DERR-1991-014036 - 0901a06880540db6

RECORDS MANAGEMENT
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00022-RS
ADDRESS: 216 URANIUM DRIVE
MONTICELLO, UTAH 84535
June 1991
Prepared for
Surplus Facilities Management Program
Division of Facilities and Site Decommissioning
Department of Energy
by
Chem-Nuclear Geotech, Inc.
P.O. Box 14000
Grand Junction, Colorado 81502-5504
Harry^lC. Pe: Perry'*
Program Manager
DERR.
SCANNED
Chem-Nuclear Geotech, Inc., has been granted authorization to conduct remedial
action under the Surplus Facilities Management Program. Remedial action was
done in accordance with the Environmental Protection Agency Standards for
Cleanup of Lands and Buildings Contaminated with Residual Radioactive Material
from Inactive Uranium Processing Sites, 40 CFR 192.12, 192.20-23.
MS-00022-RS:PCR-268
SFCMPLRPTS SFMS-00022
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-00022-RS
1.0 SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) project was accepted into
the Surplus Facilities Management Program (SFMP) with the primary
objective of reducing 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, 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 SFMP has adopted the "Standards for Remedial Action at Inactive
Uranium Processing Sites" (40 CFR Part 192) as guidelines for all
cleanup activities under the MVP project. These standards were
prepared by the Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of
buildings and open lands.
This property was evaluated on the basis of the EPA standards by the
Department of Energy (DOE) Inclusion Survey Contractor. The DOE
reviewed these evaluation results and determined that the property
contained residual radioactive material which exceeded the EPA
standards. The Remedial Action Contractor was notified of the
inclusion of this property into the SFMP and was authorized by the
DOE to conduct remedial action as required to bring the property
into conformance with the EPA standards.
1
DOE ID NO.: MS-00022-RS
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-00022-RS
The east 96 feet of the south 165 feet
of Block Q, and also beginning at the
southeast corner of Block Q, east
32.5 feet, north 165 feet, west
32.5 feet, south 165 feet to the point
of beginning, City of Monticello,
County of San Juan, State of Utah
216 Uranium Drive
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
October 14, 1988
Chem-Nuclear Geotech, Inc.
March 17, 1989
Bayless and Bayless, Inc.
1900 Saint Charles Road
Pueblo, Colorado
May 9, 1989
June 12, 1989
Interior: 0 cubic yards
Exterior: 4 cubic yards
9 square meters (m2)
June 1991
DOE ID NO.: MS-00022-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 condition comparable to that which existed prior
to remedial action activities.
2.2 Previously Unidentified Contamination
The original radiological assessment identified 2 cubic yards of
contamination, ranging from 6 inches to 18 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 12 inches deep and up to 12 inches high.
The differences in the extent of assessed contamination and the
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 performed on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the residual
radioactive material removal activities performed on the property.
3
DOE ID NO.: MS-00022-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 Chem-Nuclear
Geotech, Inc., during October 1988, as described in the final
REA dated March 1989. Appendix Figure 2.1 shows the extent
of contamination determined during the pre-remedial
assessment and identifies the areas recommended to undergo
remedial action.
3.1.2 Post-Excavation Survey
A ground-level gamma scan with a scintillometer was performed
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 one of the
verification areas. Additionally, one in-situ measurement
representing the other verification area was taken at grid
coordinates 192190 (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 19 pR/h (Appendix Figure 2.1). The in-
situ measurement result was less than 1.0 pCi/g (Appendix
Table 3.1). 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 0.0051 Working Level (WL), as indicated in Appendix
Table 3.2. Appendix Figure 2.1 shows the measurement
location on the ground floor (the lowest habitable level of
the structure).
4
DOE ID NO.: MS-00022-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) as indicated in the Certification Data Summary below.
Therefore, the property located at 216 Uranium Drive, in Monticello,
Utah, is recommended for certification as required by the SFMP
guidelines, and the appropriate record should be documented.
Certification Data Summary
Standards Applicability Survey Results
Habitable Structures
Exposure Rate: Shall not exceed 20 pR/h
above background.*
Range for the ground
floor was 12 pR/h to
13 pR/h.
Radon Decay-Product
Concentration:
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Annual average
0.0051 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.
The in-situ measurement
result was < 1.0 pCi/g.
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 15 pCi/g
above background** in any
15-cm-thick soil layer
more than 15 cm below the
surface, averaged over
100 m2.
The soil sample
result was 3.4 pCi/g.
*The background exposure rate is approximately 14 /iR/h.
**The background radium-226 concentration is approximately 2.0 pCi/g.
5
DOE ID NO.: MS-00022-RS
4.0 APPENDIX
Appendix Tables:
Table 3.1 Post-Excavation Sample/Measurement Results
Table 3.2 Radon Decay-Product Concentration (RDC)
Measurement Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00022-RS
Address: 216 Uranium Drive, Monticello, Utah
The analytical uncertainties in the table are reported at the 95-percent
confidence interval.
Exposure-Rate Soil Sample Radium-226 Potassium Thorium
Area Range (pR/h) Ticket No. (pCi/g) (pCi/g) (pCi/g)
V-l 14 - 19 MNK 399 3.4 ± 0.6 16.3 ± 3.9 0.9 ± 0.3
V-2* 13 - 16 < 1.0
See Appendix Figure 2.1 for the verification areas.
*In-situ measurement taken at grid coordinates 192190.
7
Table 3.2
Radon Decay-Product Concentration (RDC) Measurement Results
DOE ID No.: MS-00022-RS
Address: 216 Uranium Drive, Monticello, Utah
Instrument Type: Terradex Radtrak® Detector
Radon Average
Detector Tracks Per Concentration Working
Number Start Date End Date mm* (pCi/1) Level (WL)
1650020 11-13-89 12-13-90
1650059 11-13-89 12-13-90
1652396 11-13-89 12-13-90
9.3 1.02 0.0051
10.6 1.17 0.0059
7.7 0.85 0.0043
Annual Average: 0.0051
See Appendix Figure 2.1 for the measurement location.
MM-CJT:06-07-91
MS-00022-RS:PCR-268 WS 5.5
REV051791
8
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<D AVERAGEIDEPTH OF ASSESSED CONTAMINATION
ARtA OF-ASSESSED • GjONTA-M IN ANTS j j • • •
POST REMEDIAL^ ACTION EXPOSURE-RATE RANGE
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POST REMEDIAL: ACTION RADON DECAY-PRODUCT
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ASSESSED • CTJNTAM IN ANTS' 'N OT'
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• 2.1 FIGURE
EXTERIOR EXTENT OF CONTAMINATION
NO. DATE REVISION* BY CK. A.E. APP. NO. DATE REVISIONS BY CK. A.E. APP
RESIDENCE—NO. OF OCCUPANTS U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE, COLORADO THIS DRAWING, PREPARED FOR THE SURPLUS FACILITIES NON-RESIDENCE—MAN.HRSJWK MANAGEMENT PROGRAM. IS:FOR THE; SOLE U$E OF THf U.S.
DEPARTMENT .OF. .ENERGY. AND .LTS. CONTRACTORS.. .LT JS JslOT.
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
FXT.URE.L*jP.R.QYEM'£NT. .LINES
DESIGN e3i
W 216 URANIUM DRIVE
MONTICELLO, UTAH
INSTRUMENT NO. SURVEYOR DRAWN mi SCALE TN FEET Y CHECK rr ii o PROJ. ENG.:
SUBMITTEO APPROVAL DATE APPROVAL DOE DATE 20 10 20 40 SURVEY DATE TIME
x: DOE ID NO MS-00022-RS DATE Geotech, Inc. VERIFICATION
°"°-N°3_B00022-G4SHT1
22 24 26 28 20 30 10 14 36 12 16 32 34 18 38 40
JUN 21 1991
RECORDS MANAGEMENT
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00188-VL
ADDRESS: 397 SOUTH FIRST EAST STREET
MONTICELLO, UTAH 84535
JUNE 1991
Prepared for
Surplus Facilities Management Program
Division of Facilities and Site Decommissioning
Department of Energy
by
Chem-Nuclear Geotech, Inc.
P.O. Box 14000
Grand Junction, Colorado 81502-5504
Harry/A. Perry
Program Manager
Chem-Nuclear Geotech, Inc., has been granted authorization to conduct remedial
action under the Surplus Facilities Management Program. Remedial action was
done in accordance with the Environmental Protection Agency Standards for
Cleanup of Lands and Buildings Contaminated with Residual Radioactive Material
from Inactive Uranium Processing Sites, 40 CFR 192.12, 192.20-23.
MS-00188-VL:PCR-265
IIIIIIIH
SFCMPLRPTS SFMS-00188
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action .... 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
i
DOE ID NO.: MS-00188-VL
1.0 SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) project was accepted into
the Surplus Facilities Management Program (SFMP) with the primary
objective of reducing 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, tailings from the
Monticello millsite were removed from the site and used for
construction-related activities in t'he vicinity.
1.2 Criteria for Remedial Action
The SFMP has adopted the "Standards for Remedial Action at Inactive
Uranium Processing Sites" (40 CFR Part 192) as guidelines for all
cleanup activities under the MVP project. These standards were
prepared by the Environmental Protection Agency (EPA) to establish
guidelines for the control of tailings piles and the cleanup of
buildings and open lands.
This property was evaluated on the basis of the EPA standards by the
Department of Energy (DOE) Inclusion Survey Contractor. The DOE
reviewed these evaluation results and determined that the property
contained residual radioactive material which exceeded the EPA
standards. The Remedial Action Contractor was notified of the
inclusion of this property into the SFMP and was authorized by the
DOE to perform remedial action as required to bring the property
into conformance with the EPA standards.
1
DOE ID NO.: MS-00188-VL
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-00188-VL
Beginning at the NW corner of Lot 1,
Block 9, Monticello Townsite, south
107.25 feet, east 107.25 feet, north
107.25 feet, west to beginning,
County of San Juan, State of Utah
397 South First East Street
Monticello, Utah 84535

Vacant Lot (VL)
Oak Ridge National Laboratory
September 19, 1989
Chem-Nuclear Geotech, Inc.
March 29, 1990
Sonderegger Construction, Inc.
P.O. Box 6
Monticello, Utah
July 12, 1990
August 16, 1990
Interior: 0 cubic yards
Exterior: 288 cubic yards
1,032 square meters (m2)
June 1991
DOE ID NO.: MS-00188-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 condition comparable to that which existed prior
to remedial action activities.
2.2 Previously Unidentified Contamination
The original radiological assessment identified 193 cubic yards of
contamination, 6 inches deep, within the property. The remedial
action process included the removal of approximately 288 cubic yards
of residual radioactive material, ranging from 8 inches to 18 inches
deep.
The differences in the extent of assessed contamination and the
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 performed on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the residual
radioactive material removal activities performed on the property.
3
DOE ID NO.: MS-00188-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 Chem-Nuclear
Geotech, Inc., during October 1989, as described in the final
REA dated March 1990. Appendix Figure 2.1 shows the extent
of contamination determined during the pre-remedial
assessment and identifies the area recommended to undergo
remedial action.
3.1.2 Post-Excavation Survey
A ground-level gamma scan with a scintillometer was performed
after the removal of residual radioactive material and prior
to backfilling. Following the gamma scan, soil samples
representative of the 6-inch-thick soil layer at the bottom
of the excavation were collected. These samples were blended
to form composite samples representing the verification areas
(Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined
during the gamma scan, ranged from 15 microroentgens per
hour (pR/h) to 23 pR/h. The results of analyses for
radium-226 in 11 composite soil samples ranged from
1.2 picocuries per gram (pCi/g) to 3.9 pCi/g (Appendix
Table 3.2).
4
DOE ID NO.: MS-00188-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) as indicated in the Certification Data Summary below.
Therefore, the property located at 397 South First East Street, in
Monticello, Utah, is recommended for certification as required by
the SFMP guidelines, and the appropriate record should be
documented.
Applicability
Certification Data Summary
Standards Survey Results
Habitable Structures
Exposure Rate: Shall not exceed 20 pR/h
above background.
Not applicable:
vacant lot.
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.
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 ma.
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 m*.
< 5 pCi/g above
background.
The soil sample
results ranged from
1.2 pCi/g to 3.9 pCi/g.
*The background radium-226 concentration is approximately 2.0 pCi/g.
DOE ID NO.: MS-00188-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
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00188-VL
Address: 397 South First East Street, Monticello, Utah
The analytical uncertainties in the table are reported at the 95-percent
confidence interval. A less-than sign (<) indicates that the minimum
detection limit based on Compton background was reached.
Area
Exposure-Rate
Range (pR/h)
Soil Sample
Ticket No.
Radium-226
(pCi/g)
Potassium
(pCi/g)
Thorium
(pCi/g)
V-l
V-2
V-3
V-4
V-5
V-6
V-7
V-8
V-9
V-10
V-ll
16
15
17
15
16
15
16
16
17
17
16
21
21
23
20
21
20
21
19
20
19
20
NAA
NAA
NAA
NAA
NAA
NAA
NAA
NAA
NAA
NAA
NAA
456
457
458
459
460
461
462
463
464
465
466
3.9
1.5
1.2
1.5
1.9
20.5 ± 4.2 0.9 ± 0.2
15.4
9.9
13.4
19.0
16.8
18.5
18.7
19.1
18.3
19.5
0.9
0.2
0.7
1.0
0.8
1.0
0.9
0.9
1.1
1.0
± 0.2
0.2
0.2
0.2
0.2
0.2
0.2
0.2
0.2
See Appendix Figure 2.1 for the verification areas.
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-I5-IT
.THIS. DRAWING. PREPARED. FOR THE SURPLUS FACILITIES:
MANAGEMENT PROGRAM, IS FOR THE SOLE USE OF THE U.S.
DEPARTMENT: OF ENEftCY AND JTS CONtRACTORS. IT IS NOT
A LAND SURVEY PLAT; UTIUTY LOCATION PLAT. OR OTHER
JMPRO^MENT^SURVJEY. PLAT ANP IS NOT TQ PE RELIES UPON.
FOR THE ESTABLISHMENT OF FENCE, BUILDING, OR OTHER
FUTURE IMPROVEMENT LINES.:
14 18 22
1 1
24 26 28
112-15
12
• • ALL DEPTHS.IWilNCHES
ALL EXPOSURE:RATES IN fiR/h
..ASSESSED. AREA.IDENTIFIER!
AVERAGE:DEPTH OF ASSESSED CONTAMINATION
• • AR kA G F- |AS S E$S E D • do N TA MIN ANTS
POST REMEDIAL ACTION EXP|OSURE-RATE RANGE
' BOUNDARY'OF' EXCAVATION' j'
AVERAGEiEXCAVATED DEPTH FOR THE DEPOSIT
. • OF. IC ONTAMIN ATJO N ... I
VERIFICATION SOIL SAMPLE AREA iDENTIFIER
AND. EXCAVATION. EXPOSURE-RATE. RANGE....
ASSESSED CONTAMINANTS NOT FOUND AT
TIME OF REMEDIAL ACTION
RADlOlLOiGiC
FTGlDRE'2:r
EXTERIOR ^EXTENT OF CONTAMINATION
NO DATE
RESIDENCE—NO. OF OCCUPANTS
NON.RESIDENCE — MAN-HRS. WK
INSTRUMENT NO. SURVETOR
SURVEY DATE
VERIFICATION
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE. COLORADO
397 SOUTH FIRST EAST ST.
MONTICELLO, UTAH
12
SUBMITTED: [DATE .APPROVAL OOE
30 32
Geotech. Inc.
