, 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. All deficiencies noted in the initial re-
view have been resolved with additional soil sampling and documentation in 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 217 AND 249 EAST 3RD SOUTH STREET
MONTICELLO, UTAH (MS00162-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 south-
east 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 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 Properties (MVP) Project (U.S. DOE 1990b).
•The verification of remedial action was performed by members of the Environmental Assessment Group in the
Environmental TSShnology 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, RUST Geotech Inc. (Geotech), the remedial action contractor (RAC)
designated by DOE, performed remedial action on the vicinity property that is the sub-
ject of this report, a single family residence with 3 greenhouses located at 217 and 249
East 3rd South Street, Monticello, Utah. The remedial action plan required excavation
of all interior and exterior contamination. When the excavation was completed, the
property was resurveyed, including soil sampling, to ensure the removal of all contarni-
nation, backfilled with uncontaminated material, and restored to a condition compara-
ble to that which existed prior to remedial action (Geotech 1995).
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 217 and 249
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 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 1995)
indicates the property was remediated as evaluated by DOE on the basis of Environ-
mental 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 357 yd3 of mill
tailings 15 inches deep to 30 inches high. However, during the actual removal process,
a total of 518 yd3 of contaminated earth and uranium mill tailings, 48 inches deep to
30 inches high were removed from a 1622 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 20 exterior excavated verification
areas^jvere collected and blended to form representative composite soil samples for
each verification area. Individual soil samples were taken from areas V6 and V25 to
document contamination left in place.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radia-
tion 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 for the interior of the
residence were 15 to 18 /iR/h for the remediated portion of the crawl space, 14 to 32
/iR/h for the remediated portions of the attached garage, 15 to 23 /iR/h for the
remediated portion of the ground floor, 12 to 14 /iR/h for the rest of the attached
garage, and 12 to 22 /iR/h for the rest of the ground floor. The 32 /tR/h reading in the
garage was attributed to a point source. Exterior surface gamma measurements taken
from the excavated areas prior to backfilling ranged from 13 to 28 /iR/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 20 exterior verification
areas. Geotech's analysis of these samples showed 226Ra concentrations to range from
1.4 to 6.4 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 1.5 to 4.7 pCi/g. These values are below the EPA standard value of 15
pCi/g for soil layers > 15 cm below the surface. In addition, individual soil samples
from areas V6 and V25 measured 23.3 pCi/g and 6.0 pCi/g, respectively. The 226Ra
concentrations for areas V6 and V25 were averaged over 100 m2 area. These area
averages were 2.5 and 2.1 pCi/g, respectively. Hot spot calculations were also
performed to show compliance to guidelines. The hot spot limits were calculated to be
35 and 28 pCi/g for areas V6 and V25, respectively. Both of these calculations are
included in Geotech's completion report. All 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.
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 before
this procedure change. The IVC observed that VI, V3, V4, V5, V8, V13, and V16
exceed 30% of their 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 28 uR/h on this property using the RAC's correlation yields
a Ra 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. Results of Geotech and ORNL soil sample analyses are given in
Table-2.
4
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 03/13/90 to 03/11/91). The average annual
working level (WL) of radon progeny concentration, as determined by the Tech./Ops-
Landauer Corporation, was 0.0156, 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
verification assessment data, these radiological measurements fall below the limits pre-
scribed by DOE guidelines. All deficiencies noted in the initial review have been iden-
tified by the RAC as discussed in a meeting between Geotech and ORNL on May 17,
1996. Additional soil samples were collected and data added to the property folio. It
is concluded that the site successfully meets the DOE remedial action objectives.
6
Table 2. Results of ORNL analysis of Geotech soil samples
from 217 and 249 East 3rd South Street, Monticello, Utah (MS00162-MR)
"6Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No." No/ (cm)
X9 MNK641 >15 1.5 1.6
X15 MNK649 > 15 3.9 4.2
X20 MNK154 > 15 4.7 4.3
" 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.
REFERENCES
Geotech 1995. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00162-MR, Address: 217 and 249 East Third South Street,
Monticello.Utah 84535, Geotech, Grand Junction, Colorado, August 1995.
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-00162-MR
Property Addresses: 217 and 249 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 [ ] 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 the DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
YES NO NOT TAKEN
M I 1 [ 1
[>] [ ] t 1
[>•][] [ 1
[X] [ ] [ ]
[?•}[} [ ]
[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 gamma
exposure rates that do not exceed 30 percent above normal background.
SFCERTIFED SFMS-00I62
DOE ID No.: MS-00162-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
DOE EVALUATION
[X] Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy
supplemental standards per 40 CFR 192.21.
Date
U.S. Department of Energy
Date
DEC tl Wi
PROPERTY COMPLETION REPORT
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
DOE ID NO.: MS-00197-VL
ADDRESS: 249 B SOUTH THIRD EAST STREET
MONTICELLO, UTAH 84535
JULY 1995
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
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
DOE ID No.: MS-00197-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 the EPA standards and the
DOE hot spot criteria by the DOE Inclusion Survey Contractor. The DOE
reviewed these evaluation results and determined that the property
contained mill tailings (residual radioactive material) exceeding the EPA
standards. The Remedial Action Contractor was notified of the inclusion
of this property into the MVP Project and was authorized by the DOE to
conduct remedial action as required to bring the property into conformance
with the EPA standards'and the DOE hot spot criteria.
1
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
DOE ID No.: MS-00197-VL
Property Address:
Property Owner:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Construction Subcontractor:
P Re
Cco?dTUC,i°n Con^nce
Volume of Material Removed:
Area Cleaned Up:
P sS0X°dT,e,ion Rep°"
MS-00197-VL
Mon,,Ce||0 Townsite Survey- east C'
^.Cou^flfn^So;
249 B South Third East Street
Monticello, Utah 84535

Vacant Lot (VL)
Oak Ridge National Laboratory
October 23, 1989
Rust Geotech
November 11, 1993
D^mond Back Services, Inc.
9861 Trtan Park Circle
Littleton, Colorado
August 9, 1994
September 15, 1994
Interior: 0 cubic yards
Exterior: 74 cubic yards
302 square meters (m2)
July 1995
2
DOE ID No.: MS-00197-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 remedial action process included
the removal of approximately 74 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-00197-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 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 (//R/h), as indicated on Appendix Figure 2.1. The results of
analyses for radium-226 in eight composite soil samples ranged
from 3.2 to 9.2 picocuries per gram (pCi/g), as indicated in
Appendix Table 3.1. Areas V-5 through V-8 were remediated
under MS-00107-RS (Areas V-6, V-5, V-4, and V-3, respectively).
4
DOE ID No.: MS-00197-VL
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by the EPA standards (40 CFR 192.12, 192.20-23)
and the DOE hot spot criteria, as indicated in the Certification Data
Summary below.
Therefore, the property located at 249 B South Third East Street, in
Monticello, Utah, is recommended for certification as required by the
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 /yR/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 3.2 to 9.2 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-00197-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
DAG:05-03-95
MS-00197.VL WP52
REV053193
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00197-VL
Address: 249 B South Third East Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range fo/R/h) Ticket No. Method" (pCi/g)
V-l 16 - 23 NAZ 460 OCS 4.2
V-2 15 - 19 NAZ 466 OCS 3.2
V-3 16 - 21 NCA 951 OCS 3.8
V-4 15 - 19 NCA 952 OCS 5.5
V-5 16 - 23 NAZ 459 OCS 6.3
V-6 15 - 20 NAZ 458 OCS 4.8
V-7 15 - 23 NAZ 457 OCS 6.2
V-8 15 - 22 NAZ 456 OCS 9.2
See Appendix Figure 2.1 for the verification areas.
"OCS = Opposed Crystal System
7
10 12 14 16 18 20 22 24 26 28 30 32 34
"i—i—i—i—i—i—T
36 38 40 42 44 46 48 50
42 i—r i—r
40
38
36
SOUTH THIRD EAST STREET
®1
15-16 15-16 SHED
13^16
V-8
V-3 V-2
15-22 V-4 16-21 15-19
15-19
V-3
16-21
V-7 SHED
N 15-23
V-5 V-2 V-6
16-23 15-19 15-20
BSC*/
BARN 15-16
13-15
v-5
16-23
LU SHED v-1
13-:14 v-2 16-23
15-19
SHED 15-16 13-15
rv.-n
LV.-.vj
12-15
12
v-i
16-17
-*
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN /jR/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
AREAS V-5 THROUGH V-8 WERE REMEDIATED
UNDER MS-00107-RS
POINT SOURCE (ORE SAMPLE) REMOVED
34
32
30
28
26
24
22
20
18
L— X
J L
SCALE IN FEET
20 10 0 20 40
M:\FAS\OJJ\OOOJ\RM00197V OS/07/93 09:1 lom TS07S0
J I I I I I I L
NORTH
J
THIS DRAWING IS FOR THE SOLE USE OF THE U.S. OEPARTUENT
OF ENERGY ANO ITS CONTRACTORS. IT IS NOT A LANO 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 L
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
U.S. DEPARTMENT OF ENERGY
0UNO JUNCTION mOJCCTS orricf. COLOIUOO
249 6 SOUTH THIRD EAST ST.
MONTICELLO. UTAH
16
14
12
Rust Qiotwch "» MS-0019 7-VL
3-C00197-V1_ 1 _ 1 10
10 12 14 16 18 20 22 24 26 28 30 32 34 36 38 40 42 44 46 48 50
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 B SOUTH 3RD EAST STREET
MONTICELLO, UTAH (MS00197-VL)
A. R. Jones
September 1995
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY SYSTEMS, INC.
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-84OR21400
CONTENTS
LIST OF TABLES v
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 249 B South 3rd East
Street, Monticello, Utah (MS00T97-VL) 5
v
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 D. S. List for analysis of soil samples and M. K. Jensen and N. F. Lewis
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 1994, RUST
Geotech, the remedial action contractor designated by DOE, performed remedial action on
the vicinity property at 249 B 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
I
RESULTS OF THE INDEPENDENT VERD7ICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 249 B SOUTH 3RD EAST STREET
MONTICELLO, UTAH (MS00197-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) 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-AC05-84OR21400 with Lockheed Martin Energy Systems, Inc.
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 249 B 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 1995).
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 249 B 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
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 1995)
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 60 yd3 of mill tailings
6 to 12 inches deep. However, the actual removal process, a total of 74 yd3 of
contaminated earth and uranium mill tailings, 6 to 12 inches deep were removed from a
302 m2 area.
A post-excavation survey was performed by Geotech prior to backfilling of the
excavated areas. This survey consisted of a surface gamma scan, with a scintillometer,
and soil sampling. Samples representative of the bottom 15-cm (6-in.) soil layers of 8
excavated 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 gamma exposure rate measurements taken by Geotech from the excavated
areas prior to backfilling ranged from 15-23/^R/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 8 exterior verification areas.
Geotech's analysis of these samples showed 226Ra concentrations ranging from 3.2 to 9.2
pCi/g in the composite samples. ORNL ETS obtained one of these soil samples and
performed a confirmatory analysis, which showed a a6Ra concentration of 5.2 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 Guideline 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 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
Radionuclide
concentration in soil
for Hot Spot Areas
Exposure to ^Rn
progeny
Maximum permissible con-
centration of ^Ra in soil
above background levels,
averaged over a 100-m2 area
Maximum permissible
concentration of Ra^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)*, where A is the
area of the elevated region
0.03 WL
(DOE 1990a)
6
REFERENCES
Geotech 1995, Property Completion Report for Monticello Vicinity Property
Remedial Action for DOE ID NO: MS00197-VL, Address: 249 B South 3rd East
Street, Monticello, Utah 84535, Geotech, Grand Junction, Colorado, July 1995.
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.
ORNL, 1993. Environmental Technology Section (Formerly Pollutant
Assessment Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak
Ridge National Laboratory, Grand Junction, Colorado.
t
T »
DOE ID No.: MS-00197-VL
Property Address: 249 B 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 /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 the DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] f ]
[ ] [ ] [X]
(Vacant Lot)
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
in I ) I 1
[*} [ ]
[ ] [ 1
[ ]
[Y]
t ] [ ] [X] [ ] [ ]
(Vacant Lot)
[ 1 L*] [ 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.
SFCERTIFED SFMS-09828
DOE ID No.: MS-00197-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 the concurrence
of the U.S. Nuclear Regulatory Commission because supplemental
standards were applied per 40 CFR 192.21.
anda S. Busby7 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 the
concurrence of the U.S. Nuclear Regulatory Commission because
supplemental standards were applied per 40 CFR 192.21.
Certification Official
U.S. Department of Energy
Date
DOE ID No.: MS-00207-VL
Property Address: Parcel No. A33230257213, East Fifth 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 the DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[ 1 [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
[y] [ ] [ ]
[X] [ ] I ]
[ ] [ ] [X] [ ] [ ] [*]
(Vacant Lot)
MM [X] [ ] I ] [XI
(Vacant Lot)
[ ] [yl 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 gamma
exposure rates that do not exceed 30 percent above normal background.
llllllllll II1I111M
SFCERTIFED SFMS-00207
DOE ID No.: MS-00207-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 the concurrence
of the U.S. Nuclear Regulatory Commission because supplemental
standards were applied per 40 CFR 192.21.
[vl 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
Date
U.S. Department of Energy
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00207-VL
ADDRESS: PARCEL NO. A33230257213
EAST FIFTH NORTH STREET
MONTICELLO, UTAH 84535
FEBRUARY 1995
Prepared for
U.S. Department of Energy
by
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
Wandj^6. 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-00207-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 the EPA standards and the
DOE hot spot criteria by the DOE Inclusion Survey Contractor. The DOE
reviewed these evaluation results and determined that the property
contained mill tailings (residual radioactive material) exceeding the EPA
standards. The Remedial Action Contractor was notified of the inclusion
of this property into the MVP Project and was authorized by the DOE to
conduct remedial action as required to bring the property into conformance
with the EPA standards and the 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-00207-VL
MS-00207-VL
Beginning 2,094.7 feet north and
1,368.5 feet west of the SE corner of
Section 25, T33S., R23E., Salt Lake Base
Meridian; north 258.8 feet, east 114.5 feet,
south 258.8 feet, east 594 feet, south
177.4 feet, west 808.5 feet, north
177.4 feet, east 100 feet to beginning, City
of Monticello, County of San Juan, State of
Utah
Parcel No. A33230257213
East Fifth North Street
Monticello, Utah 84535

Vacant Lot (VL)
Oak Ridge National Laboratory
January 25, 1990
Rust Geotech
February 10, 1994
Diamond Back Services, Inc.
9861 Titan Park Circle
Littleton, Colorado
August 10, 1994
September 20, 1994
Interior: 0 cubic yards
Exterior: 18 cubic yards
72 square meters (m2)
February 1995
2
DOE ID No.: MS-00207-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 36 cubic yards of contamination,
ranging from 6 inches to 12 inches deep, within the property. The
remedial action process included the removal of approximately 18 cubic
yards of residual radioactive material, ranging from 6 inches 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-00207-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
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 12 microroentgens per hour (//R/h)
to 21 //R/h (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-00207-VL
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by the EPA standards (40 CFR 192.12, 192.20-23)
and the DOE hot spot criteria, as indicated in the Certification Data
Summary below.
Therefore, the property located at Parcel No. A33230257213, East
Fifth North Street, in Monticello, Utah, is recommended for certification
as required by the 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 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-00207-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:01-13-95
MS-00207.VL WP51
REV053193
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00207-VL
Address: Parcel No. A33230257213, East Fifth North Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range U/R/h) Ticket No. Method* (pCi/g)
V-l 15 - 21 NCA 957 OCS 1.9
See Appendix Figure 2.1 for the verification area.
*OCS = Opposed Crystal System
7
10 12 14 16 18 20 22 24 26 28 30 32 34 36 38
42
40
38
36
34
32
30
28
26 -
24 -
22 -
20
18
16
10
i—r
13-17
12-15
15-21
ft
V-1
15-2)
SHED 1% 12-15
X -
1? - ^ K
6IF
RUO0207V 01/U/93 TUT/712 DETAIL A
I I I I I
40 42 44 46 48 50
~1 1 1 1 1 1 1 1 1 1 1 42
40
12-15
lit |J
,,_XJ SEE DETAIL A |
|5gl - '
I z
I I
12-15
©
<D
12-15
12
v-i
16-17
WM
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
SCALE IN FEET
20 10 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.
- 34
32
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
U.S. DEPARTMENT OF ENERGY
MAMO JUNCTION mjCCTS OfflCC. COLMAOO
PARCEL NO. A33230257213
EAST FIFTH NORTH STREET
MONTICELLO. UTAH
GtxyrixH Inc. \mmLm r '••» MS-00207-VL
""•»• J-C0O2O7-V1 _ 1 _ 1 m i
38
36
30
28
26
24
22
- 20
- 18
- 16
14
12
10 12 14 16 16 20 22 24 26 28 30 32 34 36 38 40 42 44 46 48 50
10
OAK RIDGE NATIONAL LABORATORY GRAND JUNCTION OFFICE
RO. BOX 2567
MANAGED BY MARTIN MARIETTA ENERGY SYSTEMS, INC. GRAND JUNCTION, COLORADO 81502
APR 2 8 «B
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, 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 exterior 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
MS00207-VL
A33230257213 East 5th North 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
A33230257213 EAST 5TH NORTH STREET
MONTICELLO, UTAH (MS00207-VL)
A. R Jones
April 1995
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
MARTIN MARIETTA ENERGY SYSTEMS, INC.
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-84OR21400
CONTENTS
LIST OF TABLES v
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 5
iii
LIST OF TABLES
Applicable guidelines for protection against radiation
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 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
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, RUST
Geotech, the remedial action contractor designated by DOE, performed remedial action on
the vicinity property at A33230257213 East 5th 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 A33230257213 EAST 5TH NORTH STREET
MONTICELLO, UTAH (MS00207-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) 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 (Abramiuk 1989).
•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-AC05-84OR21400 with Martin Marietta Energy Systems, Inc.
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 A33230257213 East 5th 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
1995).
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 A33230257213
East 5th 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 1990).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1995)
indicates the property was remediated as evaluated by DOE on the basis of Environmental
Protection Agency standards and the DOE guidelines (DOE 1990). 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 36 yd3 of mill tailings
6 to 12 inches deep. However, during the actual removal process, a total of 18 yd3 of
contaminated earth and uranium mill tailings, 6 to 12 inches deep were removed from a
72 m2 area.
A post-excavation survey was performed by Geotech prior to backfilling of the
excavated areas. This survey consisted of a surface gamma scan, with a scintillometer,
and soil sampling. Samples representative of the bottom 15-cm (6-in.) soil layers of the
excavated areas were collected and blended to form a representative composite soil
samples 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
Exterior gamma exposure rate measurements taken by Geotech from the excavated
areas prior to backfilling ranged from 12 to 21 //R/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 1.9 pCi/g. ORNL ETS
was unable to obtain samples for confirmatory analysis. 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 Guideline for
areas <25 m2 (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
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
concentration 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
concentration of Ra^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)*, where A is the
area of the elevated region.
0.03 WL
(DOE 1990)
REFERENCES
Abramiuk I. N.et al. 1989. Monticello Remedial Action Project Site Analysis Re-
port, GJ-10, prepared by Bendix Field Engineering Corporation, Grand Junction,
Colorado, for the U.S. Department of Energy, Surplus Facilities Management
Program, Richland, Washington.
Geotech 1995, Property Completion Report for Monticello Vicinity Property
Remedial Action for DOE ID NO: MS00207-VL, Address: A33230257213 East
5th North Street, Monticello, Utah 84535, Geotech, Grand Junction, Colorado,
February 1995.
U.S. DOE 1990. 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.
ORNL, 1993. Environmental Technology Section (Formerly Pollutant
Assessment Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak
Ridge National Laboratory, Grand Junction, Colorado.
' DOE ID No.: MS-00212-VL
Property Address: 300 East Fourth South Street
VICINITY PROPERTY CERTIFICATION SUMMARY AND
SUMMARY EVALUATION
Rust Geotech
YES NO NOT TAKEN
Ra-226 is < 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2. [X]* [ ] [ ] [>] [ ] [ ]
In-situ IX] Lab [ ]
RECOMMENDATION
U.S. Department
of Energy (DOE)
YES NO NOT TAKEN
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]
[X] [ ] [ ] [y] [ ] [ ]
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 the DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
[ ] [ ] [X] [ ] [ ] ly]
(Vacant Lot)
[ ] [ ] [X] [ ] [ ] [y]
(Vacant Lot)
t ] [X] [ )
[X] [ ] [ ]
[ ] [y] I ]
[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.
Hiiiiiiiiiin •iiimin
SFCERTIFED SFMS-08212
' DOE ID No.: MS-00212-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.
Dy
iticello Pi
Rust Geotech
~' Date
Manager, Monticello Programs
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-00212-VL
ADDRESS: 300 EAST FOURTH SOUTH STREET
MONTICELLO, UTAH 84535
JULY 1995
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
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-00212-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 the EPA standards and the
DOE hot spot criteria by the DOE Inclusion Survey Contractor. The DOE
reviewed these evaluation results and determined that the property
contained mill tailings (residual radioactive material) exceeding the EPA
standards. The Remedial Action Contractor was notified of the inclusion
of this property into the MVP Project and was authorized by the DOE to
conduct remedial action as required to bring the property into conformance
with the EPA standards and the DOE hot spot criteria.
1
DOE ID No.: MS-00212-VL
1.3 Summary of Remedial Action
DOE ID No.:
Land Descriptions:
MS-00212-VL
Location No. M-215; beginning at the SW corner of Block B, Monticello
Townsite Survey, east 141.5 feet to the east boundary line of Section 36,
T33S., R23E., Salt Lake Base Meridian; north along said east boundary line
152 feet, west 141.5 feet, south 152 feet to the point of beginning, County of
San Juan, State of Utah
Portions of South Third East Street and East Fourth South Street right-of-ways
described as follows: beginning at the SW corner of Block B, Monticello
Townsite Survey, east 141.5 feet, south 99 feet, west 224 feet, north
251 feet, east 82.5 feet, south 152 feet to the point of beginning, 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:
300 East Fourth South Street
Monticello, Utah 84535

Vacant Lot (VL)
Oak Ridge National Laboratory
January 25, 1990
Rust Geotech
June 14, 1991
Sonderegger Inc.
P.O. Box 713
Monticello, Utah
June 12, 1992
November 11, 1992
2
DOE ID No.: MS-00212-VL
1.3 Summary of Remedial Action (continued)
Volume of Material Removed: Interior: 0 cubic yards
Exterior: 5,806 cubic yards
Area Cleaned Up: 5,164 square meters (m2)
Property Completion Report
Submitted: July 1995
3
DOE ID No.: MS-00212-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 1,514 cubic yards of contamination,
ranging from 6 to 21 inches deep, within the property. The remedial
action process included the removal of approximately 5,806 cubic yards of
residual radioactive material, ranging from 6 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
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-00212-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 1990, as described in the final REA dated
June 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. 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 28 microroentgens per
hour (//R/h), as indicated on Appendix Figure 2.1. The results of
analyses for radium-226 in 62 composite soil samples ranged from
less than 1.0 to 6.2 picocuries per gram (pCi/g), as indicated in
Appendix Table 3.1.
5
DOE ID No.: MS-00212-VL
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by the EPA standards (40 CFR 192.12, 192.20-23)
and the DOE hot spot criteria, as indicated in the Certification Data
Summary below.
Therefore, the property located at 300 East Fourth South Street, in
Monticello, Utah, is recommended for certification as required by the
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.1
Soil sample results
ranged from < 1.0 to
6.2 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-00212-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
DAG:05-25-95
MS-00212.VL WP52
REV053193
7
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00212-VL
Address: 300 East Fourth South Street, 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-l
V-2
V-3
V-4
V-5
V-6
V-7
V-8
V-9
V-10
V-ll
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
15
17
16
15
15
15
15
15
15
16
15
15
17
18
17
19
17
15
15
15
15
16
17
15
17
18
15
25
20
20
20
19
19
19
18
19
20
21
20
25
20
21
19
21
21
21
19
19
20
19
21
20
21
21
20
NAT 311
NAT 312
NAT 313
NAT 314
NAT 315
NAT 316
NAT 317
NAT 318
NAT 319
NAT 320
NAT 321
NAT 322
NAT 323
NAT 324
NAT 325
NAT 326
NAT 327
NAT 328
NAT 329
NAT 330
NAT 286
NAT 287
NAT 288
NAT 289
NAT 290
NAT 291
NAT 292
NAT 293
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
5.8
2.1
2.4
3.2
2.9
2
1.
2.
6.
3.0
2.2
3.1
3.9
1.8
3.0
2.7
3.8
3.8
2.9
1.7
2.3
3.6
3.2
2.9
4.1
2.7
1.0
2.3
"OCS = Opposed Crystal System
8
Table 3.1 (continued)
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00212-VL
Address: 300 East Fourth South Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (//R/h) Ticket No. Method* (pCi/g)
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-50
V-51
V-52
V-53
V-54
V-55
V-56
V-57
V-58
V-59
V-60
17 - 23
17 - 20
17 - 21
17 - 21
13 - 17
15 - 20
15 - 20
16 - 20
16 - 19
16
16
17
17
18
16
16
17
17
17
16
17
17
15
15
14
15
14
15
15
15
13
15
19
23
25
21
21
21
25
27
21
21
21
21
28
20
18
20
19
19
25
20
17
20
20
NAT 294
NAT 295
NAT 296
NAT 297
NAX 679
NAT 071
NAT 072
NAT 073
NAT 074
NAT 075
NAT 076
NAT 077
NAT 078
NAT 079
NAT 080
NAT 081
NAT 082
NAT 083
NAT 084
NAT 085
NAX 665
NAX 666
NAX 667
NAX 668
NAX 669
NAX 670
NAX 671
NAX 672
NAX 673
NAX 674
NAX 675
NAX 676
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
OCS
OCS
OCS
OCS
2.0
1.0
2.5
2.0
1.5
3.0
3.6
2,
1.
2.
2.
1.
1.
1.1
1.5
2.7
2.
1.
1.
2,
1.
1.
2.
3.
1.
2.9
2.6
"OCS = Opposed Crystal System
9
26 28 30 32 34 36 38 40 42
i T
V— 7 V-20 V-5
15-19 15-19 15-1
UJ 1 44
0 12 •••-A V-2 V-1 1 2 © 12 15-10 17-25
V-33
V-3 V-6 V-4 V-62 V-61 <1> • HD 13-17 4 4 24 15-19 17-20 14-18 16-20 15-28
108 108 V-13
V-8 V-11 v-12 V-59 V-9 V-10 V-60
15-20
24 15-25
15-18 16-21 15-20 15-19 15-20 13-20
60
© R H3 <g> © M 24 '2; 12
V-58
15-17
V- I 6 V-15 V-14 V-57 V-19 V- 18 V- 1 7
18-21 17-20 15-21 17-19 15-20 17-21 19-21
<3> 0 0 24 24 24 24 24
108
V-56
© 15-25
V-21 V-24 V-25 V-26 V-22 V-23
108 15-19 17-21 15-20 17-21 15-20 16-19
V-55
24 48 24 24 24 24 24 4-19
48 V-27 V-32 V-30 V-29 V-28 V-54 V-31
17-23 15-20 15-19 17-21 17-21 17-20 18-21
24 24 24 24 24
12-15 108
08 V-34
15-20 V-37 V-38 V-39 © V-36
© 16-20 16-19 16-19 16-23
V-l 48 V-35 18 18 18 16-17 24 15-20
15
v-52
18 15-18
V-40 V-43 V-42 V-4 I
16-21 18-21 17-21 17-25 v. 94
v-5i V-44
©^ 24 15 ra 15-20 16-25
18 © 90
V-45 V-46 V-47 V-4B
V-49
17-21 17-27 17-21 16-21
17-21
V-50
© 17-28 12
46
T
48
i—r
50
15-18 EAST FOURTH SOUTH STREET
RIGHT-OF-WAY
L,
SCALE IN FEET
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
20 10 0 20 40
M:\fAS\OJJ\OOOJ\Ry00212v 07/14/15 I0:49om T30780 NORTH
THIS ORAWING IS TOR THE SOLE USC Or THE U.S. OEPARTUENT
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. BUILOINC. OR OTHER FUTURE IMPROVEMENT LINES
10 12 1 4 16 18 20 22
J L_
24
J L
26
U.S. DEPARTMENT OF ENERGY
CJUM6 JUNCTION »N0jfC1» OnCC. COLORADO
Z2L
300 EAST FOURTH
SOUTH STREET
MONTICELLO. UTAH
RUST nu*t < mmm. MS-00212-VL
J-C00212-V1—l_l
42
4C
38
36
34
32
30
28
26
24
22
20
18
16
14
12
28 30 32 34
10
36 38 40 42 46 48 50
OAK RIDGE NATIONAL LABORATORY PHONE: (97O> 24M20O
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION FAX: [phone]
FOR THE U.S. DEPARTMENT OF ENERGY
POST OFFICE BOX 2567
GRAND JUNCTION. COLORADO 81502 FEB 2 8 1993
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 verifica-
tion 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:
Location Address:
Property Owner:
Owner Address:
Property Owner:
Owner Address:
MS00212-VL
300 East 4th 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
300 EAST 4TH SOUTH STREET
MONTICELLO, UTAH (MS00212-VL)
A. R. Jones
February 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
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 300 East 4th South
Street, Monticello, Utah (MS00212-VL) 5
V
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 D. S. List for analysis of soil samples and J. R. Sauvage 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 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,
RUST Geotech, the remedial action contractor designated by DOE, performed remedial
action on the vicinity property at 300 East 4th 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. All deficiencies noted
in an earlier review have been resolved. 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 300 EAST 4TH SOUTH STREET
MONTICELLO, UTAH (MS00212-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) 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 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 vacant lot located at 300 East 4th 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 1995).
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 300 East 4th
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 (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1995)
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 1,514 yd3 of mill
tailings 6 to 21 inches deep. However, during the actual removal process, a total of
5,806 yd3 of contaminated earth and uranium mill tailings, 6 to 144 inches deep were
removed from a 5,164 m2 area.
A post-excavation survey was performed by Geotech prior to backfilling of the
excavated areas. This survey consisted of a surface gamma scan with a scintillometer,
and soil sampling. Samples representative of the bottom 15-cm (6-in.) soil layers of 62
excavated 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 gamma exposure rate measurements taken by Geotech from the excavated
areas prior to backfilling ranged from 13-28 /xRJh.
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 62 exterior verification
areas. Geotech's analysis of these samples showed 226Ra concentrations ranging from
<1.0 to 6.2 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 1.2 to 4.7 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 the IVC on May 26, 1994,
anomalous gamma 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 areas
VI, Vll, V13, V29, V39, V40, V44, V45, V46, V50, V51, V53, V54, V55, V56,
V61, and V62 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 28 /xR/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 nr for subsurface samples.
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 an earlier review have been
identified by the RAC and resolved as provided in the letter dated August 30, from R.
K. Johnson to G. A. Pierce, MS-00212-VL Comment Resolution. 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
concentration 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
concentration 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
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)*, 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 300 East 4th South Street, Monticello Utah (MS00212-VL)
226Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No." No* (cm)
X6 NAT 316 >15 3.0 2.8
X17 NAT 327 > 15 4.4 3.8
X19 NAT 329 >15 3.8 2.9
X23 NAT 288 >15 4.7 3.2
X27 NAT 292 > 15 1.2 1.0
X30 NAT 295 >15 2.4 3.3
X45 NAT 082 > 15 3.3 1.2
X62 NAX 678 >15 2.2 2.1
" 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 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: MS00212-VL, Address: 300 East Fourth South Street,
Monticello, Utah 84535, Geotech, Grand Junction, Colorado, July 1995.
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.
ORNL, 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
DOE ID No.: MS-00220-CS
Property Address: 32 East Center Street
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
RUST Geotech Inc. of Enerov (DOE)
YES NO NOT TAKEN YES NO NOT TAKEN
Ra-226 is 2£ 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 the DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
[/] [ 1 [ 1
[XI [ 1 [ 1
lY] [ } I 1
[>] [ 1 [ 1
I 1 [ ]
M I ] 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.
Illlllll! 11111111111
SFCERTIFED
SFMS-09023
DOE ID No.: MS-00220-CS
RUST GEOTECH INC. RECOMMENDATION
Based on the RUST Geotech Inc. 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 Inc.
DOE EVALUATION
Date
U.S. Department of Energy
PROPERTY COMPLETION REPORT
DOE ID NO.: MS-00220-CS
ADDRESS: 32 EAST CENTER STREET
MONTICELLO, UTAH 84535
JANUARY 1995
Prepared for
U.S. Department of Energy
RUST Geotech Inc. 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 Inc.
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-00220-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 the EPA standards and the
DOE hot spot criteria by the DOE Remedial Action Contractor. The DOE
reviewed these evaluation results and determined that the property
contained mill tailings (residual radioactive material) exceeding the DOE
hot spot criteria. The Remedial Action Contractor was notified of the
inclusion of this property into the MVP Project and was authorized by the
DOE to conduct remedial action as required to bring the property into
conformance with the EPA standards and the DOE hot spot criteria.
1
DOE ID No.: MS-00220-CS
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
MS-O022O-CS
Beginning at the NW corner of Block 23, Monticello Townsite Survey; east
164.5 feet, south 193.5 feet, east 50 feet, south 96 feet, west 214.5 feet,
north 25 feet, east 100 feet, north 50 feet, east 3.33 feet, north 39.77 feet,
west 103.33 feet, north 174.5 feet more or less to beginning, 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:
32 East Center Street
Monticello, Utah 84535

Commercial Structure (CS)
Not applicable: inclusion requested by the
Remedial Action Contractor
October 10, 1991
RUST Geotech Inc.
December 30, 1991
Sonderegger Inc.
P.O. Box 713
Monticello, Utah
June 4, 1992
June 19, 1992
Interior:
Exterior:
0 cubic yards
2 cubic yards
12 square meters (m2)
January 1995
2
2.0 OPERATIONS SUMMARY
DOE ID No.: MS-00220-CS
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 1 cubic yard of contamination,
6 inches deep, within the property. The remedial action process included
the removal of approximately 2 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-00220-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 RUST Geotech Inc. during
October and November 1990, as described in the final REA dated
December 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. 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 microroentgens per hour (//R/h)
to 19 //R/h (Appendix Figure 2.1). The result of analysis for
radium-226 in one composite soil sample was 3.7 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 0.0005 working level (WL) for Building 1 (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 not taken in Building 2 due to excessive
ventilation caused by open bay doors; therefore, this building was
verified according to exterior standards.
4
DOE ID No.: MS-O022O-CS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by the EPA standards (40 CFR 192.12, 192.20-23)
and the DOE hot spot criteria, as indicated in the Certification Data
Summary below.
Therefore, the property located at 32 East Center Street, in Monticello,
Utah, is recommended for certification as required by the 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 //R/h to
15//R/h.
Annual average was
0.0005 WL.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above backgroundt in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above backgroundT 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
3.7 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-00220-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
SJW: 12-09-94
MS-00220.CS WP52
REV053193
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00220-CS
Address: 32 East Center Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (//R/h) Ticket No. Method* (pCi/g)
V-l 13 - 19 NAN 610 OCS 3.7
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-00220-CS
Address: 32 East Center Street, Monticello, Utah
Instrument Type: Terradex Radtrak® Detector
Detector
Number Start Date End Date
Tracks Per
mm2
Radon
Concentration
(pCi/L)
Working
Level
3718104
3718149
3718251
01-06-93
01-06-93
01-06-93
01-04-94
01-04-94
01-04-94
0.2
0.4
1.3
0.08
0.08
0.12
0.0004
0.0004
0.0006
Annual Average: 0.0005
See Appendix Figure 2.1 for the measurement location.
8
10 ,
52 i—
18
T—i—r
24 26
H—i—r
30 32
"i—i—i—i—T
36
1—r n—r
40
T"
48 50
T"
54 70
i—r ~\—i—r ~\—i—r i i r ir ir i—i—r
EAST CENTER STREET
SCALE IN FEET
20 10 0
UA cr
<5> 14-17
<5>
ROC
ONE STORY
BLOCK BUILDING 1
12-15
El 0 14-17
LLL
14-7
14-17
A
UNINHABITABLE ONE STORY
METAL BUILDING 2
12-14
v-l
5-19
14-17
14-17
J L J I l I l J L J I J L J I I L
©
<D
rv.-.vi
L _i
12-15
ED
(Soc)
L££LEHD
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
RADIOLOGICAL AS-BUILT
• FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
THIS DRAWING IS FOR THE SOLE USC OF THE U.S. DEPARTMENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVCT
PLAT. UTILITY LOCATION PLAT, OR OTHER IMPROVEMENT SURVEY
PLAT ANO IS NOT TO 8E RELIED UPON FOR THE ESTABLISHMENT
OF FENCE. BUILOINC. OR OTHER FUTURE IMPROVEMENT LINES.
J I J L
KSIKHCC-NO. or OCCUPANTS
MON-USIDEMCC- MM-HM./M
INtfMJUIMT RO.
WKIFIOATHM
BY CK. A.E. APP. NO. DATE
RU002ZOV ia/0f/|4 TMT/71S
BY CK. A.C.
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE, COLORADO
1 ffi 32 EAST CENTER STREET
MONTICELLO, UTAH
Gasmen INC.
OOC 10 HO. us-00220-CS
3-OOO2;0-VI SHT. 1 Of 1
70 72
OAK RIDGE NATIONAL LABORATORY
MANAGED BY MARTIN MARIETTA ENERGY SYSTEMS, INC.
GRAND JUNCTION OFFICE
RO. BOX 2567
GRAND JUNCTION, COLORADO 81502
JUN 2 9 1995
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, 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, 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:
Local Contact:
MS00220-CS
32 East 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
32 EAST CENTER STREET
MONTICELLO, UTAH MS00220-CS
A. R. Jones
June 1995
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY SYSTEMS, INC.
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-84OR21400
CONTENTS
LIST OF TABLES v
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
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 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 1992, RUST
Geotech, the remedial action contractor designated by DOE, performed remedial action
on the vicinity property at 32 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 32 EAST CENTER STREET
MONTICELLO, UTAH (MS00220-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
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 ofthe Environmental Assessment Group in the
Environmental Technology Section ofthe Health Sciences Research Division at Oak Ridge National Laboratory under DOE contract
DE-AC05-84OR21400 with Lockheed Martin Energy Systems, Inc.
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 commercial business located at 32 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 1995).
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 32 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
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 1995)
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 1 yd3 of mill tailings
6 inches deep. However, during the actual removal process, a total of 2 yd3 of
contaniinated earth and uranium mill tailings, 6 inches deep were removed from a 12 m2
area.
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 of the structures and the exterior, and soil sampling. Samples representative
of the bottom 15-cm (6-in.) soil layers of the excavated verification areas 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
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
structures ranged from 12 to 15 fjR/h. Exterior surface gamma measurements taken from
the excavated areas prior to backfilling ranged from 13 to 19 fjR/h.
Soil Sample Analysis
Prior to backfilling, Geotech collected a soil sample representative of the excavated
areas from the bottom 15-cm (6-in.) soil layers. Geotech's analysis of this sample shows
a 226Ra concentration of 3.7 pCi/g. 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 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 structure located on this property for a
period of approximately one year (from 1/6/93 to 1/4/94). The average annual working
level (WL) of radon progeny concentration, as determined by the Tech./Ops-Landauer
Corporation, was 0.0005, which is below the 0.03-WL guideline given in Table 1.
Excessive ventilation due to bay doors in Building #2 prevented valid RDC
measurements.
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.
REFERENCES
Geotech 1995, Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00220-CS, Address: 32 East Center Street, Monticello, Utah
84535, Geotech, Grand Junction, Colorado, January 1995.
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.
ORNL, 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual, ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
DOE ID No.: MS-00247-RS
Property Address: 17 South Third East 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 the DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
l>4 [ ] I ]
[y\ [ ] [ 1
[X] [ ] I 1
[X] [ ] [ ]
[ ] [Yl [ ]
IX] 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.
iniiiiiiim iiiiiiiiiin
SFCERTIFED SFMS-09030
DOE ID No.: MS-00247-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 the concurrence of
the U.S. Nuclear Regulatory Commission because supplemental
standards were applied per 40 CFR 192.21.
anda sby 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 the
concurrence of the U.S. Nuclear Regulatory Commission because
supplemental standards were applied per 40 CFR 192.21.
Certification Official J
U.S. Department of Energy
J3 ftb ??
Date
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00247-RS
ADDRESS: 17 SOUTH THIRD EAST STREET
MONTICELLO, UTAH 84535
APRIL 1995
Prepared for
U.S. Department of Energy
by
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
~—
Wanda S. Bustjy
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-00247-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 the EPA standards and the
DOE hot spot criteria by the DOE Remedial Action Contractor. The DOE
reviewed these evaluation results and determined that the property
contained mill tailings (residual radioactive material) exceeding the EPA
standards and the DOE hot spot criteria. The Remedial Action Contractor
was notified of the inclusion of this property into the MVP Project and was
authorized by the DOE to conduct remedial action as required to bring the
property into conformance with the EPA standards and the DOE hot spot
criteria.
1
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description;
DOE ID No.: MS-00247-RS
Property Address:
Property Owner:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
X°o?dTuction Conference
Xee°cSa' C~0n
Volume of Material Removed:
Area Cleaned Up:
MS-00247-RS
87 ?^e"° 1?,wnsite Suivey; north
iJZ ®?utJ? Tnird East Street Monticello, Utah 84535