34
MS-00188-VL
^-B001B8-M4SHT1 QF1
36 40
0330-15
OAK RIDGE NATIONAL LABORATORY
OPERATED BY MARTIN MARIETTA ENERGY SYSTEMS. INC.
GRAND JUNCTION OFFICE
P. 0. BOX 2567
GRAND JUNCTION. COLORADO 81502
Jacob W. Gatrell Vf<
Office of Environmental Restoration
Southwestern Area Programs Division
U.S. Department of Energy
EM-451/GTN/D-247
Washington, DC 20545
Dear Hr. Gatrell:
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. Depart-
ment of Energy.
Sincerely,
Mary J. Wilson
Pollutant Assessments Group
Location Number:
Location Address: 397 South 1st East Street
Monticello. Utah 84535
MS00188
Property Owner:
Owner Address:

Tenant Name: Same
Attachments
DOE ID NO.: MS- U
Property Address: 3*77 SouU first Bcuii Street
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Chem-Nuclear Geotech, Inc. of Energy (DOE)
YES NO NOT TAKEN YES NO NOT TAKEN
Ra-226 is < 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2. [X]* [ ] [ ] [ ] [ ] [ ]
In-situ [X] Lab [ ]
Ra-226 is < 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2. Mil t ] t 1 t ] [ ]
In-situ [ ] Lab b<]
Interior gamma is < 20 juR/h
above background in any
occupied or habitable
structure. [ ] [ ] [X] [ ] [ ] [ ]
(Vacant Lot)
The radon decay-product
concentration in any
occupied or habitable
structure is < 0.02
working levels or, at
most, 0.03 working levels. [ ] [ ] [X] [ ] [ ] [ ]
(Vacant Lot)
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21. [ ) £x] [ ] [ ] [ ] [ ]
Hot spot criteria met as
outlined by U.S. DOE
guidelines for FUSRAP and
Decontamination and
Decommissioning Program
(Rev. 03/02/87). [ ] [ ] f>J [ ] [ ] [ ]
COMMENTS: *The excavations were backfilled with materials which 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 which do not exceed 30-percent above normal background
DOE ID NO. : MS-0^>^'S" V ^-
CHEM-NUCLEAR GEOTECH, INC., RECOMMENDATION
Based on the Chem-Nuclear Geotech, Inc., evaluation, I recommend this property
for:
[X] Certification by the Department of Energy.
[ ] Certification by the Department of Energy with the concurrence of the
Nuclear Regulatory Commission because supplemental standards were
applied per 40 CFR 192.21.
Date
DOE EVALUATION
Should be certified by the Department of Energy.
[ ] Should be certified by the Department of Energy with the concurrence
of the Nuclear Regulatory Commission because supplemental standards
were applied per 40 CFR 192.21.
Decontamination and Decommissioning Program
Certification Official
Department of Energy
Harry A. Perry
Decontamination and Decommissioning Program Manager
Chem-Nuclear Geotech, Inc.
Date
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00159-RS
ADDRESS: 149 SOUTH SECOND EAST STREET
MONTICELLO, UTAH 84535
SEPTEMBER 1991
Prepared for
Decontamination and Decommissioning Program
Division of Facilities and Site Decommissioning
Department of Energy
by
Chem-Nuclear Geotech, Inc.
P.O. Box 14000
Grand Junction, Colorado 81502-5504
Harry A. Perry
Program Manager
Chem-Nuclear Geotech, Inc., has been granted authorization to conduct remedial
action under the Decontamination and Decommissioning Program. Remedial action
was done in accordance with the Environmental Protection Agency Standards for
Cleanup of Lands and Buildings Contaminated with Residual Radioactive Material
from Inactive Uranium Processing Sites, 40 CFR 192.12, 192.20-23.
MS-00159-RS:PCR-274
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-00159-RS
1.0 SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) project was accepted into
the Decontamination and Decommissioning Program with the primary
objective of reducing 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, 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 Decontamination and Decommissioning Program has adopted the
"Standards for Remedial Action at Inactive Uranium Processing Sites"
(40 CFR Part 192) as guidelines for all cleanup activities under the
MVP project. These standards were prepared by the Environmental
Protection Agency (EPA) to establish guidelines for the control of
tailings piles and the cleanup of buildings and open lands.
This property was evaluated on the basis of the EPA standards by the
Department of Energy (DOE) Inclusion Survey Contractor. The DOE
reviewed these evaluation results and determined that the property
contained residual radioactive material which exceeded the EPA
standards. The Remedial Action Contractor was notified of the
inclusion of this property into the Decontamination and
Decommissioning Program and was authorized by the DOE to conduct
remedial action as required to bring the property into conformance
with the EPA standards.
1
DOE ID NO.: MS-00159-RS
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-00159-RS
Parcel No. M-165-1; Block 20, SE4 of
Lot 3, and a portion of the SW4 of
Lot 3, City of Monticello, County of
San Juan, State of Utah
149 South Second East Street
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
June 26, 1987
Chem-Nuclear Geotech, Inc.
March 17, 1989
Crowley Construction
East Route
Monticello, Utah
May 3, 1989
July 10, 1989
Interior: 0 cubic yards
Exterior: 217 cubic yards
1,088 square meters (m2)
September 1991
DOE ID NO.: MS-00159-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 condition comparable to that which existed prior
to remedial action activities.
2.2 Previously Unidentified Contamination
The original radiological assessment identified 227 cubic yards of
contamination, ranging from 6 inches to 21 inches deep, within the
property. The remedial action process included the removal of
approximately 217 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 performed on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the residual
radioactive material removal activities performed on the property.
3
DOE ID NO.: MS-00159-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 Chem-Nuclear
Geotech, Inc., during July 1987, as described in the final
REA dated March 1989. Appendix Figure 2.1 shows the extent
of contamination determined during the pre-remedial
assessment and identifies the area recommended to undergo
remedial action.
3.1.2 Post-Excavation Survey
A ground-level gamma scan with a scintillometer was performed
after the removal of residual radioactive material and prior
to backfilling. Following the gamma scan, soil samples
representative of the 6-inch-thick soil layer at the bottom
of the excavation were collected. These samples were blended
to form composite samples representing the verification
areas. Additionally, four composite soil samples were
collected in unexcavated areas of contamination left in place
(Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined
during the gamma scan, ranged from 14 microroentgens per
hour (pR/h) to 24 pR/h (Appendix Figure 2.1). Residual
radioactive material was left in place in Areas V-5, V-6,
V-8, and V-10 to avoid causing permanent damage to mature
trees and shrubs. The results of analyses for radium-226 in
four composite soil samples of this material ranged from
7.5 picocuries per gram (pCi/g) to 9.5 pCi/g. The 100 m2
area averages of these concentrations ranged from 2.2 pCi/g
to 2.5 pCi/g (Appendix Table 3.1). These areas also meet the
hot spot criteria (Appendix Table 3.2). The results of
analyses for radium-226 in 12 remaining composite soil
samples ranged from 2.3 pCi/g 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 0.0151 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-00159-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) as indicated in the Certification Data Summary below.
Therefore, the property located at 149 South Second East Street, in
Monticello, Utah, is recommended for certification as required by
the Decontamination and Decommissioning Program guidelines, and the
appropriate record should be documented.
Applicability
Certification Data Summary
Standards Survey Results
Habitable Structures
Exposure Rate: Shall not exceed 20 juR/h
above background.*
Range for the ground
floor was 12 pR/h to
15 pR/h.
Radon Decay-Product
Concentration:
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Annual average
0.0151 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 ma.
The soil sample
results, averaged
over 100 m3 areas,
ranged from 2.2 pCi/g
to 2.5 pCi/g.
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 15 pCi/g
above background** in any
15-cm-thick soil layer
more than 15 cm below the
surface, averaged over
100 m*.
The soil sample
results ranged from
2.3 pCi/g to
6.4 pci/g.
*The background exposure rate is approximately 15 pR/h.
**The background radium-226 concentration is approximately 2.0 pCi/g.
5
DOE ID NO.: MS-00159-RS
4.0 APPENDIX
Appendix Tables:
Table 3.1 Calculations of Average Radium Concentrations
Over 100 ma Areas
Table 3.2 Hot Spot Calculation Results
Table 3.3 Post-Excavation Sample/Measurement Results
Table 3.4 Radon Decay-Product Concentration (RDC)
Measurement Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
6
Table 3.1
Calculations of Average Radium Concentrations Over 100 m3 Areas
DOE ID No.: MS-00159-RS
Address: 149 South Second East Street, Monticello, Utah
<cp x Ap) + (cr x l"1'076 " Ap)3
Cavg ~
1,076
Where:
Ca = Radium-226 concentration in pCi/g averaged over a 100 m3
(1,076 ft3) area.
Cp = Radium-226 concentration in pCi/g of the residual radioactive
material left in place.
Ap = Area in ft3 of the residual radioactive material left in place.
Cr = Radium-226 concentration in pCi/g for the remainder of the
100 m2 (1,076 ft2) area.
1,076 = Total area in ft3 over which the EPA guideline is applied.
===s=s=======s==s£=====r========r==========ssss2s=======ss===3==s=s=s===sssassssx
Meas./ Depth Cp Ap Cr** Cavg EPA
Sample Interval Standard
Area Type* (Inches) (pCi/g) (ft3) (pCi/g) (pCi/g) (pCi/g)
V-5 SS
V-6 SS
V-8 SS
V-10 SS
00-06 9.3
00-06 9.5
00 - 06 8.1
00 - 06 7.5
42 2.26
36 2.29
36 2.0
36 2.0
2.5 7.0
2.5 7.0
2.2 7.0
2.2 7.0
Therefore, the averaged radium-226 concentrations do not exceed the EPA
standard.
*SS = Soil Sample (Lab Analysis)
**Weighted average for Area V-5 based on 36 ft3 of Area V-6 at 9.5 pCi/g and
998 ft2 of background at 2.0 pCi/g. Weighted average for Area V-6 based on
42 ft3 of Area V-5 at 9.3 pCi/g and 998 ft3 of background at 2.0 pCi/g.
Background radium-226 concentration used for Areas V-8 and V-10.
Table 3.2
Hot Spot Calculation Results
DOE ID No.: MS-00159-RS
Address: 149 South Second East Street, Monticello, Utah
Shg " Sg x <100 / A)*5
Where:
SnQ = Hot Spot Limit of radium-226 concentration in pCi/g.
Sg = Authorized Limit of radium-226 concentration in pCi/g based
a background concentration of 2.0 pCi/g (SQ = 7.0 pCi/g for
surface soils and 17.0 pCi/g for subsurface soils).
100 = Total area in m2 over which the Hot Spot Limit guideline is
applied.
A = Area in m2 of the hot spot.
Area
Meas./
Sample
Type*
Depth
Interval
(Inches) (m2)
g
(pCi/g)
shg
(pCi/g)
Radium-226 in
Hot Spot Area
(pCi/g)
V-5
V-6
V-8
V-10
SS
SS
SS
SS
00
00
00
00
06
06
06
06
3.90
3.34
3.34
3.34
7.0
7.0
7.0
7.0
35.4
38.3
38.3
38.3
9.3
9.5
8.1
7.5
Therefore, the radium-226 concentrations in the hot spot areas do not exceed
the Hot Spot Limit.
*SS = Soil Sample (Lab Analysis)
8
Table 3.3
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00159-RS
Address: 149 South Second East Street, Monticello, Utah
The analytical uncertainties in the table are reported at the 95-percent
confidence interval. A less-than sign (<) indicates that the minimum
detection limit based on Compton background was reached.
Area
Exposure-Rate
Range (pR/h)
Soil Sample
Ticket No.
Radium-226
(pCi/g)
Potassium
(pCi/g)
Thorium
(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
16
14
14
15
17
18
15
16
14
17
14
17
15
15
15
15
21
24
21
24
20
21
20
19
21
19
19
19
19
18
18
18
MNK
MNK
MNK
MNK
MNK
MNK
MNK
MNK
MNK
MNK
MNK
MNK
MNK
MNK
MNK
MNK
393
394
395
396
315
316
407
322
408
324
401
402
403
404
405
406
9.5
4.2
8.
6.
7.
4.
5.0
3.3
3.4
3.7
4.0
0.9
0.8
0.5
0.6
1.6
0.7
0.9
0.6
0.6
0.7
0.7
18.7
18.1
20.5
19.6
18.
23.
17.
20.
18.
21.
20.
18.
19.
20.
20.
20.
4.3
4.2
4.0
5.0
4.1
5.4
4.4
4.0
4.2
4.3
4.3
4.4
0.9
1.0
1.0
1.1
0.5
0.7
1.2
0.9
0.8
1.1
0.9
0.3
0.3
0.3
0.3
0.4
0.3
0.3
0.3
0.3
See Appendix Figure 2.1 for the verification areas.
*Soil sample of residual radioactive material left in place.
9
Table 3.4
Radon Decay-Product Concentration (RDC) Measurement Results
DOE ID No.: MS-00159-RS
Address: 149 South Second East Street, Monticello, Utah
Instrument Type: Terradex Radtrak* Detector
Detector
Number Start Date End Date
Tracks Per
mm*
Radon
Concentrat ion
(pCi/1)
Average
Working
Level (WL)
1652408
1652237
1650070
11-13-89
11-13-89
11-13-89
12-12-90
12-12-90
12-12-90
27.8
27.4
25.2
3.13
3.08
2.83
0.0157
0.0154
0.0142
Annual Average: 0.0151
See Appendix Figure 2.1 for the measurement location.
MM-JEK:08-06-91
MS-00159-RS:PCR-274 WS 5.5
REV051791
10
12 14 16 18 10 20 22 26 28 24 30 32 34 36 38 40
+ I I I I I I I I 1 I I
18-21
Xrr. t LEGEND
ALi DEPTHS. JMllNCHES ]....
ALL EXPOSURE!RATES IN /iR/h
•••••••••^9% 28 V-10 V-2
V-1 ® 17-19 14-24 y ASSESS ED. AREA. .IDENTIFIER j ] j...
AVERAGE;DEPTH OF ASSESSED CONTAMINATION
AREA OF-ASSESSED GjONTAMINANTS
POST REMEDIAL; ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION'I!
16-21 V-3
14-21
26
12 V-4 12 15
21 15-24
; ONE:
; STORY
HOUSE..
W/CRAWL
; SPACE
;12-15
SHED-AVERAGE :EXCAVATED DEPTH
OF..CONTAMINATION....;
FOR THE DEPOSIT 12 V-9
24 V-8 14-21 33L5 6-19 VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE-RATE RANGE mm 16-17
POST REMEDIAL ACTION RADON DECAY—PRODUCT
CONCENTRATION MEASUREMENT LOCATION
ASSESSED • CONTAMI NANTS' NOT FQTJND' ATI"'
TIME OF REMEDIAL ACTION i
RDC 18-21-,; V-11 6 m 0 - 22 14-19 18T21
V-1 6 . AREA WITH- CONTAMINATION.- LEFT..IN-PLACE V-7 . 6 15-18 V-6 15-20
18-21 - 20
>N.-. THIS DRAWING. PREPARED FOR THE DECONTAMINATION AND
DECOMMISSIONING' PROGRAM, IS FOR THE SOLE USE OF THE
U.S. DEPARTMENT .OF ENERGY AND ITS CONTRACTORS. IT IS
NOT A LAND SURVEY PLAT, jUnUTY LOCATION; PLAT, Ofr OTHER
IMPROVEMENT SURVEY PLAT AND IS:N0T TO BE RELIED UPON
FOR THE ESTABLISHMENT OF FENCE; BUILDING, OR OTHER
FUTURE IMPROVEMENT LINES;'.