Residential Simple (RS)
JKSM^^ * the
December 31, 1991
Rust Geotech
July 27, 1992
C™w'ey Construction, Inc.
East Route HC 63 Box 66
Monticello, Utah
June 2, 1993
July 26, 1993
Interior: 0 cubic yards
Exterior: 18 cubic yards
85 square meters (m2)
April 1995
2
DOE ID No.: MS-00247-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 remedial action process included the removal of
approximately 18 cubic yards of residual radioactive material, 6 inches
deep (Appendix Figure 2.1).
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-00247-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 1991, as described in the final REA dated
July 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 microroentgens per hour (//R/h)
to 23 //R/h (Appendix Figure 2.1). The results of analyses for
radium-226 in two composite soil samples were 1.9 picocuries
per gram (pCi/g) and 3.2 pCi/g (Appendix Table 3.1). The
composite sample representing Area V-2 included soil samples
collected from MS-00106-RS (Area V-1).
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on measurements representing an annual average, the RDC
was 0.0060 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-00247-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by the EPA standards (40 CFR 192.12, 192.20-23)
and the DOE hot spot criteria, as indicated in the Certification Data
Summary below.
Therefore, the property located at 17 South Third East Street, in
Monticello, Utah, is recommended for certification as required by the
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 //R/h to
13//R/h.
Annual average was
0.0060 WL.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background1 in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above backgroundf 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
1.9 pCi/g and 3.2 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-00247-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
DAG:03-14-95
MS-00247.RS WP52
REV053193
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00247-RS
Address: 17 South Third East Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (//R/h) Ticket No. Method* (pCi/g)
V-l 13 - 18 NAS 840 OCS 1.9
V-2 13 - 23 NAW 445 OCS 3.2
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-00247-RS
Address: 17 South Third East Street, Monticello, Utah
Instrument Type: Terradex Radtrak® Detector
Detector
Number Start Date End Date
Tracks Per
mm2
Radon
Concentration
(pCi/L)
Working
Level
3853835
3839368
3853928
01-04-94
01-04-94
01-04-94
02-01-95
02-01-95
02-01-95
10.9
12.5
13.0
1.07
1.23
1.29
0.0054
0.0062
0.0065
Annual Average: 0.0060
See Appendix Figure 2.1 for the measurement location.
8
10
30
28
26
24
22
20 -
18 -
16
14
12
Y
10
12
X
24 26 22 20 16 18 14
I I I
V-2
23
SHED
13-14
12-16
Lu
cc
DC
LU
ONE STORY
FRAME HOUSE
12-13
Lu
< Lu)
RDC
V-1
12-16
13-18
J
28
TT7 7TT
SOUTH THIRD EAST STREET
I I I
30
®
©
nv.Yi
12-15
12
v-1
16-17
oc
o
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
POST-REMEDIAL ACTION RADON DECAY-PRODUCT
CONCENTRATION MEASUREMENT LOCATION
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
20 10
SCALE IN FEET
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.
40
30
28
26
24
22
20
18
RADIOLOGICAL AS-BUILT
FIGURE 2.1
16
EXTERIOR EXTENT OF CONTAMINATION
RESIDENCE-NO. OF OCCUPANTS
HOH-flESIDEHCE-UAH-HR5./«K.
INSTRUMENT NO.
SURVEY DATE
CK. A.E. APP. BY CK. A.E. APP.
14
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE. COLORADO
£2L 17 SOUTH THIRD EAST STREET
MONTICELLO, UTAH
12
GEOTECH INC
TOTE I APPROVAL DOE "BXTT"
OOEIONO. MS-00247-RS
DWC.NO. 3-B00247-V1 ^IJ
10
10 12 14 16 18 20 22 24 26 28 30 32 34 36 38 40
OAK RIDGE NATIONAL LABORATORY GRAND JUNCTION OFFICE
RO. BOX 2567
GRAND JUNCTION, COLORADO 81502 MANAGED BY MARTIN MARIETTA ENERGY SYSTEMS, INC.
JUL 2 5 19S5
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, 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, 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:
MS00247-RS
17 South 3rd East Street
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
17 SOUTH 3RD EAST STREET
MONTICELLO, UTAH (MS00247-RS)
M. K. Jensen
July 1995
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY SYSTEMS, INC.
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-84OR21400
CONTENTS
LIST OF TABLES v
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 17 South 3rd East Street,
Monticello, Utah (MS00247-RS) 5
v
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 N. F. Lewis 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 remedial actions on off-site (vicinity) properties that had been
contaminated by radioactive material resulting from mill operations. During 1993,
RUST Geotech, the remedial action contractor designated by DOE, performed remedial
action on the vicinity property at 17 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
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 17 SOUTH 3RD EAST STREET
MONTICELLO, UTAH (MS00247-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 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-AC05-84OR21400 with Lockheed Martin Energy Systems, Inc.
3
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
house 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, 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 2 exterior verification areas.
Geotech's analysis of these samples show 226Ra concentrations of 1.9 and 3.2 pCi/g in the
composite samples. ORNL ETS obtained one of these samples and performed a
confirmatory analysis which showed a ^Ra concentration of 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.
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 house located on this property for a
period of approximately one year (from 01/04/94 to 02/01/95). The average annual
working level (WL) of radon progeny concentration, as determined by the Tech./Ops-
Landauer Corporation, was 0.0060, 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
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 ^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
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
(1007A)H, where A is the
area of the elevated region
Exposure to ^Rn
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 17 South 3rd East Street, Monticello Utah (MS00247-RS)
226Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No." No/ (cm)
MS00247X1 NAS 840 >15 2.6 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.
DOE ID No.: MS-00304-RS
Property Address: 333 Abajo 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 [ ] 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 the DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
I 1 [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
M I 1 [ 1
[VI [ ] [ ]
[VI I 1 I ]
[>] [ 1 I 1
I 1 [VT [ 1
MM [ 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.
•illllllllM lliliiiui
SFCERTIFED SFMS-09040
DOE ID No.: MS-00304-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.
!./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.
Certificatio'rTOfficial y
U.S. Department of Energy
Date
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
DOE ID NO.: MS-00304-RS
ADDRESS: 333 ABAJO DRIVE
MONTICELLO, UTAH 84535
SEPTEMBER 1995
Prepared for
U.S. Department of Energy
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
Wanfla 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-00304-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 the EPA standards and the
DOE hot spot criteria by the DOE Inclusion Survey Contractor. The DOE
reviewed these evaluation results and determined that the property
contained mill tailings (residual radioactive material) exceeding the DOE
hot spot criteria. The Remedial Action Contractor was notified of the
inclusion of this property into the MVP Project and was authorized by the
DOE to conduct remedial action as required to bring the property into
conformance with the EPA standards and the 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-00304-RS
MS-00304-RS
Location No. M-290; beginning at the SW
corner of Lot 2, Block 0, Monticello
Townsite Survey, north 250 feet, east
155.25 feet, south 250 feet, west
155.25 feet to the beginning. County of
San Juan, State of Utah
333 Abajo Drive
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
June 18, 1991
Rust Geotech
November 1, 1993
Not applicable: streamlined remediation
procedures were followed
August 18, 1992
August 19, 1992
Interior: 0 cubic yards
Exterior: 0.9 cubic yards
4.4 square meters (m2)
September 1995
2
DOE ID No.: MS-00304-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, 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-09040-BK.
The remedial action process included the removal of approximately
0.9 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-00304-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. Individual soil samples were collected for Areas V-1
through V-8 (Appendix Figure 2.1).
Interior Findings: Surface exposure-rate values, determined during
the gamma scan of the house, ranged from 12 to
82 microroentgens per hour (//R/h), as shown on Appendix Figure
2.1. Elevated exposure rates were associated with a point source
(ore sample) that was left in place at the owner's request.
Exposure rates for the rest of the house ranged from 12 to
13//R/h.
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 9 to 16//R/h (Appendix Figure 2.1).
The results of analyses for radium-226 in eight individual soil
samples ranged from 1.1 to 5.5 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 0.0039 working level (WL) for the house (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 not taken in the trailer house because it
was not associated with the contamination.
4
DOE ID No.: MS-00304-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by the EPA standards (40 CFR 192.12, 192.20-23)
and the DOE hot spot criteria, as indicated in the Certification Data
Summary below.
Therefore, the property located at 333 Abajo Drive, in Monticello, Utah,
is recommended for certification as required by the 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 for the ground
floors were 12 to
82 //R/hT for the house,
and 12 to 14 //R/h for the
trailer house.
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
0.0039 WL for the
house. Not taken in the
trailer house because it
was not associated with
the contamination.
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 ranged
from 1.7 to 2.6 pCi/g.r
Soil sample results ranged
from 1.1 to 5.5 pCi/g.
*The background exposure rate is approximately 12 //R/h.
TElevated exposure rates were due to a point source (ore sample). The rest of the
house ranged from 12 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.
5
DOE ID No.: MS-00304-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:06-25-95
MS-00304.RS WP52
REV053193
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00304-RS
Address: 333 Abajo Drive, Monticello, Utah
Exposure Soil Sample Meas. Radium-226
Area Rate (//R/h) Identifier Method" (pCi/g)
V-l 16 Deposit B OCS 1.1
V-2 16 Deposit D OCS 1.7
V-3 16 Deposit E OCS 5.5
V-4 15 Deposit F OCS 2.9
V-5 16 Deposit G OCS 4.6
V-6 16 Deposit H OCS 3.2
V-7 15 Deposit C OCS 2.6
V-8 15 Deposit A OCS 2.2
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-00304-RS
Address: 333 Abajo Drive, Monticello, Utah
Instrument Type: Terradex Radtrak* Detector
Detector
Number Start Date End Date
Tracks Per
mm2
Radon
Concentration
(pCi/L)
Working
Level
3760423
3760466
3760347
03-09-93
03-09-93
03-09-93
03-07-94
03-07-94
03-07-94
7.7
9.2
8.6
0.70
0.84
0.78
0.0035
0.0042
0.0039
Annual Average: 0.0039
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
1
12 14 1 6 18 20 22 24
T
26 28 30 32 34 36 38 40 42 44 46 48 50
I 1
j CARPORT {
L~A j
6iiR/h
12-15
F Ko
12-15
V-4
!5uR/h 6uR/h
V-5
SHED
-13
/82MR/h I I V-7 SHED
1-12
(RDC)
15uR/h
ONE STORY
FRAME HOUSE
v-2
12-13 16uR/h
SHED
11-12
LP SHED SHED
10-13 12-13
SHED
SHED 9-11
11-12
16uR/h
12-15 V-8
15/iR/h
12-15
J TRAILER HOUSE
12-14 J
UJ
ce
=> o </>
o or
Ci
L, 20 10
SCALE IN FEET
20 40
M:\FAS\03J\O0OJ\RUO0JO«V 08/30/S5 07:22am T50780
I I I I I I I
12-15
12
v-i
16-17
-X-
12 14 16 18 20
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
POST-REMEDIAL ACTION RADON DECAY-PRODUCT
CONCENTRATION MEASUREMENT LOCATION
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
POINT SOURCE WAS REMOVED BUT NOT REPLACED
POINT SOURCE LEFT IN PLACED
POINT SOURCE (ORE SAMPLE)
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.
I I I I I I I
). Of OCCUMNTt
•mmiMMT wt.
U.S. DEPARTMENT OF ENERGY
CIUNO JUHCTKM PROJECTS OFFICE. COLORADO
£fc-
333 ABAJO DRIVE
MONTICELLO, UTAH
«»•"> MS-00304-RS
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
POST OFFICE BOX 2567
GRANO JUNCTION, COLORADO 81502
PHONE: (970)24*6200
FAX: [phone]
UAR S 9 1325
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 verifica-
tion 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
MS00304-RS
333 Abajo Drive
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
333 ABAJO DRIVE
MONTICELLO, UTAH (MS00304-RS)
J. R. Sauvage
March 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 S.M. Smith 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 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,
RUST Geotech, the remedial action contractor designated by DOE, performed
remedial action on the vicinity property at 333 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. 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 333 ABAJO DRIVE
MONTICELLO, UTAH (MS00304-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 of the Monticello Vicinity Properties (MVP) Project (U.S. DOE 1990b).
•The verification of remedial action was performed by members bf ihe 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 333 Abajo 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 1995).
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 333 Abajo
Drive site. This report describes the methods and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to corifirm (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 1995)
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 (using streamlined remedial action procedures).
This property was assessed as part of block 40, therefore, the quantity of material
assessed is not available. During the actual removal process, a total of 0.9 yd3 of
contaminated earth and uranium mill tailings 0 to 6 inches deep were removed from a
4.4 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. Individual
samples representative of the bottom 15-cm (6-in.) soil layers of eight excavated
verification areas were collected. 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 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 82 uR/h. Elevated exposure rates were associated with a
point source (ore sample) that was left in place at the owner's request. Exposure rates for
the rest of the house ranged from 12 to 13 uR/h. Exterior surface gamma measurements
taken from the excavated areas prior to backfilling ranged from 15 to 16 uR/h.
Soil Sample Analysis
Prior to backfilling, Geotech collected individual soil samples representative of the
eight excavated areas from the bottom 15-cm (6-in.) soil layers. Geotech's analysis of
these samples showed 226Ra concentrations ranging from 1.1 to 5.5 pCi/g. ORNL ETS
was unable to obtain samples for confirmatory analysis. 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 one year (3/09/93 to 3/07/94). The average annual working level (WL)
of radon progeny concentration, as determined by the TechVOps-Landauer Corporation,
was 0.0039, 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
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
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)H, 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
REFERENCES
Geotech 1995. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00304-RS, Address: 333 Abajo Drive, Monticello, Utah
84535, Geotech, Grand Junction, Colorado, September 1995.
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 ofDecision
and Record of Decision Summary. U.S. Department of Energy, Grand Junction Projects
Office, Grand Junction, Colorado.
DOE ID No.: MS-00322-RS
Property Address: 48 Meadowlark Lane
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech of Energy (PQE)
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 the DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]» [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
lY] [ 1 [ 1
M [ 1 [ 1
[XI [ 1 I 1
[Y] [ ] [ ]
[ ] [>4 [ ]
[yi [ ] 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. • 1
SFCERTIFED •111
SFMS-09030
DOE ID No.: MS-00322-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 the concurrence of
the U.S. Nuclear Regulatory Commission because supplemental
standards were applied per 40 CFR 192.21.
[Xl 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
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
DOE ID NO.: MS-00322-RS
ADDRESS: 48 MEADOWLARK LANE
MONTICELLO, UTAH 84535
MAY 1995
Prepared for
U.S. Department of Energy
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
WarjtTa 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.
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-00322-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 the EPA standards and the
DOE hot spot criteria by the DOE Remedial Action Contractor. The DOE
reviewed these evaluation results and determined that the property
contained mill tailings (residual radioactive material) exceeding the EPA
standards. The Remedial Action Contractor was notified of the inclusion
of this property into the MVP Project and was authorized by the DOE to
conduct remedial action as required to bring the property into conformance
with the EPA standards and the 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-00322-RS
MS-00322-RS
Lot 7, Meadowlark Acres Subdivision, City
of Monticello, County of San Juan, State of
Utah
48 Meadowlark Lane
Monticello, Utah 84535

Residential Simple (RS)
Not applicable: spillover inclusion requested
by the Remedial Action Contractor
December 31, 1991
Rust Geotech
July 27, 1992
Crowley Construction, Inc.
East Route HC 63 Box 66
Monticello, Utah
June 2, 1993
July 19, 1993
Interior: 0 cubic yards
Exterior: 5 cubic yards
26 square meters (m2)
May 1995
2
DOE ID No.: MS-00322-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 remedial action process included the removal of
approximately 5 cubic yards of residual radioactive material, 6 inches deep
(Appendix Figure 2.1).
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-00322-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 1991, as described in the final REA dated
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, 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 microroentgens per hour (//R/h)
to 18 //R/h (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.
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on measurements representing an annual average, the RDC
was 0.0057 working level (WL), as indicated in Appendix
Table 3.2. Appendix Figure 2.1 shows the measurement location
in the lowest habitable level of the structure.
4
DOE ID No.: MS-00322-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by the EPA standards (40 CFR 192.12, 192.20-23)
and the DOE hot spot criteria, as indicated in the Certification Data
Summary below.
Therefore, the property located at 48 Meadowlark Lane, in Monticello,
Utah, is recommended for certification as required by the 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 lower level
was 11 //R/h to 13 //R/h.
Annual average was
0.0057 WL.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above backgroundt in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above backgroundf 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.*
*The background exposure rate is approximately 14//R/h.
jThe 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-00322-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
DAG:03-14-95
MS-00322.RS WP52
REV053193
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00322-RS
Address: 48 Meadowlark Lane, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (//R/h) Ticket No. Method* (pCi/g)
V-l 14-17 NAW 454 OCS 1.9
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-00322-RS
Address: 48 Meadowlark Lane, Monticello, Utah
Instrument Type: Terradex Radtrak® Detector
Radon
Detector Tracks Per Concentration Working
Number Start Date End Date mm2 (pCi/L) Level
3853866 01-04-94 12-08-94
3839288 01-04-94 12-08-94
3853808 01-04-94 12-08-94
8.3 0.95 0.0048
9.8 1.12 0.0056
11.8 1.36 0.0068
Annual Average: 0.0057
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
14
12
Y
10
•7
o fc
1 4-.
13-17
RDC
BI-LEVEL
FRAME HOUSE
11-13
\
13-16
SHED
14-16
v-1 15-18
4-17
x1 3-16
9-
SCALE IN FEET
20 10 0 20 40
o
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
nv.vi
QY.Yj
12-15
12
V-1
16-17
(RDC)
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
POST-REMEDIAL ACTION 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
RESIDENCE-NO. OF OCCUPANTS
NON—RESIDENCE—MAN—HRS./WK.
INSTRUMENT NO.
SURVEY OATE
VERIFICATION
A.E. APP. NO. DATE
1 4
U.S. DEPARTMENT OF ENERGY
GRANO JUNCTION PROJECTS OFFICE. COLORADO
S-fS 48 MEADOWLARK LANE
MONTICELLO, UTAH
12
Rust Geotech
AWM»Tlll Iiyllinnilliii
DATE APPROVAL OOE
DOC ID NO. MS-00322-RS
OWJ.NO. 3-B00322-V1 SMI 1 or 1
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 MARTIN MARIETTA ENERGY SYSTEMS, INC.
GRAND JUNCTION OFFICE
RO. BOX 2S67
GRAND JUNCTION, COLORADO 81502
JUN 2 8 1985
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, 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:
MS00322-RS
48 Meadowlark Lane
Monticello. Utah 84535

Monticello. Utah 84535
Same
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
48 MEADOWLARK LANE
MONTICELLO, UTAH (MS00322-RS)
M. K. Jensen
June 1995
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY SYSTEMS, INC.
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-84OR21400
CONTENTS
LIST OF TABLES v
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
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 and N. F. Lewis 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 remedial actions on off-site (vicinity) properties that had been
contaminated by radioactive material resulting from mill operations. During 1993,
RUST Geotech, the remedial action contractor designated by DOE, performed remedial
action on the vicinity property at 48 Meadowlark 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 48 MEADOWLARK LANE
MONTICELLO, UTAH (MS00322-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 19S9 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 197S, 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 ofthe Atomic Energy Aa, 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 ofthe Environmental Assessment Group in the
Environmental Technology Section ofthe Health Sciences Research Division at Oak Ridge National Laboratory under DOE contract
DE-AC05-84OR21400 with Lockheed Martin Energy Systems, Inc.
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 48 Meadowlark 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 199S).
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 48 Meadowlark
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 1995)
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 mill tailings 6 inches
deep. During the actual removal process, a total of 5 yd3 of contaminated earth and
uranium mill tailings, 6 inches deep were removed from a 26 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 ofthe house, a surface scan of the exterior, and soil sampling. Soil 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.
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
house ranged from 11 to 13 uR/h. Exterior surface gamma measurements taken from the
excavated areas prior to backfilling ranged from 14 to 17 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 shows a ^Ra concentration of 1.9 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
determined by the Alpha-track method. To monitor radon levels, Geotech placed three
alpha-track detectors on the ground floor of the house located on this property for a
period of approximately one year (from 01/04/94 to 12/08/94). The average annual
working level (WL) of radon progeny concentration, as determined by the Tech./Ops-
Landauer Corporation, was 0.0057, 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
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
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)
5
REFERENCES
Geotech 1995, Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00322-RS, Address: 48 Meadowlark Lane, Monticello, Utah
84535, Geotech, Grand Junction, Colorado, May 1995.
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.
ORNL, 1993. Environmental Technology Section (Formerly Pollutant Assessments
Group) Procedures Manual, ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
DOE ID No.: MS-00326-RS
Property Address: 49 West Fourth South Street
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech pf Energy fpQE)—
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 [ ] 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. [X] [ ] [ ] L>] [ 1 [ 1
In-situ [X] Lab [ ]
Interior gamma is £ 20 //R/h
above background in any
occupied or habitable
structure. [X] [ ] [ ] [j4 [ 1 II
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 11
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21. [ ] [X] [ ] [ ] [y] [ ]
Hot spot criteria met as
outlined by the DOE
guidelines for FUSRAP
(Rev. 2, March 1987). [X] [ ] [ ] hf! I I t 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.
IBlIIilillllli
SFCERTIFED
DOE ID No.: MS-00326-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
[*"] 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
DOE ID NO.: MS-00326-RS
ADDRESS: 49 WEST FOURTH SOUTH STREET
MONTICELLO, UTAH 84535
AUGUST 1995
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-00326-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 the EPA standards and the
DOE hot spot criteria by the DOE Inclusion Survey Contractor. The DOE
reviewed these evaluation results and determined that the property
contained mill tailings (residual radioactive material) exceeding the EPA
standards and the DOE hot spot criteria. The Remedial Action Contractor
was notified of the inclusion of this property into the MVP Project and was
authorized by the DOE to conduct remedial action as required to bring the
property into conformance with the EPA standards and the 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-00326-RS
MS-00326-RS
Beginning at the NE corner of Lot 3,
Block 4, Monticello Townsite Survey, west
107.25 feet, south 161 feet, east
107.25 feet, north 161 feet to the
beginning. County of San Juan, State of
Utah
49 West Fourth South Street
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
September 12, 1991
Rust Geotech
Not applicable: streamlined remediation
procedures were followed
Mountain Region Corporation
117 29 3/4 Road
Grand Junction, Colorado
August 24, 1993
August 24, 1993
Interior: 0 cubic yards
Exterior: 0.7 cubic yards
2.5 square meters (m2)
August 1995
2
DOE ID No.: MS-00326-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 0.5 cubic yards of contamination,
6 inches deep, within the property. The remedial action process included
the removal of approximately 0.7 cubic yards of residual radioactive
material, 8 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-00326-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 December 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. 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 17 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
2.5 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 0.0056 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-00326-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by the EPA standards (40 CFR 192.12, 192.20-23)
and the DOE hot spot criteria, as indicated in the Certification Data
Summary below.
Therefore, the property located at 49 West Fourth South Street, in
Monticello, Utah, is recommended for certification as required by the
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 11 to 13 //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 background1 in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above backgroundf 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
2.5 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-00326-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:06-15-95
MS-00326.RS WP52
REV053193
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00326-RS
Address: 49 West Fourth South Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range fo/R/h) Ticket No. Method* (pCi/g)
V-l 14 - 17 NCD 658 OCS 2.5
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-00326-RS
Address: 49 West Fourth South Street, Monticello, Utah
Instrument Type: Terradex Radtrak* Detector
Radon
Detector Tracks Per Concentration Working
Number Start Date End Date mm3 (pCi/L) Level
3892224 06-13-94 06-06-95
3892185 06-13-94 06-06-95
3892139 06-13-94 06-06-95
9.1 1.00 0.0050
10.8 1.19 0.0060
10.7 1.17 0.0059
Annual Average: 0.0056
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
1
12
T
14 16 18 20
i—r
22
-T
24 26 28 30 32 34 36 38 40 42 44 46 48 51
WEST FOURTH SOUTH STREET
— LLL
6X A
12-16
ONE STORY
FRAME HOUSE v-i
H-17 RDC
E \12-16 11-13
METAL
SHED FRAME
SHED
11-14 11-13
0
O
o
©
<D
12-15
12
v-i
16-17
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN j*R/h
ASSESSED AREA IDENTIFIER
AVERAGE DEPTH 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
POST-REMEDIAL ACTION RADON DECAY-PRODUCT
CONCENTRATION MEASUREMENT LOCATION
12-16
SCALE IN FEET
20 10 0 20 40
M:\FAS\033\0003\RU00326V 06/16/99 3:13pm T50760
'''i I I L_
NORTH
J 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. BUILOING. OR OTHER FUTURE IMPROVEMENT LINES
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
KtiocNct-MO. or eccuMMrs U.S. DEPARTMENT OF ENERGY
eWMO JUNCTION MtOICCTS OrriCC. CW.QNMM
49 WEST FOURTH SOUTH ST.
MONTICELLO, UTAH
Rust «HH»Ueti «••» MS-00326-RS
3-C00326-V1,
12 14 16 18 20 22 24 26 28 30 32 34 36 38 40 42 46 48 5(
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 81602
PHONE: [phone]
FAX: [phone]
KB * 9 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 verifica-
tion 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
MSQQ326
49 West 4th South Street

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
49 WEST 4TH SOUTH STREET
MONTICELLO, UTAH (MS00326-RS)
M. K. Jensen
February 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 49 West 4th South Street,
Monticello, Utah (MS00326-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 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 radioactivity, disposing of or containing the tailings in an environmentally safe
manner, and rjerfonriing remedial actions on off-site (vicinity) properties that had been
contaminated by radioactive material resulting from mill operations. During 1993,
RUST Geotech, the remedial action contractor designated by DOE, performed remedial
action on the vicinity property at 49 West 4th 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 the
ETS are described in the Environmental Technology Section Procedures Manual
(ORNL 1993).
ix
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 49 WEST 4TH SOUTH STREET
MONTICELLO, UTAH (MS00326-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 mmirnal. 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 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 49 West 4th 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 1995).
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 49 West 4th
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 (DOE
1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1995)
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 using streamlined remedial action procedures.
The pre-remedial-action survey performed by Geotech identified 0.5 yd3 of mill
tailings 6 inches deep. However, during the actual removal process, a total of 0.7 yd3
of contaminated earth and uranium mill tailings 8 inches deep were removed from a
2.5 m2 area.
A post-excavation survey was performed by Geotech 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 of the exterior, and soil sampling. A
sample representative of the bottom 15-cm (6-in.) soil layers of the excavated
verification area was 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 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 11 to 13 fiR/h. Exterior surface gamma measurements taken
from the excavated areas prior to backfilling ranged from 14 tol7 juR/h.
Soil Sample Analysis
Prior to backfilling, Geotech collected a 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.
Geotech's analysis of this sample showed a ^Ra concentration of 2.5 pCi/g. ORNL
ETS obtained this sample and performed a confirmatory analysis which showed a 226Ra
concentration of 2.0 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
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 6/13/94 to 6/06/95). 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.
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
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
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
(lOO/A)*, where A is the
area of the elevated region
Exposure to ^Rn
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 49 West 4th South Street, Monticello Utah (MS00326-RS)
226Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No." No.ft (cm)
XI NCD 658 >15 2.0 2.5
" 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 1995. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00326-RS, Address: 49 West Fourth South Street,
Monticello, Utah 84535, Geotech, Grand Junction, Colorado, August 1995.
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.
ORNL, 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
DOE ID No.: MS-00329-RS
Property Address: 164 Uranium Drive
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech pf Energy (DQE)
Ra-226 is =S 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 ma.
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 the DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
[A I 1 [ 1
[>] [ ] [ 1
[XI [ ] I ]
[>1 [ ] [ 1
[ ] [y\ [ ]
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.
111IIII11H 11111111111
SFCERTIFED SFMS-09005
DOE ID No.: MS-00329-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 the concurrence of
the U.S. Nuclear Regulatory Commission because supplemental
standards were applied per 40 CFR 192.21.
[Xi 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, Wlonticello Programs
Rust Geotech
Date
DOE EVALUATION
U.S. Department of Energy
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
DOE ID NO.: MS-00329-RS
ADDRESS: 164 URANIUM DRIVE
MONTICELLO, UTAH 84535
APRIL 1995
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-00329-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 the EPA standards and the
DOE hot spot criteria by the DOE Inclusion Survey Contractor. The DOE
reviewed these evaluation results and determined that the property
contained mill tailings (residual radioactive material) exceeding the EPA
standards and the DOE hot spot criteria. The Remedial Action Contractor
was notified of the inclusion of this property into the MVP Project and was
authorized by the DOE to conduct remedial action as required to bring the
property into conformance with the EPA standards and the DOE hot spot
criteria.
1
DOE ID No.: MS-00329-RS
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
MS-00329-RS
Location No. M-13-A; beginning north 89 degrees 21 minutes west 228 feet
from the SE corner of Lot 1, Block 5, Monticello Townsite Survey; north
89 degrees 21 minutes west 65 feet, north 00 degrees 42 minutes east
165 feet, south 89 degrees 21 minutes east 65 feet, south 00 degrees
42 minutes west 165 feet to the point of beginning. 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:
164 Uranium Drive
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
December 11, 1990
Rust Geotech
November 18, 1992
Sonderegger Inc.
P.O. Box 713
Monticello, Utah
June 14, 1993
June 22, 1993
Interior:
Exterior:
0 cubic yards
2 cubic yards
5 square meters (m2)
April 1995
2
DOE ID No.: MS-00329-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 remedial action process included the removal of
approximately 2 cubic yards of residual radioactive material, ranging from
6 inches 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-00329-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 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 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 microroentgens per hour U/R/h)
to 18 //R/h (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.
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on measurements representing an annual average, the RDC
was 0.0069 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-00329-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by the EPA standards (40 CFR 192.12, 192.20-23)
and the DOE hot spot criteria, as indicated in the Certification Data
Summary below.
Therefore, the property located at 164 Uranium Drive, in Monticello,
Utah, is recommended for certification as required by the 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 //R/h to
13 //R/h.
Annual average was
0.0069 WL.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above backgroundr in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above backgroundt 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.*
•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-00329-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:03-30-95
MS-00329.RS WP52
REV053193
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00329-RS
Address: 164 Uranium Drive, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (//R/h) Ticket No. Method* (pCi/g)
V-l 13 - 18 NAW 072 OCS 1.9
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-00329-RS
Address: 164 Uranium Drive, Monticello, Utah
Instrument Type: Terradex Radtrak* Detector
Detector
Number Start Date End Date
Tracks Per
mm2
Radon
Concentration
(pCi/L)
Working
Level
3839284
3839340
3853729
01-04-94
01-04-94
01-04-94
12-08-94
12-08-94
12-08-94
10.5
12.9
13.0
1.18
1.48
1.50
0.0059
0.0074
0.0075
Annual Average: 0.0069
See Appendix Figure 2.1 for the measurement location.
8
10
42
12 14
~i—i—r
16
1—r
18 20 22 24 26
i—r
28 30 32 34 36 38
~i—r
40 42
n—i—r
44
i—i—r
46 48
-i—r
50
42 i r i i r
40 40
38 38
36
34
32
30
28
26
24 -
22
20
r
13-15
v-i
13-18
SHED
13-15
12
RDC
ONE STORY
FRAME HOUSE
12-13
13-15
13-15 L_ J
©
<D
LV.'.vj
12-15
12
v-i
16-17
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
36
34
32
30
28
26
24
22
20
18 "777 777"
URANIUM DRIVE
16
16
14
12 -
L
SCALE IN FEET
10
20 10 0
I I I
20 40
J I I I
NORTH
THIS DRAWING IS FOR THC SOLE USE OF THE U.S. DEPARTMENT
OF ENERGY AND ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT. UTILITY LOCATION PUT, 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
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
U.S. OEPARTUENT OF ENERGY <nwo JUHCTWH Humeri pffxt, comwoo
1F 1 64 URANIUM DRIVE
MONTICELLO, UTAH
16
14
12
TT
MS-00329-RS
10
10 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 MARTIN MARIETTA ENERGY SYSTEMS, INC.
GRAND JUNCTION OFFICE
RO. BOX 2567
GRAND JUNCTION, COLORADO 81502
JUL 2 5 1895
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.
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:
MS00329-RS
164 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
164 URANIUM DRIVE
MONTICELLO, UTAH (MS00329-RS)
M. K. Jensen
July 1995
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY SYSTEMS, INC.
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-84OR21400
CONTENTS
LIST OF TABLES v
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIHCATION 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 Uranium Drive,
Monticello, Utah (MS00329-RS) 5
v
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, 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 1993,
RUST Geotech, the remedial action contractor designated by DOE, performed remedial
action on the vicinity property at 164 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 164 URANIUM DRIVE
MONTICELLO, UTAH (MS00329-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 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-AC05-84OR21400 with Lockheed Martin Energy Systems, Inc.
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 164 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 1995).
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 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 (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1995)
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 1.4 yd3 of mill
tailings 6 inches deep. However, during the actual removal process, a total of 2 yd3 of
contaminated earth and uranium mill tailings, 6 to 12 inches deep were removed from a 5
m2 area.
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 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 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 12 to 13 /iR/h. Exterior surface gamma measurements taken
from the excavated areas prior to backfilling ranged from 13 to 18 /zR/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 shows a ^Ra concentration of 1.9 pCi/g. ORNL
ETS obtained this sample and performed a confirmatory analysis which showed a mRa
concentration of 2.1 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.
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 1/4/94 to 12/8/94). The average annual working
level (WL) of radon progeny concentration, as determined by the TechVOps-Landauer
Corporation, was 0.0069, 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
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
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 164 Uranium Drive, Monticello Utah (MS00329-RS)
226Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No." No/ (cm)
MS00329X1 NAW 072 >15 2.1 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 1995, Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00329-RS, Address: 164 Uranium Drive, Monticello, Utah
84535, Geotech, Grand Junction, Colorado, April 1995.
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.
ORNL, 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
DOE ID No.: MS-00336-RS
Property Address: 416 South 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 the DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
IX] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
[y] [ 1 [ 1
M [ I I 1
I ] IX] I 1
P<] [ 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.
•iiuiiuiH mimim
SFCERTIFED SFMS-09005
DOE ID No.: MS-00336-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 the concurrence of
the U.S. Nuclear Regulatory Commission because supplemental
standards were applied per 40 CFR 192.21.
[/] 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-00336-RS
ADDRESS: 416 SOUTH FIRST WEST STREET
MONTICELLO, UTAH 84535
MAY 1995
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-00336-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 taiiings 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 the EPA standards and the
DOE hot spot criteria by the DOE Inclusion Survey Contractor. The DOE
reviewed these evaluation results and determined that the property
contained mill tailings (residual radioactive material) exceeding the DOE
hot spot criteria. The Remedial Action Contractor was notified of the
inclusion of this property into the MVP Project and was authorized by the
DOE to conduct remedial action as required to bring the property into
conformance with the EPA standards and the DOE hot spot criteria.
1
DOE ID No.: MS-O0336-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-00336-RS
Location No. M-26; beginning at the
NE corner of Lot 4, Block 5, Monticello
Townsite Survey; west 134.5 feet, south
174 feet, east 134.5 feet, north 174 feet
to the point of beginning, County of
San Juan, State of Utah
416 South First West Street
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
February 26, 1991
Rust Geotech
November 18, 1992
Sonderegger Inc.
P.O. Box 713
Monticello, Utah
June 14, 1993
June 21, 1993
Interior:
Exterior:
0 cubic yards
6 cubic yards
18 square meters (m2)
May 1995
2
DOE ID No.: MS-00336-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 remedial action process included the removal of
approximately 6 cubic yards of residual radioactive material, ranging from
8 inches 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-00336-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 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 a composite
sample representing the verification area (Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 10 microroentgens per hour (//R/h)
to 21 //R/h (Appendix Figure 2.1). The result of analysis for
radium-226 in one composite soil sample was 1.1 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 0.0045 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-00336-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by the EPA standards (40 CFR 192.12, 192.20-23)
and the DOE hot spot criteria, as indicated in the Certification Data
Summary below.
Therefore, the property located at 416 South First West Street, in
Monticello, Utah, is recommended for certification as required by the
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 //R/h to
13//R/h.
Annual average was
0.0045 WL.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above backgroundT in the
15-cm surface layer,
averaged over 100 m3.
Shall not exceed 15 pCi/g
above backgroundf 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
1.1 pCi/g.*
•The background exposure rate is approximately 13 //R/h.
fThe 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-00336-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:03-30-95
MS-O0336.RS WP52
REV053193
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00336-RS
Address: 416 South First West Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (//R/h) Ticket No. Method* (pCi/g)
V-l 13 - 21 NAW 074 OCS 1.1
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-00336-RS
Address: 416 South First West Street, Monticello, Utah
Instrument Type: Terradex Radtrak* Detector
Radon
Detector Tracks Per Concentration Working
Number Start Date End Date mm2 (pCi/L) Level
3853856 01-04-94 01-10-95
3853955 01-04-94 01-10-95
3839318 01-04-94 01-10-95
10.0 1.04 0.0052
8.4 0.88 0.0044
7.6 0.78 0.0039
Annual Average: 0.0045
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
1
16 18 20 22 24 26 28 30 32
r i—r
34 36 38 40 42 44 46 48 5(
i—r
WEST FOURTH SOUTH STREET
r 10 12-15
v-i
13-21
ROC
ONE STORY
FRAME HOUSE
12-13
12-15
V-1 SHED
12-14 13-21
L--_-_J
SHED SHED
10-13 12-14
12-15
L J
SCALE IN FEET
20
J I
40
J l
NORTH
in
3
O
<D
r7..vi
|V.-.VJ
12-15
12
v-i
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
POST-REMEDIAL ACTION RADON DECAY-PRODUCT
CONCENTRATION MEASUREMENT LOCATION
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
THIS DRAWING IS FOR THE SOLE USE OF THC 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. BUILOING. OR OTHER FUTURE IMPROVEMENT LINES.
U.S. DEPARTMENT OF ENERGY
CJUHO JUNCTION MOJECTS OFflCC. COLORADO
416 SOUTH FIRST WEST STREET
MONTICELLO, UTAH
MS-00336-RS
3-C00336-V1 M 1 » 1
16 18 20 22 24 26 28 30 32 34 36 38 40 42 44 46 48 5(
OAK RIDGE NATIONAL LABORATORY
MANAGED BY MARTIN MARIETTA ENERGY SYSTEMS, INC.
GRAND JUNCTION OFFICE
RO. BOX 2567
GRAND JUNCTION, COLORADO 81502
JUL 2 5 1995
Ms. Mary Arm 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:
MS00336-RS
416 South 1st West 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
416 SOUTH 1ST WEST STREET
MONTICELLO, UTAH (MS00336-RS)
M. K. Jensen
July 1995
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY SYSTEMS, INC.
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-84OR21400
CONTENTS
LIST OF TABLES v
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 416 South 1st West
Street, Monticello, Utah (MS00336-RS) 6
v
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, 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 1993,
RUST Geotech, the remedial action contractor designated by DOE, performed remedial
action on the vicinity property at 416 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. 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 416 SOUTH 1ST WEST STREET
MONTICELLO, UTAH (MS00336-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 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-AC05-84OR21400 with Lockheed Martin Energy Systems, Inc.
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 416 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 1995).
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 416 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 (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1995)
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 3.4 yd3 mill tailings 6
inches deep. However, during the actual removal process, a total of 6 yd3 of contaminated
earth and uranium mill tailings, 8 to 10 inches deep were removed from a 18 m2 area.
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 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 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 21 //R/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 shows a 2MRa concentration of 1.1 pCi/g. ORNL ETS
obtained this sample 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. As a result of a meeting between the RAC and
the IVC on May 26, 1994, anomalous gamma 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 before this procedure change. The IVC
observed that 21 uR/h exceeds 30% of the excavation average of 15 uR/h. The IVC will
allow a correlation developed by the RAC to estimate the JJSRa pCi/g concentrations based
on gamma exposure rates. The anomalous reading of 21 uR/h on this property using the
RAC's correlation yields a w*Ra 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 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 one year (from 1/4/94 to 1/10/95). The average annual working
level (WL) of radon progeny concentration, as determined by the TechVOps-Landauer
Corporation, was 0.0045, 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
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 ^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
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)
6
Table 2. Results of ORNL analysis of Geotech soil samples
from 416 South 1st West Street, Monticello Utah (MS00336-RS)
ORNL Geotech
sample sample
No." No.*
MS00336X1 NAW 074
Depth
(cm)
>15
'Ra concentration (pCi/g)
ORNL Geotech
1.8 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 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 1995, Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00336-RS, Address: 416 South First West Street, Monticello,
Utah 84535, Geotech, Grand Junction, Colorado, May 1995.
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.
ORNL, 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
DOE ID No.: MS-00345-VL
Property Address: 380 South Main 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 the DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
I ] [ ] [X]
(Vacant Lot)
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
Del [ I I 1
[XI t ] [ I
[ ] [ ]
t ] [ ] txi t ] [ ] iy\
(Vacant Lot)
[ ] [y\ [ 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 oamma
exposure rates that do not exceed 30 percent above normal background. • SFCERTIFED
Illlllll
SFMS-09007
DOE ID No.: MS-00345-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. Btfsb /anda S. Busby Date
Manager, Monticello Programs
Rust Geotech
DOE EVALUATION
[yj 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
'est?-
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
DOE ID NO.: MS-00345-VL
ADDRESS: 380 SOUTH MAIN STREET
MONTICELLO, UTAH 84535
JUNE 1995
Prepared for
U.S. Department of Energy
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
Wapfla S~Bifsby
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
SjB£tiQQ 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-00345-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 the EPA standards and the
DOE hot spot criteria by the DOE Inclusion Survey Contractor. The DOE
reviewed these evaluation results and determined that the property
contained mill tailings (residual radioactive material) exceeding the EPA
standards and the DOE hot spot criteria. The Remedial Action Contractor
was notified of the inclusion of this property into the MVP Project and
was authorized by the DOE to conduct remedial action as required to bring
the property into conformance with the EPA standards and the 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-00345-VL
MS-00345-VL
Location Nos. M-35 and M-37; beginning at
the northeast corner of Lot 1, Block 7,
Monticello Townsite Survey, Plat A, west
157 feet, south 128.5 feet, east 57 feet,
south 86 feet, east 100 feet, north
214.5 feet to the point of beginning.
County of San Juan, State of Utah
380 South Main Street
Monticello, Utah 84535

Vacant Lot (VL)
Oak Ridge National Laboratory
June 19, 1990
Rust Geotech
May 26, 1992
DLB Unlimited Inc.
P.O. Box 740
Dove Creek, Colorado
September 16, 1992
September 29, 1992
Interior: 0 cubic yards
Exterior: 0.4 cubic yards
0.9 square meters (m2)
June 1995
2
DOE ID No.: MS-00345-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 Block MS-09007-BK.
The remedial action process included the removal of approximately
0.4 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
3.0 VERIFICATION SUMMARY
DOE ID No.: MS-00345-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 October 1991, as described in the final REA
dated May 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 16 microroentgens per
hour OyR/h), as indicated on Appendix Figure 2.1. The result of
analysis for radium-226 in one individual soil sample was
2.8 picocuries per gram (pCi/g), as indicated in Appendix
Table 3.1.
4
DOE ID No.: MS-00345-VL
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by the EPA standards (40 CFR 192.12, 192.20-23)
and the DOE hot spot criteria, as indicated in the Certification Data
Summary below.
Therefore, the property located at 380 South Main Street, in
Monticello, Utah, is recommended for certification as required by the
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 result was
2.8 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.
5
DOE ID No.: MS-00345-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
DAG:04-26-95
MS-00345.VL WP52
REV053193
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00345-VL
Address: 380 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 NAW 404 OCS 2.8
See Appendix Figure 2.1 for the verification area.
"OCS = Opposed Crystal System
7
36
34
32
30
28
26
24
22
20
18
16
14
12
10
) 12 14
-1—i—i—T
16 18 20 22
i—i—i—i—i—r
24 26 28 30 32 34
T"
36 38
n—r
40 42 44 46 48 51
o
12-15
O
12-15
SHED
J' 12-13
O
12-15
L J
G X 6 Jl 2
v-i
13-1
Ui or
t~ co
z <
I
t~
O
<D
iv.-.vj
12-15
mi
V-1
16-17
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN /jR/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
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
WEST FOURTH SOUTH STREET
SCALE IN FEET
20 10 0 20 40
M:\rAS\03J\000J\RM00J45V 03/07/96 2:34pm T5O780
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.
J L
12
J L
3g
U.S. DEPARTMENT OF ENERGY
CKAND JUNCTION HKMtCTS Of UCC. COLONAOO
£2!
380 SOUTH MAIN STREET
MONTICELLO, UTAH
•*•» MS-00345-VL
14 16 18 20 22 24 26 28 30 32 34 36 38 40 42 44 46
3-C00345-V1,
48 5(
OAK RIDGE NATIONAL LABORATORY
MANAGEP BY MARTIN MARIETTA ENERGY SYSTEMS, INC.
GRAND JUNCTION OFFICE
RO. BOX 2567
GRAND JUNCTION, COLORADO 81502
MAR 2 « 190Q
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, 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:
Location Address:
Property Owner:
Owner Address:
MS00345-VL
380 South Main 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
380 SOUTH MAIN STREET
MONTICELLO, UTAH (MS00345-VL)
A. R. Jones
February 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-AC05-84OR21400
CONTENTS
LIST OF TABLES vi
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
v
LIST OF TABLES
1 Applicable guidelines for protection against radiation 4
2 Results of ORNL analysis of Geotech soil samples from 380 South Main Street,
Monticello, Utah (MS00345-VL) 5
vi
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. K. Jensen 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 radioactivity, disposing of or containing the tailings in an environmentally safe
manner, and rjerforrning 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 380 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 during an earlier review were resolved. 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 380 SOUTH MAIN STREET
MONTICELLO, UTAH (MS00345-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) 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-AC05-84OR21400 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 vacant lot located at 380 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 contarnination, backfilled with uncontaminated material, and
restored to a condition comparable to that which existed prior to remedial action
(Geotech 1995).
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 380 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 (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1995)
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 mill tailings 6
inches deep. This property was assessed as part of Block 7, therefore the quantity of
mill tailings assessed is not available. During the actual removal process, a total of
0.4 yd3 of contaminated earth and uranium mill tailings, 12 inches deep were removed
from a 0.9 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. An individual sample representative of the bottom 15 cm soil layers
of the excavated verification area was collected.
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 gamma exposure rate measurements taken by Geotech from the excavated
areas prior to backfilling ranged from 13 to 16 fjRfh.
Soil Sample Analysis
Prior to backfilling, Geotech collected an individual soil sample representative of
the excavated areas from the bottom 15-cm (6-in.) soil layers. Geotech's analysis of
this sample showed a ^Ra concentration of 2.8 pCi/g. ORNL ETS obtained this sample
and performed a confirmatory analysis which showed a ^Ra concentration of 2.5 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 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.
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 during an earlier review were
resolved in a meeting between the RAC and ORNL on July 21, 1995 and a letter to G.
A. Pierce from R. K. Johnson dated August 30, 1995, MS00345-VL, Comment
Resolution. 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
concentration 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
concentration 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
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)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 380 South Main Street, Monticello Utah (MS00345-VL)
ORNL Geotech
sample sample
No.fl No.*
MS00345 XI NAW 404
Depth
(cm)
>15
'Ra concentration (pCi/g)
ORNL Geotech
" 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 1995. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE RO NO: MS00345-VL, Address: 380 South Main Street, Monticello,
Utah 84535, Geotech, Grand Junction, Colorado, June, 1995.
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.
ORNL, 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
DOE ID No.: MS-00347-RS
Property Address: 81 West 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 =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 the DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [1 [ ]
[X] [ ] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
[/111 I 1
[XI I 1 t 1
[ ] [ ] [X] [ ] [ 1 l#
(Trailer House)
M [X] [ ]
[X] [ ] [ ]
I 1 W [ 1
Df] [ 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.
•IIIIIIIMH lllllllllll
SFCERTIFED SFMS-09007
DOE ID No.: MS-00347-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 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.
Manager, Monticello Programs
Rust Geotech
Date
DOE EVALUATION
U.S. Department of Energy
PROPERTY COMPLETION REPORT
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
DOE ID NO.: MS-00347-RS
ADDRESS: 81 WEST THIRD SOUTH STREET
MONTICELLO, UTAH 84535
MAY 1995
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-00347-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 the EPA standards and the
DOE hot spot criteria by the DOE Inclusion Survey Contractor. The DOE
reviewed these evaluation results and determined that the property
contained mill tailings (residual radioactive material) exceeding the EPA
standards and the DOE hot spot criteria. The Remedial Action Contractor
was notified of the inclusion of this property into the MVP Project and was
authorized by the DOE to conduct remedial action as required to bring the
property into conformance with the EPA standards and the 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-00347-RS
MS-O0347-RS
Location No. M-42-2; beginning at the NW
corner of Block 7, Monticello Townsite
Survey, south 90 feet, east 147.5 feet,
north 90 feet, west 147.5 feet to point of
beginning. County of San Juan, State of
Utah
81 West Third South Street
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
February 21, 1991
Rust Geotech
May 26, 1992
DLB Unlimited Inc.
P.O. Box 740
Dove Creek, Colorado
September 16, 1992
October 7, 1992
Interior: 0 cubic yards
Exterior: 3 cubic yards
12 square meters (m2)
May 1995
2
DOE ID No.: MS-00347-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, 12 inches deep,
within the property. The remedial action process included the removal of
approximately 3 cubic yards of residual radioactive material, 8 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-00347-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 October 1991, as described in the final REA
dated May 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, 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 21 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
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 in the trailer house due to
excessive ventilation caused by no permanent foundation.
4
DOE ID No.: MS-00347-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by the EPA standards (40 CFR 192.12, 192.20-23)
and the DOE hot spot criteria, as indicated in the Certification Data
Summary below.
Therefore, the property located at 81 West Third South Street, in
Monticello, Utah, is recommended for certification as required by the
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 trailer house
was 11 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 backgroundT 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.**
•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-00347-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
DAG:04-26-95
MS-00347.RS WP52
REV053193
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00347-RS
Address: 81 West Third South Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (//R/h) Ticket No. Method" (pCi/g)
V-l 15-21 NAX 734 OCS 2.4
See Appendix Figure 2.1 for the verification area.
"OCS = Opposed Crystal System
7
10
30
12 14 16 18 20 22 24 26 28 30 32 34 36 38 40
30
28
26
24 Ld
Lul or
i—
— CO
CO
UJ
22
20
18
CO
ct:
o
CO
N
WEST THIRD SOUTH STREET
/// ///
777
® O
<D
L....I
12-15 TRAILER
HOUSE
11-13
12 11-14
SHED
11 — 13 v-i
16-7
V-1
15-21 E
SHED
1 1 T 1 3
o
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
28
26
24
22
20
18
16
14
12
Y
10
20
SCALE IN FEET
10 0 20
J L
40
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
16
RESIDENCC-NO. OF OCCUPANTS
N0N-RESIDENCE-UAN-HR5./WK.
INSTRUMENT NO.
SURVEY OATE
8T CK. A.E. APP. NO. OATC CK. A.E. APP.
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE, COLORADO
81 WEST THIRD SOUTH STREET
MONTICELLO, UTAH
APPROVAL
Rust Qeotech
APPROVAL OOE
OOE io NO. MS-00347-RS
QWO.NO. 3-B00347-V1 SHT 1 or 1
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
MANAGED BY MARTIN MARIETTA ENERGY SYSTEMS, INC.
GRAND JUNCTION OFFICE
RO. BOX 2567
GRANO JUNCTION, COLORADO 81502
AUG 3 1 1995
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.
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: MS00347
Location Address: 81 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
81 WEST 3RD SOUTH STREET
MONTICELLO, UTAH (MS00347-RS)
A. R. Jones
August 1995
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY SYSTEMS, INC.
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-84OR21400
CONTENTS
LIST OF TABLES v
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
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 N. F. Lewis 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
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, RUST
Geotech, the remedial action contractor designated by DOE, performed remedial action on
the vicinity property at 81 West 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 the ETS are
described in the Environmental Technology Section Procedures Manual (ORNL 1993).
ix
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 81 WEST 3RD SOUTH STREET
MONTICELLO, UTAH (MS00347-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 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 of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE contract
DE-AC05-84OR21400 with Lockheed Martin Energy Systems, Inc.
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 single family residence located at 81 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
1995).
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 81 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
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 1995)
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 mill tailings 12
inches deep. During the actual removal process, a total of 3 yd3 of contaminated earth and
uranium mill tailings, 8 inches deep were removed from a 12 m2 area.
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 of the structure, a surface scan 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
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 11 to 13 /iR/h. Exterior surface gamma measurements taken from
the excavated areas prior to backfilling ranged from 15 to 21 //R/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 2.4 pCi/g. ORNL ETS
was unable to obtain a 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). As a result of a meeting between the RAC and the D7C 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 before this procedure change. The IVC observed that VI exceeds 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 anomalous reading of 21
uR/h on this property using the RAC's correlation yields a ^Ra 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 not spot guideline of 25 m2, for subsurface samples.
Radon Measurement Results
No radon decay-product concentration (RDC) measurements were taken for this site
due to excessive ventilation in the trailer house with no permanent foundation.
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 ^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
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
(1007A)*, 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
REFERENCES
Geotech 1995, Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00347-RS, Address: 81 West 3rd South Street, Monticello,
Utah 84535, Geotech, Grand Junction, Colorado, May 1995.
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.
ORNL, 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
DOE ID No.: MS-00363-RS
Property Address: 248 South Second East 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 the DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
RUST Geotech Inc.
YES NO NOT TAKEN
[X]* [ ] [ ]
U.S. Department
of Energy (DOE)
YES NO NOT TAKEN
\/i [ 1 [ 1
[X] [ ] [ ] tA] [ ] [ ]
[ ] [ ] IX] [ ] [ 1
(Building Removed)
[ ] [ ] [X] [ 1 [ ]
(Building Removed)
[ ] [X] [ ] [ ] lx]
[X
[ )
[X] [ ] [ ] DO [ ] [ ]
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showino 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 iifliiuiiii
SFCERTIFED
SFMS-09012
DOE ID No.: MS-00363-RS
RUST GEOTECH INC. RECOMMENDATION
Based on the RUST Geotech Inc. 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.
[)<| 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 Inc.
DOE EVALUATION
Date
U.S. Department of Energy
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00363-RS
ADDRESS: 248 SOUTH SECOND EAST STREET
MONTICELLO, UTAH 84535
JANUARY 1995
Prepared for
U.S. Department of Energy
RUST Geotech Inc. 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 Inc.
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-00363-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 the EPA standards and the
DOE hot spot criteria by the DOE Remedial Action Contractor. The DOE
reviewed these evaluation results and determined that the property
contained mill tailings (residual radioactive material) exceeding the EPA
standards. The Remedial Action Contractor was notified of the inclusion
of this property into the MVP Project and was authorized by the DOE to
conduct remedial action as required to bring the property into conformance
with the EPA standards and the 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-00363-RS
MS-00363-RS
Beginning 70 feet north of the SE corner of
Lot 1, Block 12, Monticello Townsite
Survey; west 144.5 feet, north 70 feet,
east 144.5 feet, south 70 feet to beginning,
County of San Juan, State of Utah
248 South Second East Street
Monticello, Utah 84535

Residential Simple (RS)
Not applicable: spillover inclusion requested
by the Remedial Action Contractor
March 27, 1991
RUST Geotech Inc.
June 14, 1991
Sonderegger Inc.
P.O. Box 713
Monticello, Utah
September 30, 1991
December 4, 1991
Interior: 0 cubic yards
Exterior: 281 cubic yards
1,044 square meters (m*)
January 1995
2
DOE ID No.: MS-O0363-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 to 12 inches
deep, within the property. The remedial action process included the
removal of approximately 281 cubic yards of residual radioactive material,
ranging from 8 inches 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-0O363-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 RUST Geotech Inc. during
June 1990, as described in the final REA dated June 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. 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 microroentgens per hour U/R/h)
to 20 //R/h (Appendix Figure 2.1). The results of analyses for
radium-226 in nine composite soil samples ranged from
3.8 picocuries per gram (pCi/g) to 5.1 pCi/g (Appendix Table 3.1).
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
No RDC measurements were taken in the house because it was
removed during remedial action.
4
DOE ID No.: MS-00363-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by the EPA standards (40 CFR 192.12, 192.20-23)
and the DOE hot spot criteria, as indicated in the Certification Data
Summary below.
Therefore, the property located at 248 South Second East Street, in
Monticello, Utah, is recommended for certification as required by the
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: building
was removed.
Not applicable: building
was removed.
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 3.8 pCi/g to
5.1 pCi/g.f
*The background radium-226 concentration is approximately 2.0 pCi/g.
tThe hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-00363-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:01-06-95
MS-00363.RS WP52
REV053193
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00363-RS
Address: 248 South Second East Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (//R/h) Ticket No. Method* (pCi/g)
V-l 14 - 20 NAA 736 OCS 4.3
V-2 14-16 NAA 737 OCS 3.8
V-3 14 - 20 NAA 738 OCS 5.0
V-4 14-17 NAA 739 OCS 4.7
V-5 13 - 17 NAA 740 OCS 5.1
V-6 14 - 17 NAA 741 OCS 4.2
V-7 13 - 16 NAA 742 OCS 4.1
V-8 13-19 NAA 743 OCS 4.1
V-9 14-16 NAA 744 OCS 4.0
See Appendix Figure 2.1 for the verification areas.
*OCS = Opposed Crystal System
7
10
30
12 14 16 18 20 22 24 26 28 30 32 34 36 38 40
28
26
24
22
20
18
16
14
12
Y
10
<D
8 •. V-3 V-2
1 9 j.. .1
V-6 V-9 14-20 4-16
14-17 14-16
12
12
£3 ' ONE
1 STORY
| FRAME
. HOUSE"*"
12
•••••
12 V-1
V-4 V-5 V-8 V-7 8 •» • 14-20
'•'•'•\
14-17 13-17 3-19 13-16
SCALE IN FEET
20 10 0
RM00363V 01/10/95 TMT/712
X
20 40 NORTH
UJ
UJ or
i—
CO
I—
CO <
o o
UJ
CO
3
o
CO
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
©
<D
iv.-.vj
12-15
12
v-1
16-17
-X-
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN pR/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
HOUSE WAS REMOVED DURING REMEDIAL
ACTION
- 26
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
RESIDCHCE-HO. Of OCCUPANTS
HON—RESIDENCE—MAN—HRS,/WK.
INSTRUMENT NO.
VERIFICATION
IT CK. A.E. APP. NO. OATC CK. A.C. APP.
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE, COLORADO
Yr
^3.
OATI
)-9s' 248 SOUTH SECOND EAST ST.
MONTICELLO, UTAH
APPR6VAL
GEOIECH INC
OATE I APPROVAL DOE •DATT-
OOEIONO. MS-00363-RS
DWG.NO. 3-B00363-V1 SMT 1 „ 1
10 12 14 16 18 20 22 24 26 28 30 32 34 36 38 40
OAK RIDGE NATIONAL LABORATORY
MANAGED BY MARTIN MARIETTA ENERGY SYSTEMS, INC.
GRAND JUNCTION OFFICE
RO. BOX 2567
GRAND JUNCTION. COLORADO 81502
APR I 7 1995
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, 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/IVC Project Manager
Environmental Assessment Group
Location Number:
Location Address:
MS00363-RS
248 South 2nd East 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
248 SOUTH 2ND EAST STREET
MONTICELLO, UTAH MS00363-RS
N. F. Lewis
April 1995
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
MARTIN MARIETTA ENERGY SYSTEMS, INC.
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-84OR21400
CONTENTS
LIST OF TABLES v
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 South 2nd East Street,
Monticello, Utah (MS00363-RS) 5
v
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. 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 remedial actions on off-site (vicinity) properties that had been
contaminated by radioactive material resulting from mill operations. During 1991, RUST
Geotech, the remedial action contractor designated by DOE, performed remedial action on
the vicinity property at 248 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
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 248 SOUTH 2ND EAST STREET
MONTICELLO, UTAH (MS00363-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
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 (Abramiuk 1989).
•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-AC05-84OR21400 with Martin Marietta Energy Systems, Inc.
2
During 1991, 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 248 South 2nd East Street, Monticello, Utah. A
structure was previously located on this property, but was removed during the
remediation. 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 1995).
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 248 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 corifirm (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 1990).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1995)
indicates the property was remediated as evaluated by DOE on the basis of Environmental
Protection Agency standards and the DOE guidelines (DOE 1990). 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. However, during the actual removal process, a total of 281 yd3 of
contaminated earth and uranium mill tailings, 8 to 12 inches deep were removed from a
1,044 m2 area.
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
exterior and soil sampling. Samples representative of the bottom 15-cm (6-in.) soil layers
of 9 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
Exterior surface gamma exposure rate measurements taken from the excavated areas
prior to backfilling ranged from 13 to 20 /^R/h.
Soil Sample Analysis
Prior to backfilling, Geotech collected a soil sample representative of the excavated
areas from the bottom 15-cm (6-in.) soil layers. Geotech's analysis of these samples
showed ^Ra concentrations ranging from 3.8 to 5.1 pCi/g in the composite samples.
ORNL ETS obtained a percentage of these samples and performed a confirmatory analysis
which showed ^Ra concentrations ranging from 2.1 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. 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
No radon decay-product concentration (RDC) measurements for this site were taken
because the building was 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.
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)*, 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 1990)
5
Table 2. Results of ORNL analysis of Geotech soil samples
from 248 South 2nd East Street, Monticello Utah (MS00363-RS)
2MRa concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No." No^ (cm)
MS00363X2 NAA 737 >15 2.1 3.8
MS00363X5 NAA 740 >15 2.6 5.1
MS00363X8 NAA 743 >15 2.2 4.1
" 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
Abramiuk I. N.et al. 1989. Monticello Remedial Action Project Site Analysis Report, GJ-
10, prepared by Bendix Field Engineering Corporation, Grand Junction, Colorado, for the
U.S. Department of Energy, Surplus Facilities Management Program, Richland,
Washington.
Geotech 1995, Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00363-RS, Address: 248 South 2nd East Street, Monticello,
Utah 84535, Geotech, Grand Junction, Colorado, January 1995.
U.S. DOE 1990. 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.
ORNL, 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
DOE ID No.: MS-00364-RS
Property Address: 264 South Second East Street
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
RUST Geotech Inc. of Enemy (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 [ ]
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 the DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
tV] [ ] [ ]
[V] [ ] [ ]
[V] [ ] [ 1
[ ] [yi [ ]
[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.
Ililllllllll Illlllll
SFCERTIFED SFMS-09012
DOE ID No.: MS-00364-RS
RUST GEOTECH INC. RECOMMENDATION
Based on the RUST Geotech Inc. 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.
[V] 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 Inc.
DOE EVALUATION
U.S. Department of Energy
PROPERTY COMPLETION REPORT
DOE ID NO.: MS-00364-RS
ADDRESS: 264 SOUTH SECOND EAST STREET
MONTICELLO, UTAH 84535
JANUARY 1995
Prepared for
U.S. Department of Energy
RUST Geotech Inc. 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 Inc.
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-00364-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 the EPA standards and the
DOE hot spot criteria by the DOE Inclusion Survey Contractor. The DOE
reviewed these evaluation results and determined that the property
contained mill tailings (residual radioactive material) exceeding the EPA
standards. The Remedial Action Contractor was notified of the inclusion
of this property into the MVP Project and was authorized by the DOE to
conduct remedial action as required to bring the property into conformance
with the EPA standards and the DOE hot spot criteria.
1
DOE ID No.: MS-00364-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-00364-RS
Beginning 170 feet south of the NE corner
of Lot 4, Block 12, Monticello Townsite
Survey, Plat A; west 154.5 feet, south
30 feet, east 10 feet, south 89 feet, east
144.5 feet, north 119 feet to beginning,
County of San Juan, State of Utah
264 South Second East Street
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
June 19, 1990
RUST Geotech Inc.
June 14, 1991
Sonderegger Inc.
P.O. Box 713
Monticello, Utah
September 30, 1991
December 4, 1991
Interior: 0 cubic yards
Exterior: 354 cubic yards
1,514 square meters (m2)
January 1995
2
DOE ID No.: MS-00364-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 remedial action process included the removal of
approximately 354 cubic yards of residual radioactive material, ranging
from 6 inches 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-00364-RS
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 RUST Geotech Inc. during
June 1990, as described in the final REA dated June 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. 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 microroentgens per hour (//R/h)
to 20 //R/h (Appendix Figure 2.1). The results of analyses for
radium-226 in 16 composite soil samples ranged from
2.2 picocuries per gram (pCi/g) to 8.9 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 0.0025 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 basement was uninhabitable.
4
DOE ID No.: MS-00364-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by the EPA standards (40 CFR 192.12, 192.20-23)
and the DOE hot spot criteria, as indicated in the Certification Data
Summary below.
Therefore, the property located at 264 South Second East Street, in
Monticello, Utah, is recommended for certification as required by the
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 //R/h to
17//R/h.
Annual average was
0.0025 WL.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above backgroundf 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 2.2 pCi/g to
8.9 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-
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:01-06-95
MS-O0364.RS WP52
REV053193
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00364-RS
Address: 264 South Second East Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range Gt/R/h) Ticket No. Method* (pCi/g)
V-l
V-2
V-3
V-4
V-5
V-6
V-7
V-8
V-9
V-10
V-ll
V-12
V-13
V-14
V-15
V-16
14
13
14
14
13
14
13
13
13
13
14
14
13
16
16
13
20
20
19
18
17
19
17
14
17
16
20
18
16
17
19
19
NAP 086
NAP 087
NAP 088
NAP 089
NAP 090
NAP 091
NAP 092
NAP 093
NAP 094
NAP 095
NAP 096
NAP 097
NAP 098
NAP 099
NAP 100
NAP 101
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
6.9
8.9
3.3
5.9
4.7
5.7
4.9
3.2
5.8
5.3
5.6
6.4
4.3
7.1
5.7
2.2
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-00364-RS
Address: 264 South Second East Street, Monticello, Utah
Instrument Type: Terradex Radtrak® Detector
Radon
Detector Tracks Per Concentration Working
Number Start Date End Date mm2 (pCi/L) Level
3688270 10-06-92 10-19-93
3688288 10-06-92 10-19-93
3688257 10-06-92 10-19-93
6.2 0.56 0.0028
6.0 0.54 0.0027
4.7 0.42 0.0021
Annual Average: 0.0025
See Appendix Figure 2.1 for the measurement location.
8
10
30
12 14 16 18 20 22 24 26 28 30 32 34 36
T
38 40
30
28
26
24
22
20
18
16
14
12 -
Y
V-1 6
13-19 18
V-12
V-10 V-1 1 14-18
13-16 14-20
V-15
•A 10 16-19 10 X6
ONE STORY
FRAME HOUSE
W/UN IN HABITABLE
BASEMENT
V-13 X
13-16
13-17 ( 6 V-14
V-9 RDC 16-17
13-17
10
"H1 . v V-
(•:: A © 0 V-2 V.\
V-7 V-6 13-20
V-3
0: 13-17 14-19
14-19 8
V-1
V-8 V-5 14-20
V-4 13-14 13-17
14-18
©
FA-.VI
rv.-.vj
12-15
12
v-1
16-17
LU
ZY.
I—
if)
CO
<
o o
LU
s 00
^ X
r-
=5
o
CO
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
POST-REMEDIAL ACTION 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
10
SCALE IN FEET
20 10 0 20
RM00364V 01/10/95 TMT/712
J I I I L
40
X
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.
RESIDENCE-NO. OF OCCUPANTS
NON-RESIDENCE-MAN-MRS./WK.
INSTRUMENT NO.
SURVEY OATC
CK. A.E. APP.
14
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE, COLORADO
rr 264 SOUTH SECOND EAST ST.
MONTICELLO, UTAH
12
APPROVAL
GEOTECH INC
DATE I APPROVAL OOE •Btfr
OOEIDNO. MS-00364-RS
PWS.NO. 3-B00364-V1 SHT 1 or 1
10
10 12 14 16 18 20 22 24 26 28 30 32 34 36 38 40
OAK RIDGE NATIONAL LABORATORY
MANAGED BY MARTIN MARIETTA ENERGY SYSTEMS, INC.
GRAND JUNCTION OFFICE
RO. BOX 2567
GRAND JUNCTION. COLORADO 81502
APR 2 7 BB5
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, 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:
Location Address:
Property Owner:
Owner Address:
Tenant Name:
MS00364-RS
264 South 2nd East 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
264 SOUTH 2ND EAST STREET
MONTICELLO, UTAH MS00364-RS
N. F. Lewis
April 1995
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
MARTIN MARIETTA ENERGY SYSTEMS, INC.
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-84OR21400
CONTENTS
LIST OF TABLES v
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 264 South 2nd East Street,
Monticello, Utah (MS00364-RS) 5
v
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. 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 remedial actions on off-site (vicinity) properties that had been
contaminated by radioactive material resulting from mill operations. During 1991, RUST
Geotech, the remedial action contractor designated by DOE, performed remedial action on
the vicinity property at 264 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
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 264 SOUTH 2ND EAST STREET
MONTICELLO, UTAH (MS00364-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 of the
Monticello Vicinity Properties (MVP) Project (Abramiuk 1989).
•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-AC05-84OR21400 with Martin Marietta Energy Systems, Inc.
2
During 1991, 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 264 South 2nd 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
1995).
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 264 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 of the entire property that is to be certified and (2) that the remedial action
reduced contamination to below applicable DOE guidelines (DOE 1990).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1995)
indicates the property was remediated as evaluated by DOE on the basis of Environmental
Protection Agency standards and the DOE guidelines (DOE 1990). 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. However, during the actual removal process, a total of 354 yd3 of contaminated
earth and uranium mill tailings, 6 to 18 inches deep were removed from a 1,514 m2 area.
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 of the structures and a suface scan of the exterior and soil sampling. Samples
representative ofthe bottom 15-cm (6-in.) soil layers of 16 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 of the
residence ranged from 13 to 17 /iR/h. Exterior surface gamma measurements taken from
the excavated areas prior to backfilling ranged from 13 to 20 /iR/h.
Soil Sample Analysis
Prior to backfilling, Geotech collected soil samples representative ofthe excavated
areas from the bottom 15-cm (6-in.) soil layers. Geotech's analysis of these samples
showed ^6Ra concentrations ranging from 2.2 to 8.9 pCi/g in the composite samples.
ORNL ETS obtained a percentage of these samples and performed a confirmatory analysis
which showed ^Ra concentrations ranging from 2.6 to 5.0 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
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 10/6/92 to 10/19/93). The average annual
working level (WL) of radon progeny concentration, as determined by the Tech./Ops-
Landauer Corporation, was .0025, 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
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)H,whereAisthe
area of the elevated region.
Exposure to 222Rn Average annual radon proge- 0.03 WL
progeny ny concentration (including
background)
(DOE 1990)
5
Table 2. Results of ORNL analysis of Geotech soil samples
from 225 South 2nd East street, Monticello Utah (MS00364-RS)
22*Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No." No^ (cm)
MS00364X3 NAP 088 >15 2.6 3.3
MS00364X6 NAP 091 >15 3.3 5.7
MS00364X10 NAP 095 >15 4.0 5.3
MS00364X15 NAP 100 >15 5.0 5.7
" 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 Geotech, and these samples were blended to form a composite soil
sample, which represents an average over one of the verification areas.
6
REFERENCES
Abramiuk I. N.et al. 1989. Monticello Remedial Action Project Site Analysis Report, GJ-
10, prepared by Bendix Field Engineering Corporation, Grand Junction, Colorado, for the
U.S. Department of Energy, Surplus Facilities Management Program, Richland,
Washington.
Geotech 1995, Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00364-RS, Address: 264 South 2nd East Street, Monticello,
Utah 84535, Geotech, Grand Junction, Colorado, January 1995.
U.S. DOE 1990. 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.
ORNL, 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
DOE ID No.: MS-00367-CS
Property Addresses: 233 and 249 South First 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 [ ]
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 the DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
[>] [ ] [ 1
[)<][] [ ]
MM [ ]
I ] [ 1
W [ 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.
Ililllllllll •llllllllll
SFCERTIFED SFMS-09012
DOE ID No.: MS-00367-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.
[>] 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-00367-CS
ADDRESSES: 233 AND 249 SOUTH FIRST EAST STREET
MONTICELLO, UTAH 84535
MARCH 1995
Prepared for
U.S. Department of Energy
by
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
Wa
Manager,
LBusby
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
i
DOE ID No.: MS-00367-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 the EPA standards and the
DOE hot spot criteria by the DOE Remedial Action Contractor. The DOE
reviewed these evaluation results and determined that the property
contained mill tailings (residual radioactive material) exceeding the EPA
standards and the DOE hot spot criteria. The Remedial Action Contractor
was notified of the inclusion of this property into the MVP Project and was
authorized by the DOE to conduct remedial action as required to bring the
property into conformance with the EPA standards and the DOE hot spot
criteria.
1
DOE ID No.: MS-00367-CS
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:
MS-00367-CS
Location No. M-85-1; beginning 100 feet
east of the NW corner of Block 12,
Monticello Townsite Survey; east
104.5 feet, south 214.5 feet, east 80 feet,
south 74.5 feet, west 177.25 feet, north
13.5 feet, west 107.25 feet, north
189.5 feet, east 100 feet, north 86 feet to
beginning, County of San Juan, State
of Utah
233 and 249 South First East Street
Monticello, Utah 84535

Commercial Structure (CS)
Not applicable: inclusion requested by the
Remedial Action Contractor
March 27, 1991
Rust Geotech
June 14, 1991
Sonderegger Inc.
P.O. Box 713
Monticello, Utah
October 16, 1991
December 4, 1991
Interior: 0 cubic yards
Exterior: 69 cubic yards
339 square meters (m2)
March 1995
2
2.0 OPERATIONS SUMMARY
DOE ID No.: MS-00367-CS
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 inches to 18 inches deep, within the property. The remedial action
process included the removal of approximately 69 cubic yards of residual
radioactive material, ranging from 6 inches 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-00367-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 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. 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 11 microroentgens per hour (//R/h)
to 24 //R/h (Appendix Figure 2.1). The results of analyses for
radium-226 in five composite soil samples ranged from
3.6 picocuries per gram (pCi/g) to 5.7 pCi/g (Appendix Table 3.1).
The composite sample representing Area V-5 included soil samples
collected from MS-00365-RS (Area V-1).
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on measurements representing annual averages, the RDCs
were 0.0049 working level (WL) for the house, and 0.0025 WL for
the trailer house (Appendix Table 3.2). Appendix Figure 2.1
shows the measurement location on each ground floor (the lowest
habitable level of each structure). RDC measurements were not
taken in the building due to excessive ventilation caused by
missing windows and exterior doors; therefore, this building was
verified according to exterior standards.
4
DOE ID No.: MS-00367-CS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by the EPA standards (40 CFR 192.12, 192.20-23)
and the DOE hot spot criteria, as indicated in the Certification Data
Summary below.
Therefore, the property located at 233 and 249 South First East Street,
in Monticello, Utah, is recommended for certification as required by the
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.*
Syrvey Results
Ranges for the ground
floors were 12 //R/h to
14 //R/h for the house,
and 15 //R/h to 17 //R/h
for the trailer house.
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 averages were
0.0049 WL for the
house, and 0.0025 WL
for the trailer house.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background1 in the
15-cm surface layer,
averaged over 100 ma.
Shall not exceed 15 pCi/g
above backgroundr 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 pCi/g to
5.7 pCi/g.*
*The background exposure rate is approximately 16 //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-00367-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
SJW:01-06-95
MS-00363.CS WP52
REV053193
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00367-CS
Addresses: 233 and 249 South First East Street, Monticello, Utah
The analytical uncertainties in the table are reported at the 95-percent confidence
interval.
Exposure- Soil
Rate Range Sample Meas. Radium-226 Potassium Thorium
Area (//R/h) Ticket No. Method* (pCi/g) (pCi/g) (pCi/g)
V-l 17 - 24 NAO 333 OCS 5.7
V-2 16 - 20 NAO 334 OCS 5.1
V-3 14 - 24 NAO 340 OCS 3.6
V-4 14 - 19 NAO 341 OCS 5.0
V-5 17-20 NAO 342 AL 4.8 ± 0.7 22.9 ± 3.2 1.0 ± 0.3
See Appendix Figure 2.1 for the verification areas.
*AL = Analytical Laboratory; OCS = Opposed Crystal System
7
Table 3.2
Radon Decay-Product Concentration Measurement Results
DOE ID No.: MS-00367-CS
Addresses: 233 and 249 South First East Street, Monticello, Utah
Instrument Type: Terradex Radtrak® Detector
Radon
Detector Tracks Per Concentration Working
Number Start Date End Date mm2 (pCi/L) Level
HOUSE
3853869
3842557
3842430
10-19-93
10-19-93
10-19-93
10-11-94
10-11-94
10-11-94
8.2
10.8
8.7
0.89
1.13
0.91
0.0045
0.0057
0.0046
3688065
3688046
3688219
10-05-92
10-05-92
10-05-92
TRAILER HOUSE
10-19-93
10-19-93
10-19-93
5.5
5.9
5.3
Annual Average: 0.0049
0.49
0.53
0.48
0.0025
0.0027
0.0024
Annual Average: 0.0025
See Appendix Figure 2.1 for the measurement locations.
8
52
50
46
46
44
42
40
38
36
34
32
30
28
26
24
22
20
18
16
14
12
10
1
12 14 16 IB 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 1 1 1 1 1 1 1 1 1 1 1 1 I 1 I 1 1 1 1 1 I I I I I 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
EAST SECOND SOUTH STREET
LU.
r
V-4
14-19
14-17
14-17
UNINHABITABLE
ONE STORY
CINDER BLOCK
BUILDING
11-12
V-J
14-24
V-5
14-24
1 I
-0®
^16-20
TRAILERr
HOUSE 1 < 14-17
ONE
STORY
STUCCO
HOUSE
12-14 SHED
15-17
RDC
12-15
V-4
14-19
6 I 6 X C
14-17
V-5
17-20
=7¥
©
<D
V-1
IS-17
(RDJ)
JLECEJU2
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
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
SCALE IN FEET
L X
J L
20 10
I l_
NORTH
J I L
THIS DRAWING IS FOR THE SOU USE OF THE U.S. DEPARTMENT
OF ENERGY ANO ITS CONTRACTORS. IT IS NOT A LAND SURVCT
FLAT, UTILITY LOCATION PLAT, OR OTHER IMPROVEMENT SURVEY
PLAT AND IS HOT TO BE RCUEO UPON FOR THE ESTABLISHMENT
OF FENCE. BUILDING. OR OTHER FUTURE IMPROVEMENT LINES.
J I J L
KSNW[-W. or QCCUPMrtt
iimtr MTT
VCnflCATKM
A.E. APP. NO. DATE
MNOOMTV cj/e»/t« nn/m
CK. A.E. APP.
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE, COLORADO
233 AND 249 SOUTH FIRST EAST STREET
MONTICELLO, UTAH
GaoncH INC.
OOt 10 NO Hs_00367-CS
0»C. BO. 3_DQ0jB7_vi SHT , „, ,
12 14 22 38 40 48 50 52 54 68 70 72
OAK RIDGE NATIONAL LABORATORY
MANAGED BY MARTIN MARIETTA ENERGY SYSTEMS, INC.
GRAND JUNCTION OFFICE
RO. BOX 2567
GRAND JUNCTION, COLORADO 81502
MAY j l 1895
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. 0. Box 2567
Grand Junction, 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:
Tenant Name:
MS00367
233 and 249 South 1st East Street
Monticello. Utah 84535

Blue Mountain Trailer Court
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
233 AND 249 SOUTH 1ST EAST STREET
MONTICELLO, UTAH MS00367-CS
N. F. Lewis
May 1995
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
MARTIN MARIETTA ENERGY SYSTEMS, INC.
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-84OR21400
CONTENTS
LIST OF TABLES v
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 233 and 249 South 1 st East
Street, Monticello, Utah (MS00367-CS) 5
v
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site
Deconimissioning Projects, U.S. Department of Energy. The author wishes to
acknowledge M. K. Jensen for analysis of soil samples and M. K. Jensen and xxx 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 1991, RUST
Geotech, the remedial action contractor designated by DOE, performed remedial action
on the vicinity property at 233 and 249 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 233 AND 249 SOUTH 1ST EAST STREET
MONTICELLO, UTAH (MS00367-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
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 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 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 (Abramiuk 1989).
*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-AC05-84OR21400 with Martin Marietta Energy Systems, Inc.
2
During 1991, 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 trailer park located at 233 and 249 South 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
1995).
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 233 and 249
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
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 1990).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1995)
indicates the property was remediated as evaluated by DOE on the basis of
Environmental Protection Agency standards and the DOE guidelines (DOE 1990).
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 18
inches deep. However, during the actual removal process, a total of 69 yd3 of contaminat-
ed earth and uranium mill tailings, 6 to 12 inches deep were removed from a 339 m2 area.
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 of the structures and a surface scan of the exterior and soil sampling.
Samples representative of the bottom 15-cm (6-in.) soil layers of 5 excavated verification
areas were collected and blended to form representative composite soil samples for each
verification area.
3
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
house ranged from 12 to 14 //R/h and 15 to 17 //R/h for the trailer house. Exterior
surface gamma measurements taken from the excavated areas prior to backfilling ranged
from 14 to 24 //R/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 5 exterior verification areas.
Geotech's analysis of these samples showed ^Ra concentrations ranging from 3.6 to 5.7
pCi/g in the composite sample. ORNL ETS obtained one of these samples and performed
a confirmatory analysis which showed a ^Ra concentration of 5.3 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). 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. This
property was remediated before this procedure change. The IVC observed that
verification areas VI & V3 exceed 30% of the excavation average. The IVC will allow a
correlation developed by the RAC to estimate 226 Ra pCi/g concentrations based on
gamma exposure rates. The anomalous reading of 24 uR/h on this property using the
RAC's correlation yields a ^Ra. 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. 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 house and trailer house located on this
property for a period of approximately one year (from 10/19/93 to 10/11/94 for the house
and 10/05/92 to 10/19/93 for the trailer house). The average annual working level (WL)
of radon progeny concentration, as determined by the Tech./Ops-Landauer Corporation,
was 0.0049 for the house and 0.0025 for the trailer house, which is 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
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 ^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
Maximum Permissible
concentration of Ra226 in soil
above background level, for
areas less than 25 m2.
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.
Exposure to 222Rn Average annual radon proge- 0.03 WL
progeny ny concentration (including
background)
(DOE 1990)
6
Table 2. Results of ORNL analysis of Geotech soil samples
from 233 and 249 South 1st East Street, Monticello Utah (MS00367-CS)
^Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No." No^ (cm)
MS00367X1 NAO 333 >15 5.3 5.7
" 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 Geotech, and these samples were blended to form a composite soil
sample, which represents an average over one of the verification areas.
7
REFERENCES
Abramiuk I. N.et al. 1989. Monticello Remedial Action Project Site Analysis Report, GJ-
10, prepared by Bendix Field Engineering Corporation, Grand Junction, Colorado, for the
U.S. Department of Energy, Surplus Facilities Management Program, Richland,
Washington.
Geotech 1995, Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00367-CS, Address: 233 and 249 South 1st East Street,
Monticello, Utah 84535, Geotech, Grand Junction, Colorado, March 1995.
U.S. DOE 1990. 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.
ORNL, 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
DOE ID No.: MS-00368-RS
Property Address: 217 South First East Street
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
RUST Geotech Inc. 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 //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 the DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
[X]* [ ] [ ]
[X] t 1 [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
[>d [ 1 t ]
W [ 1 I 1
[Xl [ ] [ ]
[VI [ ] [ 1
[ ] [>] [ 1
[/] 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.
lillllllllll llltllllllli
SFCERTIFED SFMS-09012
DOE ID No.: MS-00368-RS
RUST GEOTECH INC. RECOMMENDATION
Based on the RUST Geotech Inc. 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.
[XI 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 Inc.
DOE EVALUATION
Date
U.S. Department of Energy
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00368-RS
ADDRESS: 217 SOUTH FIRST EAST STREET
MONTICELLO, UTAH 84535
JANUARY 1995
Prepared for
U.S. Department of Energy
by
RUST Geotech Inc.
P.O. Box 14000
Grand Junction, Colorado 81502-5504
Wan^S. Busby
Manager, Monticello Programs
RUST Geotech Inc. 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-00368-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 the EPA standards and the
DOE hot spot criteria by the DOE Remedial Action Contractor. The DOE
reviewed these evaluation results and determined that the property
contained mill tailings (residual radioactive material) exceeding the EPA
standards and the hot spot criteria. The Remedial Action Contractor was
notified of the inclusion of this property into the MVP Project and was
authorized by the DOE to conduct remedial action as required to bring the
property into conformance with the EPA standards and the DOE hot spot
criteria.
1
DOE ID No.: MS-00368-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-00368-RS
Beginning at the NW corner of Lot 3,
Block 12, Monticello Townsite Survey; east
100 feet, south 86 feet, west 100 feet,
north 86 feet to beginning, County of
San Juan, State of Utah
217 South First East Street
Monticello, Utah 84535