18-21 V-12
17-19
V-14
15-18 V-5
17-20 18
18-21 • ••••••
rrr V-15
mm 15-18 V-13
16 14-16 RADIOLOGICAL AS-BUILT ROOT
CELLAF
15-19
mm V-9 • r FIGURE 2.1 < » » i y
I >A.i. < >V«Vc«i 14-21 EXTENT OF CONTAMINATION EXTERIOR
14
; \= 18-21
<
3= NO. DATE REVISIONS BV CK A.E. APP NO. DATE REVISIONS BY CK. A.E. APR
RESIDENCE —NO. OF OCCUPANTS U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE. COLORAOO > I r: NON-RESIDENCE — MAN.HRS. WK OC
ft
DESIGNED
m 12 149 SOUTH SECOND
EAST STREET
MONTICELLO, UTAH
DRAWN INSTRUMENT NO. SURVEYOR
tt DC ; SCALE IN FEET Y o
APPROVAL SUBMITTED DATE APPROVAL OOE DATE
L^x ; 20 ; 10
i j i_
20 SURVEY DATE 40 TIME
OOE ID NO.
DWG. NO.
MS-00159-RS Geotech, Inc. VERIFICATION DATE
"3-B00159-G4 + SHT
22 24 20 26 28 14 16 30 34 12 18 32 36 38 10 40
Results of the
Independent Verification of
Radiological Remedial Action
at 149 South 2nd East Street
Monticello, Utah (MS00159)
M. J. Wilson
J. K. Williams
HEALTH AND SAFETY RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
149 SOUTH 2ND EAST STREET
MONTICELLO, UTAH (MS00159)
M. J. Wilson and J. K. Williams
December 1991
Work performed by the
POLLUTANT ASSESSMENTS 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 5
iii
LIST OF TABLES
1 Applicable guidelines for protection against radiation 5
2 Results of ORNL analysis of UNC Geotech soil samples from 149 South 2nd East
Street
Monticello, Utah (MS00159) 6
v
AC^OWlJEIXJIvlENTS
Research for this project was sponsored by the Division of Facility and Site
Decommissioning Projects, U.S. Department of Energy. The authors wish to acknowledge
G. A. Pierce for analysis of soil samples and A. R. Jones. S. K. Mather, and G. K Stowe
for technical reviews.
vi
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 1989 and 1990, UNC Geotech, the remedial action contractor
designated by DOE, performed remedial action on the vicinity property at 149
South 2nd East Street, Monticello, Utah. The Pollutant Assessments Group
(PAG) 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 PAG found that the site successfully
meets the DOE remedial action objectives. Procedures used by the PAG are
described.
ix
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 149 SOUTH 2ND EAST STREET
MONTICELLO, UTAH (MS00159)*
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 IL 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) Project1
*The verification of remedial action was performed by members of the Pollutant Assessments
Group of the Health and Safety Research Division at Oak Ridge National Laboratory under DOE
contract DE-AC05-84OR21400 with Martin Marietta Energy Systems, Inc.
2
During 1989 and 1990, 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 149 South 2nd East Street,
Monticello, Utah. The remedial action plan required excavation of all exterior contamina-
tion. When the excavation was completed, the property was resurveyed, including soil
sampling, to ensure the removal of all contamination, backfilled with uncontaminated
material, and restored to a condition comparable to that which existed prior to remedial
action.2
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 Pollutant Assessments Group (PAG) of Oak Ridge National
Laboratory (ORNL) has been assigned the responsibility of this task at the 149 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.
Document Reviews
Review of the property completion report prepared by Geotech2 indicates the
property was evaluated by DOE on the basis of Environmental Protection Agency
standards3 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 227 yd3 of mill
tailings 6 to 21 in. deep. However, during the actual removal process, a total of 217 yd3 of
contaminated earth and uranium mill tailings, 6 in. deep, were removed from a 1088 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, ground-level
and basement scans of the building and a surface scan of the exterior and soil sampling.
Samples representative of the bottom 15-cm (6-in.) soil layers of sixteen 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
Gamma exposure rate measurements taken by Geotech at the ground-level of the
residence ranged from 12-15 /iR/h. Exterior surface gamma measurements taken from the
excavated areas prior to backfilling ranged from 14-24 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 twelve exterior verification
area. Geotech's analysis of these samples showed 226Ra concentrations from 2.3 pCi/g to
6.4 pCi/g in the composite sample. ORNL PAG obtained these soil samples and
performed a confirmatory analysis, which showed ^Ra concentrations from 2.1 to 5.7
pCi/g. These values are below the DOE guideline value of 15 pCi/g for soil layers >15
cm below the surface (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
Terradex Track Etch* detectors on the ground floor of the residence located on this
property for a period of approximately one year (from 11/13/89 to 12/12/90). The average
annual working level (WL) of radon progeny concentration, as determined by the
Terradex Corporation, was 0.0151, 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.
* Track Etch is a registered trademark of Terradex Corporation.
4
At the property owner's request Geotech left in place four areas of contamination
associated with trees and shrubs. Composite soil samples were taken in each of the areas,
which showed ^Ra concentrations from 7.5 pCi/g to 9.5 pCi/g. ORNL PAG obtained
these soil samples and performed a confirmatory analysis which showed ^Ra
concentration from 6.1 to 7.7 pCi/g. When averaged over 100 m2, these values are below
the DOE guideline value of 5 pCi/g for sofl samples 0-15 cm below the surface. These
values are also below the DOE Hot Spot guidelines for each of these areas.
5
REFERENCES
1. L N. Abramiuk. et al., 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, 1989.
2. Geotech, Property Completion Report for Monticello Vicinity Property Remedial Action
for DOE ID NO: MS00159, Address: 149 South 2nd East Street, Monticello, Utah
84535, Geotech, Grand Junction, Colorado, September 1991.
3. Guidelines for Residual Radioactivity at Formerly United Sites, Remedial Action
Program and Remote Surplus Facilities Management Program Sites, Rev. 2, U.S.
Department of Energy, March 1987.
6
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
Exposure to 222Rn Average annual radon proge- 0.03 WL
progeny ny concentration (including
background)
Source: Adapted trom Guidelines pr Residual Radioactive Matenal at Formerly
Utilized Sites Remedial Action Program and Remote Surplus Facilities Management Program
Sites, Rev. 2, U.S. Department of Energy, March 1987.
7
Table 2. Results of ORNL analysis of UNC Geotech soil samples
from 149 South 2nd East Street, Utah (MS00159)
UNC ^Ka concentration (pU/g)
ORNL Geotech LTNC
sample sample Depth ORNL Geotech
No.' No.k (cm)
XI VI 15-30 4.4 5.2
X2 V2 15-30 3.7 4.3
X3 V3 15-30 2.1 2.3
X4 V4 15-30 3.4 3.2
X5* V5 0-15 7.2 9.3
X6* V6 0-15 7.7 9.5
X7 V7 15-30 2.9 4.2
X8* V8 0-15 6.1 8.1
X9 V9 15-30 5.7 6.4
X10* V10 0-15 6.2 7.5
XII Vll 15-30 3.9 4.1
X12 V12 15-30 5.1 5.0
X13 V13 15-30 2.7 3.3
X14 V14 15-30 2.9 3.4
X15 V15 15-30 3.4 3.7
X16 V16 15-30 2.9 4.0
"An X-type sample is a split of the sample taken by the remedial action contractor.
fcSoil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated
areas were taken by UNC Geotech, and these samples were blended to form a composite
soil sample, which represents an average over one of the verification areas.
* Soil samples of surface (0-15 cm) contamination to remain in place.
DOE ID NO. : MS- OO > 5 ^ - £ 5
Property Address: l4c1 Sov% Second Sfrecf"
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
Chem-Nuclear Geotech, Inc.
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 f>0
Interior gamma is < 20 pfR/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is < 0.02
working levels or, at
most, 0.03 working levels.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21.
Hot spot criteria met as
outlined by U.S. DOE
guidelines for FUSRAP and
Decontamination and
Decommissioning
Program (Rev. 03/02/87).
[X]'
[ ]
XI
[ ]
[ ]
( ]
[ ]
[ ]
( ]
[ ]
[ ]
[ ]
[ ]
[ ]
U.S. Department
of Energy (DOE)
YES NO NOT TAKEN
C 1 [ ] [ 1
[ ]
[ ]
[ ]
[ )
t ]
[ ]
t ]
[ ]
[ ]
( ]
[ ]
[ ]
[ ]
[ ]
[ ]
COMMENTS: *The excavations were backfilled with materials which 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 which do not exceed 30-percent above normal background.
x:
UG 28 1992
SFCERT1 FED
RFOORDS MANAP"*".-
SFMS-00159
DOE ID NO. : MS- QQ I S - £S
CHEM-NUCLEAR GEOTECH, INC., RECOMMENDATION
Based on the Chem-Nuclear Geotech, Inc., evaluation, I recommend this property
for:
[X] Certification by the Department of Energy.
[ ] Certification by the Department of Energy with the concurrence of the
Nuclear Regulatory Commission because supplemental standards were
applied per 40 CFR 192.21.
Harry A. Perry
Decontamination and Decommissioning Program Manager
Chem-Nuclear Geotech, Inc.
Date
DOE EVALUATION
[^] Should be certified by the Department of Energy.
[ ] Should be certified by the Department of Energy with the concurrence
of the Nuclear Regulatory Commission because supplemental standards
were applied per 40 CFR 192.21.
Decontamination and Decommissioning Program
Certification Official
Department of Energy
Date
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00171-RS
ADDRESS: 433 SOUTH MAIN STREET
MONTICELLO, UTAH 84535
SEPTEMBER 1991
Prepared for
Decontamination and Decommissioning Program
Division of Facilities and Site Decommissioning
Department of Energy
by
SEP l:i 1991
Chem-Nuclear Geotech, Inc.
P.O. Box 14000
Grand Junction, Colorado 81502-5504
RECORDS MANAGEMENT
Harry A. Perry
Program Manager
Chem-Nuclear Geotech, Inc., has been granted authorization to conduct remedial
action under the Decontamination and Decommissioning Program. Remedial action
was done in accordance with the Environmental Protection Agency Standards for
Cleanup of Lands and Buildings Contaminated with Residual Radioactive Material
from Inactive Uranium Processing Sites, 40 CFR 192.12, 192.20-23.
MS-00171-RS:PCR-275
SFCMPLRPTS SFMS-00171
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
410 APPENDIX 6
i
DOE ID NO.: MS-00171-RS
1.0 SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) project was accepted into
the Decontamination and Decommissioning Program with the primary
objective of reducing 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, 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 Decontamination and Decommissioning Program has adopted the
"Standards for Remedial Action at Inactive Uranium Processing Sites"
(40 CFR Part 192) as guidelines for all cleanup activities under the
MVP project. These standards were prepared by the Environmental
Protection Agency (EPA) to establish guidelines for the control of
tailings piles and the cleanup of buildings and open lands.
This property was evaluated on the basis of the EPA standards by the
Department of Energy (DOE) Inclusion Survey Contractor. The DOE
reviewed these evaluation results and determined that the property
contained residual radioactive material which exceeded the EPA
standards. The Remedial Action Contractor was notified of the
inclusion of this property into the Decontamination and
Decommissioning Program and was authorized by the DOE to conduct
remedial action as required to bring the property into conformance
with the EPA standards.
1
DOE ID NO.: MS-00171-RS
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:
MS-00171-RS
Parcel No. M-12; the south half of
Lot 3, Block 3, Monticello Townsite
Survey, Plat A, City of Monticello,
County of San Juan, State of Utah
433 South Main Street
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
March 1, 1989
Chem-Nuclear Geotech, Inc.
August 9, 1989
Crowley Construction
East Route
Monticello, Utah
September 13, 1989
September 27, 1989
Interior: 0 cubic yards
Exterior: 18 cubic yards
95 square meters (m2)
Property Completion Report
Submitted: September 1991
DOE ID NO.: MS-00171-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 condition comparable to that which existed prior
to remedial action activities.
2.2 Previously Unidentified Contamination
The original radiological assessment identified 10 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,
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 performed on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the residual
radioactive material removal activities performed on the property.
3
DOE ID NO.: MS-00171-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 Chem-Nuclear
Geotech, Inc., during April 1989, as described in the final
REA dated August 1989. Appendix Figure 2.1 shows the extent
of contamination determined during the pre-remedial
assessment and identifies the areas recommended to undergo
remedial action.
3.1.2 Post-Excavation Survey
A ground-level gamma scan with a scintillometer was performed
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 (pR/h) to 22 pR/h (Appendix Figure 2.1). The result of
analysis for radium-226 in one composite soil sample was
1.7 picocuries per gram (pCi/g), as indicated in Appendix
Table 3.1.
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on measurements representing an annual average, the
RDC was 0.0162 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-00171-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) as indicated in the Certification Data Summary below.
Therefore, the property located at 433 South Main Street, in
Monticello, Utah, is recommended for certification as required by
the Decontamination and Decommissioning Program guidelines, and the
appropriate record should be documented.
Certification Data Summary
Applicability Standards
Habitable Structures
Exposure Rate: Shall not exceed 20 pR/h
above background.*
Survey Results
Range for the basement
was 13 pR/h to 15 pR/h.
Radon Decay-Product
Concentration:
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Annual average
0.0162 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 .
< 5 pCi/g above
background.
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 15 pCi/g
above background** in any
15-cm-thick soil layer
more than 15 cm below the
surface, averaged over
100 m2.
The soil sample result
was 1.7 pCi/g.
*The background exposure rate is approximately 15 pR/h.
**The background radium-226 concentration is approximately.2.0 pCi/g.
5
DOE ID NO.: MS-00171-RS
4.0 APPENDIX
Appendix Tables:
Table 3.1 Post-Excavation Sample/Measurement Results
Table 3.2 Radon Decay-Product Concentration (RDC)
Measurement Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00171-RS
Address: 433 South Main Street, Monticello, Utah
The analytical uncertainties in the table are reported at the 95-percent
confidence interval.
Exposure-Rate Soil Sample Radium-226 Potassium Thorium
Area Range (pR/h) Ticket No. (pCi/g) (pCi/g) (pCi/g)
V-l 14 - 22 MNQ 725 1.7 ± 0.3 20.2 ± 4.2 1.3 ± 0.3
See Appendix Figure 2.1 for the verification area.
7
Table 3.2
Radon Decay-Product Concentration (RDC) Measurement Results
DOE ID No.: MS-00171-RS
Address: 433 South Main Street, Monticello, Utah
Instrument Type: Terradex Radtrak® Detector
Radon Average
Detector Tracks Per Concentration Working
Number Start Date End Date mm2 (pCi/1) Level (WL)
1652249 11-13-89
1652379 11-13-89
1650062 11-13-89
12-12-90 28.5
12-12-90 27.6
12-12-90 30.1
3.21 0.0161
3.11 0.0156
3.40 0.0170
Annual Average: 0.0162
See Appendix Figure 2.1 for the measurement location.
MM-VPF:08-14-91
MS-00171-RS:PCR-275 WS 5.5
REV051791
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THIS DRAWING. PREPARED FOR THE DECONTAMINATION AND
DECOMMISSIONING PROGRAM. IS FOR THE SOLE USE OF THE
. .U.SL DEPARTMENT. .OF. iCNERCY. AND JXS .CONTRACTORS. .UJS...
NOT A LAND SURVEY PLAT. OTILTTf LOCATION PLAT. OR OTHER
IMPROVEMENT SURVEf PLAT ADD IS NOT TO BE RELIED Ut>OH
FOR THE ESTABLISHMENT OF FENCE. BUILDING. OR OTHER
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U.S. DEPARTMENT OF ENERGY
GRANO JUNCTION PROJECTS OFFICE. COLORADO
433 SOUTH MAIN STREET
MONTICELLO. UTAH
.mom IMTI IAMMOVAL DOT"
bof ib NO.
GooUch, Inc. MS-0O171-RS
36 38 40 42 44 46
3-rnni7i-B«wi o. 1
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DOE ID No.: MS-00171-RS
Property Address: 433 South Main Street
Vicinity Property Certification Summary and Recommendation
Summary Evaluation
Certification Criteria MACTEC-ERS
U.S. Department
of Energy (DOE)
Ra-226 is <. 5 pCi/g above
background in top 15-cm-thick layer
of soil averaged over 100 m2
In situ [X] Lab [ ]
Ra-226 is < 15 pCi/g above
background in any 15-cm-thick layer
of soil more than 15 cm below the
surface averaged over 100 m2.
In situ [ ]Lab[X]
Interior gamma is < 20 uR/h above
background in any occupied or
habitable structure.
The radon decay-product
concentration in any occupied or
habitable structure is <; 0.02 WL or, at
most, 0.03 WL.
Supplemental standards were applied
in accordance with EPA standard
40 CFR 192.21.
Hot spot criteria met as outlined by
DOE guidelines for FUSRAP
(Rev.2, March 1987)
Yes No Not Taken Yes No Not Taken
[X]a [ ]
[X] [ ]
[X] [ ]
[X] [ ]
[ ] [X]
[X] [ ]
[ ]
[ ]
[ ]
[ ]
[ ]
[ ]
[/] [ ]
[ ]
L» [ ]
IX] [ ]
[ ] [\J
[ ]
[ ]
[ ]
[ ]
[ ]
''The excavations were backfilled with materials that were measured at the source indicating that the Ra-226
concentrations are in the range of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
1 of 2
DOE ID No.: MS-00171-RS
MACTEC-ERS Recommendation
On the basis ofthe Property Completion Report evaluation, this property is recommended for
[X] Certification by DOE.
[ ] Certification by DOE with the concurrence of the U.S. Nuclear Regulatory Commission
because supplemental standards were applied according to 40 CFR 192.21.
24
ams
iLa&s ——j— lew \ , \ ^ if
Dale
Manager, Monti
MACTEC-ERS
DOE Evaluation
On the basis of the Property Completion Report evaluation, this property
ft/] Should be certified by DOE.
[ ] Should be certified by DOE with the concurrence of the U.S. Nuclear Regulatory
Commission because supplemental standards were applied according to 40 CFR 192.21.
Certification Official Date
U.S. Department of Energy
Work performed under DOE Contract No. DE-AC13-95GJ87335, Task Order No. 96-05.02.14
2 of 2
•MiN i 7 1997
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00203-VL
ADDRESS: 397 SOUTH FIRST EAST STREET
MONTICELLO, UTAH 84535
SEPTEMBER 1991
Prepared for
Decontamination and Decommissioning Program
Division of Facilities and Site Decommissioning
Department of Energy
by
EP 3 0 1991
Chem-Nuclear Geotech, Inc.
P.O. Box 14000
Grand Junction, Colorado 81502-5504
RECORDS MANAGEMENT Harry A. Perry
Program Manager
Chem-Nuclear Geotech, Inc., has been granted authorization to conduct remedial
action under the Decontamination and Decommissioning Program. Remedial action
was done in accordance with the Environmental Protection Agency Standards for
Cleanup of Lands and Buildings Contaminated with Residual Radioactive Material
from Inactive Uranium Processing Sites, 40 CFR 192.12, 192.20-23.
MS-00203-VL:PCR-277
SFCMPLRPTS SFMS-39009
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-00203-VL
1.0 SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) project was accepted into
the Decontamination and Decommissioning Program with the primary
objective of reducing 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, 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 Decontamination and Decommissioning Program has adopted the
"Standards for Remedial Action at Inactive Uranium Processing Sites"
(40 CFR Part 192) as guidelines for all cleanup activities under the
MVP project. These standards were prepared by the Environmental
Protection Agency (EPA) to establish guidelines for the control of
tailings piles and the cleanup of buildings and open lands.
This property was evaluated on the basis of the EPA standards by the
Department of Energy (DOE) Inclusion Survey Contractor. The DOE
reviewed these evaluation results and determined that the property
contained residual radioactive material which exceeded the EPA
standards. The Remedial Action Contractor was notified of the
inclusion of this property into the Decontamination and
Decommissioning Program and was authorized by the DOE to conduct
remedial action as required to bring the property into conformance
with the EPA standards.
1
DOE ID NO.: MS-00203-VL
1.3 Summary of Remedial Action
DOE ID No.: MS-00203-VL
Legal Description:
Parcel No. M-58-1; beginning at the southeast corner of Lot 2, Block 9,
Monticello Townsite; west 114.5 feet, north 90 feet, west 100 feet, north
6 feet, east 162.5 feet, north 118.5 feet, east 52 feet, south 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:
397 South First East Street
Monticello, Utah 84535

Vacant Lot (VL)
Oak Ridge National Laboratory
September 19, 1989
Chem-Nuclear Geotech, Inc.
July 16, 1990
Sonderegger, Inc.
P.O. Box 6
Monticello, Utah
August 22, 1990
September 8, 1990
Interior: 0 cubic yards
Exterior: 747 cubic yards
1,874 square meters (m2)
September 1991
2
DOE ID NO.: MS-00203-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 condition comparable to that which existed prior
to remedial action activities.
2.2 Previously Unidentified Contamination
The extent of contamination identified during the original
radiological assessment for this property is shown on Appendix
Figure 2.1, and was 6 inches deep. The remedial action process
included the removal of approximately 747 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 performed on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the residual
radioactive material removal activities performed on the property.
3
DOE ID NO.: MS-00203-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 Chem-Nuclear
Geotech, Inc., during April 1990, as described in the final
REA dated July 1990. Appendix Figure 2.1 shows the extent of
contamination determined during the pre-remedial assessment
and identifies the area recommended to undergo remedial
action.
3.1.2 Post-Excavation Survey
A ground-level gamma scan with a scintillometer was performed
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 (L/R/h) to 21 juR/h (Appendix Figure 2.1). The results of
analyses for radium-226 in 21 composite soil samples ranged
from 1.2 picocuries per gram (pCi/g) to 10.2 pCi/g (Appendix
Table 3.1).
4
DOE ID NO.: MS-00203-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), as indicated in the Certification Data Summary below.
Therefore, the property located at 397 South First East Street, in
Monticello, Utah, is recommended for certification as required by
the Decontamination and Decommissioning Program guidelines, and the
appropriate record should be documented.
Certification Data Summary
Applicability Standards Survey Results
Habitable Structures
Exposure Rate: Shall not exceed 20 fjR/h
above background.
Not applicable: vacant
lot.
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.
Not applicable: vacant
lot.
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.
< 5 pCi/g above
background.
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 15 pCi/g
above background* in any
15-cm-thick soil layer
The soil sample results
ranged from 1.2 pCi/g
to 10.2 pCi/g.
more than 15 cm below the
surface, averaged over
100 m2.
*The background radium-226 concentration is approximately 2.0 pCi/g.
DOE ID NO.: MS-00203-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
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00203-VL
Address: 397 South First East Street, Monticello, Utah
The analytical uncertainties in the table are reported at the 95-percent
confidence interval.
Area
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
Exposure-Rate
Range (/uR/h)
Soil Sample
Ticket No.
15
14
15
14
15
18
17
15
14
15
17
17
14
15
15
15
16
15
17
15
15
18
17
20
21
21
21
21
21
21
21
20
21
17
19
20
19
19
20
20
21
20
NAH
NAE
NAE
NAE
NAE
NAE
NAE
NAE
NAE
NAE
NAE
NAE
NAE
NAE
NAE
NAH
NAH
NAH
NAH
NAH
NAH
750
758
759
760
761
762
763
764
765
766
767
768
769
770
771
744
745
746
747
748
749
Radium-226
(pCi/g)
Potassium
(pCi/g)
Thorium
(pCi/g)
1.5
1.2
1.7
2.
7.
9.
10.
6.
5.
4.
3.
4.
1.
4.3
5.5
0.3
0.2
0.3
0.4
1.0
1.2
1.3
0.9
0.7
0.6
0.6
0.6
0.5
0.6
0.6
0.4
16.2
17.1
16.0
15.6
22.0
23.5
22.3
23.3
21.3
21.9
17.0
17.8
15.8
17
18
15
17
17
18.3
19.7
20.9
3.0
3.1
.0
.0
, 1
.3
.1
.2
.0
. 1
4.0
4.1
3.9
4.1
4.2
3.0
3.3
3.3
3.3
3.5
3.6
0.9
1.5
0.9
1.3
1.1
1.0
0.9
0.8
1.1
0.9
0.7
1.3
1.1
0.9
1.1
1.3
1.3
0.9
0.9
1.2
1.0
0.2
0.3
0.3
0.3
0.3
0.3
0.3
0.3
0.3
0.3~
0.3
0.3
0.3
0.3
0.3
0.3
0.3
0.3
0.3
0.3
0.3
See Appendix Figure 2.1 for the verification areas.
MM-JEK:09-11-91
MS-00203-VL:PCR-277 WS
REV051791
5.5
7
42
40
38 -
36
34
32
30
28
26
24
22
20
18
16
14
12
+ 10
i—r
2a
~T~
30 32
i—r
34 36 38 40
u : o: :
y- •
.(T) ....
t-
<
. I*...:..
X :
1- :
3 :
O :
11+'-17*"'
14-17 SHED
H3-1
V-20 V-21
12 15-2 15-20
^ -
V-19 1 2 17-20
^ 0 \ D :
V-18
15-20 WW 12
V-17
16-19
0
V-1 6 f0 12 15-19 14-17
*-14-17 12
1 ;..©
0 15 14 j ©I 12 12 15-19 15-20
01 0 12-15
0 1 2 •'• 0 12
14-21 V-12 0 12 V-1
15-21 17-20 17-21 16-17
0 0J
V-8 V-7 v-a 12
18-21 17-21 15-21
V-5
15-21 12 12
) ' i
C—T-f
0 3
-44-
V-1 V-2 V-3 12 15-20 14-21 15-18 14-17
ex 12
1 777
•SHED-
42
1 r
44 46 50 +
LEGEND
ALL DEPTHS IN: INCHES j j j ';
ALL EXPOSURE: RATES IN /iR/h ;
. ASSESSED AREA. IDENTIFIER j \
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF; ASSESSED CONTAMINANTS j
PC<ST REMEDIAL1 ACTION EXPOSUR£-RATjE RANjGE
BOUNDARY OF EXCAVATION jjjI
AVERAGE EXCAVATED toEPTrj FOR THE DEPOSIT
OF' CONTAMINATION...; j | \
VERIFICATION SOIL SAMPLEiAREA IDENTIFIER j
..ANiD..Ey^AyAT.1.^ I
ASSESSED CONTAMINANTS NOT FOUND AT I
TIME OF REMEDIAL ACTION :
"ORNL DATAi!!!!
(DJ : EAST FOURTH SOUTH STREET
RADiOiLO^lCAL AS^BUILIT
40
38
36
34
32
30
28
26
24
22
20
18
16
j-'FIGURE-2. T;\
EXTERIOR: EXTEKIT OF CONTAMINATION
•tUtrlwCk-irt Of OCCu*>NTS
Y • SCALE" IN IFEET I'
••;'20';''io''':''''o'''':'
J I I L
""20":""40" ":"'
L_J L NORTH;
.. THIS ORAWINC. PREPAREO TOR THE DECONTAMINATION ANO.
OECOUUISSIONINC PROGRAM, IS TOR THE SOLE USE OF THE U.S.
DEPARTMENT: OF ENERGY AND ITS CONTRACTORS. IT IS NOT
A LAND SURVEY PLAT; UTILITY LOCATION PLA1. OR OTHER
IMPROVEMENT SURVEY PLAT ANP IS NOT TO « RELIED UPON
FOR" THE ESTABLISHMENT OF HENCE, BUILDINO. ON OtHtK
FUTURE IMPROVEMENT LINES. :
I 1 I I I I J L JL
•OttdlftlDlntl-M.
Vl«R*tC«1lOM
CK * f t\Pr me (Mil
14
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE. COLORADO
7k
397 SOUTH FIRST
EAST STREET
MONTICELLO. UTAH
12
GeoUch. Inc.
jlfMOktLOOl jD*TI
MS-00203-VL
°3-C00203-Ga-i
10 12 14 .16 18 20 22 24 26 28 30 32 34 36 38 40 42 44 AP. AQ
DOE ID No.: MS-O0203-VL
Property Address: 397 South First East Street
Vicinity Property Certification Summary and"Recommendation
Summary Evaluation
Certification Criteria MACTEC-ERS
U.S. Department
of Energy (DOE)
Ra-226 is <, 5 pCi/g above
background in top 15-cm-thick layer of
soil averaged over 100 m2
In situ [X] Lab [ ]
Ra-226 is ^ 15 pCi/g above
background in any 15-cm-thick layer
of soil more than 15 cm below the
surface averaged over 100 m2.
In situ [ ]Lab[X]
Interior gamma is ^ 20 uR/h above
background in any occupied or
habitable structure.
The radon decay-product
concentration in any occupied or
habitable structure is <. 0.02 WL or, at
most, 0.03 WL.
Supplemental standards were applied
in accordance with EPA standard
40 CFR 192.21.
Hot spot criteria met as outlined by
DOE guidelines for FUSRAP
(Rev.2, March 1987)
Yes No Not Taken Yes No Not Taken
[X]a [ ]
[X] [ ]
[ ] [ ]
[ ] [ ]
[ ] [X]
[X] t ]
[ ]
[ ]
[X]b
[X]b
[ ]
[ ]
[% [ ]
[ ] [ ]
[ ] [ ]
[ ] [V]
[ ]
[ ]
[y]
[y]
[ )
[V] [ ] [ ]
aThe excavations were backfilled with materials that were measured at the source indicating that the Ra-226
concentrations are in the range of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
bVacant lot.
1 of 2
DOE ID No.: MS-00203-VL
MACTEC-ERS Recommendation
On the basis of the Property Completion Report evaluation, this property is recommended for
[X] Certification by DOE.
[ ] Certification by DOE with the concurrence of the U.S. Nuclear Regulatory Commission
because supplemental standards were applied according to 40 CFR 192.21.
C. Butherus Y I Date,
r. Monticello Programs I
wel C. Butheros
Manager, Monticello Programs I
MACTEC-ERS
DOE Evaluation
On the basis of the Property Completion Report evaluation, this property
[V] Should be certified by DOE.