Residential Simple (RS)
Not applicable: inclusion requested by the
Remedial Action Contractor
March 27, 1991
RUST Geotech Inc.
June 14, 1991
Sonderegger Inc.
P.O. Box 713
Monticello, Utah
October 16, 1991
December 4, 1991
Interior: 0 cubic yards
Exterior: 81 cubic yards
402 square meters (m2)
January 1995
2
DOE ID No.: MS-00368-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 to 15 inches
deep, within the property. The remedial action process included the
removal of approximately 81 cubic yards of residual radioactive material,
ranging from 6 inches 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-00368-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 RUST Geotech Inc. during
June 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. 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 microroentgens per hour (//R/h)
to 20 //R/h (Appendix Figure 2.1). The results of analyses for
radium-226 in five composite soil samples ranged from
3.0 picocuries per gram (pCi/g) to 5.3 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 0.0056 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).
The basement was uninhabitable.
4
DOE ID No.: MS-00368-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by the EPA standards (40 CFR 192.12, 192.20-23)
and the DOE hot spot criteria, as indicated in the Certification Data
Summary below.
Therefore, the property located at 217 South First East Street, in
Monticello, Utah, is recommended for certification as required by the
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 11 //R/h to
12//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 backgroundf in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above backgroundf in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
< 5 pCi/g above
background.1
Soil sample results
ranged from 3.0 pCi/g to
5.3 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-00368-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:01-06-95
MS-00368.RS WP52
REV053193
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00368-RS
Address: 217 South First East Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (//R/h) Ticket No. Method* (pCi/g)
V-l 14 - 20 NAO 335 OCS 3.0
V-2 16 - 20 NAO 336 OCS 3.0
V-3 17 - 20 NAO 337 OCS 3.4
V-4 16 - 20 NAO 338 OCS 5.2
V-5 16 - 19 NAO 339 OCS 5.3
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-00368-RS
Address: 217 South First East Street, Monticello, Utah
Instrument Type: Terradex Radtrak* Detector
Radon
Detector Tracks Per Concentration Working
Number Start Date End Date mm2 (pCi/L) Level
3688249 10-05-92 10-19-93
3688209 10-05-92 10-19-93
3688230 10-05-92 10-19-93
10.1 0.91 0.0046
11.3 1.02 0.0051
15.4 1.40 0.0070
Annual Average: 0.0056
See Appendix Figure 2.1 for the measurement location.
8
10
30
28
26
24
22
20
18
16 -
14 -
12 -
Y
10
12
Ld
UJ or
i—
CO
CO
<
Ld
h-
CO
or
z>
o
CO
1 4 16 18 20 22 24
EAST SECOND SOUTH STREET
26
LL
Y ®
V-4
16-20
0
V-2
0 16-20
V-3
7-20
51
RDC
m V-1
ONE STORY
STUCCO HOUSE
W/UNINHAB.
BASEMENT
14-20
14-17
11-12
>
7 • 3
•
V-5 14-17
I 12
J 16-19
c
SCALE IN FEET
20 10 0
RM00368V 01/18/95 TMT/712
X
I I I L
20 40 NORTH
28
ONE STORY
CINDER BLOCK
BUILDING
ADDRESSED UNDER
MS-00367-CS
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
®
®
FT.-.vl
LV.-.vj
12-15
12
v-1
16-17
(RDC)
32 34 36 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
POST-REMEDIAL ACTION 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
RESIDENCE-NO. OF OCCUPANTS
HOH-RESIOEHCC-UAN-HRS./WK.
INSTRUMENT NO.
SURVEY DATE
ar CK. A.E. APP. NO. OATE
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE, COLORAOO
rr
OATE__
217 SOUTH FIRST EAST STREET
MONTICELLO, UTAH
APPROVAL
GEOTECH INC
sac APPROVAL 66t TATT
OOEONO. MS-00368-RS
DWG.NO. 3-B00368-V1 ,HT 1 Dr 1
30
28
26
24
22
20
18
1 6
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 MARTIN MARIETTA ENERGY SYSTEMS, INC.
GRAND JUNCTION OFFICE
RO. BOX 2567
GRAND JUNCTION, COLORADO 81502
APR 2 7 19flS
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, 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:
Location Address:
MS00368-RS
217 South 1st East Street
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
217 SOUTH 1ST EAST STREET
MONTICELLO, UTAH MS00368-RS
N. F. Lewis
April 1995
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
MARTIN MARIETTA ENERGY SYSTEMS, INC.
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-84OR21400
CONTENTS
LIST OF TABLES v
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 217 South 1st East Street,
Monticello, Utah (MS00368-RS) 5
v
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. 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 remedial actions on off-site (vicinity) properties that had been
contaminated by radioactive material resulting from mill operations. During 1991, RUST
Geotech, the remedial action contractor designated by DOE, performed remedial action on
the vicinity property at 217 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 217 SOUTH 1ST EAST STREET
MONTICELLO, UTAH (MS00368-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 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 (Abramiuk 1989).
•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-AC05-84OR21400 with Martin Marietta Energy Systems, Inc.
2
During 1991, 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 217 South 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 1995).
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 217 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
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 1990).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1995)
indicates the property was remediated as evaluated by DOE on the basis of Environmental
Protection Agency standards and the DOE guidelines (DOE 1990). 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 15
inches deep. However, during the actual removal process, a total of 81 yd3 of contaminat-
ed earth and uranium mill tailings, 6 to 12 inches deep were removed from a 402 m2 area.
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 of the structures and a suface scan of the exterior and soil sampling. Samples
representative of the bottom 15-cm (6-in.) soil layers of 5 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 of the
residence ranged from 11 to 12 /iR/h. Exterior surface gamma measurements taken from
the excavated areas prior to backfilling ranged from 14 to 20 /iR/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. Geotech's analysis of these samples
showed 226Ra concentrations ranging from 3.0 to 5.3 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 3.8 to 5.1 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.
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 10/05/92 to 10/19/93). The average annual
working level (WL) of radon progeny concentration, as determined by the Tech./Ops-
Landauer Corporation was 0.0056, 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
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
concentrations in soil
for Hot Spot areas
Maximum permissible con-
centration 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.
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.
Exposure to 222Rn Average annual radon proge- 0.03 WL
progeny ny concentration (including
background)
(DOE 1990)
5
Table 2. Results of ORNL analysis of Geotech soil samples
from 217 South 1st East Street, Monticello Utah (MS00368-RS)
^Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No." No^ (cm)
MS00368X1 NAO 335 >15 3.8 3.0
MS00368X4 NAO 338 >15 5.1 5.2
° 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 Geotech, and these samples were blended to form a composite soil
sample, which represents an average over one of the verification areas.
6
REFERENCES
Abrarniuk I. N.et al. 1989. Monticello Remedial Action Project Site Analysis Report, GJ-
10, prepared by Bendix Field Engineering Corporation, Grand Junction, Colorado, for the
U.S. Department of Energy, Surplus Facilities Management Program, Richland,
Washington.
Geotech 1995, Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00368-RS, Address: 217 South 1st East Street, Monticello,
Utah 84535, Geotech, Grand Junction, Colorado, January 1995.
U.S. DOE 1990. 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.
ORNL, 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
DOE ID No.: MS-00369-RS
Property Address: 180 East Second South Street
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
I/] [ 1 I 1
(Xl [ ] [ 1
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
RUST Geotech Inc. 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 [ ]
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 5 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 the DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
Lx] [ ] [ ]
M [ 1 I 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.
llllllllll
SFCERTIFED SFMS-09012
DOE ID No.: MS-00369-RS
RUST GEOTECH INC. RECOMMENDATION
Based on the RUST Geotech Inc. 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.
[Xl 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 Inc.
Date
DOE EVALUATION
U.S. Department of Energy
PROPERTY COMPLETION REPORT
DOE ID NO.: MS-00369-RS
ADDRESS: 180 EAST SECOND SOUTH STREET
MONTICELLO, UTAH 84535
JANUARY 1995
Prepared for
U.S. Department of Energy
RUST Geotech Inc. 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 Inc.
P.O. Box 14000
Grand Junction, Colorado 81502-5504
TABLE OF CONTENTS
Section Pape
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-00369-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 the EPA standards and the
DOE hot spot criteria by the DOE Remedial Action Contractor. The DOE
reviewed these evaluation results and determined that the property
contained mill tailings (residual radioactive material) exceeding the EPA
standards. The Remedial Action Contractor was notified of the inclusion
of this property into the MVP Project and was authorized by the DOE to
conduct remedial action as required to bring the property into conformance
with the EPA standards and the 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-00369-RS
MS-00369-RS
Beginning at the NE corner of Block 12,
Monticello Townsite Survey; south
170 feet, west 154.5 feet, north 170 feet,
east 154.5 feet to beginning, County of
San Juan, State of Utah
180 East Second South Street
Monticello, Utah 84535

Residential Simple (RS)
Not applicable: spillover inclusion requested
by the Remedial Action Contractor
March 27, 1991
RUST Geotech Inc.
June 14, 1991
Sonderegger Inc.
P.O. Box 713
Monticello, Utah
October 3, 1991
December 4, 1991
Interior: 0 cubic yards
Exterior: 358 cubic yards
1,862 square meters (m2)
January 1995
2
DOE ID No.: MS-00369-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). A portion of exterior assessed Area A
(crawl space of House 2) was verified according to interior standards.
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 to
18 inches deep, within the property. The remedial action process included
the removal of approximately 358 cubic yards of residual radioactive
material, ranging from 6 inches 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-00369-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 RUST Geotech Inc. during
June 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 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 of House 2, ranged from 17 microroentgens per
hour (//R/h) to 24 //R/h for the remediated portion of the crawl
space, and 15 //R/h to 17 //R/h for the ground floor (Appendix
Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 13 //R/h to 24 //R/h (Appendix
Figure 2.1). The results of analyses for radium-226 in
19 composite soil samples ranged from 2.0 picocuries per
gram (pCi/g) to 10.0 pCi/g (Appendix Table 3.1). The composite
samples representing Areas V-17 and V-19 included soil samples
collected from the House 2 crawl space excavation (Areas V-20
and V-21, respectively).
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on measurements representing annual averages, RDCs were
0.0065 working level (WL) for House 1, and 0.0084 WL for
House 2 (Appendix Table 3.1). Appendix Figure 2.1 shows the
measurement locations on the ground floors (the lowest habitable
level of each structure).
4
DOE ID No.: MS-00369-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by the EPA standards (40 CFR 192.12, 192.20-23)
and the DOE hot spot criteria, as indicated in the Certification Data
Summary below.
Therefore, the property located at 180 East Second South Street, in
Monticello, Utah, is recommended for certification as required by the
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 for the ground
floors were 12 //R/h to
15 //R/h for House 1 and
15//R/h to 17 //R/h for
House 2. Range was
17//R/h to 24//R/h for
the remediated portion of
the crawl space of
House 2.
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.
Averages were
0.0065 WL for House 1
and 0.0084 WL for
House 2.
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 m3.
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 pCi/g to
10.0 pCi/g.*
*The background exposure rate is approximately 15 //R/h.
TThe 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-00369-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 Interior and Exterior Extent of Contamination -
RADIOLOGICAL AS-BUILT
SJW:01-06-95
MS-00369.RS WP52
REV053193
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00369-RS
Address: 180 East Second South Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (pR/h) Ticket No. Method* (pCi/g)
EXTERIOR
V-l 13 - 19 NAP 144 OCS 2.5
V-2 14 - 19 NAP 145 OCS 2.9
V-3 13 - 17 NAP 146 OCS 4.1
V-4 14 - 19 NAP 147 OCS 6.8
V-5 14-19 NAP 148 OCS 10.0
V-6 13 - 19 NAP 149 OCS 5.8
V-7 13 - 19 NAP 043 OCS 4.6
V-8 13 - 19 NAP 044 OCS 3.2
V-9 15 - 19 NAP 045 OCS 4.8
V-10 13 - 17 NAP 046 OCS 7.9
V-ll 13 - 17 NAP 047 OCS 5.7
V-12 13 - 15 NAP 048 OCS 8.0
V-13 13 - 19 NAP 049 OCS 8.1
V-14 15 - 19 NAP 050 OCS 6.8
V-15 15 - 19 NAP 051 OCS 3.1
V-16 17 - 20 NAP 052 OCS 2.0
V-17 17 - 20 NAP 053 OCS 3.5
V-18 15 - 24 NAP 054 OCS 5.9
V-19 17 - 24 NAP 055 OCS 7.7
INTERIOR
V-20 17 - 20 Not applicable
V-21 17 - 24 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-00369-RS
Address: 180 East Second South Street, Monticello, Utah
Instrument Type: Terradex Radtrak*1 Detector
Radon
Detector Tracks Per Concentration Working
Number Start Date End Date mm2 (pCi/L) Level
HOUSE 1
3687981
3688047
3688022
10-19-92
10-19-92
10-19-92
10-19-93
10-19-93
10-19-93
13.9
13.4
13.7
1.31
1.26
1.29
0.0066
0.0063
0.0065
HOUSE 2
Annual Average: 0.0065
3688043
3688006
3688021
10-05-92
10-05-92
10-05-92
10-19-93
10-19-93
10-19-93
18.7
17.8
19.1
1.70
1.62
1.74
0.0085
0.0081
0.0087
Annual Average: 0.0084
See Appendix Figure 2.1 for the measurement locations.
8
42
40
38
36
34
32
30
28
26
24
22
20
18
16
14
12
10
1
12 14 16 18 20 22 24 26 28 30 32 34 36
i—r i—r
38 40 42 44 46 48 51
i—r
CRAWL SPACE
20 10
SCALE IN FEET
20
J L
12
EAST SECOND SOUTH STREET
LU
V-1 V-2
13-19 14-19 ft
(6 14-17
V-4
.'.1 0 14-19
15-19
V-3
13-17
TWO STORY
FRAME
HOUSE 1
V-10 0 13-17 pa GARAGE
14-15 0 12-15
RDC
V-5 V-11
0 V-6 14-19 13-17 0:::::y 13-19
V-12
14-17 3-15
I2>.-
O
0 14-17
ONE STORY
MODULAR
HOUSE 2
15-17
SEE
DETAIL A
V-13
13-19
0
V -16 <D ROC
17-20
18
0 V- 17 0 17-20 V-14 V-15
0a> 15-19 15-19
V-18 V-19
17-24 15-24
V-21
17-24
V-20
0 *3 i*e> 17-20
DETAIL A
NOT TO SCALE
in <
o o
UI
m
I
i-
3
O
in
®
<D
rv.vTi
LV.vj
12-15
12
v-i
16-17
(ROC;
i£GJEM!
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 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
/bo -7*So
UJ Lii> lfl 1 » Q
0a1BI +5.15- -uf'/l~
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 SE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE, BUILDING, OR OTHER FUTURE IMPROVEMENT LINES
14 16 18 20
_J L
22 24
J |_
26
3H
U.S. OEPARTUENT OF ENERGY
ID JUNCTION PNOJCCn OmCf. COLOMBO
LS2
MAUD J
180 EAST SECOND SOUTH ST.
MONTICELLO. UTAH
«•»• MS-00369-RS
28 30 32 34 36 38 40 42 44 46 48 5(
OAK RIDGE NATIONAL LABORATORY
MANAGED BY MARTIN MARIETTA ENERGY SYSTEMS, INC.
GRAND JUNCTION OFFICE
RO. BOX 2567
GRAND JUNCTION. COLORADO 81502
APR £8 1085
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, 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: MS00369-RS
Location Address: 180 East 2nd 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
180 EAST 2ND SOUTH STREET
MONTICELLO, UTAH MS00369-RS
N. F. Lewis
April 1995
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
MARTIN MARIETTA ENERGY SYSTEMS, INC.
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-84OR21400
CONTENTS
LIST OF TABLES v
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 180 East 2nd South Street,
Monticello, Utah (MS00369-RS) 6
v
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. 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 remedial actions on off-site (vicinity) properties that had been
contaniinated by radioactive material resulting from mill operations. During 1991, RUST
Geotech, the remedial action contractor designated by DOE, performed remedial action on
the vicinity property at 180 East 2nd 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 the ETS are
described in the Environmental Technology Section Procedures Manual (ORNL 1993).
ix
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 180 EAST 2ND SOUTH STREET
MONTICELLO, UTAH (MS00369-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 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 ofthe 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 (Abramiuk 1989).
*Thc 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-AC05-84OR21400 with Martin Marietta Energy Systems, Inc.
2
During 1991, 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 180 East 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 restored to
a condition comparable to that which existed prior to remedial action (Geotech 1995).
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 East 2nd
South Street site. This report describes the methods and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to corifirm (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 1990).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1995)
indicates the property was remediated as evaluated by DOE on the basis of Environmental
Protection Agency standards and the DOE guidelines (DOE 1990). 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 of mill tailings 6 to
18 inches deep. However, during the actual removal process, a total of 358 yd3 of
contaminated earth and uranium mill tailings, 6 to 12 inches deep were removed from a
1,862 m2 area.
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 ofthe structures and a suface scan of the exterior and soil sampling. Samples
representative ofthe bottom 15-cm (6-in.) soil layers of 19 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 of the
residence ranged from 12 to 15 //R/h for House 1 and 15 to 17 //R/h for House 2. The
gamma exposure rate range was 17 to 24 //R/h for the remediated portion of the crawl
space of House 2. Exterior surface gamma measurements taken from the excavated areas
prior to backfilling ranged from 13 to 24 //R/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. Geotech's analysis of these samples
showed ^Ra concentrations ranging from 2.0 to 10:0 pCi/g in the composite samples.
ORNL ETS ETS obtained a percentage of these soil samples and performed a
confirmatory analysis, which showed ^Ra concentrations ranging from 3.1 to 8.3 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
determined 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 one year (from 10/19/92 to 10/19/93 for House 1 and from
10/5/92 to 10/19/93 for House 2). The average annual working level (WL) of radon
progeny concentrations, as determined by the Tech./Ops-Landauer Corporation were
0.0065 for House 1 and 0.0084 for House 2, which are 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
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 ^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
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
(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 1990)
6
Table 2. Results of ORNL analysis of Geotech soil samples
from 180 East 2nd South Street, Monticello Utah (MS00369-RS)
2MRa concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No." No* (cm)
MS00369X6 NAP 149 >15 4.9 5.8
MS00369X9 NAP 045 >15 6.5 4.8
MS00369X12 NAP 048 >15 8.3 8.0
MS00369X16 NAP 052 >15 3.1 2.0
MS00369X19 NAP 055 >15 7.9 7.7
" 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 Geotech, and these samples were blended to form a composite soil
sample, which represents an average over one of the verification areas.
7
REFERENCES
Abramiuk I. N.et al. 1989. Monticello Remedial Action Project Site Analysis Report, GJ-
10, prepared by Bendix Field Engineering Corporation, Grand Junction, Colorado, for the
U.S. Department of Energy, Surplus Facilities Management Program, Richland,
Washington.
Geotech 1995, Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00369-RS, Address: 180 East 2nd South Street, Monticello,
Utah 84535, Geotech, Grand Junction, Colorado, January 1995.
U.S. DOE 1990. 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.
ORNL, 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
DOE ID No.: MS-00382-VL
Property Address: 80 West Third 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. [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 m*. [X] [ ] [] [X] [ ] []
In-situ [ ] Lab [X]
Interior gamma is s 20 uR/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]** [ ] [ ] [X]**
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21. [ ] [X] [] [ ] [X] []
Hot spot criteria met as
outlined by the DOE
guidelines for FUSRAP
(Rev. 2, March 1987). [X] [ ] [] [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.
**Excessive ventilation caused by open bay doors.
DOE ID No.: MS-00382-VL
RUST GEOTECH RECOMMENDATION
Based on the Rust Geotech 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.
[XJ 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
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00382-VL
ADDRESS: 80 WEST THIRD SOUTH STREET
MONTICELLO, UTAH 84535
MAY 1995
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 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
DOE ID No.: MS-00382-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 the EPA standards and the
DOE hot spot criteria by the DOE Inclusion Survey Contractor. The DOE
reviewed these evaluation results and determined that the property
contained mill tailings (residual radioactive material) exceeding the EPA
standards and the DOE hot spot criteria. The Remedial Action Contractor
was notified of the inclusion of this property into the MVP Project and was
authorized by the DOE to conduct remedial action as required to bring the
property into conformance with the EPA standards and the DOE hot spot
criteria.
1
DOE ID No.: MS-00382-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-00382-VL
Location Nos. M-104-1 and M-106;
beginning 75 feet east of the SW corner of
Lot 2, Block 14, Monticello Townsite
Survey; north 61 feet, east 39.5 feet, north
153.5 feet, east 88 feet, north 75 feet,
east 12 feet, south 202.25 feet, west
70 feet, south 87.25 feet, west 69.5 feet
to beginning, County of San Juan, State of
Utah
80 West Third South Street
Monticello, Utah 84535

Vacant Lot (VL)
Oak Ridge National Laboratory
June 18, 1991
Rust Geotech
March 4, 1993
Mountain Region Corporation
117 29 3/4 Road
Grand Junction, Colorado
July 29, 1993
September 22, 1993
Interior: 0 cubic yards
Exterior: 11 cubic yards
37 square meters (m2)
May 1995
2
DOE ID No.: MS-00382-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 remedial action process included the removal of
approximately 11 cubic yards of residual radioactive material, ranging from
6 to 20 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
TVs p»y-£. re-c'd iz/mfr
DOE ID No.: MS-00382-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 December 1991 and March 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. An
individual soil sample was collected for Area V^3. 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 11 to 21 microroentgens per hour (uR/h),
as indicated on Appendix Figure 2.1. The results of analyses for
radium-226 in one individual and two composite soil samples ranged
from 2.5 to 3.0 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-00384-AP (Area V-1).
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
RDC measurements were not taken in the structures due to excessive
ventilation caused by open bay doors; therefore, these structures were
verified according to exterior standards.
4
TAi's fAt^e, re-i'd Ujllfa-r
DOE ID No.: MS-00382-VL
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to the
extent required by the EPA standards (40 CFR 192.12,192.20-23) and the
DOE hot spot criteria, as indicated in the Certification Data Summary below.
Therefore, the property located at 80 West Third South Street, in Monticello,
Utah, is recommended for certification as required by the 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 uR/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
floors of the buildings
ranged from 13 to 15 uR/h.
Not applicable: excessive
ventilation caused by open
bay doors.
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 2.5 to 3.0 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-00382-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:01-06-95
MS-00382.VL WP51
REV053193
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00382-VL
Address: 80 West Third South Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range U/R/h) Ticket No. Method" (pCi/g)
V-l 13 - 21 NCD 395 OCS 2.7
V-2 13 - 19 NCD 396 OCS 2.5
V-3 13 - 19 NCD 398 OCS 3.0
See Appendix Figure 2.1 for the verification areas.
•OCS = Opposed Crystal System
7
I I I I I I • i i i i i i i i i i i i i r
50
48
42
13-I4|
r • C X 6 J 6
20(6X0
ONE STORY
BLOCK
BUILDING
13-15 ONE STORY
METAL
BUILDING
13-14
HEDS 11-15
6XE v-J
I I V 13-19
Lzl • ii-it
0
1-15
r
J
r 11-15
Y-i
L J
WEST THIRD SOUTH STREET
L
SCALE IN FEET
20 10 0
I I I I
20 40
I I L_ J I I I I I I J I
10 12 14 16 ie 20 22 24 26 30 32 34 36 38 40 42
I FGFND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN pR/h
© ASSESSED AREA IDENTIFIER
(D AVERAGE DEPTH OF ASSESSEO CONTAMINATION
£J AREA OF ASSESSED CONTAMINATION
12-15 POST—REMEDIAL ACTION EXPOSURE—RATE RANGE
BOUNDARY OF EXCAVATION
rrri AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
LL£J CONTAMINATION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
ANO EXCAVATION EXPOSURE-RATE RANGE
ASSESSEO CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
•CSOCKt-NQ V OCCUPANTS
THIS OftAtalNC is FOR THC SOU use or THC U.S. DCPAftTuCMT
or CKC*CY AND ITS CONTRACTORS, IT IS MOT A U*NO SURVCT
PLAT, UTILITY LOCATION PLAT, OB OTHH IUPROVCUCMT suRvcr PLAT ANO IS NOT TO K RCHCO UPON ron TMC CJUBuSHUCNT
or renee. BUILOINC. OR OTHER FUTURC IUPROVCUENT LINCS.
54
BY CK. A.E. APP. NO. OATC
*«MU» Ql/Qt/tS TMt/711
CK. A.E. APP
U.S. DEPARTMENT OF ENERGY
GRANO JUNCTION PROJECTS OFFICE. COIORAQO
80 WEST THIRD SOUTH STREET
MONTICELLO. UTAH
Rust Ojiot«ch oot io m us.00j,2.VL
0»C. KO. j_poo3a2-vi WI i of i
J 70 72 7
OAK RIDGE NATIONAL LABORATORY
MANAGED BY MARTIN MARIETTA ENERGY SYSTEMS, INC.
GRAND JUNCTION OFFICE
RO. BOX 2567
GRAND JUNCTION. COLORADO 81502
AU6 3 1 1995
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: MS00382
Location Address: 80 West 3rd South 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 WEST 3RD SOUTH STREET
MONTICELLO, UTAH (MS00382-VL)
N. F. Lewis
August 1995
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY SYSTEMS, INC.
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-84OR21400
CONTENTS
LIST OF TABLES v
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 80 West 3rd South Street,
Monticello, Utah (MS00382-VL) 5
v
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site
DeconMnissioning 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 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 1993, RUST
Geotech, the remedial action contractor designated by DOE, performed remedial action on
the vicinity property at 80 West 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 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 WEST 3RD SOUTH STREET
MONTICELLO, UTAH (MS00382-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) 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-AC05-84OR21400 with Lockheed Martin Energy Systems, Inc.
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 vacant lot located at 80 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 1995).
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 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
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 1995)
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 mill tailings 6 inches
deep. During the actual removal process, a total of 11 yd3 of contaminated earth and
uranium mill tailings, 6 to 20 inches deep were removed from a 37 m2 area.
A post-excavation survey was performed by Geotech prior to backfilling of 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 3
excavated 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 gamma exposure rate measurements taken by Geotech from the excavated
areas prior to backfilling ranged from 13 to 21 /iR/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 3 exterior verification areas.
Geotech's analysis of these samples showed 226Ra concentrations to range from 2.5 to 3.0
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
2.1 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. 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. This
property was remediated before this procedure change. The IVC observed that area VI
exceeds 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
anomalous reading of 21 uR/h on this property using the RAC's correlation yields a ^Ra
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. 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.
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.
4
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Radionuclide
concentration 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
concentration of Ra^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
(1007A)*, 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 80 West 3rd South Street, Monticello Utah (MS00382-VL)
^Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No." Np^ (cm}
MS00382X1 NCD 395 >15 3.6 2.7
MS00382X2 NCD 396 >15 2.1 2.5
" 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.
REFERENCES
Geotech 1995, Property Completion Report for Monticello Vicinity Property
Remedial Action for DOE ID NO: MS00382-VL, Address: 80 West 3rd South
Street, Monticello, Utah 84535, Geotech, Grand Junction, Colorado, May 1995.
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.
ORNL, 1993. Environmental Technology Section (Formerly Pollutant
Assessment Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak
Ridge National Laboratory, Grand Junction, Colorado.
DOE ID No.: MS-00397-RS
Property Address: 181 West Second South 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 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 the DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
W [ 1 [ ]
[ X] [ ] [ ]
[» [ ] [ ]
[ 1 M
[>] [ ] [ ]
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 oamma
exposure rates that do not exceed 30 percent above normal background.
•IlIlllllllH lllllliili
SFCERTIFED SFMS-09015
DOE ID No.: MS-00397-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 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.
Manager/Monticello Programs
Rust Geotech
DOE EVALUATION
Date
U.S. Department of Energy
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00397-RS
ADDRESS: 181 WEST SECOND SOUTH STREET
MONTICELLO, UTAH 84535
JULY 1995
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-00397-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 the EPA standards and the
DOE hot spot criteria by the DOE Inclusion Survey Contractor. The DOE
reviewed these evaluation results and determined that the property
contained mill tailings (residual radioactive material) exceeding the DOE
hot spot criteria. The Remedial Action Contractor was notified of the
inclusion of this property into the MVP Project and was authorized by the
DOE to conduct remedial action as required to bring the property into
conformance with the EPA standards and the DOE hot spot criteria.
1
DOE ID No.: MS-00397-RS
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
MS-00397-RS
Location No. M-119; beginning 100 feet east of the NW corner of Lot 3,
Block 15, Monticello Townsite Survey; east 14.5 feet, south 214 feet, west
14.5 feet, north 214 feet to beginning; and beginning at the NE corner of Lot 3,
Block 15, Monticello Townsite Survey Plat A, west 100 feet, south 214.5 feet,
east 100 feet, north 214.5 feet to beginning, 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:
181 West Second South Street
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
February 21, 1991
Rust Geotech
October 21, 1991
Crowley Construction, Inc.
East Route 63 HC Box 66
Monticello, Utah
July 28, 1992
August 26, 1992
Interior:
Exterior:
0 cubic yards
1 cubic yard
2 square meters (m2)
July 1995
2
DOE ID No.: MS-00397-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, 12 inches deep,
within the property. The remedial action process included the removal of
approximately 1 cubic yard of residual radioactive material, 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-00397-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. 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 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
1.3 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 0.0037 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-00397-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by the EPA standards (40 CFR 192.12, 192.20-23)
and the DOE hot spot criteria, as indicated in the Certification Data
Summary below.
Therefore, the property located at 181 West Second South Street, in
Monticello, Utah, is recommended for certification as required by the
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 10 to 12 //R/h.
Annual average was
0.0037 WL.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background1 in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above backgroundf 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
1.3 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-00397-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:06-30-95
MS-00397.RS WP52
REV053193
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00397rRS
Address: 181 West Second South Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range U/R/h) Ticket No. Method" (pCi/g)
V-l 15 - 18 NAT 852 OCS 1.3
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-00397-RS
Address: 181 West Second South Street, Monticello, Utah
Instrument Type: Terradex Radtrak® Detector
Radon
Detector Tracks Per Concentration Working
Number Start Date End Date mm2 (pCi/L) Level
3853804 08-19-93 08-17-94 6.5 0.69 0.0035
3853785 08-19-93 08-17-94 6.7 0.71 0.0036
3853825 08-19-93 08-17-94 7.4 0.79 0.0040
Annual Average: 0.0037
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
1
12 14 16 18 20 22 24 26 28 30 32 34 36 38 40 42 44 46 48 51
WEST SECOND SOUTH STREET
LU
If n 11-15
TWO STORY
FRAME HOUSE
W/CRAWL
SPACE
10-12
ROC
18 12X I
v-1
15-18
11-15
11-15
11-15
SCALE IN FEET
20 10 0 20 40
M:\FAS\033\0003\RU00397V 07/11/M 2:06pm TS07S0
NORTH
J L
12 14 16 18 20 22 24 26 28 30
<D
(V..VJ
12-15
12
v-i
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
POST-REMEDIAL ACTION RADON DECAY-PRODUCT
CONCENTRATION MEASUREMENT LOCATION
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.
0.1 man.
nsmKf-m. 0« OCCUMNTI
Mfnwmrt "0. iwnw
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS Of "CC. COLORADO
*W3 3F 181 WEST SECOND SOUTH ST.
MONTICELLO. UTAH
MS-00397-RS
32 34 36 38 40 42 44
• ~ 3-C00397-V1 „ 1 _ 1
46 48 5(
OAK RIDGE NATIONAL LABORATORY
MANAGED BY MARTIN MARIETTA ENERGY SYSTEMS, INC.
GRAND JUNCTION OFFICE
PO. 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
^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
MS00397-RS
181 West 2nd South Street
Monticello. Utah 84535

Same
SEP 2 6 1895
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
181 WEST 2ND SOUTH STREET
MONTICELLO, UTAH (MS00397-RS)
A. R. Jones
September 1995
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY SYSTEMS, INC.
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-84OR21400
CONTENTS
LIST OF TABLES v
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. Lewis 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 1992, RUST
Geotech, the remedial action contractor designated by DOE, performed remedial action on
the vicinity property at 181 West 2nd 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 the ETS are
described in the Environmental Technology Section Procedures Manual (ORNL 1993).
ix
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 181 WEST 2ND SOUTH STREET
MONTICELLO, UTAH (MS00397-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 n. Various
government agencies operated the mill until 1947. In 1948 the Atomic Energy
Commission (AEC) obtained the mill and operated it under contract through 19S9 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 ofthe Environmental Assessment Group in the
Environmental Technology Section ofthe Health Sciences Research Division at Oak Ridge National Laboratory under DOE contract
DE-AC05-84OR21400 with Lockheed Martin Energy Systems, Inc.
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 single family residence located at 181 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
restored to a condition comparable to that which existed prior to remedial action (Geotech
1995).
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 181 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
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 1995)
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 mill tailings 12
inches deep. During the actual removal process, a total of 1 yd3 of contaminated earth and
uranium mill tailings, 18 inches deep were removed from a 2 m2 area.
A post-excavation survey was performed by Geotech prior to backfilling of the
excavated 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. 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
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 12 uR/h. Exterior surface gamma measurements taken from
the excavated areas prior to backfilling ranged from IS to 18 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 ^Ra concentration of 1.3 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
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 08/19/93 to 08/17/94). The average annual
working level (WL) of radon progeny concentration, as determined by the Tech./Ops-
Landauer Corporation, was 0.0037, 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
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
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 Rn Average annual radon proge- 0.03 WL
progeny ny concentration (including
background)
(DOE 1990a)
5
REFERENCES
Geotech 1995, Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00397-RS, Address: 181 West Second South Street,
Monticello.Utah 84535, Geotech, Grand Junction, Colorado, July 1995.
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.
ORNL, 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
DOE ID No.: MS-00427-RS
Property Address: 165 East Second South Street
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech pf 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 =s 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 the 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] [ ] [ ]
[ ] [M [ 1
IV] [ ] [ 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.
mini iiiiiiiMi
SFCERTIFED SFMS-09019
DOE ID No.: MS-00427-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 the concurrence of
the U.S. Nuclear Regulatory Commission because supplemental
standards were applied per 40 CFR 192.21.
[Al 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.
ManagerA^Ionticello Programs
Rust Geotech
Date
DOE EVALUATION
U.S. Department of Energy
PROPERTY COMPLETION REPORT
DOE ID NO.: MS-00427-RS
ADDRESS: 165 EAST SECOND SOUTH STREET
MONTICELLO, UTAH 84535
MARCH 1995
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-00427-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 the EPA standards and the
DOE hot spot criteria by the DOE Remedial Action Contractor. The DOE
reviewed these evaluation results and determined that the property
contained mill tailings (residual radioactive material) exceeding the EPA
standards. The Remedial Action Contractor was notified of the inclusion
of this property into the MVP Project and was authorized by the DOE to
conduct remedial action as required to bring the property into conformance
with the EPA standards and the DOE hot spot criteria.
1
DOE ID No.: MS-00427-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-00427-RS
Location No. M-152-2; beginning at the
SW corner of Lot 1, Block 19, Monticello
Townsite Survey, north 124.5 feet, east
107.25 feet, south 124.5 feet, west to the
point of beginning, County of San Juan,
State of Utah
165 East Second South Street
Monticello, Utah 84535

Residential Simple (RS)
Not applicable: spillover inclusion requested
by the Remedial Action Contractor
June 18, 1991
Rust Geotech
September 13, 1991
Crowley Construction, Inc.
East Route HC 63 Box 66
Monticello, Utah
May 14, 1992
August 12, 1992
Interior: 0 cubic yards
Exterior: 145 cubic yards
434 square meters (ma)
March 1995
2
DOE ID No.: MS-00427-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 remedial action process included the removal of
approximately 145 cubic yards of residual radioactive material, ranging
from 6 inches 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
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-00427-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 1990, as described in the final REA dated
September 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. 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 microroentgens per hour (//R/h)
to 19 //R/h (Appendix Figure 2.1). The results of analyses for
radium-226 in five composite soil samples ranged from
2.3 picocuries per gram (pCi/g) to 5.5 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 0.0116 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-00427-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by the EPA standards (40 CFR 192.12, 192.20-23)
and the DOE hot spot criteria, as indicated in the Certification Data
Summary below.
Therefore, the property located at 165 East Second South Street, in
Monticello, Utah, is recommended for certification as required by the
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 //R/h to
15//R/h.
Annual average was
0.0116 WL.
Land.
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above backgroundf in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above backgroundT 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 2.3 pCi/g to
5.5 pCi/g.*
*The background exposure rate is approximately 15 //R/h.
fThe 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-00427-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
DAG:01-10-94
MS-00427.RS WP51
REV053193
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00427-RS
Address: 165 East Second South Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (jt/R/h) Ticket No. Method* (pCi/g)
V-l 14 - 19 NAT 835 OCS 2.3
V-2 14 - 19 NAT 836 OCS 3.2
V-3 14 - 19 NAT 837 OCS 5.5
V-4 14 - 18 NAT 838 OCS 4.3
V-5 14 - 19 NAT 839 OCS 3.2
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-00427-RS
Address: 165 East Second South Street, Monticello, Utah
Instrument Type: Terradex Radtrak® Detector
Radon
Detector Tracks Per Concentration Working
Number Start Date End Date mm3 (pCi/L) Level
3718274 01-06-93 01-04-94
3718239 01-06-93 01-04-94
3718117 01-06-93 01-04-94
24.8 2.29 0.0115
26.1 2.41 0.0121
24.1 2.23 0.0112
Annual Average: 0.0116
See Appendix Figure 2.1 for the measurement location.
8
10
30
12 14 16 18 20 22 24
"T
26 28 30 32 34 36 38 40
30
28
26
24
22
20
18
16 -
14
12
Y
10
V-4
14-8
r
WW"
1 V-5
14-19
0
10 V-3
14-9
15-16
V. 12
V-2
4-19
ONE STORY
BRICK HOUSE ,
12-15 (RES)]
16
D V-1 10 \
14-19 U6
/.•••
15-16
16 v.<6
10
V
"—777
EAST SECOND SOUTH STREET
SCALE IN FEET
X
20 10 20 40 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
12-15
12
V-1
16-17
(RDC)
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN fj,R/b
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
28
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
RESIOENCt-NO. Of OCCUPANTS
NON—RESIDENCE—MAN—KR5./WK.
INSTRUMENT NO.
VERIFICATION
•T CK. A.E. APP. NO. OATE CK. A.E. APP.
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE. COLORADO
ML
3/95
165 EAST SECOND SOUTH ST.
MONTICELLO, UTAH
APPROVAL
GEOTECH INC
DATE I APPROVAL DOE "BATE"
OOEIDNO. MS-00427-RS
owe.NO. 3-B00427-V1 SHT 1 „ 1
26
24
22
- 20
- 18
16
14
12
10
10 12 14 1 6 18 20 22 24 26 28 30 32 34 36 38 40
GRAND JUNCTION OFFICE
RO. BOX 2567
GRAND JUNCTION. COLORADO 81502
JUN 2 0 1995
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, 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.
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
OAK RIDGE NATIONAL LABORATORY
MANAGED BY MARTIN MARIETTA ENERGY SYSTEMS, INC.
Location Number:
Location Address:
Property Owner:
Owner Address:
Tenant Name:
MS00427-RS
165 East 2nd South 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
165 EAST 2ND SOUTH STREET
MONTICELLO, UTAH (MS00427-RS)
M. K. Jensen
June 1995
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY SYSTEMS, INC.
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-84OR21400
CONTENTS
LIST OF TABLES v
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 165 East 2nd South Street
Monticello, Utah (MS00427-RS) 5
v
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 N. F. Lewis 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
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, RUST
Geotech, the remedial action contractor designated by DOE, performed remedial action
on the vicinity property at 165 East 2nd 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 the
ETS are described in the Environmental Technology Section Procedures Manual (ORNL
1993).
ix
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 165 EAST 2ND SOUTH STREET
MONTICELLO, UTAH (MS00427-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 TJ. 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 ofthe Health Sciences Research Division at Oak Ridge National Laboratory under DOE contract
DE-AC05-84OR21400 with Lockheed Martin Energy Systems, Inc.
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 165 East 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 restored to
a condition comparable to that which existed prior to remedial action (Geotech 1995).
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 165 East 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
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 1990).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1995)
indicates the property was remediated as evaluated by DOE on the basis of Environmental
Protection Agency standards and the DOE guidelines (DOE 1990). 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. However, during the actual removal process, a total of 145 yd3 of contaminated
earth and uranium mill tailings, 6 to 16 inches deep were removed from a 434 m2 area.
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 of the structure, a surface scan of the exterior, and soil sampling. Samples
representative of the bottom 15-cm (6-in.) soil layers of 5 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 of the
residence ranged from 12 to 15 juR/h. Exterior surface gamma measurements taken from
the excavated areas prior to backfilling ranged from 14 to 19 /iR/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 5 exterior verification areas.
Geotech's analysis of these samples showed ^Ra concentrations ranging from 2.3 to 5.5
pCi/g in the composite samples. ORNL ETS obtained one of these samples and
performed a confirmatory analysis which showed a^Ra concentration of 2.5 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 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 one year (from 01/06/93 to 01/04/94). The average annual
working level (WL) of radon progeny concentration, as determined by the TechVOps-
Landauer Corporation, was 0.0116, which is well below the 0.03-WL guideline given in
Table 1.
CONCLUSION
Results of Geotech soil sample analysis and confinnatory 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
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
(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 1990)
Table 2. Results of ORNL analysis of Geotech soil samples
from 165 East 2nd South Street, Monticello Utah (MS00427-RS)
226Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth . ORNL Geotech
No." No^ (cm)
MS00427X5 NAT 839 >15 2.5 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 1995, Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00427-RS, Address: 165 East Second South Street,
Monticello, Utah 84535, Geotech, Grand Junction, Colorado, March 1995.
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.
ORNL, 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
DOE ID No.: MS-00428-RS
Property Address: 164 South Second East 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 =s 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 the DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
Rust Geotech
YES NO NOT TAKEN
[X]* [ ]
[X] [ ]
[X] [ ]
[X] [ ]
[ ] [X]
[X] [ ]
[ ]
[ ]
[ 3
[ ]
[ ]
[ ]
U.S. Department
of Energy (DOE)
YES NO NOT TAKEN
A'
I 1
V1
[XJ \
{]
[ i
[ i
[/]. 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.
SFCERTIFED SFMS-09019
DOE ID No.: MS-00428-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 the concurrence of
the U.S. Nuclear Regulatory Commission because supplemental
standards were applied per 40 CFR 192.21.
Date
Rust Geotech
DOE EVALUATION
CX3 Should be certified by the U.S. Department of Energy.
[ 1 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
U.S. Department of Energy
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00428-RS
ADDRESS: 164 SOUTH SECOND EAST STREET
MONTICELLO, UTAH 84535
FEBRUARY 1995
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 Pape
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-00428-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 the EPA standards and the
DOE hot spot criteria by the DOE Remedial Action Contractor. The DOE
reviewed these evaluation results and determined that the property
contained mill tailings (residual radioactive material) exceeding the EPA
standards. The Remedial Action Contractor was notified of the inclusion
of this property into the MVP Project and was authorized by the DOE to
conduct remedial action as required to bring the property into conformance
with the EPA standards and the DOE hot spot criteria.
1
DOE ID No.: MS-O0428-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-00428-RS
Location No. M-152-1; beginning 20 feet
south of the NE corner of Lot 1, Block 19,
Monticello Townsite Survey, Plat A;
south 87.5 feet, west 107.25 feet, north
17.5 feet, west 12.75 feet, north 60 feet,
east 10 feet, north 10 feet, east 110 feet
to the point of beginning. County of San
Juan, State of Utah
164 South Second East Street
Monticello, Utah 84535