[ ] Should be certified by DOE with the concurrence of the U.S. Nuclear Regulatory
Commission because supplemental standards were applied according to 40 CFR 192.21.
tt
Certification Official Date
U.S. Department of Energy
Work performed under DOE Contract No. DE-AC13-95GJ87335, Task Order No. 96-05.02.14
2 of 2
DEC 2 7 1996
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00204-RS
ADDRESS: 365 SOUTH FIRST EAST STREET
MONTICELLO, UTAH 84535
SEPTEMBER 1991
Prepared for
Decontamination and Decommissioning Program
Division of Facilities and Site Decommissioning
Department of Energy
RECORDS MANAQSBfiffiflT
by
Chem-Nuclear Geotech, Inc.
P.O. Box 14000
Grand Junction, Colorado 81502-5504
Harry A. Perry
Program Manager
Chem-Nuclear Geotech, Inc., has been granted authorization to conduct remedial
action under the Decontamination arid Decommissioning Program. Remedial action
was done in accordance with the Environmental Protection Agency Standards for
Cleanup of Lands and Buildings Contaminated with Residual Radioactive Material
from Inactive Uranium Processing Sites, 40 CFR 192.12, 192.20-23.
•IS-00204-RS : PCR-277
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-00204-RS
1.0 SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) project was accepted into
the Decontamination and Decommissioning Program with the primary
objective of reducing 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, 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 Decontamination and Decommissioning Program has adopted the
"Standards for Remedial Action at Inactive Uranium Processing Sites"
(40 CFR Part 192) as guidelines for all cleanup activities under the
MVP project. These standards were prepared by the Environmental
Protection Agency (EPA) to establish guidelines for the control of
tailings piles and the cleanup of buildings and open lands.
This property was evaluated on the basis of the EPA standards by the
Department of Energy (DOE) Inclusion Survey Contractor. The DOE
reviewed these evaluation results and determined that the property
contained residual radioactive material which exceeded the EPA
standards. The Remedial Action Contractor was notified of the
inclusion of this property into the Decontamination and
Decommissioning Program and was authorized by the DOS to conduct
remedial action as required to bring the property into conformance
with the EPA standards.
1
DOE ID NO.: MS-00204-RS
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
MS-00204-RS
Block 9 Mon^ I 165'5 feet "~th ot the SW corner of Lot 2,
Block 9, Monticello Townsite; east 162.5 feet, north 49 feet, west
162.5 feet, south 49 feet to beginning, County of San Juan, sJtfof 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:
365 South First East Street
.Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
September 19, 1989
Chem-Nuclear Geotech, Inc.
July 16, 1990
Sonderegger, Inc.
P.O. Box 6
Monticello, Utah
August 22, 1990
September 8, 1990
Interior: 0 cubic yards
Exterior: 72 cubic yards
359 square meters (m2)
September 1991
2
DOE ID NO.: MS-00204-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 condition comparable to that which existed prior
to remedial action activities.
2.2 Previously Unidentified Contamination
The extent of contamination identified during the original
radiological assessment for this property is shown on Appendix
Figure 2.1, and was 6 inches deep. The remedial action process
included the removal of approximately 72 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 performed on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the residual
radioactive material removal activities performed on the property.
3
DOE ID NO.: MS-002O4-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 Chem-Nuclear
Geotech, Inc., during April 1990, as described in the final
REA dated July 1990. Appendix Figure 2.1 shows the extent of
contamination determined during the pre-remedial assessment
and identifies the areas recommended to undergo remedial
action.
3.1.2 Post-Excavation Survey
A ground-level gamma scan with a scintillometer was performed
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 25 fjR/h (Appendix Figure 2.1). The results of
analyses for radium-226 in three composite soil samples
ranged from 4.4 picocuries per gram (pCi/g) to 5.3 pCi/g
(Appendix Table 3.1).
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
The trailer house that was on this property was removed after
remediation; therefore, RDC measurements were not taken.
'1
DOE ID NO.: MS-00204-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), as indicated in the Certification Data Summary below.
Therefore, the property located at 365 South First East Street, in
Monticello, Utah, is recommended for certification as required by
the Decontamination and Decommissioning Program guidelines, and the
appropriate record should be documented.
Certification Data Summary
Applicability Standards Survey Results
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Shall not exceed 20 pR/h
above background.
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Not applicable: vacant
lot.
Not applicable: vacant
lot.
Land
Radium-226 Concentration Shall not exceed 5 pCi/g < 5 pCi/g above
in Surface Soil: above background* in background.
the 15-cm surface layer,
averaged over 100 m2.
Radium-226 Concentration Shall not exceed 15 pCi/g The soil sample results
in Subsurface Soils: above background* in any ranged from 4.4 pCi/g
15-cm-thick soil layer to 5.3 pCi/g.
more than 15 cm below the
surface, averaged over
100 m2.
*The background radium-226 concentration is approximately 2.0 pCi/g.
5
DOE ID NO.: MS-00204-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
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00204-RS
Address: 365 South First East Street, Monticello, Utah
The analytical uncertainties in the table are reported at the 95-percent
confidence interval.
Exposure-Rate Soil Sample Radium-226 Potassium Thorium
Area Range (/jR/h) Ticket No. (pCi/g) (pCi/g) (pCi/g)
V-l 15 - 20 NAH 743 4.4 ± 0.6 19.1 ± 3.4 0.9 ± 0.3
V-2 16 - 25 NAE 004 5.3 ± 0.7 25.8 ± 3.5 1.0 ± 0.3
V-3 15 - 21 NAE 005 5.0 + 0.7 23.5 ± 3.2 0.6 ± 0.3
See Appendix Figure 2.1 for the verification areas.
MM-JEK:09-13-91
MS-00204-RS:PCR-277 WS 5.5
REV051791
14 16 12 20 24 10 22 28 32 34 38 40
+ 30
: : LEGEND j j
ALL DEPTriSIN INCHES...; i
ALL EXPOSURE RATES INiuR/hi
28 28
ASSESSED: AR EA JDjENTIFJIER j • _
AVERAGE DEPTH OF ASSESSED jcONTAMINATION
AREA OF ASSESSED CONTAMINANTS---! -
POST REMEDIAL ACTION EXPOSURE-RATE R^NGE
BOUNDARY OF EXCAVATION-
V-3
15-21 SHED
13-16 26 26
12-15
Ui AVERAGE EXCAVATED DEPTH FOR THE
OF CONTAMINATION
DEPOSIT Ld 14-17: 12 : O 24 24 6 >...:. V-1 VERIFICATION SOILiSAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE-RATE RANGE ': O 16-17
<•
t".
ASSESSED CONTAMINANTS NOT
TIME OF REMEDIALiACTION
FOUND AT A r. r—. TIME OF REMEDIAL
ORNL DATA !
cr 22 22
m Z2
mm o 07 \>.~/c\V.j fi 6 ).-/.V.-.V'-.V.^ 6
20 20
V-2 V-1
16-25 15-20
18 18
16 16 RADIOLOGICAL AS B UIUT
FIGURE .2.r -
EXTENT OF GONTAMINATI EXTERIOR ON
14 14
NO. DATE REVISIONS REVISIONS CK : At. * PP NO. DATE BY CK A E. APP
HE5IOENCI-NO. OF OCCUPANTS
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE, COLORADO NON-RESIDENCE —MANHRS. WK
DESIGNED
12 365 SOUTH FIRST
EAST STREET
MONTICELLO, UTAH
THIS. DRAWING,.PREPARED. .FOB.THE. DECONTAMINATION ANO..:...
DECOMMISSIONING PROGRAM, 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 *,ND IS NOT TO BE RELIED UPON:
12 INSTRUMENT NO. SURVEYOR SCALE "fN- FEET DRAWN
Y 5>i
PflOJ ENG
APPROVAL Uo MITT E D DATE APPROVAL DOE 20 10 20 40 FOR THE ESTABLISHMENT :OF FENCE
FUTUREMMPROVEMENT LINES.
BUILDING, OR OTHER DATE
SURVEY DATE I tM E
NORTH!
J I
DOE iC SO MS-00204-RS
G«otecrt, Inc VERIFICATION DATE
DWG NC
10 3-B00203-Gl<HT 1 OF 1
22 24 26 20 28 14 16 30 12 18 32 36 34 38 40
DOE ID NO. : MS- Q02.0 4- ~ (^5
Property Address: 3£S S&^TK first Eaof 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 m*.
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 hx]
Interior gamma is < 20 pR/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is < 0.02
working levels or, at
most, 0.03 working levels.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21.
Hot spot criteria met as
outlined by U.S. DOE
guidelines for FUSRAP and
Decontamination and
Decommissioning Program
(Rev. 03/02/87).
Chem-Nuclear Geotech, Inc.
YES NO NOT TAKEN
[X]* ( 1 [ 1
U.S. Department
of Energy (DOE)
[ 1
( ]
YES NO NOT TAKEN
ifi] [ ] [ ]
[ ) [ ]
[ ] [ ) (X]
(Vacant Lot)
[ ] [X]
(Vacant Lot)
[ ]
( 1 [
REpQPDS MANAGEMENT]
[ ]
[ ]
ty i ]
] ( ] (/]
COMMENTS: *The excavations were backfilled with materials which 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 which do not exceed 30-percent above normal background.
SFCERTI FED SFMS-00204 cvoO°\
DOE ID NO. : MS- O 020i - ^-->
CHEM-NUCLEAR GEOTECH, INC., RECOMMENDATION
Based on the Chem-Nuclear Geotech, Inc., evaluation, I recommend this property
for:
[X] Certification by the Department of Energy.
[ ] Certification by the Department of Energy with the concurrence of the
Nuclear Regulatory Commission because supplemental standards were
applied per 40 CFR 192.21.
3
Harry A. Perry
Decontamination and Decommissioning Program Manager
Chem-Nuclear Geotech, Inc.
Date "
DOE EVALUATION
[)0 Should be certified by the Department of Energy.
[ ] Should be certified by the Department of Energy with the concurrence
of the Nuclear Regulatory Commission because supplemental standards
were applied per 40 CFR 192.21.
nat on Decbnta
Certification Official
Department of Energy
Decommissioning Program Date
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00170-RS
ADDRESS: SOUTH HIGHWAY 191
MONTICELLO, UTAH 84535
OCTOBER 1991
Prepared for
Decontamination and Decommissioning Program
Division of Facilities and Site Decommissioning
Department of Energy
by
Chem-Nuclear Geotech, Inc.
P.O. Box 14000
Grand Junction, Colorado 81502-5504 iv 1 1991
RECORDS MANAGEMENT
Harr^ A.Perry
Program Manager
Chem-Nuclear Geotech, Inc., has been granted authorization to conduct remedial
action under the Decontamination and Decommissioning Program. Remedial action
was done in accordance with the Environmental Protection Agency Standards for
Cleanup of Lands and Buildings Contaminated with Residual Radioactive Material
from Inactive Uranium Processing Sites, 40 CFR 192.12, 192.20-23.
MS-00171-RS:PCR-276
SFCMPLRPTS SFMS-00170
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-00170-RS
1.0 SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) project was accepted into
the Decontamination and Decommissioning Program with the primary
objective of reducing 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, 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 Decontamination and Decommissioning Program has adopted the
"Standards for Remedial Action at Inactive Uranium Processing Sites"
(40 CFR Part 192) as guidelines for all cleanup activities under the
MVP project. These standards were prepared by the Environmental
Protection Agency (EPA) to establish guidelines for the control of
tailings piles and the cleanup of buildings and open lands.
This property was evaluated on the basis of the EPA standards by the
Department of Energy (DOE) Remedial Action Contractor. The DOE
reviewed these evaluation results and determined that the property
contained residual radioactive material which exceeded the EPA
standards. The Remedial Action Contractor was notified of the
inclusion of this property into the Decontamination and
•Decommissioning Program and was authorized by the DOE to conduct
remedial action as required to bring the property into conformance
with the EPA standards.
1
DOE ID NO.: MS-00170-RS
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-00170-RS
Parcel Number M-645, Lot 11, Block 4,
City of Monticello, County of San Juan,
State of Utah
South Highway 191
Monticello, Utah 84535

Residential Simple (RS)
Not applicable; spillover inclusion
requested by the Remedial Action
Contractor
May 22, 1987
Chem-Nuclear Geotech, Inc.
March 17, 1989
Bayless and Bayless, Inc.
1900 St. Charles Road
Pueblo, Colorado
May 11, 1989
June 3, 1989
Interior: 0 cubic yards
Exterior: 102 cubic yards
279 square meters (m2)
October 1991
DOE ID NO.: MS-00170-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 condition comparable to that which existed prior
to remedial action activities.
2.2 Previously Unidentified Contamination
The original radiological assessment identified 76 cubic yards of
contamination, ranging from 6 inches to 12 inches deep, within the
property. The remedial action process included the removal of
approximately 102 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 performed on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the residual
radioactive material removal activities performed on the property.
3
DOE ID NO.: MS-00170-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 Chem-Nuclear
Geotech, Inc., during July 1987, as described in the final
REA dated March 1989. Appendix Figure 2.1 shows the extent
of contamination determined during the pre-remedial
assessment and identifies the areas recommended to undergo
remedial action.
3.1.2 Post-Excavation Survey
A ground-level gamma scan with a scintillometer was performed
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 (pR/h) to 21 juR/h (Appendix Figure 2.1). The results of
analyses for radium-226 in five composite soil samples ranged
from 2.0 picocuries per gram (pCi/g) to 3.7 pCi/g (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-00170-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) as indicated in the Certification Data Summary below.
Therefore, the property located at South Highway 191, in Monticello,
Utah, is recommended for certification as required by the
Decontamination and Decommissioning Program guidelines, and the
appropriate record should be documented.
Certification Data Summary
Standards Applicability Survey Results
Habitable Structures
Exposure Rate: Shall not exceed 20 ^R/h
above background.*
Range for the ground
floor of the trailer
house was 14 AfR/h to
15 pR/h.
Radon Decay-Product
Concentration:
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Not applicable for the
trailer house due to no
permanent foundation.
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.
< 5 pCi/g above
background.
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 15 pCi/g
above background** in any
15-cm-thick soil layer
more than 15 cm below the
surface, averaged over
100 m2.
The soil sample results
ranged from 2.0 pCi/g
to 3.7 pCi/g.
*The background exposure rate is approximately 16 pR/h.
**The background radium-226 concentration is approximately 2.0 pCi/g.
5
DOE ID NO.: MS-00170-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
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00170-RS
Address: South Highway 191, Monticello, Utah
The analytical uncertainties in the table are reported at the 95-percent
confidence interval.
Area
Exposure-Rate
Range (/iR/h)
Soil Sample
Ticket No.
Radium-226
(pCi/g)
Potassium
(pCi/g)
Thorium
(pCi/g)
V-l
V-2
V-3
V-4
V-5
13
13
13
13
13
19
18
21
19
18
MNK 442
MNK 443
MNK 444
MNK 445
MNK 446
3.2 ± 0.5
2.0 ± 0.3
3.7 ± 0.5
2.3 ± 0.4
2.0 ± 0.3
18.8 ± 3.4
18.3 ± 3.3
20.3 ± 3.5
20.9 ± 3.5
19.7 ± 3.4
1.0 ± 0.3
0.9 ± 0.3
1.2 ± 0.3
1.2 ± 0.3
1.0 ± 0.3
See Appendix Figure 2.1 for the verification areas.
MM-JEK:08-26-91
MS-00170-RS:PCR-276
REV051791
WS 5.5
7
30 28 32
15-17
15-17
V-5
13-18
34
i—r
36 38
THIS DRAWING, PREPARE!) FOR THE DECONTAMINATION AND I
DECOMMISSIONING PROGRAM. 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 UPOt*
FOR THE ESTABLISHMENT OF rENCE, BUILDING. OR OTHER :
FUTURE! IMPROVEMENT LINES.
28 30 32
J i L
34
-0 42 44
;—i—i—i—r
46 4.0 50 +
112-15
12
V-1
16-17
. ALL DEPTHS IN INCHES ..
ALL EXPOSURE! RATES IN uR/h \
.. ASSESSED. .AREA. IDENTIFIER: |
AVERAGE DEPTH OF ASSESSED CONTAMINATION
• AREA OF:ASSESSED CONTAMINANTS j- 1
POST REMEDIAL ACTION EXPOSURE—RATE RANGE
BOUNDARY OF EXCAVATION'!Ij!
AVERAGE! EXCAVATED ;DEPTH FOR THE DEPOSlf
. OF CONTAMINATION....; | j ; j
VERIFICATION SOIL SAMPLE AREA IDENTIFIER I
AND EXCAVATION.EXPOSURE-RATE.. RANGE •
ASSESSED CONTAMINANTS NOT FOUND AT
TIME OF REMEDIAL ACTION
40
38
36
34
32
30
28
26
24
22
20
18
16
FIGURE !2.T
EXTERIOR;EXTENT OF CONTAMINATION
M(tlDtNCI~MO (HOCCUMNTI
N&N.ft£tlDINCI-HAft^MM •<
J L
36
• T CK Af APP HO. MTI
U.S. DEPARTMENT OF ENERGY
GWAND JUNCTION PROJECT* OFFICt. COLORADO
• V C*. At APP
14
SOUTH HIGHWAY 191
MONTICELLO. UTAH 12
38 40 42
Geotech, Inc.
~44
[OATI Ci
ilTBB ui
I^PAOWL ooi JDSTI
MS-6U176-RS
46
cooi7o-cy.,i o. 1 I i
48 Cft ' 50
DOE ID No.: MS-00170-RS
Property Address: South Highway 191
Vicinity Property Certification Summary and Recommendation
Summary Evaluation
U.S. Department
Certification Criteria MACTEC-ERS of Energy (DOE)
Yes No Not Taken Yes No Not Taken
Ra-226 is <, 5 pCi/g above
background in top 15-cm-thick layer of
soil averaged over 100 m2
lnsitu[X]Lab[ ] [X]a [ ] [ ] [% [ ] [ ]
Ra-226 is < 15 pCi/g above
background in any 15-cm-thick layer
of soil more than 15 cm below the
surface averaged over 100 m2.
Insitu[ ]Lab[X] [X] [ ] [ ] L*] [ ] [ ]
Interior gamma is <; 20 uR/h above
background in any occupied or
habitable structure. [X] [ ] [ ] DG [ ] [ ]
The radon decay-product
concentration in any occupied or
habitable structure is < 0.02 WL or, at
most, 0.03 WL. [ ] [ ] [X]b [ ] [ ]
Supplemental standards were applied
in accordance with EPA standard
40 CFR 192.21. [ ] [X] [ ] [ ] [ $ [ ]
Hot spot criteria met as outlined by
DOE guidelines for FUSRAP
(Rev.2, March 1987) [X] [ ] [ ] [/] [ ] [ j
aThe excavations were backfilled with materials that were measured at the source indicating that the Ra-226
concentrations are in the range of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
bTrailer house with no permanent foundation.
1 of 2
DOE TD No.: MS-00170-RS
MACTEC-ERS Recommendation
On the basis of the Property Completion Report evaluation, this property is recommended for
[X] Certification by DOE.
[ ] Certification by DOE with the concurrence of the U.S. Nuclear Regulatory Commission
because supplemental standards were applied according to 40 CFR 192.21.
Manager, Monticello Programs
MACTEC-ERS
DOE Evaluation
On the basis of the Property Completion Report evaluation, this property
[ Should be certified by DOE.
[ ] Should be certified by DOE with the concurrence of the U.S. Nuclear Regulatory
Commission because supplemental standards were applied according to 40 CFR 192.21.
Date
U.S. Department of Energy
Work performed under DOE Contract No. DE-AC13-95GJ87335, Task Order No. 96-05.02.14
2 of 2
JAN 1 7 1997
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00073-RS
ADDRESS: 65 EAST FIFTH SOUTH STREET
MONTICELLO, UTAH 84535
AUGUST 1991
Prepared for
Decontamination and Decommissioning Program
Division of Facilities and Site Decommissioning
Department of Energy
by
Chem-Nuclear Geotech, Inc.
P.O. Box 14000
Grand Junction, Colorado 81502-5504
Harr'y/A".Perrj
Program Manager
Chem-Nuclear Geotech, Inc., has been granted authorization to conduct remedial
action under the Decontamination and Decommissioning Program. Remedial action
was done in accordance with the Environmental Protection Agency Standards for
Cleanup of Lands and Buildings Contaminated with Residual Radioactive Material
from Inactive Uranium Processing Sites, 40 CFR 192.12, 192.20-23.
MS-00073-RS:PCR-269
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
i
DOE ID NO.: MS-00073-RS
1.0 SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) project was accepted into
the Decontamination and Decommissioning Program with the primary
objective of reducing 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, 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 Decontamination and Decommissioning Program has adopted the
"Standards for Remedial Action at Inactive Uranium Processing Sites"
(40 CFR Part 192) as guidelines for all cleanup activities under the
MVP project. These standards were prepared by the Environmental
Protection Agency (EPA) to establish guidelines for the control of
tailings piles and the cleanup of buildings and open lands.
This property was evaluated on the basis of the EPA standards by the
Department of Energy (DOE) which determined that the property
contained residual radioactive material which exceeded the EPA
standards. The Remedial Action Contractor was notified of the
inclusion of this property into the Decontamination and
Decommissioning Program and was authorized by the DOE to conduct
remedial action as required to bring the property into conformance
with the EPA standards.
1
DOE ID NO.: MS-00073-RS
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-00073-RS
Parcel Number M-644, in the NW4SE4,
Section 36, T33S., R23E., Salt Lake
Meridian; City of Monticello, County
of San Juan, State of Utah
65 East Fifth South Street
Monticello, Utah 84535

Residential Simple (RS)
Not applicable; historical inclusion
by the Department of Energy
January 27, 1984
Chem-Nuclear Geotech, Inc.
June 1984
Eldon Ray, Contractor
P.O. Box 10
Moab, Utah
September 10, 1984
October 23, 1984
Interior: 0 cubic yards
Exterior: 18 cubic yards
81 square meters (m2)
August 1991
DOE ID NO.: MS-00073-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 condition comparable to that which existed prior
to remedial action activities.
2.2 Previously Unidentified Contamination
The original radiological assessment identified 11 cubic yards of
contamination, 6 inches deep, within the property. The remedial
action process included the removal of approximately 18 cubic yards
of residual radioactive material, ranging from 3 inches to 14 inches
deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix
Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities performed on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the residual
radioactive material removal activities performed on the property.
3
DOE ID NO.: MS-00073-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 Chem-Nuclear
Geotech, Inc., during March 1984, as described in the final
REA dated June 1984. Appendix Figure 2.1 shows the extent of
contamination determined during the pre-remedial assessment
and identifies the areas recommended to undergo remedial
action.
3.1.2 Post-Excavation Survey
A ground-level gamma scan with a scintillometer was performed
after the removal of residual radioactive material and prior
to backfilling. Two individual soil samples collected at
grid coordinates 182267 and 171227 represented the
verification area.
Exterior Findings: Surface exposure-rate values, determined
during the gamma scan, ranged from 11 microroentgens per
hour (juR/h) to 15 /iR/h (Appendix Figure 2.1). Residual
radioactive material was left in place in assessed Area C to
avoid causing damage to a sewer line that crosses the
property. A soil sample was collected at the highest
exposure-rate location, and the result of analysis for
radium-226 of this material was 10.1 picocuries per
gram (pCi/g). The 100 m2 area average of this material was
4.8 pCi/g (Appendix Table 3.1). This material also meets the
hot spot criterion (Appendix Table 3.2). The result of
analysis for radium-226 in one remaining individual soil
sample was 2.0 pCi/g, as indicated in Appendix Table 3.3.
4
DOE ID NO.: MS-00073-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) as indicated in the Certification Data Summary below.
Therefore, the property located at 65 East Fifth South Street, in
Monticello, Utah, is recommended for certification as required by
the Decontamination and Decommissioning Program guidelines, and the
appropriate record should be documented.
Certification Data Summary
Standards Applicability Survey Results
Habitable Structures
Exposure Rate: Shall not exceed 20 /iR/h
above background.
Not applicable:
vacant lot.
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.
Not applicable:
vacant lot.
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.
The soil sample result,
averaged over a 100 m2
area, was 4.8 pCi/g.
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 15 pCi/g
above background* in any
15-cm-thick soil layer
more than 15 cm below the
surface, averaged over
100 m2.
The soil sample results
were 2.0 pCi/g and
10.1 pCi/g.
*The background radium-226 concentration is approximately 2.0 pCi/g.
5
I ' •
DOE ID NO.: MS-00073-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
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
6
Table 3.1
Calculation of Average Radium Concentration Over a 100 m2 Area
DOE ID No.: MS-00073-RS
Address: 65 East Fifth South Street, Monticello, Utah
Where:
avg
avg
(Cp x Ap) + [Cr x (1,076 - Ap)]
1,076
r
1,076 =
Radium-226 concentration in pCi/g averaged over a 100 m2
(1,076 ft2) area.
Radium-226 concentration in pCi/g of the residual radioactive
material left in place.
Area in ft2 of the residual radioactive material left in place.
Radium-226 concentration in pCi/g for the remainder of the
100 m2 (1,076 ft2) area.
Total area in ft2 over which the EPA guideline is applied.
Area
Sample
Loc.
Grid
Coord.
Meas./
Sample
Type*
Depth Cp Ap Cr Cavg EPA
Interval Standard
(Inches) (pCi/g) (ft2) (pCi/g) (pCi/g) (pCi/g)
V-l 171227 SS 03 - 09 10.1 375 2.0** 4.8 7.0***
Therefore, the averaged radium-226 concentration does not exceed the EPA
standard.
*SS = Soil Sample (Lab Analysis)
**Background radium-226 concentration.
***The soil sample, representing both the surface and subsurface soil layers,
was averaged for comparison to the EPA surface soil layer standard.
7
Table 3.2
Hot Spot Calculation Results
DOE ID No.: MS-00073-RS
Address: 65 East Fifth South Street, Monticello, Utah
Shg = Sg x (100 / A)*
Shg = Hot Spot Limit of radium-226 concentration in pCi/g.
Sg = Authorized Limit of radium-226 concentration in pCi/g based
a background concentration of 2.0 pCi/g (Sg = 7.0 pCi/g for
surface soils and 17.0 pCi/g for subsurface soils).
100 = Total area in m2 over which the Hot Spot Limit guideline is
applied.
A = Area in m2 of the hot spot.
Where:
Sample
Loc. Meas./ Depth A Sg Shg Radium-226 in
Grid Sample Interval Hot Spot Area
Area Coord. Type* (Inches) (m2) (pCi/g) (pCi/g) (pCi/g)
V-l 171227 SS 03 - 09 34.8 7.0** 11.9 10.1
Therefore, the radium-226 concentration in the hot spot area does not exceed
the Hot Spot Limit.
*SS = Soil Sample (Lab Analysis)
**Since the soil sample represented both the surface and subsurface soil
layers, the Hot Spot Limit was calculated using the Authorized Limit for
surface soils.
8
Table 3.3
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00073-RS
Address: 65 East Fifth South Street, Monticello, Utah
The analytical uncertainties in the table are reported at the 95-percent
confidence interval. A question mark (?) indicates that the analysis is
semiquantitative because of a low count.
Exposure-Rate Soil Sample Radium-226 Potassium Thorium
Area Range (pR/h) Ticket No. (pCi/g) (pCi/g) (pCi/g)
V-l 11 - 14 MMU 020 2.0 ± 1.0 24.3 ± 1.7 1.0 + 0.1
V-l 11 - 14 MMK 621* 10.1 ± 1.6 ?16.3 ± 1.7 ?0.8 ± 1.0
See Appendix Figure 2.1 for the verification area.
•Individual soil sample of residual radioactive material left in place at
grid coordinates 171227.
MM-JEK:06-14-91
MS-00073-RS:PCR-269 WS 5.5
REV051791
12 14 16 18 22 24 10 20
30
14
28
14
26
V-1 12-15
11-14
24
22
20
18
26
T
28
T
30
T
N
N
•4-V
\
A
11-14
32
i—r
34
®
<D
ALL DEPTHS. JN
ALL EXPOSURE
i—r
36 38
LEGEND
INCHES
RATES IN /iR/h
ASSESSED AREA IDENTIFIER:
AVERAGE; DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESS ED CONTAMINANTS
12-15 POST REMEDIAL ACTION EXPOSURE-RATE RANGE
SO U NOARY OF EXCAVATI ON i
12 AVERAGE ^EXCAVATED PEPTH FOR tHE DEPOSIT
. OF. iCONTAMIN ATI.QN....;
V-1
16-17
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE-RATE RANGE
AREA WITH CONTAMINATION LEFT IN PLACE
40
28
26
24
22
20
18
\
16 16
14
12
Y
•
SCALE TN FEET
RADIOLOGICAL AS BUILT
FIGURE
EXTERIOR EXTENT OF CONTAMINATION
10
20 ; 10 T
• x;
I L
20 40
J ! I L
NORTH
J
. THIS DRAWING,. PREPARED FOR: THE DECONTAMINATION AND
DECOMMISSIONING PROGRAM. SS 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.SURYE*.PLAT AND.JS NQT.TP. BE. JtELIEO.UfQN..
FOR THE ESTABLISHMENT OF FENCE, BUILDING. OR OTHER
FUTURE IMPROVEMENT LINES. :
J I I I I I I I
HESIOENCE-NO OF OCCUPANTS
NON-RESIDENCE — MAN-HRS.'WK.
INSTRUMENT NO SURVEYOR
SURVEY OATE
VERIFICATION
BY CK A E APP. NO DATE
14
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE, COLORADO
SUBMITTED
65 EAST FIFTH SOUTH STREET
MONTICELLO, UTAH
12
Geotech,Inc.
APPROVAL DOE
MS-00073-RS
3-B318-G2 1
10 12 14 16 18 20 22 24 26 28 3D ^9 9/I
I
Results of the
Independent Verification of
Radiological Remedial Action
at 65 East 5th South Street
Monticello, Utah (MS00073)
M. J. Wilson
J. K. Williams
I
HEALTH AND SAFETY RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
65 EAST 5TH SOUTH STREET
MONTICELLO, UTAH (MS00073)
M. J. Wilson and J. K. Williams
December 1991
Work performed by the
POLLUTANT ASSESSMENTS 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
VERIHCATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
CONCLUSION 3
REFERENCES 4
iii
LIST OF TABLES
1 Applicable guidelines for protection against radiation
2 Results of ORNL analysis of UNC Geotech soil samples from 65 East 5th South Street
Monticello, Utah (MS00073) 6
v
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site
Decommissioning Projects, U.S. Department of Energy. The authors wish to acknowledge
G. A Pierce for analysis of soil samples and G. K Stowe. A R. Jones, and S. K. Mather
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 1984, UNC Geotech, the remedial action
contractor designated by DOE, performed remedial action on the vicinity property at 65
East 5th South Street, Monticello, Utah. The Pollutant Assessments Group (PAG) 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 PAG found that the site successfully meets the DOE remedial action objectives.