Residential Simple (RS)
Not applicable; spillover inclusion requested
by the Remedial Action Contractor
June 18, 1991
Rust Geotech
September 13, 1991
Crowley Construction, Inc.
East Route HC 63 Box 66
Monticello, Utah
May 14, 1992
August 3, 1992
Interior: 0 cubic yards
Exterior: 9 cubic yards
44 square meters (m2)
February 1995
2
DOE ID No.: MS-00428-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 inches to 12 inches deep, within the property. The remedial action
process included the removal of approximately 9 cubic yards of residual
radioactive material, ranging from 6 inches to 8 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-00428-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 1990, as described in the final REA dated
September 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. 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 microroentgens per hour (//R/h)
to 25 //R/h (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 measurements representing an annual average, the RDC
was 0.0025 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-00428-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by the EPA standards (40 CFR 192.12, 192.20-23)
and the DOE hot spot criteria, as indicated in the Certification Data
Summary below.
Therefore, the property located at 164 South Second East Steet, in
Monticello, Utah, is recommended for certification as required by the
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 //R/h to 15 //R/h.
Annual average was
0.0025 WL.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above backgroundf in the
15-cm surface layer,
averaged over 100 ma.
Shall not exceed 15 pCi/g
above backgroundr 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 15 //R/h.
fThe 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-00428-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
DAG:01-11-95
MS-00428.RS WP51
REV053193
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00428-RS
Address: 164 South Second East Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (//R/h) Ticket No. Method* (pCi/g)
V-l 14 - 25 NAT 846 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-00428-RS
Address: 164 South Second East Street, Monticello, Utah
Instrument Type: Terradex Radtrak® Detector
Radon
Detector Tracks Per Concentration Working
Number Start Date End Date mm2 (pCi/L) Level
3718314 01-06-93 01-04-94
3718202 01-06-93 01-04-94
3718259 01-06-93 01-04-94
6.7 0.60 0.0030
5.0 0.45 0.0023
4.8 0.43 0.0022
Annual Average: 0.0025
See Appendix Figure 2.1 for the measurement location.
8
10
30
12 14 16 18 20 22 24
T
26 28 30 32 34 36 38 40
30
28 28
26
24
22
20
18
16
1 4
12 -
Y
©
15-16
ONE STORY
BRICK HOUSE
W/BASEMENT
13-15
(RDC)
0 15-16 i r
L • V-1
14-25 12
4^"
v.
•
V-1
14-25
SCALE IN FEET
20 10 0 20 40
10 J I J L
NORTH
I I I
UJ
UJ or (—
CO
00
<
UJ
o o
UJ
CO
Z>
o
CO
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.
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN fiR/h
® ASSESSED AREA IDENTIFIER
(6) AVERAGE DEPTH OF ASSESSED CONTAMINATION
[J'v] AREA OF ASSESSED CONTAMINATION
12-15 POST-REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
12
V-1
16-17
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE-RATE RANGE
/^N POST-REMEDIAL ACTION RADON DECAY-PRODUCT
CONCENTRATION MEASUREMENT LOCATION
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
RtStOENCE-HO. OF OCCUPANTS
NOH-RESIOENCE-MAN-HRS./WK.
INSTRUMENT NO.
SURVEY DATE
VERIFICATION
CK. A.E. APP. NO.
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE, COLORADO
23£ 164 SOUTH SECOND EAST ST.
MONTICELLO, UTAH
GEOTECH INC
DATE I APPROVAL OOE TSATT"
DOEIONO. MS-00428-RS
DWG.NO. 3-BQQ428-V1 SHT, 1 or 1
26
24
22
20
18
16
14
12
10
10 12 14 1 6 18 20 22 24 26 28 30 32 34 36 38 40
OAK RIDGE NATIONAL LABORATORY GRAND JUNCTION OFFICE
RO. BOX 2567
MANAGED BY MARTIN MARIETTA ENERGY SYSTEMS, INC. GRAND JUNCTION, COLORADO 81502
MAY 3 1 1995
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, 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:
Tenant Name:
MS00428-RS
164 South 2nd East 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 VERD7ICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
164 SOUTH 2ND EAST STREET
MONTICELLO, UTAH MS00428-RS
M. K. Jensen
May 1995
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
MARTIN MARIETTA ENERGY SYSTEMS, INC.
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-84OR21400
CONTENTS
LIST OF TABLES v
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 South 2nd East
Street, Monticello, Utah (MS00428-RS) 5
v
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 J.R. Sauvage and N. F. Lewis 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
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 164 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
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 164 SOUTH 2ND EAST STREET
MONTICELLO, UTAH (MS00428-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
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 miriimal. 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 (Abramiuk 1989).
"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-AC05-84OR21400 with Martin Marietta Energy Systems, Inc.
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 164 South 2nd 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 1995).
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 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 of the entire property that is to be certified and (2) that the remedial action
reduced contamination to below applicable DOE guidelines (DOE 1990).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1995)
indicates the property was remediated as evaluated by DOE on the basis of Environmental
Protection Agency standards and the DOE guidelines (DOE 1990). 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. However, during the actual removal process, a total of 9 yd3 of contaminated
earth and uranium mill tailings, 6 to 8 inches deep were removed from a 44 m2 area.
A post-excavation survey was performed by Geotech prior to backfilling of the
excavated area. This survey consisted of gamma scans with a scintillometer of the
basement level of the structure and a surface scan of the exterior and soil sampling. A
sample representative of the bottom 15-cm (6-in.) soil layer of the excavated verification
areas was 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 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 basement level of the
residence ranged from 13 to IS (jR/h. Exterior surface gamma measurements taken from
the excavated areas prior to backfilling ranged from 14 to 25 //R/h.
Soil Sample Analysis
Prior to backfilling, Geotech collected a soil sample representative of the excavated
area from the bottom 15-cm (6-in.) soil layer. This sample was 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 3.4 pCi/g. ORNL ETS
obtained this sample and performed a confirmatory analysis which showed a ^Ra
concentration of 2.4 pCi/g. 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).
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 in the basement level of the residence located on this property for a
period of approximately one year (from 01/06/93 to 01/04/94). The average annual
working level (WL) of radon progeny concentration, as determined by the Tech./Ops-
Landauer Corporation, was 0.0025, 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
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
(1007A)'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 1990)
5
Table 2. Results of ORNL analysis of Geotech soil samples
from 164 South 2nd East Street, Monticello Utah (MS00428-RS)
226Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No.° No* (cm)
MS00428X1 NAT 846 >15 2.4 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 Geotech, and these samples were blended to form a composite soil
sample, which represents an average over one of the verification areas.
REFERENCES
Abramiuk I. N.et al. 1989. Monticello Remedial Action Project Site Analysis Report, GJ-
10, prepared by Bendix Field Engineering Corporation, Grand Junction, Colorado, for the
U.S. Department of Energy, Surplus Facilities Management Program, Richland,
Washington.
Geotech 1995, Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00428-RS, Address: 164 South Second East Street,
Monticello, Utah 84535, Geotech, Grand Junction, Colorado, February 1995.
U.S. DOE 1990. 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.
ORNL, 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
DOE ID No.: MS-00429-RS
Property Address: 117 East 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 [ ]
[X]* [ ] [ 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 [ 1 [ ]
In-situ [ ] Lab [X]
Interior gamma is £ 20 //R/h
above background in any
occupied or habitable
structure. [X] [ ] [ ] Wil [ 1
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] [ ] [ ] [)4 [ ]
Hot spot criteria met as
outlined by the 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.
•llllllllll Ililllllllll
SFCERTIFED SFMS-09019
DOE ID No.: MS-00429-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 the concurrence of
the U.S. Nuclear Regulatory Commission because supplemental
standards were applied per 40 CFR 192.21.
[/*] 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
DOE ID NO.: MS-00429-RS
ADDRESS: 117 EAST SECOND SOUTH STREET
MONTICELLO, UTAH 84535
MARCH 1995
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
SectiQn 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-0O429-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 the EPA standards and the
DOE hot spot criteria by the DOE Remedial Action Contractor. The DOE
reviewed these evaluation results and determined that the property
contained mill tailings (residual radioactive material) exceeding the EPA
standards. The Remedial Action Contractor was notified of the inclusion
of this property into the MVP Project and was authorized by the DOE to
conduct remedial action as required to bring the property into conformance
with the EPA standards and the 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-00429-RS
MS-00429-RS
Location No. M-154; beginning at the
SW corner of Lot 2, Block 19, Monticello
Townsite Survey; north 214.5 feet, east
147.5 feet, south 214.5 feet, west
147.5 feet to the point of beginning,
County of San Juan, State of Utah
117 East Second South Street
Monticello, Utah 84535

Residential Simple (RS)
Not applicable: inclusion requested by the
Remedial Action Contractor
June 18, 1991
Rust Geotech
September 13, 1991
Crowley Construction, Inc.
East Route HC 63 Box 66
Monticello, Utah
May 14, 1992
July 30, 1992
Interior: 0 cubic yards
Exterior: 125 cubic yards
552 square meters (m2)
March 1995
2
DOE ID No.: MS-00429-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 remedial action process included the removal of
approximately 125 cubic yards of residual radioactive material, ranging
from 6 inches 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-00429-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 1990, as described in the final REA dated
September 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. 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 microroentgens per hour (//R/h)
to 18 //R/h (Appendix Figure 2.1). The results of analyses for
radium-226 in seven composite soil samples ranged from
1.1 picocuries per gram (pCi/g) to 3.1 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 0.0161 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-00429-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by the EPA standards (40 CFR 192.12, 192.20-23)
and the DOE hot spot criteria, as indicated in the Certification Data
Summary below.
Therefore, the property located at 117 East Second South Street, in
Monticello, Utah, is recommended for certification as required by the
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 15 //R/h to
22 //R/h.
Annual average was
0.0161 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 1.1 pCi/g to
3.1 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-00429-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
DAG:01-11-95
MS-00429.RS WP51
REV053193
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00429-RS
Address: 117 East Second South Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (//R/h) Ticket No. Method* (pCi/g)
V-l 13 - 16 NAT 503 OCS 1.4
V-2 13 - 16 NAT 504 OCS 3.1
V-3 13 - 16 NAT 505 OCS 1.1
V-4 13 - 18 NAT 506 OCS 1.9
V-5 13 - 16 NAT 507 OCS 2.2
V-6 13 - 18 NAT 508 OCS 1.7
V-7 13-18 NAO 323 OCS 1.9
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-00429-RS
Address: 117 East Second South Street, Monticello, Utah
Instrument Type: Terradex Radtrak* Detector
Radon
Detector Tracks Per Concentration Working
Number Start Date End Date mm3 (pCi/L) Level
3718114 01-07-93 01-04-94
3718158 01-07-93 01-04-94
3718281 01-07-93 01-04-94
31.7 2.97 0.0149
34.8 3.27 0.0164
35.8 3.37 0.0169
Annual Average: 0.0161
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
1
22 24 26 28 30 32 34 36 38 40 42
T
44 46 48 5(
-13-
13-18
15-17
v-6
13-18
SHED
15-16
1
15-17
v-i
13-16
12
V-2
V-6
13-16
13-18
TWO STORY
BRICK •A AND FRAME ©:•: HOUSE RDC • •I
15-22
E V-5
13-16
V-2
13-16
V-4
€: 13-18 V-3
13-16
V-7
13-18
777
iv.-.vj
12-15
EH
V-1
16-17
(ROC;
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
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
EAST SECOND SOUTH STREET
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.
22 24 26 28 30
J l_
32
J L
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION MOJCCTt OFFICt. COLORADO
22b-
CU. CM*
117 EAST SECOND SOUTH ST.
MONTICELLO, UTAH
INC
-J-TJ,
MS-00429-RS
34 36 38 40 42 44 46 48 51
OAK RIDGE NATIONAL LABORATORY
MANAGED BY MARTIN MARIETTA ENERGY SYSTEMS, INC.
GRAND JUNCTION OFFICE
RO. BOX 2567
GRAND JUNCTION, COLORADO 81502
JUN 2 0 1995
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, 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.
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
MS00429-RS
117 East 2nd South 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
117 EAST 2ND SOUTH STREET
MONTICELLO, UTAH (MS00429-RS)
M. K. Jensen
June 1995
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY SYSTEMS, INC.
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-84OR21400
CONTENTS
LIST OF TABLES v
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 117 East 2nd South Street,
Monticello, Utah (MS00429-RS) 5
v
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 N. F. Lewis 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
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, RUST
Geotech, the remedial action contractor designated by DOE, performed remedial action
on the vicinity property at 117 East 2nd 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 the
ETS are described in the Environmental Technology Section Procedures Manual (ORNL
1993).
ix
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 117 EAST 2ND SOUTH STREET
MONTICELLO, UTAH (MS00429-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 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-AC05-84OR21400 with Lockheed Martin Energy Systems, Inc.
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 117 East 2nd South Street, Monticello, Utah.
The remedial action plan required excavation bf 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 1995).
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 117 East 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
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 1990).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1995)
indicates the property was remediated as evaluated by DOE on the basis of Environmental
Protection Agency standards and the DOE guidelines (DOE 1990). 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. However, during the actual removal process, a total of 125 yd3 of contaminated
earth and uranium mill tailings, 6 to 12 inches deep were removed from a 552 m2 area.
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 of the structures, a surface scan of the exterior, soil sampling. Samples
representative of the bottom 15-cm (6-in.) soil layers of 7 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 of the
residence ranged from IS to 22 ,uR/h. Exterior surface gamma measurements taken from
the excavated areas prior to backfilling ranged from 13 to 18 //R/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 7 exterior verification areas.
Geotech's analysis of these samples showed ^Ra concentrations ranging from 1.1 to 3.1
pCi/g in the composite samples. ORNL ETS obtained a percentage of these samples and
performed a confirmatory analysis which showed ^Ra concentrations ranging from 1.3 to
2.5 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 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 one year (from 01/07/93 to 01/04/94). The average annual
working level (WL) of radon progeny concentration, as determined by the Tech./Ops-
Landauer Corporation, was 0.0161, 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
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
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
(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 1990)
5
Table 2. Results of ORNL analysis of Geotech soil samples
from 117 East 2nd South Street, Monticello Utah (MS00429-RS)
^Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No." No^ (cm)
MS00429X1 NAT 503 >15 1.9 1.4
MS00429X3 NAT 505 >15 1.3 1.1
MS00429X6 NAT 508 >15 2.5 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 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: MS00429-RS, Address: 117 East Second South Street,
Monticello, Utah 84535, Geotech, Grand Junction, Colorado, March 1995.
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.
ORNL, 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
DOE ID No.: MS-00489-RS
Property Address: 217 Lower Uranium Drive
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech Of Energy (PQE)
Ra-226 is 25 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 the DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
IX] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
[*] [ ] [ ]
MM [ }
[>] I ] I ]
I ] [M [ ]
[>d [ 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.
IIIIIIIM
SFCERTIFED SFMS-00489
DOE ID No.: MS-00489-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 the concurrence of
the U.S. Nuclear Regulatory Commission because supplemental
standards were applied per 40 CFR 192.21.
pt] 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
DOE ID NO.: MS-00489-RS
ADDRESS: 217 LOWER URANIUM DRIVE
MONTICELLO, UTAH 84535
FEBRUARY 1995
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
DOE ID No.: MS-00489-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 the EPA standards and the
DOE hot spot criteria by the DOE Inclusion Survey Contractor. The DOE
reviewed these evaluation results and determined that the property
contained mill tailings (residual radioactive material) exceeding the EPA
standards and the DOE hot spot criteria. The Remedial Action Contractor
was notified of the inclusion of this property into the MVP Project and was
authorized by the DOE to conduct remedial action as required to bring the
property into conformance with the EPA standards and the DOE hot spot
criteria.
1
DOE ID No.: MS-00489-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-00489-RS
Location No. M-468; beginning north
89 degrees 21 minutes west 216.7 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
83.65 feet, south 00 degrees 42 minutes
west 82.5 feet, south 89 degrees
21 minutes east 83.65 feet, north
00 degrees 42 minutes east 82.5 feet to
beginning, City of Monticello, County of
San Juan, State of Utah
217 Lower Uranium Drive
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
August 20, 1992
Rust Geotech
Not applicable; streamlined remediation
procedures were followed
Not applicable; streamlined remediation
procedures were followed
September 9, 1992
September 10, 1992
Interior: 0 cubic yards
Exterior: 0.1 cubic yards
0.5 square meters (m2)
February 1995
2
DOE ID No.: MS-0O489-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 contamination, 6 inches deep,
within the property. The remedial action process included the removal of
approximately 0.1 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-00489-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 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 microroentgens per hour (//R/h)
to 15 //R/h (Appendix Figure 2.1). The result of analysis for
radium-226 in one individual soil sample was 2.3 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 0.0027 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-00489-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by the EPA standards (40 CFR 192.12, 192.20-23)
and the DOE hot spot criteria, as indicated in the Certification Data
Summary below.
Therefore, the property located at 217 Lower Uranium Drive, in
Monticello, Utah, is recommended for certification as required by the
DOE guidelines, and the appropriate records should be documented.
Certification Data Summary
Applicability
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Standard?
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 10 //R/h to
12 //R/h.
Annual average was
0.0027 WL.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background1 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
2.3 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-00489-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
DAG:02-01-95
MS-00489.RS WP51
REV053193
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00489-RS
Address: 217 Lower Uranium Drive, Monticello, Utah
Exposure Soil Sample Meas. Radium-226
Area Rate (jt/R/h) Number Method* (pCi/g)
V-l 15 Rl OCS 2.3
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-00489-RS
Address: 217 Lower Uranium Drive, Monticello, Utah
Instrument Type: Terradex Radtrak® Detector
Radon
Detector Tracks Per Concentration Working
Number Start Date End Date mm2 (pCi/L) Level
3718296 01-06-93 01-04-94
3718280 01-06-93 01-04-94
3718189 01-06-93 01-04-94
5.8 0.53 0.0027
5.3 0.48 0.0024
6.5 0.58 0.0029
Annual Average: 0.0027
See Appendix Figure 2.1 for the measurement location.
8
10
30
12 14 16 18 20 22 24 26 28 30 32 34 36 38 40
30
28 28
26
24
22
20
18
16
14
12
Y
20
10
r LOWER URANIUM DRIVE ~1
/// ///
12-13
CARPORT-j^
I
12-13
ONE STORY
FRAME HOUSE
10-12
IRDC) X
I o
z co
V-1 12-13
15uR/h
SCALE IN FEET
10 0 20
I I I
40 NORTH
I I I
LU
UJ
DC
I—
CO
if)
UJ
o
o
UJ
CO
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.vi
IV.VJ
12-15
12
V-1
16-17
(RDC)
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN fxR/b
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
POST-REMEDIAL ACTION RADON DECAY-PRODUCT
CONCENTRATION MEASUREMENT LOCATION
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
RESI0ENCE-NO. OF OCCUPANTS
NON—RESIDENCE—MAN-HRS./WK.
INSTRUMENT NO.
SURVEY OATE
VERIFICATION
CK. A.C. APP. NO. DATE BY CK. A.C. APP.
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE. COLORADO
217 LOWER URANIUM DRIVE
MONTICELLO, UTAH
APPROVAL
GEOTECH INC
BATE I APPROVAL DOE
OOEIONO. MS-00489-RS
owe, NO. 3-B00489-V1 SHT 1 or 1
26
24
22
20
18
16
14
12
10
10 12 14 1 6 18 20 22 24 26 28 30 32 34 36 38 40
OAK RIDGE NATIONAL LABORATORY
MANAGED BY MARTIN MARIETTA ENERGY SYSTEMS, INC.
GRAND JUNCTION OFFICE
RO. BOX 2567
GRAND JUNCTION, COLORADO 61502
MAR 2 8 1995
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
MS 00489-RS
217 Lower Uranium Drive
Monticello. Utah 84535

Joanne Christensen
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
217 LOWER URANIUM DRIVE
MONTICELLO, UTAH (MS00489-RS)
M. K. Jensen
March 1995
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
MARTIN MARIETTA ENERGY SYSTEMS, INC.
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-84OR21400
CONTENTS
LIST OF TABLES v
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
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 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
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, RUST
Geotech, the remedial action contractor designated by DOE, performed remedial action on
the vicinity property at 217 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
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 217 LOWER URANIUM DRIVE
MONTICELLO, UTAH (MS00489-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 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 (Abramiuk 1989).
*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-AC05-84OR21400 with Martin Marietta Energy Systems, Inc.
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 217 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 (Geotech 1995).
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 217 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 (DOE 1990).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1995)
indicates the property was remediated as evaluated by DOE on the basis of Environmental
Protection Agency standards and the DOE guidelines (DOE 1990). 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 0.1 yd3 of mill
tailings 6 inches deep. During the actual removal process, a total of 0.1 yd3 of
contaminated earth and uranium mill tailings, 6 inches deep were removed from a 0.5 m2
area.
A post-excavation survey was performed by Geotech prior to backfilling of the
excavated areas. This survey consisted of gamma scans with a scintillometer, a ground-
level scan of the building, a surface scan ofthe exterior and soil sampling. An individual
sample representative of the bottom 15 cm soil layer of the excavated area was collected.
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 12uR/h. Exterior surface gamma measurements taken from
the excavated area prior to backfilling were 15 uR/h.
Soil Sample Analysis
Prior to backfilling, Geotech collected an individual soil sample representative of the
excavated areas from the bottom 15-cm (6-in.) soil layers. Geotech's analysis of this
sample show a ^Ra concentration of 2.3 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
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 1/6/93 to 1/4/94). The average annual working
level (WL) of radon progeny concentration, as determined by the Tech./Ops-Landauer
Corporation, was 0.0027, 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
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
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
(lOO/A)*, 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 1990)
5
REFERENCES
Abramiuk I. N.et al. 1989. Monticello Remedial Action Project Site Analysis Re-
port, GJ-10, prepared by Bendix Field Engineering Corporation, Grand Junction,
Colorado, for the U.S. Department of Energy, Surplus Facilities Management
Program, Richland, Washington.
Geotech 1995, Property Completion Report for Monticello Vicinity Property
Remedial Action for DOE ID NO: MS00489-RS, Address: 217 Lower Uranium
Drive, Monticello, Utah 84535, Geotech, Grand Junction, Colorado, February
1995.
U.S. DOE 1990. 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.
ORNL, 1993. Environmental Technology Section Procedures Manual. ORNL
6645/RI Oak Ridge National Laboratory, Grand Junction, Colorado.
DOE ID No.: MS-00512-RS
Property Address: 196 West First South Street
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech Qf 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 /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 the DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
W I 1 [ 1
[>] [ ] I 1
IA [ 1 [ 1
[)d [ 1 [ 1
[ ] [ 1
[y] [ ] 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.
1
SFCERTIFED
IlllllllH
SFMS-09025
DOE ID No.: MS-00512-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.
52 tenda S. tfusby
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
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00512-RS
ADDRESS: 196 WEST FIRST SOUTH STREET
MONTICELLO, UTAH 84535
SEPTEMBER 1995
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-00512-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 the EPA standards and the
DOE hot spot criteria by the DOE Inclusion Survey Contractor. The DOE
reviewed these evaluation results and determined that the property
contained mill tailings (residual radioactive material) exceeding the EPA
standards and the DOE hot spot criteria. The Remedial Action Contractor
was notified of the inclusion of this property into the MVP Project and was
authorized by the DOE to conduct remedial action as required to bring the
property into conformance with the EPA standards and the DOE hot spot
criteria.
1
DOE ID No.: MS-00512-RS
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
MS-00512-RS
Location No. M-209; beginning at the SW corner of Block 25, Monticello
Townsite Survey; north 214.5 feet, east 93.4 feet, south 214.5 feet, west
93.4 feet to the point of beginning, 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:
196 West First South Street
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
January 31, 1991
Rust Geotech
December 4, 1992
Sonderegger Inc.
P.O. Box 713
Monticello, Utah
June 15, 1993
June 30, 1993
Interior:
Exterior:
0 cubic yards
7 cubic yards
18 square meters (m2)
September 1995
2
DOE ID No.: MS-00512-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). Exterior assessed areas D and E were
point sources (ore samples) on shelves in a block shed. These point
sources were removed with no excavation. 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
15 inches deep, within the property. The quantity of contamination for
this property was not specified because it was assessed as part of
Block MS-09O25-BK. The remedial action process included the removal of
approximately 7 cubic yards of residual radioactive material, ranging from
6 to 20 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-00512-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
December 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 a composite
sample representing the verification area (Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 9 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
1.1 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 0.0133 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-00512-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by the EPA standards (40 CFR 192.12, 192.20-23)
and the DOE hot spot criteria, as indicated in the Certification Data
Summary below.
Therefore, the property located at 196 West First South Street, in
Monticello, Utah, is recommended for certification as required by the
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 backgroundf in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above backgroundt in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 m2.
Range for the ground
floor was 13 to 15 //R/h.
Annual average was
0.0133 WL.
< 5 pCi/g above
background.**
Soil sample result was
1.1 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-00512-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:07-25-95
MS-00512.RS WP52
REV053193
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00512-RS
Address: 196 West First South Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range U/R/h) Ticket No. Method' (pCi/g)
V-l 13 - 19 NAW 077 OCS 1.1
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-00512-RS
Address: 196 West First South Street, Monticello, Utah
Instrument Type: Terradex Radtrak® Detector
Radon
Detector Tracks Per Concentration Working
Number Start Date End Date mm2 (pCi/L) Level
3853859 01-04-94 12-08-94
3853900 01-04-94 12-08-94
3839319 01-04-94 12-08-94
22.5 2.63 0.0132
23.0 2.68 0.0134
23.0 2.66 0.0133
Annual Average: 0.0133
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
1
12 14 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 1—i—i—i—i—i—i—i—i—i—r
o
z
o
CJ
13
o
V-1
13-19 12-15
V-1
13-19
20
777
20
LLL LLL
12-15
SHED
9-12
v-i
3-19
RDC
<D
iv.-.vj
12-15
12
ONE STORY
BRICK HOUSE
13-15
V-1
16-17
(RDC)
L.
12-15
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 AREAS D AND E (ORE SAMPLES ON
SHELVES) WERE REMOVED BUT NOT REPLACED
POINT SOURCES (ORE SAMPLES) WERE REMOVED
BUT NOT REPLACED
WEST FIRST SOUTH STREET
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
L
SCALE IN FEET
20 10 0 20 40
M:\FAS\03J\0003\RU00512V 07/26/95 4:17pm T507BO
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 I I I
MMOKI-MO. v oceunuis
MNTrMTI
U.S. DEPARTMENT OF ENERGY
GRANO JUNCTION PROJECTS OFFICE, COLOftADO
m 196 WEST FIRST SOUTH STREET
MONTICELLO, UTAH
MS-00512-RS
12 14 16 18 20 22 24 26 28 30 32 34 36 38 40 42 44 46 48 5C
OAK RIDGE NATIONAL LABORATORY PHONE: <970) 24M2oo
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION FAX: [phone]
FOR THE U.S. DEPARTMENT OF ENERGY
POST OFFICE BOX 2567 . .
GRAND JUNCTION, COLORADO 81502 HAR £ $ 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 verifica-
tion 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: MS00512-RS
Location Address: 196 West 1st 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 1ST SOUTH STREET
MONTICELLO, UTAH (MS00512-RS)
M. K. Jensen
March 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
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
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 J. R. Sauvage 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, 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 1993, RUST
Geotech, the remedial action contractor designated by DOE, performed remedial action
on the vicinity property at 196 West 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. 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 WEST 1ST SOUTH STREET
MONTICELLO, UTAH (MS00512-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 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 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 196 West 1st 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 1995).
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 196 West 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
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 1995)
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 mill tailings 6 to 15
inches deep. This property was assessed as part of Block 25, 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 20 inches deep was removed from a
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. A sample repre-
sentative ofthe bottom 15-cm (6-in.) soil layers of the excavated verification area was
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.
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 a soil sample representative of the excavated
areas 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.
Geotech's analysis of this sample showed a ^Ra concentration of 1.1 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
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 01/04/94 to 12/08/94). The average annual
working level (WL) of radon progeny concentration, as determined by the TechVOps-
Landauer Corporation, was 0.0133, 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
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
concentrations in soil
for Hot Spot areas
Maximum permissible con-
centration of 226Ra 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
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
Average annual radon proge- 0.03 WL
ny concentration (including
background)
(DOE 1990a)
Exposure to 222Rn
progeny
5
REFERENCES
Geotech 1995. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00512-RS, Address: 196 West First South Street,
Monticello, Utah 84535, Geotech, Grand Junction, Colorado, September 1995.
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-00513-RS
Property Address: 180 West First 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 ma.
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 the DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
LX] [ ] [ ]
[A i 1 I 1
[ ] [y] [ ]
[XI 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 gamma
exposure rates that do not exceed 30 percent above normal background.
SFCERTIFED SFMS-09025
DOE ID No.: MS-00513-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.
^£^^1^ ?/ztr/ir
Wanda S.'Busby ^ Date
Manager, 'Monticello Programs
Rust Geotech
DOE EVALUATION
[/J 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-00513-RS
ADDRESS: 180 WEST FIRST SOUTH STREET
MONTICELLO, UTAH 84535
AUGUST 1995
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 Pape
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-00513-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 the EPA standards and the
DOE hot spot criteria by the DOE Inclusion Survey Contractor. The DOE
reviewed these evaluation results and determined that the property
contained mill tailings (residual radioactive material) exceeding the EPA
standards and the DOE hot spot criteria. The Remedial Action Contractor
was notified of the inclusion of this property into the MVP Project and was
authorized by the DOE to conduct remedial action as required to bring the
property into conformance with the EPA standards and the DOE hot spot
criteria.
1
1 -3 Summary of Remedial Action
DOE ID No.:
Legal Description:
DOE ID No.: MS-00513-RS
MS-00513-RS
State of Utah eei T0 tne P°,nt of beginning. County of San Juan,
Property Address:
Property Owner:
Property Category:
inclusion Survey Contractor:
inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
PReco?dTUCtl0n Confe™ce
Xee°cSa' C°mp,etl0n
Volume of Material Removed:
Area Cleaned Up:
Prac
e°dretion Repo«
180 West First South Street
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
January 31, 1991
Rust Geotech
December 4, 1992
Sonderegger Inc.
P.O. Box 713
Monticello, Utah
June 15, 1993
June 30, 1993
Interior:
Exterior: 0 cubic yards
1 cubic yard
2 square meters (ma)
August 1995
2
2.0 OPERATIONS SUMMARY
DOE ID No.: MS-00513-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 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, 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-09025-BK.
The remedial action process included the removal of approximately 1 cubic
yard of residual radioactive material, 12 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-00513-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
December 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 16 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
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 0.0052 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).
4
DOE ID No.: MS-00513-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by the EPA standards (40 CFR 192.12, 192.20-23)
and the DOE hot spot criteria, as indicated in the Certification Data
Summary below.
Therefore, the property located at 180 West First South Street, in
Monticello, Utah, is recommended for certification as required by the
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 15 jt/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 backgroundf 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 1.0 pCi/g.**
*The background exposure rate is approximately 13 //R/h.
^he 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-00513-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:07-25-95
MS-00513.RS WP52
REV053193
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00513-RS
Address: 180 West First South Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (//R/h) Ticket No. Method' (pCi/g)
V-l 14 - 16 NAY 660 OCS 1.0
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-00513-RS
Address: 180 West First South Street, Monticello, Utah
Instrument Type: Terradex Radtrak* Detector
Detector
Number Start Date End Date
Tracks Per
mm2
Radon
Concentration
(pCi/L)
Working
Level
3964198
3964281
3964368
02-28-95
02-28-95
02-28-95
06-01-95
06-01-95
06-01-95
2.6
2.7
2.8
0.97
1.03
1.07
0.0049
0.0052
0.0054
Average: 0.0052
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
1
12 1 4 1 6 18 20 22 24 26 28 30 32 34 36 38 40
12-15
12-15
SHED
12-14
RDC)
ONE STORY
FRAME HOUSE
12-15
12-15
v-i
14-16 M XI2 1 2
®
<D
12-15
12
V-1
16-17
42 44 46 48 5(
l£££JsLD
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
POST-REMEDIAL ACTION RADON DECAY-PRODUCT
CONCENTRATION MEASUREMENT LOCATION
""777 777-
WEST FIRST SOUTH STREET
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
SCALE IN FEET
20 10 0 20 40
M:\F»S\OJJ\OOOJ\.RIK>OS1JV 07/26/»3 1:29pm T507BO
12 14 16 18 20
NORTH
I I
22
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 AND IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE, BUILDING. OR OTHER FUTURE IMPROVEMENT LINES.
tpurnn-wo. or ICWMI U.S. DEPARTMENT OF ENERGY
JUNCTION M04TCTS gtnH, COLORADO
180 WEST FIRST SOUTH STREET
MONTICELLO, UTAH
MS-00513-RS
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
POST OFFICE BOX 2567
GRAND JUNCTION, COLORADO 81502
PHONE: [phone]
FAX: [phone]
MAR 29 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 verifica-
tion 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/TVC Project Manager
Environmental Assessment Group
Location Number:
Location Address:
Property Owner:
Owner Address:
Tenant Name:
MS00513-RS
180 West 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
180 WEST 1ST SOUTH STREET
MONTICELLO, UTAH (MS00513-RS)
M. K. Jensen
March 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
VERTPICATION 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 West 1st South
Street, Monticello, Utah (MS00513-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 J. R. Sauvage 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, 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 1993,
RUST Geotech, the remedial action contractor designated by DOE, performed remedial
action on the vicinity property at 180 West 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. 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 WEST 1ST SOUTH STREET
MONTICELLO, UTAH (MS00513-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 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 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 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 single family residence located at 180 West 1st 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, 1995).
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 West 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
documentation adequately and accurately describes the post-remedial-action radio-
logical 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 1995)
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 mill tailings 12
inches deep. This property was assessed as part of Block 25, 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, 12 inches deep, was removed from a
2 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. An individual soil sample representative of the bottom 15-cm
(6 in.) soil layer of the excavated area was collected.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radi-
ation 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 12 to 15 u,R/h. Exterior surface gamma measurements taken
from the excavated areas prior to backfilling ranged from 14 to 16 /iR/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 226Ra concentration of 1.0 pCi/g. ORNL ETS obtained this sample and
performed a confirmatory analysis which showed a ^Ra 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. 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 2/28/95 to 6/01/95). 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.
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.
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
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)14, where A is the
area of the elevated region
Exposure to ^Rn 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 180 West 1st South Street, Monticello Utah (MS00513-RS)
226Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No." No/ (cm)
XI NAY 660 >15 1.3 1.0
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.
6
REFERENCES
Geotech 1995. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00513-RS, Address: 180 West First South Street, Monticello,
Utah 84535, Geotech, Grand Junction, Colorado, August, 1995.
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-00515-RS
Property Address: 17 South Second West 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 the DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
[/] [ ] [ 1
[>•)[} I ]
[>J [ ] [ ]
[A I 1 [ 1
I 1 [ 1
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 gamma
exposure rates that do not exceed 30 percent above normal background.
Illlllll
SFCERTIFED
Ililllllllll
SFMS-flCiaPFi
DOE ID No.: MS-00515-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.
da*
usby 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
FOR
DOE ID NO.: MS-00515-RS
ADDRESS: 17 SOUTH SECOND WEST STREET
MONTICELLO, UTAH 84535
AUGUST 1995
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
3.1.3 Radon Decay-Product Concentration (RDC) Measurement .... 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
DOE ID No.: MS-00515-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 the EPA standards and the
DOE hot spot criteria by the DOE Inclusion Survey Contractor. The DOE
reviewed these evaluation results and determined that the property
contained mill tailings (residual radioactive material) exceeding the EPA
standards and the DOE hot spot criteria. The Remedial Action Contractor
was notified of the inclusion of this property into the MVP Project and was
authorized by the DOE to conduct remedial action as required to bring the
property into conformance with the EPA standards and the DOE hot spot
criteria.
1
DOE ID No.: MS-00515-RS
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
MS-00515-RS
Location No. M-210-1-1; beginning at the NW corner of Lot 3, Block 25,
Monticello Townsite Survey Plat A; south 100 feet, east 114.5 feet, north
100 feet, west 114.5 feet to the point of beginning, 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:
17 South Second West Street
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
August 27, 1991
Rust Geotech
December 4, 1992
Sonderegger Inc.
P.O. Box 713
Monticello, Utah
June 15, 1993
June 21, 1993
Interior:
Exterior:
0 cubic yards
1 cubic yard
3 square meters (m2)
August 1995
2
DOE ID No.: MS-00515-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-09025-BK.
The remedial action process included the removal of approximately 1 cubic
yard 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-00515-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
December 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, 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 OyR/h), as indicated on Appendix Figure 2.1. The result of
analysis for radium-226 in one composite 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 0.0055 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-00515-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by the EPA standards (40 CFR 192.12, 192.20-23)
and the DOE hot spot criteria, as indicated in the Certification Data
Summary below.
Therefore, the property located at 17 South Second West Street, in
Monticello, Utah, is recommended for certification as required by the
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 basement
was 12 to 14//R/h.
Annual average was
0.0055 WL.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above backgroundT in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above backgroundf in any
15-cm-thick soil layer
more than 15 cm below
the surface, averaged
over 100 mJ.
< 5 pCi/g above
background.**
Soil sample result was
< 1.0 pCi/g.**
*The background exposure rate is approximately 13 j/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-00515-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:07-25-95
MS-00515.RS WP52
REV053193
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00515-RS
Address: 17 South Second West 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-l 13 - 19 NAW 076 OCS < 1.0
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-00515-RS
Address: 17 South Second West Street, Monticello, Utah
Instrument Type: Terradex Radtrak* Detector
Radon
Detector Tracks Per Concentration Working
Number Start Date End Date mm3 (pCi/L) Level
3853891 01-04-94 12-08-94
3853933 01-04-94 12-08-94
3839348 01-04-94 12-08-94
9.8 1.13 0.0057
9.4 1.07 0.0054
9.7 1.10 0.0055
Annual Average: 0.0055
See Appendix Figure 2.1 for the measurement location.
8
10
30
12 14 16 18 20 22 24 26 28 30 32 34 36 38 40
28 WEST CENTER STREET
/// ///
26
24
22
20
18
16
14
12 -
Y
10
or
r-
co
i—
ul
O o
LU
CO
X
I—
o co
12-15
(RDC)
ONE STORY
FRAME HOUSE
W/BASEMENT
12-14
12-15
l_.
SCALE IN FEET
20 10 0 20 40
M:\FAS\033\0003\RM00515V 07/27/95 10:10am T50780
NORTH
12-15
V-1
13-19
2
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 1 I I I I
®
<D
nv.vi
iv.-.vj
12-15
12
v-1
16-17
(RDC)
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
POST-REMEDIAL ACTION RADON DECAY-PRODUCT
CONCENTRATION MEASUREMENT LOCATION
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
RESIDENCE-NO. OF OCCUPANTS
NON—RESIDENCE—UAH-HRS./WK.
msnuueia NO.
SURVEY DATE
CK. A.C. APP. NO. DATE
U.S. DEPARTMENT OF ENERGY
GRANO JUNCTION PROJECTS OFFICE, COLORADO
'rr 9-BE 17 SOUTH SECOND WEST ST.
MONTICELLO, UTAH
APPROVAL
Rust Oeot«ch
AW«Tllll«lD|lllCllimi|
DATE I APPROVAL ODE DATE
OOEIONO. MS-00515-RS
DWC.NO. 3-B00515-V1 SHT 1 „ 1
10 1 2 1 4 1 6 18 20 22 24 26 28 30 32 34 36 38 40
OAK RIDGE NATIONAL LABORATORY PHONE: (970)24<W200
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION FAX: [phone]
FOR THE U.S. DEPARTMENT OF ENERGY
POST OFFICE BOX 2567
GRAND JUNCTION, COLORADO 81502 MAR tligge
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 verifica-
tion 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:
Location Address:
Property Owner:
Owner Address:
Tenant Name:
MS00515-RS
17 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
17 SOUTH 2ND WEST STREET
MONTICELLO, UTAH (MS00515-RS)
M. K. Jensen
March 1996
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY SYSTEMS, INC.
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-84OR21400
CONTENTS
LIST OF TABLES v
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 17 South 2nd West Street,
Monticello, Utah (MS00515-RS) 5
v
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 J. R. Sauvage 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 contaminated by
radioactive material resulting from mill operations. During 1993, RUST Geotech, the
remedial action contractor designated by DOE, performed remedial action on the vicinity
property at 17 South 2nd West Street, Monticello, Utah. The Environmental Technology
Section (ETS) of Oak Ridge National Laboratory was assigned the responsibility of verify-
ing 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
remedial action objectives. Procedures used by the ETS are described in the Environ-
mental Technology Section Procedures Manual (ORNL, 1993).
ix
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 17 SOUTH 2ND WEST STREET
MONTICELLO, UTAH (MS00515-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 of the Monticello Vicinity
Properties (MVP) Project (U.S. DOE 1990b).
*Tbe 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-AC05-84OR21400 with Lockheed Martin Energy Systems, Inc.
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 17 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 1995).
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 17 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 (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1995) indi-
cates 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 inches
deep. This property was assessed as part of Block 25, therefore the quantity of material
assessed is not available. However, during the actual removal process, a total of 1 yd3 of
contaminated earth and uranium mill tailings, 12 inches deep was removed from a 3 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 sam-
pling. A soil sample representative of the bottom 15-cm (6-in.) soil layers of the exca-
vated area was 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 of the resi-
dence ranged from 12-14 uR/h. Exterior surface gamma measurements taken from the
excavated areas prior to backfilling ranged from 13-19 /iR/h.
Soil Sample Analysis
Prior to backfilling, Geotech collected a soil sample representative of the excavated
area from the bottom 15-cm (6-in.) soil layers. This sample was blended to form a com-
posite soil sample representative of an average over the exterior verification area.
Geotech's analysis of this sample showed a ^Ra concentration of <1.0 pCi/g. ORNL ETS
obtained this sample and performed a confirmatory analysis which showed a ^Ra concen-
tration of 1.4 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 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 in the basement of the residence located on this property for a period of approxi-
mately one year (from 01/04/94 to 12/08/94). The average annual working level (WL) of
radon progeny concentration, as determined by the Tech./Ops-Landauer Corporation, was
0.0055, 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 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 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
concentration 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
(lOO/A)*, where A is the
area of the elevated region
Average annual radon proge- 0.03 WL
ny concentration (including
background)
(DOE 1990a)
Exposure to 222Rn
progeny
5
Table 2. Results of ORNL analysis of Geotech soil samples
from 17 South 2nd West Street, Monticello Utah (MS00515-RS)
226Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No." No/ (cm)
XI NAW 076 >15 1.4 <1.0
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.
6
REFERENCES
Geotech 1995. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00515-RS, Address: 17 South Second West Street,
Monticello, Utah 84535, Geotech, Grand Junction, Colorado, August 1995.
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-00529-MR
Property Address: 116 North First West 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 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
PC I 1 [ 1
[» [ 1 [ 1
M I 1 f 1
[Ml] I 1
LX] I 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 oamma
exposure rates that do not exceed 30 percent above normal background.
mil
SFCERTIFED SFMS-09050
DOE ID No.: MS-00529-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.
rr y/-rf ?//r/*r
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.
Certification Official
U.S. Department of Energy
Date
PROPERTY COMPLETION REPORT
DOE ID NO.: MS-00529-MR
ADDRESS: 116 NORTH FIRST WEST STREET
MONTICELLO, UTAH 84535
SEPTEMBER 1995
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
Warura 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-00529-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-00529-MR
MS-00529-MR
Beginning 82.5 feet north of the NW corner
of Block J, Monticello Townsite Survey;
east 108.5 feet, north 108.5 feet, west
108.5 feet, south 108.5 feet to beginning,
County of San Juan, State of Utah
116 North First West Street
Monticello, Utah 84535