Procedures used by PAG are described.
ix
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 65 EAST 5TH SOUTH STREET
MONTICELLO, UTAH (MS00073)*
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 IL 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 decorjimissioning 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.1
*The verification of remedial action was performed by members of the Pollutant Assessments
Group of the Health and Safety Research Division at Oak Ridge National Laboratory under DOE
contract DE-AC05-84OR21400 with Martin Marietta Energy Systems, Inc.
During 1984, 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, vacant land located at 65 East 5th 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.2
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 Pollutant Assessments Group (PAG) of Oak Ridge National Laboratory
(ORNL) has been assigned the responsibility of this task at the 65 East 5th South Street
site. This report describes the methods and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available documenta-
tion adequately and accurately describes the post-remedial-action radiological conditions of
the entire property that is to be certified and (2) that the remedial action reduced
contamination to below applicable DOE guidelines.
Document Reviews
Review of the property completion report prepared by Geotech2 indicates the property
was evaluated by DOE on the basis of Environmental Protection Agency standards3 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 11 yd3 of mill tailings
6 in. deep. However, during the actual removal process, a total of 18 yd3 of contaminated
earth and uranium mill tailings, 3 to 14 in. deep, were removed from a 81-m2 area. Residual
radioactive material was left in place to prevent damage to the sewer line that crosses the
property.
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 surface scan of the
exterior and soil sampling. Samples representative of the bottom 15-cm (6-in.) soil layers
of the excavated area were collected and blended to form a representative composite soil
sample. Additionally one sample representative of the residual radioactive material, left in
place, was taken.
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 from the excavated areas prior
to backfilling ranged from 11 to 15 /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 exterior verification area. Geotech's
analysis of this sample showed 2*Ra concentrations of 2.0 pCi/g in the composite sample.
ORNL PAG obtained these soil samples and performed a confirmatory analysis, which
showed a ^a concentration of 1.5 pCi/g. These values are below the DOE guideline value
of 15 pCi/g for soil layers >15 cm below the surface (Table 1). Geotech's analysis of the
residual radioactive material left in place showed a ^Ra concentration of 10 pCi/g. ORNL
agrees with the RAC's determination that these values are below the DOE guidelines of 5
pCi/g for soil layers 15 cm below the surface (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.
REFERENCES
1. L N. Abramiuk et al., Monticello Remedial Action Project She 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, 1989.
2. Geotech, Property Completion Report for Monticello Vicinity Property Remedial Action for
DOE ID NO: MS00073, Address: 65 East 5th South Street, Monticello, Utah 84535,
Geotech, Grand Junction, Colorado, September 1991.
3. Guidelines for Residual Radioactivity at Formerly Utilized Sites, Remedial Action Program
and Remote Surplus Facilities Management Program Sites, Rev. 2, U.S. Department of
Energy, March 1987.
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
Source: Adapted from Guidelines for Residual Radioactive Material at Formerly Utilized
Sites Remedial Action Program and Remote Surplus Facilities Management Program Sites,
Rev. 2, U.S. Department of Energy, March 1987.
6
Table 2. Results of ORNL analysis of UNC Geotech soil samples
from 65 East 5th South Street, Utah (MS00073)
ORNL
sample
No.i
UNC
Geotech
sample
No.fe
^a concentration (pCi/g)
Depth
(cm) ORNL
UNC
Geotech
XI
X2*
MMU-020
MMK-621
15-30
15-30
1.5
8.8
ZO
10
sAn 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 UNC Geotech, and these samples were blended to form a composite soil
sample, which represents an average over one of the verification areas.
*Soil sample taken of residual radioactive material left in place.
- V -
DOE ID NO. : MS- Q Q O ~7 3 ~ »S S
Property Address: (o^> BdSt FlffU South S~free"t
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
Chem-Nuclear Geotech, Inc.
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 ExJ^
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 OxJ
Interior gamma is < 20 juR/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is < 0.02
working levels or, at
most, 0.03 working levels.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21.
Hot spot criteria met as
outlined by U.S. DOE
guidelines for FUSRAP and
Decontamination and
Decommissioning Program
(Rev. 03/02/87).
[X]'
[ ]
[ ]
[ ]
[ 1
[ ]
[ 1
[ ]
[ ] [X]
(Vacant Lot)
[ ] [X]
(Vacant Lot]
( 1
[ 1
U.S. Department
of Energy (DOE)
YES NO NOT TAKEN
[ ] [ ] [
[ ]
[ ]
I ]
[ ]
( ]
I ]
[ ]
[ ]
[ 1
[ ]
C ]
[ ]
[ ]
[ ]
[ 1
COMMENTS: *The excavations were backfilled with materials which 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 which do not exceed 30-percent above normal background.
Part cf one, .•sa^pie \Ajtto -fy-ci^ "hie. IS-cm SufW lfiyer;
OSY\ cl w tip 1 CK h - CK v\ A I ^ z e c/»
SFCERTIFED SFMS-00373
DOE ID NO. : MS- OQOl'3 ~~ ^-S
CHEM-NUCLEAR GEOTECH, INC., RECOMMENDATION
Based on the Chem-Nuclear Geotech, Inc., evaluation, I recommend this property
for:
[X] Certification by the Department of Energy.
f ] Certification by the Department of Energy with the concurrence of the
Nuclear Regulatory Commission because supplemental standards were
applied per 40 CFR 192.21.
iarry A. J?e'rry /
Decontamination and Decommissioning Program Manager
Chem-Nuclear Geotech, Inc.
Date '
DOE EVALUATION
[)^] Should be certified by the Department of Energy.
[ ] Should be certified by the Department of Energy with the concurrence
of the Nuclear Regulatory Commission because supplemental standards
were applied per 40 CFR 192.21.
I/2T7/?
Decontamination and Decommissioning Program
Certification Official
Department of Energy
Date
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00151-RS
ADDRESS: 149 WEST THIRD SOUTH STREET
MONTICELLO, UTAH 84535
AUGUST 1991
Prepared for
Decontamination and Decommissioning Program
Division of Facilities and Site Decommissioning
Department of Energy
by
Chem-Nuclear Geotech, Inc.
P.O. Box 14000
Grand Junction, Colorado 81502-5504
Harjfy A. Perry
Program Manager
Chem-Nuclear Geotech, Inc., has been granted authorization to conduct remedial
action under the Decontamination and Decommissioning Program. Remedial action
was done in accordance with the Environmental Protection Agency Standards for
Cleanup of Lands and Buildings Contaminated with Residual Radioactive Material
from Inactive Uranium Processing Sites, 40 CFR 192.12, 192.20-23.
MS-00151-RS:PCR-270
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-00151-RS
1.0 SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) project was accepted into
the Decontamination and Decommissioning Program with the primary
objective of reducing 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, 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 Decontamination and Decommissioning Program has adopted the
"Standards for Remedial Action at Inactive Uranium Processing Sites"
(40 CFR Part 192) as guidelines for all cleanup activities under the
MVP project. These standards were prepared by the Environmental
Protection Agency (EPA) to establish guidelines for the control of
tailings piles and the cleanup of buildings and open lands.
This property was evaluated on the basis of the EPA standards by the
Department of Energy (DOE) Inclusion Survey Contractor. The DOE
reviewed these evaluation results and determined that the property
contained residual radioactive material which exceeded the EPA
standards. The Remedial Action Contractor was notified of the
inclusion of this property into the Decontamination and
Decommissioning Program and was authorized by the DOE to conduct
remedial action as required to bring the property into conformance
with the EPA standards.
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-00151-RS
MS-00151-RS
Parcel No. M-31; beginning at the
northwest corner of Lot 3, Block 6,
east 127.5 feet, south 214.5 feet,
west 50.25 feet, north 95.0 feet,
west 77.0 feet, north 119.5 feet to
the beginning; City of Monticello,
County of San Juan, State of Utah
149 West Third South Street
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
March 1, 1989
Chem-Nuclear Geotech, Inc.
August 9, 1989
Crowley Construction
East Route
Monticello, Utah
September 12, 1989
September 27, 1989
Interior: 0 cubic yards
Exterior: 17 cubic yards
60 square meters (m2)
August 1991
2
DOE ID NO.: MS-00151-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 condition comparable to that which existed prior
to remedial action activities.
2.2 Previously Unidentified Contamination
The original radiological assessment identified 7 cubic yards of
contamination, ranging from 9 inches to 15 inches deep, within the
property. The remedial action process included the removal of
approximately 17 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 performed on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the residual
radioactive material removal activities performed on the property.
3
DOE ID NO.: MS-00151-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 Chem-Nuclear
Geotech, Inc., during April 1989, as described in the final
REA dated August 1989. Appendix Figure 2.1 shows the extent
of contamination determined during the pre-remedial
assessment and identifies the areas recommended to undergo
remedial action.
3.1.2 Post-Excavation Survey
A ground-level gamma scan with a scintillometer was performed
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 (pR/h) to 18 pR/h (Appendix Figure 2.1). The result of
analysis for radium-226 in one composite soil sample was
1.8 picocuries per gram (pCi/g), as indicated in Appendix
Table 3.1.
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on measurements representing an annual average, the
RDC was 0.0107 Working Level (WL), as indicated in Appendix
Table 3.2. Appendix Figure 2.1 shows the measurement
location in the basement of the north house (the lowest
habitable level of the structure). RDC measurements were not
taken in the house to the southwest since it was not
associated with the contamination.
4
DOE ID NO.: MS-00151-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) as indicated in the Certification Data Summary below.
Therefore, the property located at 149 West Third South Street, in
Monticello, Utah, is recommended for certification as required by
the Decontamination and Decommissioning Program guidelines, and the
appropriate record should be documented.
Applicability
Certification Data Summary
Standards Survey Results
Habitable Structures
Exposure Rate: Shall not exceed 20 juR/h
above background.*
Range for the partial
basement and the ground
floor of the north
house was 13 A/R/h to
14 fjR/h, and the range
for the ground floor
of the southwest house
was 13 /jR/h to 14 pR/h.
Radon Decay-Product
Concentration:
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Annual average
0.0107 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.
The soil sample result
was 1.8 pCi/g.
*The background exposure rate is approximately 15 pR/h.
**The background radium-226 concentration is approximately 2.0 pCi/g.
5
DOE ID NO.: MS-00151-RS
4.0 APPENDIX
Appendix Tables:
Table 3.1 Post-Excavation Sample/Measurement Results
Table 3.2 Radon Decay-Product Concentration (RDC)
Measurement Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00151-RS
Address: 149 West Third South Street, Monticello, Utah
The analytical uncertainties in the table are reported at the 95-percent
confidence interval.
Exposure-Rate Soil Sample Radium-226 Potassium Thorium
Area Range (/uR/h) Ticket No. (pCi/g) (pCi/g) (pCi/g)
V-l 13 - 18 MNQ 720 1.8 ± 0.4 20.9 ± 4.3 1.4 ± 0.3
See Appendix Figure 2.1 for the verification area.
7
Table 3.2
Radon Decay-Product Concentration (RDC) Measurement Results
DOE ID NO.: MS-00151-RS
Address: 149 West Third South Street, Monticello, Utah
Instrument Type: Terradex Radtrak® Detector
Radon Average
Detector , Tracks Per Concentration Working
Number Start Date End Date mm2 (pCi/1) Level (WL)
1650004 11-13-89
1652382 11-13-89
1652227 11-13-89
12-12-90 20.3
12-12-90 19.3
12-12-90 17.8
2.27 0.0114
2.16 0.0108
1.98 0.0099
Annual Average: 0.0107
See Appendix Figure 2.1 for the measurement location.
MM-JEK:07-05-91
MS-00151-RS:PCR-270 WS 5.5
REV051791
8
16 18 20 22 10 12 24 26 28 30 32 34 36 38 40 42 44 14 46 48 50
FT 9d
SHED
4-16
0 Si
"l3-6
V-1 13-16
13-18
ALL DEPTHS. IN;IN.CHE;S ;
ALL EXPOSURE: RATES IN uf?/h RDC 13-16
(A).| ASSESSEp AREA ipENTIFIER ONE STORY
BRICK & FRAME i
HOUSE W/;PART.;
(D ; AVERAGE; DEPTH OF ASSESSED CONTAMINATION
AREA-OF.ASSESSED-CONTAMINANTS j !••
12-15 POST REMEDIAL ACTION EXPOSURE-RATE RANpE
•——! BOUNDARY OF EXCAVATION iii!"
Ml
AVERAGE-EXCAVATED DEPTH FOR THE DEPOSIT
O.F. iCQNTAMlNATilON....; ; 12
v-i VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE-RATE RANGE 16-17
POST REMEDIAL ACTION RADON DECAY—PRODUCT
CONCENTRATION MEASUREMENT LOCATION RDC
G 13-16• 13 14
BRICK & FRAME
HOUSE..-
777 777
SOUTH SECOND WEST STREET
RADIOLOGICAL AS^BUILT
FIGURE -2.1 II '
EXTENT OF CONTAMINATION EXTER OR
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE. COLORADO NON-RIklDEWCC-HAM.IMt WK
149 WEST. THIRD SOUTH STREET
MONTICELLO. UTAH SCALE IN FEET THIS ORAWINS;: PREPARED FOR- TMC DECOHTAW NATION AND: •
DECOMMISSIONING PROCRAU, IS FOR THE SOLE USE OF THE
U.S. DEPARTMENT OF ENERCY AND ITS CONTRACTORS. IT IS
NOT K LAND SURVEY PLAT. UTILITY LOCATION PLAT, OR OTHER
IMPROVEMENT- SURVEY-PLAT-ANO IS NOT TO -BE RFjL-IEB- UPON
FOR THE ESTABLISHMENT OF FENCE. BUILDINC. OR OTHER :
FUTURE IMPROVEMENT LINES.
;• 20 ; 10 T O : : 20 : 40 :
I I I I I I I I
DOI Kt NO
m. MS-00151-RS
G*ot*ch.Inc
3-00151-C4,„,1 „\
94 14 1fi 1R 34 3R 44 19 PR 39 40 49 4R
12 -
Results of the
Independent Verification of
Radiological Remedial Action
at 149 West 3rd South Street
Monticello, Utah (MS00151)
M. J. Wilson
J. K. Williams
HEALTH AND SAFETY RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
149 WEST 3RD SOUTH STREET
MONTICELLO, UTAH (MS00151)
M. J. Wilson and J. K. Williams
December 1991
Work performed by the
POLLUTANT ASSESSMENTS 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 4
iii
LIST OF TABLES
1 Applicable guidelines for protection against radiation 5
2 Results of ORNL analysis of UNC Geotech soil samples from 149 West 3rd South
Street Monticello, Utah (MS00151) 6
v
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site
Decommissioning Projects, U.S. Department of Energy. The authors wish to acknowledge
Gretchen A. Pierce for analysis of soil samples and Greg K. Stowe. Amy R. Jones, and
Shawn K. Mather 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 1989 and 1990, UNC Geotech, the remedial
action contractor designated by DOE, performed remedial action on the vicinity property
at 149 WEST 3RD SOUTH STREET, Monticello, Utah. The Pollutant Assessments Group
(PAG) 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 PAG found that the site successfully meets the DOE remedial action
objectives. Procedures used by PAG are described.
ix
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 149 WEST 3RD SOUTH STREET
MONTICELLO, UTAH (MS00151)*
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 IL 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.1
*The verification of remedial action was performed by members of the Pollutant Assessments
Group of the Health and Safety Research Division at Oak Ridge National Laboratory under DOE
contract DE-AC05-84OR21400 with Martin Marietta Energy Systems, Inc.