Major Residential (MR)
Oak Ridge National Laboratory
January 31, 1991
Rust Geotech
November 17, 1993
Diamond Back Services, Inc.
9861 Titan Park Circle
Littleton, Colorado
September 15, 1994
October 12, 1994
Interior: 0.3 cubic yards
Exterior: 0.3 cubic yards
3 square meters (m2)
September 1995
2
DOE ID No.: MS-00529-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, 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-09050-BK.
The remedial action process included the removal of approximately
0.6 cubic yards of residual radioactive material, ranging from 6 to
12 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-00529-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 June 1992 and January 1993, 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 exterior excavation
were collected. These samples were blended to form a composite
sample representing the exterior verification area (Appendix
Figure 2.1).
Interior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 15 to 21 microroentgens per
hour U/R/h) for the remediated portion of the crawl space, 12 to
16 pR/h for the partial basement, and 12 to 15 //R/h for the
ground floor (Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined
during the gamma scan, ranged from 12 to 17 //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 0.0060 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-00529-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 116 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
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
Ranges were 15 to
21 //R/h for the
remediated portion of the
crawl space, 12 to
16 //R/h for the partial
basement, and 12 to
15 //R/h for the ground
floor.
Average was 0.0060 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.
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-00529-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:08-30-95
MS-00529.MR WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00529-MR
Address: 116 North First West Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (//R/h) Ticket No. Method' (pCi/g)
V-1 14-17 NCA 970 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-00529-MR
Address: 116 North First West Street, Monticello, Utah
Instrument Type: Terradex Radtrak Detector
Radon
Detector Tracks Per Concentration Working
Number Start Date End Date mm2 (pCi/L) Level
3964335 02-27-95 05-30-95
3964204 02-27-95 05-30-95
3964115 02-27-95 05-30-95
3.2 1.21 0.0061
2.9 1.10 0.0055
3.3 1.25 0.0063
Average: 0.0060
See Appendix Figure 2.1 for the measurement location.
8
10
30
28
26
24
22
20
18
1 6
1 4
12
12 14 16 18 20 22 24 26 28
12-15
BASEMENT
1 2 1 6
V-2
(RDC)
15-21
CH
in ONE STORY
BRICK HOUSE
W/PARTIAL
BASEMENT
GROUND
FLOOR
CRAWL
SPACE Ld
-SHED
12-14 LO SEE DETAIL A 12 ca 12-15
GROUND
FLOOR
12-15
x 12-15 DETAIL A
NOT TO SCALE
CH
O
1
V-1
V-1 14-17
14-17
•SHED
12-K L_ l3_l
"777 777"
WEST FIRST NORTH STREET
Y
X
SCALE IN FEET
20 10 0 20 40
M:\FAS\033\0003\RM00529V 09/08/95 12:54pm T50780
10
NORTH
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
®
nv.vn
Lv.vj
12-15
1 2
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 AREA IDENTIFIER AND
EXCAVATION EXPOSURE-RATE RANGE
POST-REMEDIAL ACTION RADON DECAY-PRODUCT
CONCENTRATION MEASUREMENT LOCATION
ASSESSED DEPTH UNDETERMINED
40
RADIOLOGICAL AS-BUILT
FIGURE 2.1
INTERIOR AND EXTERIOR EXTENT OF CONTAMINATION
RESIDENCE-NO. OF OCCUPANTS
NON—RESIDENCE—MAN—HRS./WK.
INSTRUMENT NO.
BY CK. A.E. APP. NO. DATE BY CK. A.E. APP
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE, COLORADO
t~7 9-fr
u6s 1 1 6 NORTH FIRST WEST STREET
MONTICELLO, UTAH
APPROVAL
Rust Qeotech
AWMXTllliUntHl&JNt
DATE I APPROVAL DOE "EATT
DOE ID NO. MS-00529-MR
owe.NO. 3-B00529-V1 SHT 1 „ 1
10 12 14 1 6 18 20 22 24 26 28 30 32 34 36 38 40
OAK RIDGE NATIONAL LABORATORY PHONE: (gro) 248-6200
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION FAX: [phone]
FOR THE U.S. DEPARTMENT OF ENERGY
POST OFFICE BOX 2567
GRAND JUNCTION, COLORADO 81502 MAR 29 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 verifica-
tion 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: MS00529-MR
Location Address: 116 North 1st West Street
Monticello. Utah 84535
Property Owner:

Tenant Name: J. Burton Black
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
116 NORTH 1ST WEST STREET
MONTICELLO, UTAH (MS00529-MR)
S. M. Smith
March 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 116 North 1st West Street,
Monticello, Utah (MS00529-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'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 1994, RUST
Geotech, the remedial action contractor designated by DOE, performed remedial action
on the vicinity property at 116 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
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 116 NORTH 1ST WEST STREET
MONTICELLO, UTAH (MS00529-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) 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 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 private residence located at 116 North 1st West Street, Monticello, Utah.
The remedial action plan required excavation of all exterior and interior 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 1995).
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 116 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 (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1995)
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 50, therefore, the quantity of material
assessed is not available. During the actual removal process, a total of 0.6 yd3 of
contaminated earth and uranium mill tailings, 6 to 12 inches deep were removed from a
3 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 and basement of the structure, a surface scan 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.
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 12 to 21 uR/h. Exterior surface gamma measurements taken from
the excavated areas prior to backfilling ranged from 14 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 226Ra concentration of 2.8 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
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 2/27/95 to 5/30/95). The average annual
working level (WL) of radon progeny concentration based on the DOE approved prompt
method, as determined by the Tech./Ops-Landauer Corporation, was 0.0060, 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
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 m\ 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)
5
Table 2. Results of ORNL analysis of Geotech soil samples
from 116 North 1st West Street, Monticello Utah (MS00529-MR)
226Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No.a No/ (cm)
XI NCA 970 >15 1.7 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 1995. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00529-MR, Address: 116 North First West Street,
Monticello, Utah 84535, Geotech, Grand Junction, Colorado, September 1995.
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-00534-VL
Property Address: 164 North First West 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 =S 15 pCi/g
above background in any
15-cm layer bf 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 the DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
Rust Geotech
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[ 1 [ ] IX]
(Vacant Lot)
[ ] [X] [ ]
[X] [ ] [ ]
U.S. Department
of Enerov (DOE)
YES NO NOT TAKEN
[>] [ ] [ I
[>] [ ] [ ]
[ ] I 1 [VI
[ ] [ ] [X] [ ] [ ] [)*
(Vacant Lot)
[ ] [>] [ ]
[YJ 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.
11
SFCERTIFED
SFMS-09058
DOE ID No.: MS-00534-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. JEjusby 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.
jrtification Officii
U.S. Department of Energy
Date
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
DOE ID NO.: MS-00534-VL
ADDRESS: 164 NORTH FIRST WEST STREET
MONTICELLO, UTAH 84535
AUGUST 1995
Prepared for
U.S. Department of Energy
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
FOR
by
Wand<S. Busb/
er, 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-00534-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 the EPA standards and the
DOE hot spot criteria by the DOE Inclusion Survey Contractor. The DOE
reviewed these evaluation results and determined that the property
contained mill tailings (residual radioactive material) exceeding the EPA
standards. The Remedial Action Contractor was notified of the inclusion
of this property into the MVP Project and was authorized by the DOE to
conduct remedial action as required to bring the property into conformance
with the EPA standards and the DOE hot spot criteria.
1
DOE ID No.: MS-00534-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-00534-VL
Location No. M-327-1; beginning 367 feet
north and 114.5 feet east of the NW corner
of Block J, Monticello Townsite Survey,
south 70 feet, east 70 feet, north 70 feet,
west 70 feet to beginning, County of
San Juan, State of Utah
164 North First West Street
Monticello, Utah 84535

Vacant Lot (VL)
Oak Ridge National Laboratory
June 19, 1990
Rust Geotech
November 17, 1993
Diamond Back Services, Inc.
9861 Titan Park Circle
Littleton, Colorado
September 15, 1994
October 12, 1994
Interior:
Exterior:
0 cubic yards
7 cubic yards
34 square meters (m2)
August 1995
2
DOE ID No.: MS-00534-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 Block MS-09050-BK.
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-00534-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
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 15 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
2.3 picocuries per gram (pCi/g), as indicated in Appendix
Table 3.1.
4
DOE ID No.: MS-00534-VL
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by the EPA standards (40 CFR 192.12, 192.20-23)
and the DOE hot spot criteria, as indicated in the Certification Data
Summary below.
Therefore, the property located at 164 North First West Street, in
Monticello, Utah, is recommended for certification as required by the
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 result was
2.3 pCi/g.f
•The background radium-226 concentration is approximately 2.0 pCi/g.
TThe hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-00534-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:07-10-95
MS-00534.VL WP52
REV053193
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00534-VL
Address: 164 North First West Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range U/R/h) Ticket No. Method" (pCi/g)
V-l 12-15 NCG 443 OCS 2.3
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 -
Y
10
12 1 4 16 18 20 22 24 26 28
NORTH FIRST WEST STREET
r n 12-15
12-15
O 0* V-1
12-15
L J 12-15
SCALE IN FEET
20 10 0 20 40
M:\FAS\033\0003\RM00534V 07/26/95 11:09om 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.
J I
30
©
<D
FJ.vTl
LV/.Vj
12-15
12
V-1
16-17
32 34 36 38
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 SURVEY
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
RESIDENCE-NO. OF OCCUPANTS
NON—RES10ENCE—MAN—HRS./WK.
INSTRUMENT NO.
SURVEY DATE
VERIFICATION
BY CK. A.E. APP. NO. DATE
40
- 28
- 24
WY CK. A.E. APP.
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE, COLORADO
DRAWN rr CHECKED^^^^
PROJ. ENOC
SUBMITTED
164 NORTH FIRST WEST STREET
MONTICELLO, UTAH
Rust Qeotech
T)ATE I APPROVAL DOE
DOE io NO. MS-00534-VL
DWC.NO. 3-B00534-V1 5HT 1 or 1
30
26
22
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 PHONE: (970) 24<W20O
MANAGED BY LOCKHEED MARTIN ENERGY RESEARCH CORPORATION FAX: [phone]
FOR THE U.S. DEPARTMENT OF ENERGY
POST OFFICE BOX 2567
GRAND JUNCTION, COLORADO 81502 MAR t 6 1866
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 verifica-
tion 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:
Property Owner:
Owner Address:
Tenant Name:
MS00534-VL
164 North 1st 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
164 NORTH 1ST WEST STREET
MONTICELLO, UTAH (MS00534-VL)
S. M. Smith
March 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 164 North 1st West Street,
Monticello, Utah (MS00534-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
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, RUST
Geotech, the remedial action contractor designated by DOE, performed remedial action
on the vicinity property at 164 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
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 164 NORTH 1ST WEST STREET
MONTICELLO, UTAH (MS00534-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) 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 ofthe 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.DOE1990b).
*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 164 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 (Geotech
1995).
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 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 ofthe 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 ofthe property completion report prepared by Geotech (Geotech 1995)
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 50, 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 inches deep were removed from a 34 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
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 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 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 2.3 pCi/g. ORNL ETS
obtained this sample and performed a confirmatory analysis which showed a 226Ra
concentration of 2.8 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.
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.
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
(10G7A),/l, 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 164 North 1st West Street, Monticello Utah (MS00534-VL)
226Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No." No/ (cm)
XI NCG 443 >15 2.8 2.3
" 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: MS00534-VL, Address: 164 North First West Street,
Monticello, Utah 84535, Geotech, Grand Junction, Colorado, August 1995.
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-00585-RS
Property Address: 33 Blue Mountain Drive
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 the DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] I ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
pc] [ ] [ ]
[/] [ ] [ ]
[>1 I 1 U
PS [ 1 [ 1
[ 1 IX [ 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.
Ililllllllll llllllllll
SFCERTIFED SFMS-00585
DOE ID No.: MS-00585-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 the concurrence of
the U.S. Nuclear Regulatory Commission because supplemental
standards were applied per 40 CFR 192.21.
*>Hfriil.)1«Tfg
/anda SJBusby 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 the
concurrence of the U.S. Nuclear Regulatory Commission because
supplemental standards were applied per 40 CFR 192.21.
Certification Officii
U.S. Department of Energy
ate 9 Date
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
DOE ID NO.: MS-00585-RS
ADDRESS: 33 BLUE MOUNTAIN DRIVE
MONTICELLO, UTAH 84535
MARCH 1995
Prepared for
U.S. Department of Energy
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
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-00585-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 the EPA standards and the
DOE hot spot criteria by the DOE Inclusion Survey Contractor. The DOE
reviewed these evaluation results and determined that the property
contained mill tailings (residual radioactive material) exceeding the EPA
standards and the DOE hot spot criteria. The Remedial Action Contractor
was notified of the inclusion of this property into the MVP Project and was
authorized by the DOE to conduct remedial action as required to bring the
property into conformance with the EPA standards and the 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-00585-RS
MS-00585-RS
Location No. M-405; beginning at the
NE corner of Lot 23, Blue Mountain
Subdivision, south 84 degrees 22 minutes
west 108.65 feet, south 5 degrees
33 minutes east 100 feet, north 84 degrees
22 minutes east 121.08 feet, north
12 degrees 45 minutes west 100 feet more
or less to the point of beginning, City of
Monticello, County of San Juan, State of
Utah
33 Blue Mountain Drive
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
August 27, 1991
Rust Geotech
Not applicable: streamlined remediation
procedures were followed
Mountain Region Corporation
117 29 3/4 Road
Grand Junction, Colorado
August 24, 1993
September 22, 1993
Interior: 0 cubic yards
Exterior: 4.6 cubic yards
17.8 square meters (ma)
March 1995
2
DOE ID No.: MS-00585-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 3 cubic yards of contamination,
12 inches deep, within the property. The remedial action process included
the removal of approximately 4.6 cubic yards of residual radioactive
material, ranging from 6 inches 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-00585-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 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 12 microroentgens per hour U/R/h)
to 23 fjR/h (Appendix Figure 2.1). The results of analyses for
radium-226 in two composite soil samples were both
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 0.0060 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-00585-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by the EPA standards (40 CFR 192.12, 192.20-23)
and the DOE hot spot criteria, as indicated in the Certification Data
Summary below.
Therefore, the property located at 33 Blue Mountain Drive, in
Monticello, Utah, is recommended for certification as required by the
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 12 //R/h to 14 //R/h.
Annual average was
0.0060 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 were
both 1.6 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-00585-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
DAG:01-31-95
MS-00585.RS WP51
REV053193
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00585-RS
Address: 33 Blue Mountain Drive, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range U/R/h) Ticket No. Method* (pCi/g)
V-l 15 - 23 NCD 662 OCS 1.6
V-2 17 - 21 NCE 480 OCS 1.6
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-00585-RS
Address: 33 Blue Mountain Drive, Monticello, Utah
Instrument Type: Terradex Radtrak® Detector
Detector
Number Start Date End Date
Tracks Per
mm2
Radon
Concentration
(pCi/L)
Working
Level
3839298
3853850
3839308
01-04-94
01-04-94
01-04-94
12-08-94
12-08-94
12-08-94
9.8
10.9
10.8
1.12
1.26
1.23
0.0056
0.0063
0.0062
Annual Average: 0.0060
See Appendix Figure 2.1 for the measurement location.
8
10
30
12 14 16 18 20 22 24 26
"i—i—i—i—T
28 30 32 34 36 38 40
30
28 28
26
24
22
20
18
16
1 4
12 -
Y
10
V-1
15-23
V-2
03 17-21
C RDC 12-15 rn 1 2 1 2X A
O
MULTI-LEVEL
FRAME HOUSE
W/BASEMENT z
o 70 12-14
12-14
SCALE IN FEET
20 10 0 20 40
I
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.
©
<D
rvi-.vi
iv.-.vj
12-15
12
V-1
16-17
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
POST-REMEDIAL ACTION 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
16
RESIDENCE-NO. or OCCUPANTS
NON—RESIOENCE—MAN—HRS./WK.
INSTRUMENT NO.
SURVEY DATE
VERIFICATION
BY CK. A.E. APP. CK. A.E. APP.
14
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE. COLORADO
7~ T
*J3£
33 BLUE MOUNTAIN DRIVE
MONTICELLO, UTAH
12
APPROVAL •OATT APPROVAL OOE -BSfT
OOEIDNO. MS-00585-RS
DWO.NO. 3-B00585-V1 ,HT 1 nr 1
10
10 12 1 4 16 18 20 22 24 26 28 30 32 34 36 38 40
OAK RIDGE NATIONAL LABORATORY
MANAGED BY MARTIN MARIETTA ENERGY SYSTEMS, INC.
GRAND JUNCTION OFFICE
RO. BOX 2567
GRAND JUNCTION. COLORADO 81502
AUG 3 1 1995
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.
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. MS00585-RS
Location Address: 33 Blue Mountain 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 VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
33 BLUE MOUNTAIN DRIVE
MONTICELLO, UTAH (MS00585-RS)
M. K. Jensen
August 1995
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY SYSTEMS, INC.
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-84OR21400
CONTENTS
LIST OF TABLES v
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 33 Blue Mountain Drive,
Monticello, Utah (MS00585-RS) 6
v
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, 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 1993, RUST
Geotech, the remedial action contractor designated by DOE, performed remedial action on
the vicinity property at 33 Blue Mountain 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 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 33 BLUE MOUNTAIN DRIVE
MONTICELLO, UTAH (MS00585-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 ofthe 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-AC05-84OR21400 with Lockheed Martin Energy Systems, Inc.
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 33 Blue Mountain 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 1995).
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 33 Blue
Mountain 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 (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1995)
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 using streamlined remedial action procedures, based on a memo to the
folio dated August 9, 1995.
The pre-remedial-action survey performed by Geotech identified 3 yd3 of mill tailings
12 inches deep. However, during the actual removal process, a total of 4.6 yd3 of
contaminated earth and uranium mill tailings, 6 to 12 inches deep were removed from a
17.8 m2 area.
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 of the structure and a suface 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 of the
residence ranged from 12 to 14 /jR/h. Exterior surface gamma measurements taken from
the excavated areas prior to backfilling ranged from 15 to 23 /iR/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 1.6 pCi/g for
both composite samples. ORNL ETS obtained these samples and performed a
confirmatory analysis which showed ^Ra concentrations ranging from 2.4 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. 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. This property was
remediated before this procedure change. The IVC observed that verification areaVl
exceeds 30% of the excavation average. The IVC will allow a correlation developed by
the RAC to estimate 226 Ra 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
concentration of 5.0 pCi/g. This value is well below the minimum concentration of 42
pCi/g needed, when assuming the maximum area under the hot spot guideline of 12 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). 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 one year (from 1/4/94 to 12/8/94). The average annual working
level (WL) of radon progeny concentration, as determined by the Tech./Ops-Landauer
Corporation, was 0.0060, 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
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 resolved as discussed in a meeting between Geotech and ORNL
on July 21, 1995. 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 ofthe elevated region.
Average annual radon proge- 0.03 WL
ny concentration (including
background)
(DOE 1990a)
Exposure to 222Rn
progeny
6
Table 2. Results of ORNL analysis of Geotech soil samples
from 33 Blue Mountain Drive, Monticello Utah (MS00585-RS)
^Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No.a No^ (cm)
MS00585X1 NCD 662 >15 2.6 1.6
MS00585X2 NCE 480 >15 2.4 1.6
" 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.
7
REFERENCES
Geotech 1995, Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00585-RS, Address: 33 Blue Mountain Drive, Monticello,
Utah 84535, Geotech, Grand Junction, Colorado, March 1995.
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.
ORNL, 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
DOE ID No.: MS-00624-VL
Property Address: Parcel No. A00170000010, North Creek Lane
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 £ 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 the DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ I
[ 1 [ 1 IX]
(Vacant Lot)
[ 1 [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
IX] [ 1 [ 1
[y] t ]
[ ] [ ]
[ ]
[>]
[ ] [ ] [X] [ ] [ ] [>]
(Vacant Lot)
I ] \X\ I ]
IX] 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.
•iiiiiii Milium
SFCERTIFED SFMS-00624
DOE ID No.: MS-00624-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 the concurrence
of the U.S. Nuclear Regulatory Commission because supplemental
standards were applied per 40 CFR 192.21.
[A 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
Date
U.S. Department of Energy
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00624-VL
ADDRESS: PARCEL NO. A00170000010
NORTH CREEK LANE
MONTICELLO, UTAH 84535
MARCH 1995
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
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
DOE ID No.: MS-00624-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 the EPA standards and the
DOE hot spot criteria by the DOE Inclusion Survey Contractor. The DOE
reviewed these evaluation results and determined that the property
contained mill tailings (residual radioactive material) exceeding the EPA
standards and the DOE hot spot criteria. The Remedial Action Contractor
was notified of the inclusion of this property into the MVP Project and was
authorized by the DOE to conduct remedial action as required to bring the
property into conformance with the EPA standards and the DOE hot spot
criteria.
1
DOE ID No.: MS-00624-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-00624-VL
Beginning at a point south 1,990.78 feet,
east 979.68 feet from the NW corner of
Section 36, T33S., R23E., Salt Lake Base
Meridian to the NW corner of Lot 1,
Mountain West Subdivision; east 280 feet,
south 00 degrees 27 minutes west
128.72 feet, west 258.16 feet, north
30 degrees 24 minutes 20 seconds west
42.57 feet, north 00 degrees 27 minutes
east 92 feet to the point of beginning, City
of Monticello, County of San Juan, State of
Utah
Parcel No. A00170000010
North Creek Lane
Monticello, Utah 84535

Vacant Lot (VL)
Oak Ridge National Laboratory
November 6, 1992
Rust Geotech
April 7, 1994
Crowley Construction, Inc.
East Route HC 63 Box 66
Monticello, Utah
September 14, 1994
September 26, 1994
Interior:
Exterior:
0 cubic yards
5 cubic yards
26 square meters (m2)
March 1995
2
DOE ID No.: MS-00624-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 8 cubic yards of contamination,
6 inches deep, within the property. The remedial action process included
the removal of approximately 5 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-00624-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
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 microroentgens per hour (//R/h)
to 16 //R/h (Appendix Figure 2.1). The result of analysis for
radium-226 in one composite soil sample was 1.1 picocuries per
gram (pCi/g), as indicated in Appendix Table 3.1.
4
DOE ID No.: MS-00624-VL
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by the EPA standards (40 CFR 192.12, 192.20-23)
and the DOE hot spot criteria, as indicated in the Certification Data
Summary below.
Therefore, the property located at Parcel No. A00170000010, North
Creek Lane, in Monticello, Utah, is recommended for certification as
required by the 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
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 ma.
< 5 pCi/g above
background/
Soil sample result was
1.1 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
4 0 *>"END,X
A»Pendix is """^"at/on <t„
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00624-VL
Address: Parcel No. A00170000010, North Creek Lane, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (//R/h) Ticket No. Method* (pCi/g)
V-l 13-16 NCG 106 OCS 1.1
See Appendix Figure 2.1 for the verification area.
*OCS = Opposed Crystal System
7
10
42
12 14 16 18 20 22 24 26 28 30 32 34 36 38 40 42 44
i—r
46 48
-i—r
50
42 i—r
40 40
38
36
34
32
30
28 -
26 -
24
22 -
•P v-i 13-16
12-16
z >
\
12-16
38
36
34
- 32
30
28
26
24
22
20
18
16
14
12
10
10
j L
12
NORTH
SCALE IN FEET
20 10 0
14
20
16
40
I
18
<D
LV.vj
12-15
12
v-1
16-17
J L
20
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
22 24
—I L
26 28
J L.
30
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 I L
32 34 36 38
- 20
- 18
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
mncNec-MQ. OF occuMHft
ci. AI. *PP. «. tut
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OmCf, COLORADO
"T-r 3Ji"
PARCEL NO. A00170000010
NORTH CREEK LANE
MONTICELLO, UTAH
16
14
12
'*•» MS-00824-VL
*•**3-C00624-V1 ,..1||f 1
40 42 44 46 48 50
10
GRAND JUNCTION OFFICE
RO. BOX 2567
GRAND JUNCTION, COLORADO 81502
MAY 2 2 1095
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, 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 exterior 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
MS00624-VL
A00170000010. North Creek Lane
Monticello. Utah 84535

OAK RIDGE NATIONAL LABORATORY
MANAGED BY MARTIN MARIETTA ENERGY SYSTEMS, INC.
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
A00170000010, NORTH CREEK LANE
MONTICELLO, UTAH (MS00624-VL)
N. F. Lewis
May 1995
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
MARTIN MARIETTA ENERGY SYSTEMS, INC.
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-84OR21400
CONTENTS
LIST OF TABLES v
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 5
iii
LIST OF TABLES
Applicable guidelines for protection against radiation
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 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 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 A00170000010 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 A00170000010, NORTH CREEK LANE
MONTICELLO, UTAH (MS00624-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) 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 (Abramiuk 1989).
•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-AC05-84OR21400 with Martin Marietta Energy Systems, Inc.
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 A00170000010, North Creek 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
1995).
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
A00170000010, 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 1990).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1995)
indicates the property was remediated as evaluated by DOE on the basis of
Environmental Protection Agency standards and the DOE guidelines (DOE 1990).
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 inches deep. However, during the actual removal process, a total of 5 yd3 of
contaminated earth and uranium mill tailings, 6 inches deep were removed from a 26 m2
area.
A post-excavation survey was performed by Geotech prior to backfilling of the
excavated areas. This survey consisted of a surface gamma scan, with a scintillometer,
and soil sampling. A sample representative ofthe bottom 15-cm (6-in.) soil layers ofthe
excavated area was 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
subtracted from radionuclide concentrations in soil samples. Applicable DOE guidelines
for protection against radiation are given in Table 1.
Gamma Measurements
Exterior gamma exposure rate measurements taken by Geotech from the excavated
areas prior to backfilling ranged from 13 to 16 fxR/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 of 1.1 pCi/g. ORNL ETS was unable to
obtain samples for corifirmatory 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 Guideline for areas <25 m2
(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
measurements fall below the limits prescribed by DOE guidelines. It is concluded that
the site successfully meets the DOE remedial action objectives.
« » •
5
REFERENCES
Abramiuk I. N.et al. 1989. Monticello Remedial Action Project Site Analysis Re-
port, GJ-10, prepared by Bendix Field Engineering Corporation, Grand Junction,
Colorado, for the U.S. Department of Energy, Surplus Facilities Management
Program, Richland, Washington.
Geotech 1995, Property Completion Report for Monticello Vicinity Property
Remedial Action for DOE ID NO: MS00624-VL, Address: Parcel No.
A00170000010 North Creek Lane, Monticello, Utah 84535, Geotech, Grand
Junction, Colorado, March 1995.
U.S. DOE 1990. 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.
ORNL, 1993. Environmental Technology Section (Formerly Pollutant
Assessment Group) Procedures Manual, ORNL 6645/R2, September 1993. Oak
Ridge National Laboratory, Grand Junction, Colorado.
DOE ID No.: MS-00658-RS
Property Address: 81 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 the DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ 1 [X] t ]
[X] [ ] [ ]
YES NO NOT TAKEN
Mil I 1
[V] [ ] [ ]
1X1 I 1 [ 1
[ 1 [A [ I
IX] I ] 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
SFCERTIFED
SFMS-09030
DOE ID No.: MS-00658-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 the concurrence of
the U.S. Nuclear Regulatory Commission because supplemental
standards were applied per 40 CFR 192.21.
[xl 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
DOE EVALUATION
U.S. Department of Energy
» »
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00658-RS
ADDRESS: 81 SOUTH THIRD EAST STREET
MONTICELLO, UTAH 84535
APRIL 1995
Prepared for
U.S. Department of Energy
by
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
Wa^oa S. Busfjy
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-00658-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 the EPA standards and the
DOE hot spot criteria by the DOE Remedial Action Contractor. The DOE
reviewed these evaluation results and determined that the property
contained mill tailings (residual radioactive material) exceeding the EPA
standards. The Remedial Action Contractor was notified of the inclusion
of this property into the MVP Project and was authorized by the DOE to
conduct remedial action as required to bring the property into conformance
with the EPA standards and the 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-00658-RS
MS-00658-RS
Lot 11, Meadowlark Acres Subdivision, City
of Monticello, County of San Juan, State of
Utah
81 South Third East Street
Monticello, Utah 84535

Residential Simple (RS)
Not applicable: inclusion requested by the
Remedial Action Contractor
December 31, 1991
Rust Geotech
July 27, 1992
Crowley Construction, Inc.
East Route HC 63 Box 66
Monticello, Utah
June 2, 1993
July 14, 1993
Interior: 0 cubic yards
Exterior: 48 cubic yards
175 square meters (m2)
April 1995
2
DOE ID No.: MS-00658-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-09030-BK.
The remedial action process included the removal of approximately
48 cubic yards of residual radioactive material, ranging from 7 inches to
8 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-00658-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 1991, as described in the final REA dated
July 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 microroentgens per hour (//R/h)
to 17 //R/h (Appendix Figure 2.1). The results of analyses for
radium-226 in two composite soil samples were 1.5 picocuries
per gram (pCi/g) and 2.1 pCi/g (Appendix Table 3.1). The
composite sample representing Area V-2 included soil removed
from MS-00659-RS (Area V-2).
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on measurements representing an annual average, the RDC
was 0.0070 working level (WL), as indicated in Appendix
Table 3.2. Appendix Figure 2.1 shows the measurement location
in the lowest habitable level of the structure.
4
DOE ID No.: MS-00658-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by the EPA standards (40 CFR 192.12, 192.20-23)
and the DOE hot spot criteria, as indicated in the Certification Data
Summary below.
Therefore, the property located at 81 South Third East Street, in
Monticello, Utah, is recommended for certification as required by the
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 lower level
was 10 //R/h to 12 //R/h.
Annual average was
0.0070 WL.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background1 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 mJ.
< 5 pCi/g above
background.*
Soil sample results were
1.5 pCi/g and 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 radium-226 concentration in the averaged area met the hot spot criteria.
5
DOE ID No.: MS-00658-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
DAG:03-14-95
MS-00658.RS WP52
REV053193
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00658-RS
Address: 81 South Third East Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range U/R/h) Ticket No. Method* (pCi/g)
V-l 14 - 17 MAW 070 OCS 2.1
V-2 13 - 17 NAW 079 OCS 1.5
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-00658-RS
Address: 81 South Third East Street, Monticello, Utah
Instrument Type: Terradex Radtrak® Detector
Radon
Detector Tracks Per Concentration Working
Number Start Date End Date mm2 (pCi/L) Level
3853857 01-04-94 12-08-94
3853820 01-04-94 12-08-94
3853805 01-04-94 12-08-94
13.3 1.53 0.0077
10.6 1.22 0.0061
12.3 1.41 0.0071
Annual Average: 0.0070
See Appendix Figure 2.1 for the measurement location.
8
10
30
12 14 16 18 20 22
T"
24 26 28 30 32 34 36 38 40
30
28 28
26
24
22
20
18
16
1 4
12
Y
10
20 10
— X
"1 5
v.v.
14-16 |
0 V-2
13-17 N
0 V-1
12-16 14-17
(RDC)
BI-LEVEL FRAME
HOUSE
10-12
Li 12-16 J
~7TT
SOUTH THIRD EAST STREET
SCALE IN FEET
20 40
o
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, BUILDrNG. OR OTHER FUTURE IMPROVEMENT LINES.
©
®
FT/.vl
QV.VJ
12-15
12
v-1
16-17
(RDC)
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN /x.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
POST-REMEDIAL ACTION RADON DECAY-PRODUCT
CONCENTRATION MEASUREMENT LOCATION
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
26
24
22
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
NO. QATt
RESIBENCE-NO. OT OCCUPANTS
NON-HIESIDENCE-IIAN-HRS./WK.
INSTRUMENT NO.
SURVEY DATE
VERIFICATION
CK. A.E. APP. NO. DATE BY CK. A.E. APP.
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE, COLORADO
81 SOUTH THIRD EAST STREET
MONTICELLO, UTAH
APPROVAL
GEOTECH INC
DATE I APPROVAL DOE T5ATT~
DOE ID NO. MS-00658-RS
DWC.NO. 3-B00658-V1 ,„ 1 „ 1
20
18
- 16
1 4
12
10
10 12 14 16 18 20 22 24 26 28 30 32 34 36 38 40
OAK RIDGE NATIONAL LABORATORY
MANAGED BY MARTIN MARIETTA ENERGY SYSTEMS, INC.
GRAND JUNCTION OFFICE
RO. BOX 2567
GRAND JUNCTION. COLORADO 81502
SEP 2 0 1995
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, 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: MS00658-RS
Location Address: 81 South 3rd East Street
Monticello. Utah 84535
Property Owner:

Monticello. Utah 84535
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
81 SOUTH 3RD EAST STREET
MONTICELLO, UTAH (MS00658-RS)
M. K. Jensen
September 1995
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY SYSTEMS, INC.
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-84OR21400
CONTENTS
LIST OF TABLES v
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 81 South 3rd East Street,
Monticello, Utah (MS00658-RS) 5
v
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. Lewis 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 1993, RUST
Geotech, the remedial action contractor designated by DOE, performed remedial action on
the vicinity property at 81 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. All deficiencies noted in the initial
review were corrected 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 81 SOUTH 3RD EAST STREET
MONTICELLO, UTAH (MS00658-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 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-AC05-84OR21400 with Lockheed Martin Energy Systems, Inc.
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 81 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 1995).
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 81 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
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 1995)
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 mill tailings 6 inches
deep. During the actual removal process, a total of 48 yd3 of contaniinated earth and
uranium mill tailings, 7 to 8 inches deep were removed from a 175 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 ofthe house and a surface scan of the exterior and soil sampling. Soil
samples representative of the bottom 15-cm (6-in.) soil layers of the 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
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
house ranged from 10 to 12 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, 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 of the two exterior verification areas.
Geotech's analysis of these samples show ^Ra concentrations of 2.1 and 1.5 pCi/g in the
composite samples. ORNL ETS obtained these samples and performed a confirmatory
analysis which showed ^Ra concentrations of 3.0 pCi/g for both samples. 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
determined by the Alpha-track method. To monitor radon levels, Geotech placed three
alpha-track detectors on the ground floor of the house located on this property for a
period of approximately one year (from 01/04/94 to 12/08/94). 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 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 were corrected
in the revised completion report as discussed in the meeting between Geotech and ORNL
on July 21, 1995. 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; 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)M,whereAisthe
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 81 South 3rd East Street, Monticello Utah (MS00658-RS)
226Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No." No* (cm)
MS00658X1 NAW-070 >15 3.0 2.1
MS00658X2 NAW-079 >15 3.0 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 1995, Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00658-RS, Address: 81 South Third East Street, Monticello,
Utah 84535, Geotech, Grand Junction, Colorado, April 1995.
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.
ORNL, 1993. Environmental Technology Section (Formerly Pollutant Assessments
Group) Procedures Manual, ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
1 <
DOE ID No.: MS-00659-RS
Property Address: 80 Meadowlark Lane
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech Qf 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. [XI • [ ] 11 l/i I 1 11
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] [ ] [ ] hr] [ ] I )
In-situ [ ] Lab [X]
Interior gamma is < 20 //R/h
above background in any
occupied or habitable
structure. [X] [ ] [ ] [X] [ ] 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] [ ] [ ] [*1 [ ] [ ]
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21. [ ] [X] [ ] [ ] [y] [ )
Hot spot criteria met as
outlined by the DOE
guidelines for FUSRAP
(Rev. 2, March 1987). [X] [ ] [ ] [yl 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
llllllllll
SFMS-09030
DOE ID No.: MS-00659-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 the concurrence of
the U.S. Nuclear Regulatory Commission because supplemental
standards were applied per 40 CFR 192.21.
[>] 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
Date
U.S. Department of Energy
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00659-RS
ADDRESS: 80 MEADOWLARK LANE
MONTICELLO, UTAH 84535
APRIL 1995
Prepared for
U.S. Department of Energy
by
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
WanddS. BusbT
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 Pape
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-00659-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 the EPA standards and the
DOE hot spot criteria by the DOE Remedial Action Contractor. The DOE
reviewed these evaluation results and determined that the property
contained mill tailings (residual radioactive material) exceeding the EPA
standards. The Remedial Action Contractor was notified of the inclusion
of this property into the MVP Project and was authorized by the DOE to
conduct remedial action as required to bring the property into conformance
with the EPA standards and the 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-00659-RS
MS-00659-RS
Lot 14, Meadowlark Acres Subdivision, City
of Monticello, County of San Juan, State of
Utah
80 Meadowlark Lane
Monticello, Utah 84535

Residential Simple (RS)
Not applicable: spillover inclusion requested
by the Remedial Action Contractor
December 31, 1991
Rust Geotech
July 27, 1992
Crowley Construction, Inc.
East Route HC 63 Box 66
Monticello, Utah
June 2, 1993
July 13, 1993
Interior: 0 cubic yards
Exterior: 4 cubic yards
19 square meters (m2)
April 1995
2
DOE ID No.: MS-00659-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 remedial action process included the removal of
approximately 4 cubic yards of residual radioactive material, ranging from
6 inches to 7 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-00659-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 1991, as described in the final REA dated
July 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 13 microroentgens per hour (//R/h)
to 18 //R/h (Appendix Figure 2.1). The results of analyses for
radium-226 in two composite soil samples were 1.5 picocuries
per gram (pCi/g) and 3.0 pCi/g (Appendix Table 3.1). The
composite sample representing Area V-2 included soil samples
collected from MS-00658-RS (Area V-2).
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on measurements representing an annual average, 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).
4
DOE ID No.: MS-00659-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by the EPA standards (40 CFR 192.12, 192.20-23)
and the DOE hot spot criteria, as indicated in the Certification Data
Summary below.
Therefore, the property located at 80 Meadowlark Lane, in Monticello,
Utah, is recommended for certification as required by the 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.
Suryev Results
Range for the ground
floor was 12 //R/h to
13//R/h.
Annual average was
0.0023 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 m3.
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
1.5 pCi/g and 3.0 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-00659-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
DAG:03-14-95
MS-00659.RS WP52
REV053193
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00659-RS
Address: 80 Meadowlark Lane, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range Ot/R/h) Ticket No. Method* (pCi/g)
V-l 13 - 18 NAW 758 OCS 3.0
V-2 13 - 17 NAW 079 OCS 1.5
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-00659-RS
Address: 80 Meadowlark Lane, Monticello, Utah
Instrument Type: Terradex Radtrak® Detector
Detector
Number Start Date End Date
Tracks Per
mm2
Radon
Concentration
(pCi/L)
Working
Level
3839394
3839302
3839344
01-04-94
01-04-94
01-04-94
12-08-94
12-08-94
12-08-94
4.2
3.5
4.2
0.47
0.39
0.47
0.0024
0.0020
0.0024
Annual Average: 0.0023
See Appendix Figure 2.1 for the measurement location.
8
10
30
12 14 16 18 20 22 24 26 28 30 32 34 36
~T~
38 40
30
28 - 28
26
24
22
20
18
16 -
14 -
12 -
Y
MEADOWLARK LANE
/// LLL.
13-16
ONE STORY FRAME
HOUSE
12-13
~l
I
3-16
V-1
13-18
• •
o • SHED
13-16 • •
L= 2
K 6 7
SCALE IN FEET x
or o
20 40 20 10
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
10 J I J L
nv.vi
[V/.VJ
12-15
12
V-1
16-17
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
POST-REMEDIAL ACTION RADON DECAY-PRODUCT
CONCENTRATION MEASUREMENT LOCATION
- 26
- 24
22
20
18
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
16
RESIDENCE-NO. or OCCUPANTS
NOK-RESIOENCE-MAN-HRS./WK.
INSTRUMENT NO.
VERIFICATION
CK. A.E. APP. NO. DATE BY CK. A.E. APP.
14
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE. COLORADO
H1S 80 MEADOWLARK LANE
MONTICELLO, UTAH
12
APPROVAL
GEOTICH INC
DATE I APPROVAL 66C
OOEIDNO. MS-00659-RS
DWC.NO. 3-B00659-V1 ,HT 1 „ 1
10
10 12 14 16 18 20 22 24 26 28 30 32 34 36 38 40
OAK RIDGE NATIONAL LABORATORY
MANAGED BY MARTIN MARIETTA ENERGY SYSTEMS, INC.
GRAND JUNCTION OFFICE
RO. BOX 2567
GRAND JUNCTION. COLORADO 81502
'Mi 2 8 m5
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, 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.
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: MS00659-RS
Location Address: 80 Meadowlark 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
80 MEADOWLARK LANE
MONTICELLO, UTAH (MS00659-RS)
M. K.Jensen
June 1995
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY SYSTEMS, INC.
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-84OR21400
CONTENTS
LIST OF TABLES v
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 80 Meadowlark Lane,
Monticello, Utah (MS00659-RS) 5
v
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 and N. F. Lewis 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 remedial actions on off-site (vicinity) properties that had been
contaminated by radioactive material resulting from mill operations. During 1993,
RUST Geotech, the remedial action contractor designated by DOE, performed remedial
action on the vicinity property at 80 Meadowlark 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 80 MEADOWLARK LANE
MONTICELLO, UTAH (MS00659-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
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 ofthe Environmental Assessment Group in the
Environmental Technology Section ofthe Health Sciences Research Division at Oak Ridge National Laboratory under DOE contract
DE-AC05-84OR21400 with Lockheed Martin Energy Systems, Inc.
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 80 Meadowlark 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 1995).
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 Meadowlark
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 1995)
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 mill tailings 6 inches
deep. During the actual removal process, a total of 4 yd3 of contaminated earth and
uranium mill tailings, 6 to 7 inches deep were removed from a 19 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. Soil samples
representative of the bottom 15-cm (6-in.) soil layers of the two excavated verification
areas were collected and blended to form representative composite soil samples.
Composite sample V2 includes soil samples taken from MS00658-RS.
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
house ranged from 12 to 13 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, 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 show ^Ra concentrations of 3.0 and 1.5 pCi/g
in the composite samples. ORNL ETS obtained one of these samples and performed a
confirmatory analysis which showed a 226Ra concentration of 3.2 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 nr (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 house located on this property for a
period of approximately one year (from 01/04/94 to 12/08/94). 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 upon the results of the post-remedial-action data, which are corifirmed 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 ^Ra 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 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.
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.
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 80 Meadowlark Lane, Monticello Utah (MS00659-RS)
226Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No." No^ (cm)
MS00659X1 NAW 758 >15 3.2 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.
6
REFERENCES
Geotech 1995, Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00659-RS, Address: 80 Meadowlark Lane, Monticello, Utah
84535, Geotech, Grand Junction, Colorado, April 1995.
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.
ORNL, 1993. Environmental Technology Section (Formerly Pollutant Assessments
Group) Procedures Manual, ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
! DOE ID No.: MS-00662-RS
Property Address: 381 First South Meadowlark Lane
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech of Energy (PQE)
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 the DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
OC] [ ] [ ]
[X] [ ] I 1
[y] [ ] [ ]
[*] [ ] [ ]
[ } [X 11
IX] [ ] [ ]
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 illlllll
SFMS-09044 v
DOE ID No.: MS-00662-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. JBusby 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.
Rification Official ' Certification Official ' Date
U.S. Department of Energy
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00662-RS
ADDRESS: 381 FIRST SOUTH MEADOWLARK LANE
MONTICELLO, UTAH 84535
AUGUST 1995
Prepared for
U.S. Department of Energy
by
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
Manag
Busby
onticello 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-00662-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 the EPA standards and the
DOE hot spot criteria by the DOE Remedial Action Contractor. The DOE
reviewed these evaluation results and determined that the property
contained mill tailings (residual radioactive material) exceeding the EPA
standards. The Remedial Action Contractor was notified of the inclusion
of this property into the MVP Project and was authorized by the DOE to
conduct remedial action as required to bring the property into conformance
with the EPA standards and the DOE hot spot criteria.
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-00662-RS
MS-00662-RS
Lot 22, Meadowlark Acres Subdivision,
City of Monticello, County of San Juan,
State of Utah
381 First South Meadowlark Lane
Monticello, Utah 84535

Residential Simple (RS)
Not applicable: inclusion requested by the
Remedial Action Contractor
December 9, 1991
Rust Geotech
November 21, 1992
Crowley Construction, Inc.
East Route HC 63 Box 66
Monticello, Utah
May 18, 1993
July 13, 1993
Interior: 0 cubic yards
Exterior: 32 cubic yards
160 square meters (ma)
August 1995
DOE ID No.: MS-00662-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-09044-BK.
The remedial action process included the removal of approximately
32 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-00662-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 1991, as described in the final REA dated
November 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 11 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 were 2.7
and 3.7 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 0.0078 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-00662-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by the EPA standards (40 CFR 192.12, 192.20-23)
and the DOE hot spot criteria, as indicated in the Certification Data
Summary below.
Therefore, the property located at 381 First South Meadowlark Lane, in
Monticello, Utah, is recommended for certification as required by the
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 11 to 13 //R/h.
Annual average was
0.0078 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 were
2.7 and 3.7 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-00662-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:07-18-95
MS-00662.RS WP52
REV053193
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00662-RS
Address: 381 First South Meadowlark Lane, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (//R/h) Ticket No. Method' (pCi/g)
V-l 15 - 20 NCC Oil OCS 2.7
V-2 14 - 19 NCC 012 OCS 3.7
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-00662-RS
Address: 381 First South Meadowlark Lane, Monticello, Utah
Instrument Type: Terradex Radtrak* Detector
Radon
Detector Tracks Per Concentration Working
Number Start Date End Date mm2 (pCi/L) Level
3853863 01-04-94 12-08-94
3853909 01-04-94 12-08-94
3854022 01-04-94 12-08-94
14.8 1.71 0.0086
12.7 1.46 0.0073
13.1 1.51 0.0076
Annual Average: 0.0078
See Appendix Figure 2.1 for the measurement location.
8
10
30
12 14 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
1 r 0 O 0
11-16
0
SHED
13-15 [
(RDC) 6 .-.
TWO STORY
FRAME HOUSE v-2
14-19
11-13
® o
o
a a OOO Oooooo 11-16
o
V-1
0 >63 15-20 © J IS" O
V77 777"
FIRST SOUTH MEADOWLARK LANE
SCALE IN FEET
20 10 0 20 40
M:\FAS\033\0003\RM00662V 07/18/95 10:45om 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.
J I
®
FT/.Ti
LV.vj
12-15
12
v-1
16-17
(RDC)
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
POST-REMEDIAL ACTION RADON DECAY-PRODUCT
CONCENTRATION MEASUREMENT LOCATION
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
- 28
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
RESIDENCE-NO. OF OCCUPANTS
HO N - HCS 10 E NCE-MAN-HRS /WK.
INSTRUMENT NO.
SURVEY DATE
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE. COLORADO
ano
381 FIRST SOUTH
MEADOWLARK LANE
MONTICELLO, UTAH
APPROVAL
Rust Qeotech
APPROVAL OOC
DOE.ONO. MS-00662-RS
owe.HO. 3-B00662-V1 SHT, 1 „
26
24
22
20
18
- 16
14
12
10
1 0 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 U.S. DEPARTMENT OF ENERGY
POST OFFICE BOX 2567
GRAND JUNCTION, COLORADO 81502
PHONE: [phone]
FAX: [phone]
MAR 2 6 1986
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 verifica-
tion 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:
Tenant Name:
MS00662-RS
381 1st South Meadowlark Lane
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
3811ST SOUTH MEADOWLARK LANE
MONTICELLO, UTAH (MS00662-RS)
M. J. Wilson-Nichols
March 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 381 1 st South Meadowlark
Lane, Monticello, Utah (MS00662-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 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
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 1993, RUST
Geotech, the remedial action contractor designated by DOE, performed remedial action
on the vicinity property at 381 1st South Meadowlark 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 3811ST SOUTH MEADOWLARK LANE
MONTICELLO, UTAH (MS00662-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 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 381 1st South Meadowlark 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
1995).
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 381 1st South
Meadowlark 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 1995)
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 44, therefore, the quantity of material
assessed is not available. During the actual removal process, a total of 32 yd3 of
contaminated earth and uranium mill tailings, approximately 6 inches deep were removed
from a 160 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 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 11 to 13 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 ofthe two
excavated areas from the bottom 15-cm (6-in.) soil layers. Geotech's analysis of these
samples showed 226Ra concentrations of 2.7 and 3.7 pCi/g in the composite samples.
ORNL ETS obtained these samples and performed a confirmatory analysis, which
showed 226Ra concentrations of 5.4 to 6.7 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
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 January 4,1994 to December 8,1994). The
average annual working level (WL) of radon progeny concentration, as determined by
the TechVOps-Landauer Corporation, was 0.0078, 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 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
(1007A)'/J, 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 3811st South Meadowlark Lane, Monticello Utah (MS00662-RS)
226Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No.° No* (cm)
XI NCC Oil >15 5.4 2.7
X2 NCC 012 >15 6.7 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 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: MS00662-RS, Address: 381 First South Meadowlark Lane,
Monticello, Utah 84535, Geotech, Grand Junction, Colorado, August 1995.
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-00663-RS
Property Address: 97 Meadowlark 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 :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 the DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
[Xl I 1 [ 1
MM [ ]
W [ 1 [ 1
LX] [ ] [ ]
[ 1 IX [ 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 oamma
exposure rates that do not exceed 30 percent above normal background.
llllllllll
SFCERTIFED •••111 SFMS-09044
DOE ID No.: MS-00663-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 sby 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.
Cettlfication Official Date
U.S. Department of Energy
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00663-RS
ADDRESS: 97 MEADOWLARK LANE
MONTICELLO, UTAH 84535
AUGUST 1995
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-00663-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 the EPA standards and the
DOE hot spot criteria by the DOE Remedial Action Contractor. The DOE
reviewed these evaluation results and determined that the property
contained mill tailings (residual radioactive material) exceeding the EPA
standards. The Remedial Action Contractor was notified of the inclusion
of this property into the MVP Project and was authorized by the DOE to
conduct remedial action as required to bring the property into conformance
with the EPA standards and the 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-00663-RS
MS-00663-RS
Lot 25, Meadowlark Acres Subdivision, City
of Monticello, County of San Juan, State of
Utah
97 Meadowlark Lane
Monticello, Utah 84535

Residential Simple (RS)
Not applicable: inclusion requested by the
Remedial Action Contractor
December 9, 1991
Rust Geotech
November 21, 1992
Crowley Construction, Inc.
East Route HC 63 Box 66
Monticello, Utah
May 18, 1993
July 13, 1993
Interior: 0 cubic yards
Exterior: 110 cubic yards
496 square meters (m2)
August 1995
2
DOE ID No.: MS-00663-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-09044-BK. The remedial action process included the removal of
approximately 110 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-00663-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 1991, as described in the final REA dated
November 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 13 to 19 microroentgens per
hour (//R/h), as indicated on Appendix Figure 2.1. The results of
analyses for radium-226 in five composite soil samples ranged
from 1.8 to 2.7 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 0.0046 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-00663-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by the EPA standards (40 CFR 192.12, 192.20-23)
and the DOE hot spot criteria, as indicated in the Certification Data
Summary below.
Therefore, the property located at 97 Meadowlark Lane, in Monticello,
Utah, is recommended for certification as required by the 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
0.0046 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 backgroundt 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
2.7 pCi/g.**
*The background exposure rate is approximately 14 //R/h.
fThe 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-00663-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
WKR:07-18-95
MS-00663.RS WP52
REV053193
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00663-RS
Address: 97 Meadowlark Lane, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (//R/h) Ticket No. Method* (pCi/g)
V-l 13 - 19 NCC 006 OCS 2.3
V-2 14 - 19 NCC 007 OCS 2.7
V-3 13 - 17 NCC 008 OCS 1.8
V-4 14 - 18 NCC 009 OCS 2.0
V-5 13 - 18 NCC 010 OCS 2.2
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-00663-RS
Address: 97 Meadowlark Lane, Monticello, Utah
Instrument Type: Terradex Radtrak* Detector
Detector
Number Start Date End Date
Tracks Per
mm2
Radon
Concentration
(pCi/L)
Working
Level
3853818
3853959
3839366
01-04-94
01-04-94
01-04-94
12-08-94
12-08-94
12-08-94
6.6
7.4
9.8
0.76
0.85
1.11
0.0038
0.0043
0.0056
Annual Average: 0.0046
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 - 28
26
24
22
20
18
16
14
12
Y
10
or
<
o o <
13-16
O V-5
13-18
s 13-16
QQOQ ONE STORY
FRAME HOUSE
WITH CRAWL
SPACE
ID
o v-i V-4
13-19 14-18 12-13
OGOOOOOQOOOOO •
RDC ?1.
v.-o
o
13-16
V-3
V-2 13-17
14-9 V-1 1 2
•SHED 13-19
12 12
777
FIRST SOUTH MEADOWLARK LANE
SCALE IN FEET
20 10 0 20 40
M:\FAS\033\0003\RM00663V 07/18/95 1:21pm T50780
J I
ft
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.
©
<D
rv.-.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
POST-REMEDIAL ACTION RADON DECAY-PRODUCT
CONCENTRATION MEASUREMENT LOCATION
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION
- 26
24
- 22
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
RESIOEMCE-NO. Of OCCUPANTS
NON-RESIDCNCE-UAN-HRS./WK.
INSTRUMENT NO.
CK. A.E. APP. NO. DATC BY CK. A.E. AFP.
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE, COLORADO
-r-r 97 MEADOWLARK LANE
MONTICELLO, UTAH
APPROVAL
Rust Qeotech
"BATE-APPROVAL DOE -OAff
DOC ID NO. MS-00663-RS
DWG.HO. 3-BQQ663-V1 SHT, 1 or 1
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
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]
WAR Z 6 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 verifica-
tion 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:
Tenant Name:
MS00663-RS
97 Meadowlark Lane
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
97 MEADOWLARK LANE
MONTICELLO, UTAH (MS00663-RS)
M. J. Wilson-Nichols
March 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 97 Meadowlark Lane,
Monticello, Utah (MS00663-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
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
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 1993, RUST
Geotech, the remedial action contractor designated by DOE, performed remedial action
on the vicinity property at 97 Meadowlark 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 97 MEADOWLARK LANE
MONTICELLO, UTAH (MS00663-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 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 single family residence located at 97 Meadowlark Lane, Monticello,
Utah. The remedial action plan re-quired 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 (Geotech
1995).
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 97
Meadowlark 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 property completion report prepared by Geotech (Geotech 1995)
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 44, therefore, the quantity of material
assessed is not available. During the actual removal process, a total of 110 yd3 of
contaminated earth and uranium mill tailings, 6 to 12 inches deep were removed from a
496 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 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 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 19 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
composite soil samples representative of an average over the five exterior verification
areas. Geotech's analysis of these samples showed 226Ra concentrations ranging from 1.8
to 2.7 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 2.6 to 3.4 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).
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 one year (from January 4,1994 to December 8,1994). 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 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
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
(1007A)'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 97 Meadowlark Lane, Monticello Utah (MS0Q663-RS)
226Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No." No^ (cm)
X2 NCC 007 >15 3.4 2.7
X4 NCC 009 >15 3.0 2.0
X5 NCC 010 >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.
6
REFERENCES
Geotech 1995. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00663-RS, Address: 97 Meadowlark Lane, Monticello, Utah
84535, Geotech, Grand Junction, Colorado, August 1995.
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-00758-RS
Property Address: 97 North Fourth West Street
VICINITY PROPERTY CERTIFICATION SUMMARY AND
SUMMARY EVALUATION
Rust Geotech
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 //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.
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
I 1 [X] [ ]
RECOMMENDATION
U.S. Department
of Energy (DOE)
YES NO NOT TAKEN
M [ 1 [ I
[/] I 1 [ 1
[XJ [ ] [ ]
Mil I ]
Ml* I 1
Hot spot criteria met as
outlined by the DOE
guidelines for FUSRAP
(Rev. 2, March 1987). [X] [ ] [ ] [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.
•Illlllll IIIM11I1IU
SFCERTIFED SFMS-00758
DOE ID No.: MS-00758-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 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.
Manager, Monticello Programs
Rust Geotech
Date
DOE EVALUATION
Date
U.S. Department of Energy
PROPERTY COMPLETION REPORT
DOE ID NO.: MS-00758-RS
ADDRESS: 97 NORTH FOURTH WEST STREET
MONTICELLO, UTAH 84535
MARCH 1995
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
DOE ID No.: MS-00758-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 the EPA standards and the
DOE hot spot criteria by the DOE Inclusion Survey Contractor. The DOE
reviewed these evaluation results and determined that the property
contained mill tailings (residual radioactive material) exceeding the EPA
standards and the DOE hot spot criteria. The Remedial Action Contractor
was notified of the inclusion of this property into the MVP Project and was
authorized by the DOE to conduct remedial action as required to bring the
property into conformance with the EPA standards and the 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-00758-RS
MS-00758-RS
Beginning at a point 249.5 feet north of the
SE corner of the SW4SW4 of Section 25,
T33S., R23E., Salt Lake Base Meridian;
north 130 feet, west 249.5 feet, south
130 feet, east 249.5 feet to the point of
beginning, City of Monticello, County of
San Juan, State of Utah
97 North Fourth West Street
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
August 30, 1991
Rust Geotech
Not applicable: streamlined remediation
procedures were followed
Not applicable: streamlined remediation
procedures were followed
July 27, 1992
July 29, 1992
Interior: 0 cubic yards
Exterior: 0.1 cubic yards
0.3 square meters (m2)
March 1995
2
DOE ID No.: MS-00758-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 contamination, 6 inches deep,
within the property. The remedial action process included the removal of
approximately 0.1 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-00758-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 microroentgens per hour (/vR/h)
to 18 //R/h (Appendix Figure 2.1). The result of analysis for
radium-226 in one individual soil sample was 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 0.0110 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).
4
DOE ID No.: MS-00758-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by the EPA standards (40 CFR 192.12, 192.20-23)
and the DOE hot spot criteria, as indicated in the Certification Data
Summary below.
Therefore, the property located at 97 North Fourth West Street, in
Monticello, Utah, is recommended for certification as required by the
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 12 //R/h to 13 //R/h.
Annual average was
0.0110 WL.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above backgroundr in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above backgroundt 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
1.0 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-00758-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:03-01-95
MS-00758.RS WP52
REV053193
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00758-RS
Address: 97 North Fourth West Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (//R/h) Number Method* (pCi/g)
^ V
V-l 17 - 18 Rl OCS 1.0
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-00758-RS
Address: 97 North Fourth West Street, Monticello, Utah
Instrument Type: Terradex Radtrak® Detector
Detector
Number Start Date End Date
Tracks Per
mm2
Radon
Concentration
(pCi/L)
Working
Level
3760364
3760413
3760451
03-10-93
03-10-93
03-10-93
03-07-94
03-07-94
03-07-94
24.0
23.5
23.3
2.23
2.18
2.16
0.0112
0.0109
0.0108
Annual Average: 0.0110
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 20 22 24 26
i—T
28 30 32
i—T
34 36 38 40 42 44
~T~
46 48 51
///
WEST FIRST NORTH STREET
-LU LU
13-15
13-15
V-1
17-18
13-15
GARAGE
12-15
13-15
I
(ROC)
ONE STORY
BRICK HOUSE
W/BASEMENT
12-13
13-15
<D
iv.-.vj
12-15
12
v-1
16-17
i£G_ENfi
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
POST—REMEDIAL ACTION RADON DECAY—PRODUCT
CONCENTRATION MEASUREMENT LOCATION
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
20 10
SCALE IN FEET
20 40 NORTH
_J
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.
NE-HO. or OCGUNim U.S. DEPARTMENT OF ENERGY
6RAMD JUNCTION WWJCCTS OFflCt. COLORADO
97 NORTH FOURTH WEST ST.
MONTICELLO, UTAH
"•••»• MS-00758-RS
| MI jAPHWULHt j I
• 3-C0075B-V1 „ 1 _ 1
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 MARTIN MARIETTA ENERGY SYSTEMS, INC.
GRAND JUNCTION OFFICE
RO. BOX 2567
GRAND JUNCTION. COLORADO 81502
MAY 1 6 1995
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P.O. Box 2567
Grand Junction, 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
MS00758-RS
97 North 4th West 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
97 NORTH 4TH WEST STREET
MONTICELLO, UTAH (MS00758-RS)
M. K. Jensen
May 1995
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
MARTIN MARIETTA ENERGY SYSTEMS, INC.
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-84OR21400
CONTENTS
LIST OF TABLES v
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
ii
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 N. F. Lewis and A. R. Jones for technical reviews.
viii
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-she (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 97 North 4th 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).
vii
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 97 NORTH 4TH WEST STREET
MONTICELLO, UTAH (MS00758-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 IX 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 (Abramiuk 1989).
*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-AC05-84OR21400 with Martin Marietta Energy Systems, Inc.
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 97 North 4th 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 1995).
The DOE adopted a policy to assign an independent contractor to verity 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 97 North 4th
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 ofthe entire property that is to be certified and (2) that the remedial action
reduced contamination to below applicable DOE guidelines (DOE 1990).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1995)
indicates the property was remediated as evaluated by DOE on the basis of Environmental
Protection Agency standards and the DOE guidelines (DOE 1990). 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 mill tailings 6 inches
deep. However, during the actual removal process, a total of 0.1 yd3 of contaminated
earth and uranium mill tailings, 12 inches deep were removed from a 0.3 m2 area.
A post-excavation survey was performed by Geotech prior to backfilling of the
excavated area. This survey consisted of gamma scans with a scintillometer of the ground
level ofthe structures and a suface scan of the exterior and soil sampling. An individual
sample representative of the bottom 15-cm (6-in.) soil layer of the excavated area was
collected.
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 12 to 13//R/h. Exterior surface gamma measurements taken from
the excavated area prior to backfilling ranged from 17 to 18//R/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 1.0 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. 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 detectors on the ground floor of the residence located on this property for a
period of approximately one year (from 3/10/93 to 3/7/94). The average annual working
level (WL) of radon progeny concentration, as determined by the Tech./Ops-Landauer
Corporation, was 0.0110, which is 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
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 IS 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
Maximum Permissible
concentration of Ra226 in soil
above background level, for
areas less than 25 m2.
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.
Average annual radon proge- 0.03 WL
ny concentration (including
background)
(DOE 1990)
Exposure to Rn
progeny
5
REFERENCES
Abramiuk I. N.et al. 1989. Monticello Remedial Action Project Site Analysis Report, GJ-
10, prepared by Bendix Field Engineering Corporation, Grand Junction, Colorado, for the
U.S. Department of Energy, Surplus Facilities Management Program, Richland,
Washington.
Geotech 1995, Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00758-RS, Address: 97 North 4th West Street, Monticello,
Utah 84535, Geotech, Grand Junction, Colorado, March 1995.
U.S. DOE 1990. 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.
ORNL, 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
DOE ID No.: MS-00782-RS
Property Address: 97 East Fifth North 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 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 the DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
MM I 1
I/] [ 1 [ 1
»1 I 1 I 1
[y] I ] I 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.
iniiiiii iinnnim
SFCERTIFED SFMS-80782
DOE ID No.: MS-00782-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 the concurrence of
the U.S. Nuclear Regulatory Commission because supplemental
standards were applied per 40 CFR 192.21.
[A] 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
Date
U.S. Department of Energy
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00782-RS
ADDRESS: 97 EAST FIFTH NORTH STREET
MONTICELLO, UTAH 84535
MARCH 1995
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-00782-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 the EPA standards and the
DOE hot spot criteria by the DOE Inclusion Survey Contractor. The DOE
reviewed these evaluation results and determined that the property
contained mill tailings (residual radioactive material) exceeding the DOE
hot spot criteria. The Remedial Action Contractor was notified of the
inclusion of this property into the MVP Project and was authorized by the
DOE to conduct remedial action as required to bring the property into
conformance with the EPA standards and the 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-00782-RS
MS-00782-RS
Location No. M-516; beginning at a point
2,640 feet north and 1,254 feet west of
the SE corner of Section 25, T33S., R23E.,
Salt Lake Base Meridian; south 214.5 feet,
east 100 feet, north 214.5 feet, west
100 feet to the point of beginning, City of
Monticello, County of San Juan, State of
Utah
97 East Fifth North Street
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
February 21, 1991
Rust Geotech
Not applicable: streamlined remediation
procedures were followed
Not applicable: streamlined remediation
procedures were followed
June 18, 1992
July 15, 1992
Interior: 0 cubic yards
Exterior: 0.1 cubic yards
0.3 square meters (m2)
March 1995
2
DOE ID No.: MS-00782-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 contamination, 6 inches deep,
within the property. The remedial action process included the removal of
approximately 0.1 cubic yards of residual radioactive material, 6 inches
deep (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-00782-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. 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 microroentgens per hour (//R/h)
to 19 //R/h (Appendix Figure 2.1). The result of analysis for
radium-226 in an individual soil sample of this area was
3.6 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 0.0041 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-00782-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by the EPA standards (40 CFR 192.12, 192.20-23)
and the DOE hot spot criteria, as indicated in the Certification Data
Summary below.
Therefore, the property located at 97 East Fifth North Street, in
Monticello, Utah, is recommended for certification as required by the
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 //R/h to
13//R/h.
Annual average was
0.0041 WL.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above backgroundr in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above backgroundf 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
3.6 pCi/g.*
*The background exposure rate is approximately 13 //R/h.
TThe 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-00782-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
DAG:02-28-95
MS-00782.RS WP52
REV053193
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00782-RS
Address: 97 East Fifth North Street, Monticello, Utah
Exposure Soil Sample Meas. Radium-226
Area Rate (//R/h) Number Method* (pCi/g)
V-l 19 Rl OCS 3.6
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-00782-RS
Address: 97 East Fifth North Street, Monticello, Utah
Instrument Type: Terradex Radtrak® Detector
Radon
Detector Tracks Per Concentration Working
Number Start Date End Date mm2 (pCi/L) Level
3760503 03-09-93 03-08-94
3760472 03-09-93 03-08-94
3760392 03-09-93 03-08-94
10.4 0.94 0.0047
8.7 0.79 0.0040
8.0 0.73 0.0037
Annual Average: 0.0041
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
16 18 20 22
i—r
24
"T
26 28 30 32 34 36 38 40 42 44 46 48 51
12-15
ONE STORY
FRAME HOUSE
W/CRAWL SPACE
12-13
6 6YA
V-1
19pR/h
12-15
<D
rv.-.vi
|V.\Yj
12-15
FH
V-1
16-17
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
POST—REMEDIAL ACTION RADON DECAY—PRODUCT
CONCENTRATION MEASUREMENT LOCATION
-777-
EAST FIFTH NORTH STREET
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
SCALE IN FEET
20 40
J l_
16 18
J l_
20
NORTH
J 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.
22 24
J L
26
J L
a-m. or occuMm U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION WOJCCTt Off ICC. COLORADO
'i §7 EAST FIFTH NORTH STREET
MONTICELLO, UTAH
«•"• MS-00782-RS
28 30 32 34 36 38 40 42 44 46 48 5i
OAK RIDGE NATIONAL LABORATORY
MANAGED BY MARTIN MARIETTA ENERGY SYSTEMS, INC.
GRAND JUNCTION OFFICE
RO. BOX 2567
GRAND JUNCTION, COLORADO 81502
MAY 1 6 1995
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, 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.
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
MS00782-RS
97 East 5th North Street
Monticello. Utah 84535

Unknown
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
97 EAST 5TH NORTH STREET
MONTICELLO, UTAH (MS00782-RS)
M. K. Jensen
May 1995
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
MARTIN MARIETTA ENERGY SYSTEMS, INC.
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-84OR21400
CONTENTS
LIST OF TABLES v
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
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 N. F. Lewis 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 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 97 East 5th 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 97 EAST 5TH NORTH STREET
MONTICELLO, UTAH (MS00782-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 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 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 (Abramiuk 1989).
•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-AC05-84OR21400 with Martin Marietta Energy Systems, Inc.
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 97 East 5th 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 1995).
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 97 East 5th
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 1990).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1995)
indicates the property was remediated as evaluated by DOE on the basis of Environmental
Protection Agency standards and the DOE guidelines (DOE 1990). 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 mill tailings 6 inches
deep. During the actual removal process, a total of 0.1 yd3 of contaniinated earth and
uranium mill tailings, 6 inches deep were removed from a 0.3 m2 area.
A post-excavation survey was performed by Geotech prior to backfilling of the
excavated area. This survey consisted of gamma scans with a scintillometer of the ground
level ofthe structure and a suface scan of the exterior and soil sampling. An individual
sample representative of the bottom 15-cm (6-in.) soil layer of the excavated area was
collected.
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 12 to 13//R/h. The exterior surface gamma measurement taken
from the excavated area prior to backfilling was 12 to 19/zR/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 3.6 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. 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 detectors on the ground floor of the residence located on this property for a
period of approximately one year (from 3/9/93 to 3/8/94). The average annual working
level (WL) of radon progeny concentration, as determined by the Tech./Ops-Landauer
Corporation, was 0.0041, 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
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
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
(lOO/A)*, 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 1990)
5
REFERENCES
Abramiuk I. N.et al.1989. Monticello Remedial Action Project Site Analysis Report, GJ-
10, prepared by Bendix Field Engineering Corporation, Grand Junction, Colorado, for the
U.S. Department of Energy, Surplus Facilities Management Program, Richland,
Washington.
Geotech 1995, Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00782-RS, Address: 97 East 5th North Street, Monticello,
Utah 84535, Geotech, Grand Junction, Colorado, March 1995.
U.S. DOE 1990. 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.
ORNL, 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
DOE ID No.: MS-00799-RS
Property Address: 537 North Main 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. [X]* [ ] [ ] Lx] [ ] [ ]
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 < 20 //R/h
above background in any
occupied or habitable
structure. [X] [ ] [ ] [ft [ ] [ ]
The radon decay-product
concentration in any
occupied or habitable
structure is < 0.02
working level or, at
most, 0.03 working level. [X] [ ] [ ] pr] [ ] [ ]
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21. [ ] [X] [ ] [ ] [X []
Hot spot criteria met as
outlined by the DOE
guidelines for FUSRAP
(Rev. 2, March 1987). [X] [ ] [ ] [Xl I I II
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 HiUili
SFCERTIFED SFMS-00799
DOE ID No.: MS-00799-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 the concurrence of
the U.S. Nuclear Regulatory Commission because supplemental
standards were applied per 40 CFR 192.21.
LX] 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
DOE ID NO.: MS-00799-RS
ADDRESS: 537 NORTH MAIN STREET
MONTICELLO, UTAH 84535
JULY 1995
Prepared for
U.S. Department of Energy
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
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 Paoe
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-00799-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 the EPA standards and the
DOE hot spot criteria by the DOE Inclusion Survey Contractor. The DOE
reviewed these evaluation results and determined that the property
contained mill tailings (residual radioactive material) exceeding the DOE
hot spot criteria. The Remedial Action Contractor was notified of the
inclusion of this property into the MVP Project and was authorized by the
DOE to conduct remedial action as required to bring the property into
conformance with the EPA standards and the 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-00799-RS
MS-00799-RS
Beginning at a point north 1,320 feet and
east 854.75 feet of the S4 corner of
Section 25, T33S., R23E., Salt Lake Base
Meridian; west 214.5 feet, north
185.65 feet, north 80 degrees 48 minutes
18 seconds east 217.31 feet, south
220.5 feet to the point of beginning. City of
Monticello, County of San Juan, State of
Utah
537 North Main Street
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
August 30, 1991
Rust Geotech
Not applicable: streamlined remediation
procedures were followed
Not applicable: streamlined remediation
procedures were followed
October 2, 1992
October 7, 1992
Interior: 0 cubic yards
Exterior: 0.4 cubic yards
2.1 square meters (m3)
July 1995
2
DOE ID No.: MS-00799-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, 6 inches deep,
within the property. The remedial action process included the removal of
approximately 0.4 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-00799-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. 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, individual soil samples representative
of the 6-inch-thick soil layer at the bottom of the excavation were
collected (Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 12 to 19 microroentgens per
hour Ot/R/h), as indicated on Appendix Figure 2.1. The results of
analyses for radium-226 in six individual soil samples ranged from
2.6 to 12.3 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 0.0021 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 basement was uninhabitable.
4
DOE ID No.: MS-00799-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by the EPA standards (40 CFR 192.12, 192.20-23)
and the DOE hot spot criteria, as indicated in the Certification Data
Summary below.
Therefore, the property located at 537 North Main Street, in Monticello,
Utah, is recommended for certification as required by the 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
0.0021 WL.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background1 in the
15-cm surface layer,
averaged over 100 m2.
Shall not exceed 15 pCi/g
above backgroundt 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 2.6 to
12.3 pCi/g.**
*The background exposure rate is approximately 15 //R/h.
fThe 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-00799-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
DAG:04-27-95
MS-00799.RS WP52
REV053193
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-0079S>RS
Address: 537 North Main Street, Monticello, Utah
Exposure Soil Sample Meas. Radium-226
Area Rate Ot/R/h) Ticket No. Method" (pCi/g)
V-l 18 NAP 302 OCS 12.3
V-2 18 NAP 303 OCS 8.5
V-3 19 NAP 304 OCS 2.6
V-4 17 NAP 305 OCS 7.1
V-5 16 NAP 306 OCS 3.9
V-6 17 NAP 301 OCS 6.5
See Appendix Figure 2.1 for the verification areas.
"OCS = Opposed Crystal System
Table 3.2
Radon Decay-Product Concentration Measurement Results
DOE ID No.: MS-00799-RS
Address: 537 North Main Street, Monticello, Utah
Instrument Type: Terradex Radtrak® Detector
Radon
Detector Tracks Per Concentration Working
Number Start Date End Date mm2 (pCi/L) Level
3729775 07-20-93 08-16-94
3729881 07-20-93 08-16-94
3729913 07-20-93 08-16-94
5.5 0.45 0.0023
3.5 0.29 0.0015
5.8 0.48 0.0024
Annual Average: 0.0021
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
1
D 12 14 16 18 20
-1—i—i—i—i—i—i—i—i—r
22 24 26 28 30 32 34 36 38 40
T"
42 44 46 48 5i
1
r 12-15
12-15 17uR/h
V-5
19/iR/h 16/lR/h
18uR/h
RDC
ONE STORY L
BRICK HOUSE 1
W/UNINHABITABLE
BASEMENT
12 13
17/iR/h
8uR/h
12-15
L J
in
z
<
2
X
I-
CK
O
z
©
<D
12-15
12
v-1
16-17
LES-EMD.
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
POST-REMEDIAL ACTION RADON DECAY-PRODUCT
CONCENTRATION MEASUREMENT LOCATION
u
I L
12
SCALE IN FEET
20 10 0 20 40
O:\ORAWINGS\033\0003\RU00799V 04/26/95 0S:60om K308S8
I I ' ' I L
14 16 18 20 22
NORTH
24
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 AND IS NOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE. BUILDING, OR OTHER FUTURE IMPROVEMENT LINES.
_l L
26
J I I L
U.S. DEPARTMENT OF ENERGY
6RAHP JUHCTIOM PROJECT! OFFICE, COLORADO
*8-537 NORTH MAIN STREET
MONTICELLO, UTAH
rr MS-00799-RS
28 30 32 34 36 38 40 42 44 46
' 3-C00799-V1 „ 1 , 1
48 5l
OAK RIDGE NATIONAL LABORATORY
MANAGED BY MARTIN MARIETTA ENERGY SYSTEMS, INC.
GRAND JUNCTION OFFICE
FO. BOX 2567
GRAND JUNCTION. COLORADO 81502
AUG 3 1 1995
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: MS00799-RS
Location Address: 537 North Main Street
Monticello. Utah 84535
Property Owner:

Tenant Name: Vacant
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
537 NORTH MAIN STREET
MONTICELLO, UTAH (MS00799-RS)
A. R. Jones
August 1995
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY SYSTEMS, INC.
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-84OR21400
CONTENTS
LIST OF TABLES v
ACKNOWLEDGMENTS vii
ABSTRACT . . ix
lTSfTRODUCTION 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
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 J. R. Sauvage 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'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
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 537 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
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 537 NORTH MAIN STREET
MONTICELLO, UTAH (MS00799-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 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 of the Health Sciences Research Division at Oak Ridge National Laboratory under DOE contract
DE-AC05-84OR21400 with Lockheed Martin Energy Systems, Inc.
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 single family residence located at 537 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
1995).
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 537 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 (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1995)
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 using streamlined remedial action procedures.
The pre-remedial-action survey performed by Geotech identified mill tailings 6 inches
deep. During the actual removal process, a total of 0.4 yd3 of contaniinated earth and
uranium mill tailings, 6 inches deep were removed from a 2.1 m2 area.
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 of the structure, a surface scan of the exterior, and soil sampling. Individual
samples representative of the bottom 15 cm soil layers of the six excavated areas were
collected 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 of the
residence ranged from 12 to 13 //R/h. Exterior surface gamma measurements taken from
the excavated areas prior to backfilling ranged from 16 to 19 //R/h.
Soil Sample Analysis
Prior to backfilling, Geotech collected a representative soil sample from each of the
six excavated areas from the bottom 15-cm (6-in.) soil layer. Geotech's analysis of these
samples showed ^Ra concentrations ranging from 2.6 to 12.3 pCi/g in the composite
sample. ORNL ETS was unable to obtain samples for confirmatory analysis. 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 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 one year (from 07/20/93 to 08/16/94). The average annual
working level (WL) of radon progeny concentration, as determined by the Tech./Ops-
Landauer Corporation, was 0.0021, 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
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 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.
Radionuclide
concentrations in soil
for Hot Spot areas
Maximum Permissible
concentration of Ra226 in soil
above background level, for
areas less than 25 m2.
Ra concentrations, m 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)
5
REFERENCES
Geotech 1995, Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00799-RS, Address: 537 North Main Street, Monticello, Utah
84535, Geotech, Grand Junction, Colorado, July 1995.
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.
ORNL, 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
DOE ID No.: MS-00800-RS
Property Address: 348 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 £ 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
IX [ 1 [ 1
W I 1 I 3
[ ] [ ] [X] [ ] [ ] L*]
(Missing Window)
[ ] [X] [ ]
[X] [ ] [ ]
[ 1 [/< [ 1
L>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 oamma
exposure rates that do not exceed 30 percent above normal background.
11111111111
SFCERTIFED
111IH
SFMS-00800
1 T
DOE ID No.: MS-00800-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 sby Date
Manager, Monticello Programs
Rust Geotech
DOE EVALUATION
[XI 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-00800-RS
ADDRESS: 348 NORTH MAIN STREET
MONTICELLO, UTAH 84535
SEPTEMBER 1995
Prepared for
U.S. Department of Energy
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
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
S^ciion Eage
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-00800-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-00800-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):
Ccnsii uction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
MS-00800-RS
Location No. M-360; beginning 1,683 feet
west and 967.5 feet south of the E4 corner
of Section 25, T33S., R23E., Salt Lake
Base Meridian; east 214.5 feet, south
150 feet, west 214.5 feet, north 150 feet
to the beginning, City of Monticello, County
of San Juan, State of Utah
348 North Main Street
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
September 12, 1991
Rust Geotech
February 9, 1994
Diamond Back Services, Inc.
9861 Titan Park Circle
Littleton, Colorado
August 8, 1994
September 8, 1994
Interior: 0 cubic yards
Exterior: 2 cubic yards
7 square meters (m2)
September 1995
2
DOE ID No.: MS-00800-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 4 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 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-00800-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
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 12 to 23 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 in the house due to excessive
ventilation caused by a missing window.
4
DOE ID No.: MS-00800-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 348 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 was 10 to 12 //R/h.
Not taken due to a
missing window.
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.**
*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-00800-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
MRW:08-23-95
MS-00800.RS WP61
REV080195
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00800-RS
Address: 348 North Main Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range U/R/h) Ticket No. Method" (pCi/g)
V-1 16-23 NCA 955 OCS 2.4
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
!6
14
12
10
1
12 14 16 18 20 22 24 26 28
T
30 32 34 36 38 40 42 44 46 48 5i
UJ
ui or
O
r~" SHED SHED
12-14 12-14
12 12-15
v-i 12-15
16-23
12-15
v-i v-i 12-15 16-23 16-23
15
0
8-
ONE STORY
STUCCO HOUSE
W/CRAWL SPACE
10-12
Lv.vj
12-15
12
v-i
16-17
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
L
SCALE IN FEET
20 10 0 20 40
U:\F4S\0J3\OOO3\RM00S00V 0«/2«/«3 0g:57om TS07S0
J L
12 14 16 18
NORTH
20
J L
22
J L
24 26 28 30
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
WW JUHCTWI WWCCT* QfFtCt. COLOMBO
348 NORTH MAIN STREET
MONTICELLO. UTAH
•"»•«•• MS-00800-RS
I—-1"- 3-C00800-V1 _ 1 _ 1
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
POST OFFICE BOX 2567
GRANO JUNCTION, COLORADO 81502
PHONE: (970) 24*6200
FAX: [phone]
FEB 2 • 1998
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 verifica-
tion 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 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
MSQQ8QQ-RS
348 North Main Street

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
348 NORTH MAIN STREET
MONTICELLO, UTAH (MS00800-RS)
M. K. Jensen
February 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 348 North Main Street,
Monticello, Utah (MS00800-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 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 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,
RUST Geotech, the remedial action contractor designated by DOE, performed remedial
action on the vicinity property at 348 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 were resolved in a meeting with ORNL and RUST Geotech.
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 348 NORTH MAIN STREET
MONTICELLO, UTAH (MS00800-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 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 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 private residence located at 348 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 1995).
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 348 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 contarnination to below applicable DOE guidelines (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1995)
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 4 yd3 of mill
tailings 6 to 12 inches deep. However, during the actual removal process, a total of
2 yd3 of contaminated earth and uranium mill tailings, 6 to 15 inches deep were
removed from a 7 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 ofthe structure, a surface scan 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.
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 12 /*R/h. Exterior surface gamma measurements taken
from the excavated areas prior to backfilling ranged from 16 to 23/tR/h.
Soil Sample Analysis
Prior to backfilling, Geotech collected a soil sample representative of the exca-
vated areas 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. Geotech'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
^Ra concentration of 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.
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were not
taken as the structure had broken windows and excessive ventilation prohibited valid
RDC measurements.
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 and corrected as discussed in a meeting between Geotech and
ORNL on February 28, 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 ^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
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 ^Rn
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 348 North Main Street, Monticello Utah (MS00800-RS)
226Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No." NoS (cm)
XI NCA 955 >15 2.6 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 1995. Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00800-RS, Address: 348 North Main Street, Monticello, Utah
84535, Geotech, Grand Junction, Colorado, September, 1995.
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.
ORNL, 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
DOE ID No.: MS-00826-SC
Property Address: 164 South Second West 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 [ ]
[X]* [ ] [ 1 [X] [ 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] [ ] [ ] L*] [ ) I ]
In-situ [ ] Lab [X]
Interior gamma is £ 20 //R/h
above background in any
occupied or habitable
structure. [ ] [ ] [X] [ ] [ ] [ <t
(Uninhabitable Structure)
The radon decay-product
concentration in any
occupied or habitable
structure is £ 0.02
working level or, at
most, 0.03 working level. MM [X] MM [>]
(Uninhabitable Structure)
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21. [ ] [X] [ ] [ ] [» I 1
Hot spot criteria met as
outlined by the DOE
guidelines for FUSRAP
(Rev. 2, March 1987). [XJ [ ] [ ] [Yl [ ] [ ]
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.
Ililllllllll Ililllllllll
SFCERTIFED SFMS-09826
DOE ID Nos.: MS-00826-SC
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.
f/l 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-00826-SC
ADDRESS: 164 SOUTH SECOND WEST STREET
MONTICELLO, UTAH 84535
MARCH 1995
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-00826-SC
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 the EPA standards and the
DOE hot spot criteria by the DOE Inclusion Survey Contractor. The DOE
reviewed these evaluation results and determined that the property
contained mill tailings (residual radioactive material) exceeding the DOE
hot spot criteria. The Remedial Action Contractor was notified of the
inclusion of this property into the MVP Project and was authorized by the
DOE to conduct remedial action as required to bring the property into
conformance with the EPA standards and the 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-00826-SC
MS-O0826-SC
Beginning at a point 334.5 feet north of the
SW corner of the NE4NW4 of Section 36,
T33S., R23E., Salt Lake Base Meridian;
north 483.4 feet, southeasterly 660 feet,
south 143.67 feet, southeasterly 36.6 feet,
southwesterly 311 feet, west 92 feet,
south 27 feet, north 89 degrees 03 minutes
west 600.7 feet to beginning, City of
Monticello, County of San Juan, State of
Utah
164 South Second West Street
Monticello, Utah 84535

School (SC)
Oak Ridge National Laboratory
January 31, 1991
Rust Geotech
Not applicable: streamlined remediation
procedures were followed
Mountain Region Corporation
117 29 3/4 Road
Grand Junction, Colorado
November 11, 1993
November 22, 1993
Interior: 0 cubic yards
Exterior: 7.0 cubic yards
20.0 square meters (ma)
March 1995
2
DOE ID No.: MS-00826-SC
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 14 cubic yards of contamination,
ranging from 6 inches to 12 inches deep, within the property. The
remedial action process included the removal of approximately 7.0 cubic
yards of residual radioactive material, ranging from 6 inches 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
3.0 VERIFICATION SUMMARY
DOE ID No.: MS-O0826-SC
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 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 10 microroentgens per hour (//R/h)
to 16 //R/h (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.
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-00826-SC
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by the EPA standards (40 CFR 192.12, 192.20-23)
and the DOE hot spot criteria, as indicated in the Certification Data
Summary below.
Therefore, the property located at 164 South Second West Street, in
Monticello, Utah, is recommended for certification as required by the
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
Not applicable:
uninhabitable structure.
Not applicable:
uninhabitable structure.
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.r
Soil sample result was
1.5 pCi/g.'
•The background radium-226 concentration is approximately 2.0 pCi/g.
TThe hot spot criteria were met based on gamma scans and/or soil sample results.
5
DOE ID No.: MS-00826-SC
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:03-02-95
MS-00826.SC WP52
REV053193
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00826-SC
Address: 164 South Second West Street, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (//R/h) Ticket No. Method* (pCi/g)
V-l 13 - 16 NAO 921 OCS 1.5
See Appendix Figure 2.1 for the verification area.
•OCS = Opposed Crystal System
7
5z
50
46
46
44
42
40
38
36
34
32
30
28
26
24
22
20
18
16
14
12
10
12 14 16 IB 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
i i i i i i i i i i i i i i i i i i i r~~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—i—i—i—i—i—r
X
J I
1
UNINHABITABLE
CINDER BLOCK
BUILDING C
11-12
V-1
I3-I«
SHED
10712 GARAGE
10-12
• 12-16
_J 12-15 11-12
J fl iffi. =^
SOUTH SECOND WEST STREET
L.
©
<D
r-i
12-15
V-1
16-17
i£2EHD
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
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
SCALE IN FEET
0
I
80
I
ft
NORTH
J I L
THI5 DRAWING IS FOR THE SOU USC OF THE U.S. DEPARTMENT
OF ENERGY AHO ITS CONTRACTORS. IT IS NOT A LAND SURVEY
PLAT, UTILITY LOCATION PLAT, OR OTHER IMPROVEMENT SURVEY
PLAT AND IS HOT TO BE RELIED UPON FOR THE ESTABLISHMENT
OF FENCE. BUILOING. OR OTHER FUTURE IMPROVEMENT LINES.
J L J L
tt-m. or occuMHft
CK. A.E. APP. NO. DATE CK. A.E. APP.
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE, COLORADO
3r 164 SOUTH SECOND WEST STREET
MONTICELLO. UTAH
OOE 10 MO. „s-ooej«-sc
3-DO0«2»-V1 SHT. I Of 1
20 22 24 28 30 32 34 36 50
GRAND JUNCTION OFFICE
RO. BOX 2567
GRAND JUNCTION, COLORADO 81502
M 28 1995
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, 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 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
MSQQ826-SC
164 South 2nd West Street
Monticello. Utah 84535

Same
OAK RIDGE NATIONAL LABORATORY
MANAGED BY MARTIN MARIETTA ENERGY SYSTEMS, INC.
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 SOUTH 2ND WEST STREET
MONTICELLO, UTAH (MS00826-SC)
M. K. Jensen
June 1995
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY SYSTEMS, INC.
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-84OR21400
CONTENTS
LIST OF TABLES v
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 South 2nd West
Street, Monticello, Utah (MS00826-SC) 5
v
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 G. A. Pierce 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 remedial actions on off-site (vicinity) properties that had been
contaminated by radioactive material resulting from mill operations. During 1993,
RUST Geotech, the remedial action contractor designated by DOE, performed remedial
action on the vicinity property at 164 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. 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 SOUTH 2ND WEST STREET
MONTICELLO, UTAH (MS00826-SC)*
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).
*Thc 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-AC05-84OR21400 with Lockheed Martin Energy Systems, Inc.
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, public school property located at 164 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
1995).
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 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 (DOE 1990).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1995)
indicates the property was remediated as evaluated by DOE on the basis of Environmental
Protection Agency standards and the DOE guidelines (DOE 1990). 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 14 yd3 of mill tailings
6 to 12 inches deep. However, during the actual removal process, a total of 7 yd3 of
contaminated earth and uranium mill tailings, 6 to 12 inches deep were removed from a 20
m2 area.
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 of the structures, a surface scan 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.
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
buildings ranged from 10 to 12 /iR/h. Exterior surface gamma measurements taken
from the excavated areas prior to backfilling ranged from 13 to 16 ^R/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 shows a ^Ra concentration of 1.5 pCi/g. ORNL
ETS obtained this sample and performed a corifirmatory analysis which showed a mRa
concentration of 1.1 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.
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were not taken
as none of the buildings on the property were habitable.
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
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
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
(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 1990)
5
Table 2. Results of ORNL analysis of Geotech soil samples
from 164 South 2nd West Street, Monticello Utah (MS00826-SC)
ORNL Geotech
sample sample
No." No.*
MS00826X1 NAO 921
Depth
(cm)
>15
226Ra concentration (pCi/g)
ORNL Geotech
1.1 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 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: MS00826-SC, Address: 164 South Second West Street,
Monticello, Utah 84535, Geotech, Grand Junction, Colorado, March 1995.
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.
ORNL, 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
I t
DOE ID No.: MS-00844-RS
Property Address: 180 Uranium Drive
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech pf 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]* [ ] [ ] MM 11
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] [ ] [ ] IXI [ 1 II
In-situ [ ] Lab [X]
Interior gamma is ^ 20 //R/h
above background in any
occupied or habitable
structure. [X] [ ] [ ] [>] 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] [ ] [ ] [ ^ [ ] [ ]
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21. [ ] [X] [ ] [ ] [>J [ ]
Hot spot criteria met as
outlined by the DOE
guidelines for FUSRAP
(Rev. 2, March 1987). [X] [ ] [ ] [>4 [ ] 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 •illlllll
SFCERTIFED SFMS-09805
DOE ID No.: MS-00844-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 the concurrence of
the U.S. Nuclear Regulatory Commission because supplemental
standards were applied per 40 CFR 192.21.
IX] 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, Tvlonticello Programs
Rust Geotech
r/fl/ir
Date
DOE EVALUATION
Date
U.S. Department of Energy
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00844-RS
ADDRESS: 180 URANIUM DRIVE
MONTICELLO, UTAH 84535
MAY 1995
Prepared for
U.S. Department of Energy
by
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
Warjda 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-00844-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 the EPA standards and the
DOE hot spot criteria by the DOE Inclusion Survey Contractor. The DOE
reviewed these evaluation results and determined that the property
contained mill tailings (residual radioactive material) exceeding the EPA
standards and the DOE hot spot criteria. The Remedial Action Contractor
was notified of the inclusion of this property into the MVP Project and was
authorized by the DOE to conduct remedial action as required to bring the
property into conformance with the EPA standards and the DOE hot spot
criteria.
1
DOE ID No.: MS-00844-RS
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
MS-00844-RS
Location No. M-23-E; beginning north 89 degrees 21 minutes west 293 feet
from the SE corner of Lot 1, Block 5, Monticello Townsite Survey; north
89 degrees 21 minutes west 59 feet, north 00 degrees 42 minutes east
165 feet, south 89 degrees 21 minutes east 59 feet, south 00 degrees
42 minutes west 165 feet to the point of beginning, 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:
180 Uranium Drive
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
September 12, 1991
Rust Geotech
November 18, 1992
Sonderegger Inc.
P.O. Box 713
Monticello, Utah
June 14, 1993
June 22, 1993
Interior:
Exterior:
0 cubic yards
16 cubic yards
33 square meters (m2)
May 1995
2
DOE ID No.: MS-00844-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 inches to 12 inches deep, within the property. The remedial action
process included the removal of approximately 16 cubic yards of residual
radioactive material, ranging from 6 inches 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
DOE ID No.: MS-00844-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 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 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 microroentgens per hour (//R/h)
to 19 //R/h (Appendix Figure 2.1). The result of analysis for
radium-226 in one composite soil sample was 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 measurements representing an annual average, the RDC
was 0.0081 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-00844-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by the EPA standards (40 CFR 192.12, 192.20-23)
and the DOE hot spot criteria, as indicated in the Certification Data
Summary below.
Therefore, the property located at 180 Uranium Drive, in Monticello,
Utah, is recommended for certification as required by the 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 //R/h to
15 //R/h.
Annual average was
0.0081 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 ma.
< 5 pCi/g above
background.*
Soil sample result was
1.3 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-00844-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:03-30-95
MS-00844.RS WP52
REV053193
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00844-RS
Address: 180 Uranium Drive, Monticello, Utah
Exposure-Rate Soil Sample Meas. Radium-226
Area Range (//R/h) Ticket No. Method* (pCi/g)
V-l 13 - 19 NAW 073 OCS 1.3
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-00844-RS
Address: 180 Uranium Drive, Monticello, Utah
Instrument Type: Terradex Radtrak® Detector
Radon
Detector Tracks Per Concentration Working
Number Start Date End Date mm1 (pCi/L) Level
3853865 10-19-93 10-27-94
3853892 10-19-93 10-27-94
3853848 10-19-93 10-27-94
17.3 1.82 0.0091
16.3 1.71 0.0086
12.3 1.29 0.0065
Annual Average: 0.0081
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
1
16 18 20 22 24 26 28 30 32 34 36 38
T"
40 42 44 46 48 51
SCALE IN FEET
20
J L
13-15
30
v-i
13-19
V-1
13-19
K X 6 112
10
SHED
3-15
RDC
ONE STORY
FRAME HOUSE
v-l
13-15 13-19
13-15
-e
40
J L
T77 777"
URANIUM DRIVE
NORTH
J I I L
©
<D
rr.-.Ti
IV.'.VJ
12-15
EH
V-1
16-17
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURE RATES IN /jR/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
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. BUILOING. OR OTHER FUTURE IMPROVEMENT LINES.
J i i i L
U.S. OEPARTUENT OF ENERGY
MUM JUNCTION PROJECTS OTnCC. COLONMO
180 URANIUM DRIVE
MONTICELLO, UTAH
MS-00844-RS
16 18 20 22 24 26 28 30 32 34 36 38 40 42 44 46 48 5(
OAK RIDGE NATIONAL LABORATORY
MANAGED BY MARTIN MARIETTA ENERGY SYSTEMS, INC.
GRAND JUNCTION OFFICE
RO. BOX 2567
GRAND JUNCTION. COLORADO 81502
AUG 3 1 1995
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
rates 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:
Location Address:
MS00844-RS
180 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 B INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
180 URANIUM DRIVE
MONTICELLO, UTAH (MS00844-RS)
M. K. Jensen
August 1995
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY SYSTEMS, INC.
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-84OR21400
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 180 Uranium Drive,
Monticello, Utah (MS00844-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
acknowledge A. R. Jones and N. F. Lewis 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 1993, RUST
Geotech Inc., the remedial action contractor designated by DOE, performed remedial
action on the vicinity property at 180 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 ETS
are described in the Environmental Technology Section Procedures Manual (ORNL,
1993).
viii
1
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 180 URANIUM DRIVE
MONTICELLO, UTAH (MS00844-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 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 ofthe Environmental
Technology Section ofthe Health Sciences Research Division at Oak Ridge National Laboratory
under DOE contract DE-AC05-84OR21400 with Lockheed Martin Energy Systems, Inc.
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 180 Uranium 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 199S). 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 180 Uranium 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 1995)
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 3.5 yd3 mill tailings 6
to 12 inches deep. However, during the actual removal process, a total of 16 yd3 of
contaminated earth and uranium mill tailings, 6 to 30 inches deep were removed from a 33
m2 area.
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, a surface scan of the exterior, and soil
sampling. Samples representative of the bottom 15-cm (6-in.) soil layer of the excavated
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 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 13-15 fJR/h. Exterior surface gamma measurements taken from the
excavated area prior to backfilling ranged from 13-19 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 layer. 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 1.3 pCi/g. ORNL ETS
obtained this soil sample and performed a confirmatory analysis, which showed ^Ra
concentrations of 1.4 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 one year (from 10/19/93 to 10/27/94). The IVC was present
during placement and retrieval of the detectors to verity the RDC measurements. The
average annual working level (WL) of radon progeny concentration, as determined by the
Tech./Ops-Landauer Corporation, was 0.0081, 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
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 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)*,
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 180 Uranium Drive, Utah (MS00844)
mRa concentration (pCi/g)
ORNL Geotech
sample sample Depth
No." No* (cm) Confirmatory* ORNL'' Geotech
VI NAW-073 >15 5.7 1.4 1.3
" 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 RUST Geotech Inc., and these samples were blended to
form composite soil samples, which represent an average over verification areas.
' 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 area prior to
backfilling ranged from 12 to 16 uR/h (Figure 1).
Soil Sample Analysis
ORNL sampled the excavated area prior to backfilling, collecting aliquots
representative of this area from the bottom 15-cm (6-in.) soil layer. 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 1.4 pCi/g. This value is below the DOE guideline value of 15 pCi/g for soil layers > 15
cm below the surface (Table 1). Results of ORNLand Geotech 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
radiological measurements fall below the limits prescribed by DOE guidelines. It is
concluded that the site successfully meets the DOE remedial action objectives.
-1
V1
SHED
RDC
V1
SINGLE STORY
FRAME HOUSE
or LJ
<
cc
EXPLANATION
Concrete
Assessed
contamination
Excavated
area
Remaining
contamination
RDC
measurement
Area identifier &
Composite sample
• I Identifier of
I I averaged area Sc
Biased sample
vTI 12-16/zR/h
0
0 1
FEET
5 10 20
MS00844
180 URANIUM DRIVE
MONTICELLO, UTAH
URANIUM DRIVE
Figure 1. Property Map AKJ 7/19/98
8
REFERENCES
Geotech 1995, Property Completion Report for Monticello Vicinity Property
Remedial Action for DOE ID NO: MS00844, Address: 180 Urnaium Drive,
Monticello, Utah 84535, Geotech, Grand Junction, Colorado, May 1995.
U.S. JX)E 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.
ORNL, 1993. Environmental Technology Section Procedures Manual.
6645/RI Oak Ridge National Laboratory, Grand Junction, Colorado.
ORNL
DOE ID No.: MS-00877-RS
Property Address: 249 Lower Uranium Drive
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech pf 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 ss 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 the DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
mil [ ]
IX1 I 1 I I
i i iyi i i
IX] l 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.
•niiiiiiiii iiniiiuiiu
SFCERTIFED SFMS-08877
DOE ID No.: MS-00877-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 the concurrence of
the U.S. Nuclear Regulatory Commission because supplemental
standards were applied per 40 CFR 192.21.
[ ?\ 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, t/lonticello 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-00877-RS
ADDRESS: 249 LOWER URANIUM DRIVE
MONTICELLO, UTAH 84535
JUNE 1995
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
Wanda7 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-00877-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 the EPA standards and the
DOE hot spot criteria by the DOE Inclusion Survey Contractor. The DOE
reviewed these evaluation results and determined that the property
contained mill tailings (residual radioactive material) exceeding the EPA
standards and the DOE hot spot criteria. The Remedial Action Contractor
was notified of the inclusion of this property into the MVP Project and was
authorized by the DOE to conduct remedial action as required to bring the
property into conformance with the EPA standards and the DOE hot spot
criteria.
1
DOE ID No.: MS-00877-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-00877-RS
Beginning at a point north 89 degrees
21 minutes west 383.95 feet and south
00 degrees 42 minutes west 132.5 feet
from 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 point of beginning,
City of Monticello, County of San Juan,
State of Utah
249 Lower Uranium Drive
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 1, 1992
July 1, 1992
Interior: 0 cubic yards
Exterior: 0.1 cubic yards
0.6 square meters (m2)
June 1995
2
DOE ID No.: MS-00877-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 contamination, 6 inches deep,
within the property. The remedial action process included the removal of
approximately 0.1 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-00877-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. 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 17 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
2.2 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 0.0049 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-00877-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property to
the extent required by the EPA standards (40 CFR 192.12, 192.20-23)
and the DOE hot spot criteria, as indicated in the Certification Data
Summary below.
Therefore, the property located at 249 Lower Uranium Drive, in
Monticello, Utah, is recommended for certification as required by the
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
0.0049 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
2.2 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-00877-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
DAG:04-24-95
MS-00877.RS WP52
REV053193
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00877-RS
Address: 249 Lower Uranium Drive, Monticello, Utah
Exposure Soil Sample Meas. Radium-226
Area Rate ijyR/h) Number Method" (pCi/g)
V-l 17 NAP 292 OCS 2.2
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-00877-RS
Address: 249 Lower Uranium Drive, Monticello, Utah
Instrument Type: Terradex Radtrak® Detector
Detector
Number Start Date End Date
Tracks Per
mm2
Radon
Concentration
(pCi/L)
Working
Level
3760459
3760410
3760500
03-09-93
03-09-93
03-09-93
03-07-94
03-07-94
03-07-94
11.1
9.9
10.9
1.01
0.90
1.00
0.0051
0.0045
0.0050
Annual Average: 0.0049
See Appendix Figure 2.1 for the measurement location.
8
10
30
12 14 16 18 20 22 24 26 28 30 32 34 36 38 40
30
28 28
26
24
22
20
18
r LOWER URANIUM DRIVE
/// ///
12-15
I
' CAR-
I PORT
ONE STORY
FRAME HOUSE
W/CRAWL SPACE
12-13 |12-1
RDC
V-1
17/iR/h
A X 6
12-15
mm
©
<D
nv.vi
LV.-.vj
12-15
12
V-1
16-17
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
POST-REMEDIAL ACTION RADON DECAY-PRODUCT
CONCENTRATION MEASUREMENT LOCATION
- 26
24
22
20
18
16
14
12
Y
10
SCALE IN FEET
20 10 0 20 40
M:\FAS\033\0003\RM00877V 06/01/95 10:12am T50780
I I
ft
NORTH
J 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
RESrOENCE-NO. or OCCUPANTS
HON—RESIDENCE—MAN—HRS./WK.
INSTRUMENT NO.
BY CK. AC. APP. NO. DATE BY CK. A.E. APP.
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE. COLORADO
35a&.
249 LOWER URANIUM DRIVE
MONTICELLO, UTAH
APPROVAL
Rust Oeotcch
TSATF" APPROVAL OOE •OATTT
OOEIONO. MS-00877-RS
owc.No. 3-B00877-V1 SHT 1 or 1
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
MANAGED BY MARTIN MARIETTA ENERGY SYSTEMS, INC.
GRAND JUNCTION OFFICE
RO. BOX 2567
GRAND JUNCTION, COLORADO 81502
JUL 2 5 1995
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, 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
n6Ra 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: MS00877
Location Address: 249 Lower Uranium Drive
Monticello. Utah 84535
Property Owner:

Tenant Name: Unknown
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
249 LOWER URANIUM DRIVE
MONTICELLO, UTAH (MS00877)
A. R. Jones
July 1995
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY SYSTEMS, INC.
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-84OR21400
CONTENTS
LIST OF TABLES v
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
1 Applicable guidelines for protection against radiation
v
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 J. R Sauvage and N. F. Lewis 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 (DOEs) 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, RUST
Geotech, the remedial action contractor designated by DOE, performed remedial action on
the vicinity property at 249 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
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 249 LOWER URANIUM DRIVE
MONTICELLO, UTAH (MS00877)*
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 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 ofthe Environmental Assessment Group in the
Environmental Technology Section ofthe Health Sciences Research Division at Oak Ridge National Laboratory under DOE contract
DE-AC05-84OR21400 with Lockheed Martin Energy Systems, Inc.
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 249 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 (Geotech 1995).
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 249 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 (DOE 1990a).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1995)
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, using streamlined remedial action procedures.
The pre-remedial-action survey performed by Geotech identified mill tailings 6 inches
deep. During the actual removal process, a total of 0.1 yd3 of contaminated earth and
uranium mill tailings, 6 inches deep were removed from a 0.6 m2 area.
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 of the structure, a surface scan of the exterior, and soil sampling. An
individual sample representative of the bottom 15 cm soil layer of the excavated area was
collected for the verfication 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 of the
residence ranged from 12 to 13 //R/h. Exterior surface gamma measurements taken from
the excavated area prior to backfilling was 17 //R/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
show a 2MRa concentration of 2.2 pCi/g. ORNL ETS was unable to obtain a sample for
confirmatory analysis. This value is below the EPA standard value of IS 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, 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 03/09/93 to 03/07/94). The average annual
working level (WL) of radon progeny concentration, as determined by the Tech./Ops-
Landauer Corporation, was 0.0049, 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
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
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)54, where A is the
area of the elevated region
Exposure to ^Rn Average annual radon proge- 0.03 WL
progeny ny concentration (including
background)
(DOE 1990a)
5
REFERENCES
Geotech 1995, Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00877-RS, Address: 249 Lower Uranium Drive, Monticello,
Utah 84535, Geotech, Grand Junction, Colorado, June 1995.
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.
ORNL, 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.
DOE ID Nos.: MS-00199-RS and MS-01061-RS
Property Address: 264 East Second 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 the DOE
guidelines for FUSRAP
(Rev. 2, March 1987).
YES NO NOT TAKEN
[X]* [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
[ ] [X] [ ]
[X] [ ] [ ]
YES NO NOT TAKEN
[Xl [ ] I ]
M [ ] [ ]
[Xl I 1 [ 1
[Vl [ 1 [ 1
[ 1 [tf [ 1
[Yl [ 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.
liii llllllllll
SFCERTIFED SFMS-09011
DOE ID Nos.: MS-00199-RS and MS-01061-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 the concurrence of
the U.S. Nuclear Regulatory Commission because supplemental
standards were applied per 40 CFR 192.21.
[*) 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
DOE EVALUATION
Date
U.S. Department of Energy
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NOS.: MS-00199-RS AND MS-01061-RS
ADDRESS: 264 EAST SECOND SOUTH STREET
MONTICELLO, UTAH 84535
JULY 1995
Prepared for
U.S. Department of Energy
by
Rust Geotech
P.O. Box 14000
Grand Junction, Colorado 81502-5504
' WandsTS!.Busby7
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-00199-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).
These properties were evaluated on the basis of the EPA standards and
the DOE hot spot criteria by the DOE Inclusion Survey Contractor. The
DOE reviewed these evaluation results and determined that the properties
contained mill tailings (residual radioactive material) exceeding the EPA
standards. The Remedial Action Contractor was notified of the inclusion
of these properties into the MVP Project and was authorized by the DOE
to conduct remedial action as required to bring the properties into
conformance with the EPA standards and the DOE hot spot criteria.
1
DOE ID No.: MS-00199-RS
1.3 Summary of Remedial Action
DOE ID Nos.:
Legal Descriptions:
MS-00199-RS and MS-01061-RS
Location No. M-73; beginning at the NW corner of Lot 4, Block 11, Monticello
Townsite Survey; south 267 feet, east 154.5 feet, north 52.5 feet, west
47 feet, north 144.5 feet, west 30 feet, north 70 feet, west 77.5 feet to
beginning. County of San Juan, State of Utah
Location No. M-74; beginning 60 feet west of the NE corner of Lot 4, Block 11,
Monticello Townsite Survey; west 77 feet, south 70 feet, east 30 feet, south
144.5 feet, east 47 feet, north 214.5 feet to beginning, 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:
264 East Second South Street
Monticello, Utah 84535

Residential Simple (RS) - Both DOE ID Nos.
Oak Ridge National Laboratory - Both
DOE ID Nos.
July 25, 1990 - Both DOE ID Nos.
Rust Geotech
January 4, 1991
Sonderegger, Inc.
P.O. Box 713
Monticello, Utah
April 23, 1991
May 31, 1991
Interior:
Exterior:
0 cubic yards
276 cubic yards
1,386 square meters (m2)
July 1995
2
DOE ID No.: MS-00199-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 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 identified contamination, ranging from
6 inches to 12 inches deep, within the properties. The remedial action
process included the removal of approximately 276 cubic yards of residual
radioactive material, ranging from 6 inches 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 properties.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the properties.
3
DOE ID No.: MS-00199-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 January 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. These samples were blended to form composite
samples representing the verification areas (Appendix Figure 2.1).
Soil samples and post-restoration scans were obtained in areas
that required additional information to verify conformance with the
DOE hot spot criteria.
Exterior Findings: Surface exposure-rate values, determined during
the gamma scan, ranged from 13 microroentgens per hour (//R/h)
to 28 //R/h (Appendix Figure 2.1). Residual radioactive material
was left in place in Areas V-34 and V-35 to avoid causing
permanent damage to mature trees. The results of analyses for
radium-226 in two composite soil samples of these areas were
18.0 picocuries per gram (pCi/g) and 8.3 pCi/g, respectively. The
100 m2 area averages were 3.5 pCi/g and 2.2 pCi/g (Appendix
Table 3.1). Areas V-34 and V-35 also met the hot spot criteria, as
indicated in Appendix Table 3.2. The results of analyses for
radium-226 in 41 remaining composite soil samples ranged from
1.0 pCi/g to 11.2 pCi/g (Appendix Table 3.3).
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on measurements representing an annual average, the RDC
was 0.0193 working level (WL), as indicated in Appendix
Table 3.4. 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-00199-RS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this properties
to the extent required by the EPA standards (40 CFR 192.12,
192.20-23) and the DOE hot spot criteria, as indicated in the
Certification Data Summary below.
Therefore, the properties located at 264 East Second South Street, in
Monticello, Utah, are recommended for certification as required by the
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 //R/h to
14//R/h.
Annual average was
0.0193 WL.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above backgroundt 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.
Soil sample results,
averaged over 100 m2
areas, were 2.2 pCi/g and
3.5 pCi/g.**
Soil sample results
ranged from 1.0 pCi/g to
11.2 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-00199-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
SJW:05-02-95
MS-00199.RS WP52
REV053193
6
Table 3.1
Calculations of Average Radium Concentrations over 100 m2 Areas
Where:
DOE ID Nos.: MS-00199-RS and MS-01061-RS
Address: 264 East Second South Street, Monticello, Utah
_ (CpXAp) + [Cr x (1,076 - Ap)l
°av9 " 1,076
Cava = Radium-226 concentration in pCi/g averaged over a 100 m2
y (1,076 ft2) area.
Cp = Radium-226 concentration in pCi/g of the residual radioactive
material left in place.
Ap = Area in ft2 of the residual radioactive material left in place.
Cr = Radium-226 concentration in pCi/g for the remainder of the
100 m2 area, including excavated and unexcavated areas.
1,076 = Total area in ft2 over which the EPA guideline is applied.
C— A_ Cp ^avo EPA
Meas. Depth a Standard
Area Method" (inches) (pCi/g) (ft2) (pCi/g) (pCi/g) (pCi/g)
V-34 AL 00 - 06 18.0 104 2.0b 3.5 7.0
V-35 AL 00 - 06 8.3 38 2.0b 2.2 7.0
Therefore, the averaged radium-226 concentrations do not exceed the EPA standard.
"AL = Analytical Laboratory
background radium-226 concentration.
7
Table 3.2
Hot Spot Calculation Results
DOE ID Nos.: MS-00199-RS and MS-01061-RS
Address: 264 East Second South Street, Monticello, Utah
Where:
b9
100
A
Bkg
Sng = [Sgx(100/A)1/2] + Bkg
Hot Spot Limit of radium-226 concentration in pCi/g.
Authorized Limit of radium-226 concentration in pCi/g
(Sg = 5.0 pCi/g for surface soil and 15.0 pCi/g for subsurface soils).
Total area,in m2 over which the Hot Spot Limit guideline is applied.
Area in mz of the hot spot.
Background radium-226 concentration in pCi/g (Bkg = 2.0 pCi/g for
Monticello).
Area
Meas.
Method'
Depth
(inches)
A
(m2)
g
(pCi/g)
&hg
(pCi/g)
Radium-226 in
Hot Spot Area
(pCi/g)
V-34
V-35
AL
AL
00 - 06
00 - 06
9.7
3.5
5.0
5.0
18.1
28.7
18.0
8.3
Therefore, the radium-226 concentrations in the hot spot areas do not exceed the
Hot Spot Limits.
"AL = Analytical Laboratory
8
Table 3.3
Post-Excavation Sample/Measurement Results
DOE ID Nos.: MS-00199-RS and MS-01061-RS
Address: 264 East Second South 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)
V-l
V-2
V-3
V-4
V-5
V-6
V-7
V-8
V-9
V-10
V-ll
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
13
13
14
13
13
13
16
14
14
13
13
13
17
17
14
14
14
14
14
16
16
14
16
14
14
16
19
22
17
17
19
19
19
17
17
20
17
22
19
15"
19"
19
19
20
19
19
19
19
19
19
NAE 952
NAE 953
NAE 954
NAE 955
NAE 956
NAE 957
NAE 958
NAE 959
NAE 960
NAE 961
NAE 962
NAE 964
NAE 965
NAE 966
NCJ 157
NCJ 153
NAF 104
NAF 105
NAF 106
NAF 107
NAF 108
NAF 109
NAF 110
NAF 111
NAF 112
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
OCS
OCS
AL
AL
AL
AL
AL
AL
AL
AL
AL
5.0
2.9
3.4
2.0
2.2
1.9
10.1
4.8
1.0
1.1
7.8
4.3
5.1
8.4
5.7
6.8
2.9
4.1
9.4
4.9
7.1
2.3
6.3
6.1
2.4
0.4
0.2
0.3
0.2
0.2
0.2
0.7
0.4
0.1
0.1
0.6
0.3
0.4
0.6
0.2
0.3
0.6
0.3
0.5
0.2
0.4
0.4
0.2
20.2
18.6
16.9
18.0
20.3
17.3
18.3
20.2
17.7
18.3
19.5
19.7
19.1
19.5
17.9
23.8
23.1
22.3
23.4
18.2
24.6
23.3
21.9
2.2
2.1
2.1
2.1
0.2
2.1
2.1
2.2
2.1
2.2
2.1
2.2
2.2
2.1
1.3
1.6
1.6
1.5
1.6
1.3
1.7
1.6
1.5
0.9
1.2
0.2
0.7
0.1
1.0
0.9
0.7
0.9
0.2
1.0
0.7
0.2
1.1
0.1
0.2
± 0.1
0.1
0.1
0.1
0.1
0.1
0.1
± 0.2
0.8 ± 0.1
0.3 ± 0.1
0.7 ± 0.1
0.9 ± 0.1
0.2
0.1
0.2
1.2 ±
0.8 ±
0.1
0.1
"AL = Analytical Laboratory; OCS = Opposed Crystal System
bPost-restoration scan.
9
Table 3.3 (continued)
Post-Excavation Sample/Measurement Results
DOE ID Nos.: MS-00199-RS and MS-01061-RS
Address: 264 East Second South Street, Monticello, Utah
Exposure- Soil
Rate Range Sample Meas. Radium-226 Potassium Thorium
Area (//R/h) Ticket No. Method" (pCi/g) (pCi/g) (pCi/g)
V-26
V-27
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
17
16
14
17
17
16
17
17
19
17
14
14
15
13
14
14
14
14
20
19
20
20
20
19
19
19
24
28
19
19
22
24
19
21
18
15b
NAF 113
NAF 114
NAF 115
NAF 116
NAE 963
NAE 967
NAE 968
NAE 969
NAE 973
NAE 974
NAB 978
NAB 979
NAB 980
NAB 981
NAB 982
NAB 983
NAB 984
NCJ 155
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
OCS
4.2
3.2
5.9
2.8
9.4
9.0
8.3
8.2
18.0
8.3
5.6
5.0
11.2
7.1
4.0
5.1
4.1
4.0
0.3
0.2
0.4
0.2
0.7
0.7
0.6
0.6
1.3
0.6
0.4
0.3
0.7
0.5
0.3
0.4
0.3
23.4
23.9
23.6
23.4
18.6
19.8
1.6
1.6
1.6
1.6
2.1
2.1
±
±
±
±
±
±
18.6 ± 2.1
17.9 ± 2.1
± 2.3
± 2.1
±
±
±
±
±
±
±
20
18
15
23
23
23.1
22.1
25.2
23.2
1.1
1.7
1.6
1.6
1.6
1.8
1.6
0.6 ± 0.1
< 0.2
1.0 ± 0.1
1.1 ± 0.1
0.6 ± 0.1
< 0.3
1.3 ± 0.2
< 0.2
0.4 ± 0.1
1.2 ± 0.2
0.9 ± 0.1
< 0.2
< 0.3
1.0 ± 0.1
0.6 ± 0.1
0.4 ± 0.1
< 0.2
See Appendix Figure 2.1 for the verification areas.
"AL = Analytical Laboratory; OCS = Opposed Crystal System
bPost-restoration scan.
10
Table 3.4
Radon Decay-Product Concentration Measurement Results
DOE ID Nos.: MS-00199-RS and MS-01061-RS
Address: 264 East Second South Street, Monticello, Utah
Instrument Type: Terradex Radtrak® Detector
Radon
Detector Tracks Per Concentration Working
Number Start Date End Date mm2 (pCi/L) Level
3853830 01-04-94 12-08-94
3839361 01-04-94 12-08-94
3853969 01-04-94 12-08-94
34.1 4.04 0.0202
33.3 3.91 0.0196
30.8 3.63 0.0182
Annual Average: 0.0193
See Appendix Figure 2.1 for the measurement location.
11
42
40
38
36
34
32
30
28
26
24
22
20
18
16
14
12
10
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—i—T
V-16 V-34 V-42
19-2* 14-18 14-19
EAST SECONO SOUTH STREET
LU LU
/ f.
6 X A 6 I V-29
LU 17-20 ® LU LU ®
® ® V-41 V-40
V-27
14-21 14-19 LU ® LU 16-19 V-39 V-28
13-24
<5> 14-20
LU ® V-25 V-26
LU 14-19
LU 17-20 ONE STORY
FRAME HOUSE
W/UNINHABITABLE
PARTIAL BASEMENT
®
V-43 1 LU ®. V-38 1 6 14-15
15-22 12-14
® V-37 V-23 LU 14-19
16-19 V-15 12
4 14-15 V-24 LU ® V-22 14-19
0LU 14-19
fc ® ® V-20 V-36 V-22 V-35 LU 16-19 SHED 14-19 14-19
LU LU V-21
16-19
LU V-33
17-19
® V-19
V-18 V-17 14-20
14-19 14-19
B ® LU SHED
® V-14 V-31 V-32
17-19 16-19 17-19
V-13 V-12
17-22 13-17
LU: LU LU
®
® ® LU LU V-l 1
13-20 V-30
V-10 V-9 17-20 ® LU 13-17 14-17
rs LU ® 4> ® V-7
® V-B 16-19
V-6 V-5 14-19 NORTH
SCALE IN FEET
13-19 13-17 (ST
LU LU LU 20 10 20 V-2 V-1
V-3 ® V-4 13-19 13-16
® 14-22 13-17
® ®
M:\FAS\033\0003\RUOO 1S9V 06/26/95 12:22pm T90760
I I I 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.
<D
rr.-.vi
12-15
12
v-1
16-17
LEGEND
ALL DEPTHS ARE IN INCHES
ALL EXPOSURE RATES ARE 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 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
A PORTION OF ASSESSED AREA B WILL BE
ADDRESSED UNDER MS-00098-RS
RADIOLOGICAL AS-BUILT
FIGURE 2.1
EXTERIOR EXTENT OF CONTAMINATION
no. Mn imm
•f MUCC~NO. or occuPMfn U.S. DEPARTMENT OF ENERGY
JUNCTION PROJECTS OFFICE. COLORADO
!3i ,264 EAST SECOND SOUTH ST.
MONTICELLO, UTAH
I Mt imnwrar-
» MS-00199. 01061-RS
••—< 3-CO0I99-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 GRAND JUNCTION OFFICE
RO. BOX 2567
GRANO JUNCTION. COLORADO 81502 MANAGED BY MARTIN MARIETTA ENERGY SYSTEMS, INC.
SEP 2 0 1995
Ms. Mary Ann Rondinella
Project Coordinator, Monticello Projects
U.S. Department of Energy
P. O. Box 2567
Grand Junction, 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:
MS00199-RS and MS01061-RS
264 East 2nd South Street
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
264 EAST 2ND SOUTH STREET
MONTICELLO, UTAH MS00199-RS and MS01061-RS
A. R. Jones
September 1995
Work performed by the
ENVIRONMENTAL ASSESSMENT GROUP
Prepared by the
OAK RIDGE NATIONAL LABORATORY
Grand Junction, CO 81502
managed by
LOCKHEED MARTIN ENERGY SYSTEMS, INC.
for the
U.S. DEPARTMENT OF ENERGY
under Contract No. DE-AC05-84OR21400
CONTENTS
LIST OF TABLES v
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 samples from 264 East 2nd South Street,
Monticello, Utah (MS00199-RS and MS01061-RS) 5
V
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 D. S. List for analysis of soil samples and J. R. Sauvage and N. F. Lewis 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 1991, RUST
Geotech, the remedial action contractor designated by DOE, performed remedial action on
the vicinity property at 264 East 2nd 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 the ETS are
described in the Environmental Technology Section Procedures Manual (ORNL 1993).
ix
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 264 EAST 2ND SOUTH STREET
MONTICELLO, UTAH (MS00199-RS and MS01061-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 ofthe 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).
*Thc 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-AC05-84OR21400 with Lockheed Martin Energy Systems, Inc.
2
During 1991, 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 264 East 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
restored to a condition comparable to that which existed prior to remedial action (Geotech
1995).
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 264 East 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
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 1995)
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 mill tailings 6 to 12
inches deep. During the actual removal process, a total of 276 yd3 of contaminated earth
and uranium mill tailings, 6 to 12 inches deep were removed from a 1386 m2 area.
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 of the structure, a surface scan of the exterior, and soil sampling. Samples
representative of the bottom 15-cm (6-in.) soil layers of 43 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 14 /iR/h. Exterior surface gamma measurements taken from
the excavated areas prior to backfilling ranged from 13 to 28 fJR/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 43 exterior verification areas.
Geotech's analysis of these samples showed ^Ra concentrations ranging from 1.0 to 18
pCi/g in the composite sample. ORNL ETS obtained a percentage of these soil samples
for confirmatory analysis which showed ^Ra concentration ranging from 6.9 to 9.8 pCi/g.
These value 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
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 01/04/94 to 12/08/94). The average annual
working level (WL) of radon progeny concentration, as determined by the Tech./Ops-
Landauer Corporation, was 0.0193, 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
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 ^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
Maximum Permissible
concentration of Ra226 in soil
above background level, for
areas less than 25 m2.
Ra concentrations, m any
surface or subsurface area
less than 25 m2, is below the
guideline by a factor of
(100/A)*,whereAisthe
area of the elevated region.
Average annual radon proge- 0.03 WL
ny concentration (including
background).
(DOE 1990a)
Exposure to 722Rn
progeny
5
Table 2. Results of ORNL analysis of Geotech soil samples
from 264 East 2nd South Street, Monticello Utah (MS00199-RS and MSO1061-RS)
^Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No." No^ (cm)
X7 NAE 958 >15 9.8 10.1
X21 NAF 108 >15 6.9 7.8
" 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.
REFERENCES
Geotech 1995, Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00199-RS and MSO1061-RS, Address: 264 East 2nd South
Street, Monticello, Utah 84535, Geotech, Grand Junction, Colorado, July 1995.
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.
ORNL, 1993. Environmental Technology Section (Formerly Pollutant Assessment
Group) Procedures Manual. ORNL 6645/R2, September 1993. Oak Ridge National
Laboratory, Grand Junction, Colorado.