2
During 1989, and 1990, 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 149 WEST 3RD SOUTH STREET,
Monticello, Utah. The remedial action plan required excavation of all exterior contamina-
tion. When the excavation was completed, the property was resurveyed, including soil
sampling, to ensure the removal of all contamination, backfilled with uncontaminated
material, and restored to a condition comparable to that which existed prior to remedial
action.2
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 Pollutant Assessments Group (PAG) of Oak Ridge National Laboratory
(ORNL) has been assigned the responsibility of this task at the 149 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 documenta-
tion adequately and accurately describes the post-remedial-action radiological conditions of
the entire property that is to be certified and (2) that the remedial action reduced
contamination to below applicable DOE guidelines.
Document Reviews
Review of the property completion report prepared by Geotech2 indicates the property
was evaluated by DOE on the basis of Environmental Protection Agency standards3 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 7 yd3 of mill tailings 9
to 15 in. deep. However, during the actual removal process, a total of 17 yd3 of contaminat-
ed earth and uranium mill tailings, 6 to 12 in. deep were removed from a 60-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, ground-level and
basement scans of the building and a surface scan of the exteriorand soil sampling. Samples
representative of the bottom 15-cm (6-in.) soil layers of two excavated areas were collected
and blended to form representative composite soil samples for each verification area.
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 13-14 /iR/h. Exterior surface gamma measurements taken from the
excavated areas prior to backfilling ranged from 13-18 /xR/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 2MRa concentration of 1.8 pCi/g in the composite sample.
ORNL PAG obtained this soil sample and performed a confirmatory analysis, which showed
a^a concentration of 1.9 pCi/g. These values are below the DOE guideline value of 15
pCi/g for soil layers >15 cm below the surface (Table 1). Results of 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 Terradex Track
Etch* detectors on the ground floor of the residence located on this property for a period
of approximately one year (from 11/13/89 to 12/12/90). The average annual working level
(WL) of radon progeny concentration, as determined by the Terradex Corporation, was
0.0107, 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.
* Track Etch is a registered trademark of Terradex Corporation.
4
REFERENCES
1. I. N. Abramiuk et al., 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, 1989.
2. Geotech, Property Completion Report for Monticello Vicinity Property Remedial Action for
DOE ID NO: MS00151, Address: 149 West 3rd South Street, Monticello, Utah 84535,
Geotech, Grand Junction, Colorado, September 1991
3. Guidelines for Residual Radioactivity at Formerly Utilized Sites, Remedial Action Program
and Remote Surplus Facilities Management Program Sites, Rev. 2, U.S. Department of
Energy, March 1987.
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Exposure to ^Rn
progeny
Maximum permissible con-
centration of ^Ra in soil
above background levels,
averaged over a 100-m2 area
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
0.03 WL
Source: Adapted from Guidelines for Residual Radioactive Material at Formerly Utilized
Sites Remedial Action Program and Remote Surplus Facilities Management Program Sites,
Rev. 2, U.S. Department of Energy, March 1987.
6
Table 2. Results of ORNL analysis of UNC Geotech soil samples
from 149 West 3rd South Street, Utah (MS00151)
ORNL
sample
No.a
UNC
Geotech
sample
No.fe
mRa concentration (pCi/g)
Depth
(cm) ORNL
UNC
Geotech
MS00151X1 MNQ-720 15-30 1.9 1.8
2An X-type sample is a split of the sample taken by the remedial action contractor.
^Soil samples representative ofthe bottom 15-cm (6-in.) soil layers ofthe excavated areas
were taken by UNC 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- 1^1; ' • ~- ~>
Property Address: |41 U-W Th.Vcl SCOTI, Street
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
Chem-Nuclear Geotech, Inc.
YES NO NOT TAKEN
U.S. Department
of Energy (DOE,*
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 [X] Lab [ ]
Ra-226 is < 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 ma. M t ] t J
In-situ [ ] Lab pxj
Interior gamma is < 20 pR/h
above background in any
occupied or habitable
structure. [>] [ ] [ ]
The radon decay-product
concentration in any
occupied or habitable
structure is < 0.02
working levels or, at
most, 0.03 working levels. [X [ ] [ ]
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21. [ ] [>] [ ]
Hot spot criteria met as
outlined by U.S. DOE
guidelines for FUSRAP and
Decontamination and
Decommissioning [ ] [ ] p<J
Program (Rev. 03/02/87).
t ] ( ] t ]
[ ]
[ ]
[ ]
[ ]
[ )
[ ]
[ )
[ ]
[ ]
[ ]
[ J
[ ]
[ ]
[ ]
t ]
COMMENTS: *The excavations were backfilled with materials which 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 which do not exceed 30-percent above normal background.
SFCERTIFED SFMS-00151
DOE ID NO.: MS- 00151 - £5
CHEM-NUCLEAR GEOTECH, INC., RECOMMENDATION
Based on the Chem-Nuclear Geotech, Inc., evaluation, I recommend this property
for:
[X] Certification by the Department of Energy.
[ ] Certification by the Department of Energy with the concurrence of the
Nuclear Regulatory Commission because supplemental standards were
applied per 40 CFR 192.21.
Harry A. Perry /
Decontamination and Decommissioning Program Manager
Chem-Nuclear Geotech, Inc.
Date'
DOE EVALUATION
^] Should be certified by the Department" of Energy.
[ ] Should be certified by the Department of Energy with the concurrence
of the Nuclear Regulatory Commission because supplemental standards
were applied per 40 CFR 192.21.
r
Decontamination and Decommissioning Program
Certification Official
Department of Energy
Date
DEC 3 1 "896 ^
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00086-RS
ADDRESS: 164 EAST FOURTH SOUTH STREET
MONTICELLO, UTAH 84535
AUGUST 1991
Prepared for
Decontamination and Decommissioning Program
Division of Facilities and Site Decommissioning
Department of Energy
by
Chem-Nuclear Geotech, Inc.
P.O. Box 14000
Grand Junction, Colorado 81502-5504
Program Manager
Chem-Nuclear Geotech, Inc., has been granted authorization to conduct remedial
action under the Decontamination and Decommissioning Program. Remedial action
was done in accordance with the Environmental Protection Agency Standards for
Cleanup of Lands and Buildings Contaminated with Residual Radioactive Material
from Inactive Uranium Processing Sites, 40 CFR 192.12, 192.20-23.
MS-00086-RS:PCR-272
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-00086-RS
1.0 SUMMARY
1.1 Basis for Remedial Action
The Monticello Vicinity Properties (MVP) project was accepted into
the Decontamination and Decommissioning Program with the primary
objective of reducing 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, 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 Decontamination and Decommissioning Program has adopted the
"Standards for Remedial Action at Inactive Uranium Processing Sites"
(40 CFR Part 192) as guidelines for all cleanup activities under the
MVP project. These standards were prepared by the Environmental
Protection Agency (EPA) to establish guidelines for the control of
tailings piles and the cleanup of buildings and open lands.
This property was evaluated on the basis of the EPA standards by the
Department of Energy (DOE), which determined that the property
contained residual radioactive material which exceeded the ,EPA
standards. The Remedial Action Contractor was notified of the
inclusion of this property into the Decontamination and
Decommissioning Program and was authorized by the DOE to conduct
remedial action as required to bring the property into conformance
with the EPA standards.
1
DOE ID NO.: MS-00086-RS
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-00086-RS
Parcel No. M-8-1, Block 2, City of
Monticello, County of San Juan, State
of Utah
164 East Fourth South Street
Monticello, Utah 84535

Residential Simple (RS)
Not applicable; historical inclusion
by the Department of Energy
February 6, 1984
Chem-Nuclear Geotech, Inc.
July 1984
Crowley Construction
East Route
Monticello, Utah
June 19, 1985
September 25, 1985
Interior: 0 cubic yards
Exterior: 844 cubic yards
1,062 square meters (m2)
August 1991
DOE ID NO.: MS-00086-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 condition comparable to that which existed prior
to remedial action activities.
2.2 Previously Unidentified Contamination
The original radiological assessment identified 194 cubic yards of
contamination, ranging from 6 inches to 12 inches deep, within the
property. The remedial action process included the removal of
approximately 844 cubic yards of residual radioactive material,
ranging from 6 inches to 24 inches deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix
Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities performed on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the residual
radioactive material removal activities performed on the property.
3
DOE ID NO.: MS-00086-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 Chem-Nuclear
Geotech, Inc., during April 1984, as described in the final
REA dated July 1984. Appendix Figure 2.1 shows the extent of
contamination determined during the pre-remedial assessment
and identifies the areas recommended to undergo remedial
action.
3.1.2 Post-Excavation Survey
A ground-level gamma scan with a scintillometer was performed
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 16 microroentgens per
hour (fjR/h) to 26 t/R/h (Appendix Figure 2.1). The results of
analyses for radium-226 in nine composite soil samples ranged
from 1.0 picocurie per gram (pCi/g) to 6.6 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 0.0204 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-00086-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) as indicated in the Certification Data Summary below.
Therefore, the property located at 164 East Fourth South Street, in
Monticello, Utah, is recommended for certification as required by
the Decontamination and Decommissioning Program guidelines, and the
appropriate record should be documented.
Certification Data Summary
Standards Applicability Survey Results
Habitable Structures
Exposure Rate: Shall not exceed 20 /v/R/h
above background.*
Range for the basement
was 13 /iR/h to 16 juR/h.
Radon Decay-Product
Concentration:
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Annual average
0.0204 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.
< 5 pCi/g above
background.
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 15 pCi/g
above background** in any
15-cm-thick soil layer
more than 15 cm below the
surface, averaged over
100 m2.
The soil sample results
ranged from 1.0 pCi/g
to 6.6 pCi/g.
*The background exposure rate is approximately 18 pR/h.
**The background radium-226 concentration is approximately 2.0 pCi/g.
5
DOE ID NO.: MS-00086-RS
4.0 APPENDIX
Appendix Tables:
Table 3.1 Post-Excavation Sample/Measurement Results
Table 3.2 Radon Decay-Product Concentration (RDC)
Measurement Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00086-RS
Address: 164 East Fourth South Street, Monticello, Utah
The analytical uncertainties in the table are reported at the 95-percent
confidence interval. A question mark (?) indicates that the analysis is
semiquantitative because of a low count rate.
Area
Exposure-Rate
Range (pR/h)
Soil Sample
Ticket No.
Radium-226
(pCi/g)
Potassium
(pCi/g)
Thorium
(pCi/g)
V-l
V-2
V-3
V-4
V-5
V-6
V-7
V-8
V-9
18
18
18
18
17
18
18
19
17
22
24
24
22
19
22
24
24
26
MAY
MAY
MAY
MAY
MAY
MAY
MAY
MAY
717
718
719
720
721
722
723
724
MAY 725
6.6
4.1
6.6
3.6
.0
.0
.0
0
,0
4
.0
4
,0
12.2
8.7
9.1
11.
9.
13.
14.
13.
13.
2.8
1.7
1.7
2.5
1.8
4.4
5.0
4.4
3.5
1.3
0.9
1.0
1.0
0.9
0.7
1.1
0.9
1.0
1.0
1.0
1.0
1.0
1.0
1.0
1.0
1.0
1.0
See Appendix Figure 2.1 for the verification areas.
7
Table 3.2
Radon Decay-Product Concentration (RDC) Measurement Results
DOE ID No.: MS-00086-RS
Address: 164 East Fourth South Street, Monticello, Utah
Instrument Type: Terradex Track Etch® Detector
Radon Average
Detector Tracks Per Concentration Working
Number Start Date End Date mm2 (pCi/1) Level (WL)
526263 01-19-89 01-19-90
526044 01-19-89 01-19-90
526493 01-19-89 01-19-90
32.1 4.22 0.0211
31.5 4.14 0.0207
29.3 3.85 0.0193
Annual Average: 0.0204
See Appendix Figure 2.1 for the measurement location.
MM-JEK:07-12-91
MS-00086-RS:PCR-272 WS 5.5
REV051791
8
28 -
12 16 38 40 14 18 20 28 30 32 34 36 10 22 24 26
V-8
19-24
16
.! • 1 6 18 16 24
G X12>.7. C K 6 14 V-9 ui V-5 LU
17-26 rr 7-19 ONE STORY • H C/l HOUSE W/
BASEMENT 2 12 12 12 F X 6 BASEMEN
13-16 16-20
o 20 12 to 20
RDC
QC
:
=5 V-6 o V-2 V-4 V-3 V-1 18-22
18-22 18-24 8-24 18-22
< UJ B X 6 V-7 2 '.1 D K 6
20 18-24 12 E X 6
3
V-8
19-24
THIS DRAWING, PREPARED FOR THE DECONTAMINATION AND
DECOMMISSIONING PROGRAM. IS FOR THE -SOLE USE "OP THE'
U.S. DEPARTMENTiOF ENERGY AND £TS CONTRACTORS- IT IS
NOT A LAND SURVEY PLAT, :UTILITY LOCATION PLAT, OR OTHER
fMPROVEMENT SURVEY PLAT AND IS:NOT TO &E RELIED UPON
FOR- THE- ESTABLISHMENT QF-FE-NCE, -BUILDING-.-OR- OTHER
FUTURE IMPROVEMENT LINES.
LEGEND
DEPTHS IN IINCHES
EXPOSURE;RATES IN' fiR/h
ALL
Alt
0 ASSESSED AREA IDENTIFIER;
AVERAGE:DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED.C.O.NTAMINANIS
POST REMEDIAL: ACTION EXP:OSURE-RATE RANGE
BOUNDARY OF EXCAVATION•':
RADIOtOGICAtu AS-BUILO" ®
12-15
EXTENT OF CONTAMINATION EXTERIOR
x
AVERAGE £XCAVATED DEPTH: FOR THE DEPOSIT O 12 OF CONTAMINATION REVISIONS DATE CK. A.E •ATE REVISIONS APP NO APP. NO
RESIDENCE — NO Or OCCUPANTS U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE, COLORADO V-1 VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE-RATE RANGE
NON* RE SIDENCE — MAN-HR5.'WK
DATE-. DESIGUE 16-17 1 64 EAST FOURTH
SOUTH STREET
MONTICELLO, UTAH
INSTRUMENT NO SURVEYOR DRAWN SCALE IN FEET Y POST REMEDIAL ACTION RADON DECAY-PRODUCT
CONCENTRATION MEASUREMENT LOCATION ML RDC
• NG
APPROVAL DATE APPROVAL DOE SUBMITTED DATE 20 TO 20 40 SURVEY DATE TIME DOE ID NO
x; MS-00086-RS
Geotech, Inc VERIFICATION DATE DWG. NO 3-B337-G7 SHT 1
22 24 36 38 26 28 30 40 20 32 34 10 12 14 16 18
Results of the
Independent Verification of
Radiological Remedial Action
at 164 East 4th South Street
Monticello, Utah (MS00086)
M. J. Wilson
J. K. Williams
HEALTH AND SAFETY RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
164 EAST 4TH SOUTH STREET
MONTICELLO, UTAH (MS00086)
M. J. Wilson and J. K. Williams
December 1991
Work performed by the
POLLUTANT ASSESSMENTS 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 4
iii
LIST OF TABLES
1 Applicable guidelines for protection against radiation 5
2 Results of ORNL analysis of UNC Geotech soil samples from 164 East 4th South
Street Monticello, Utah (MS00086) 6
v
ACKNOWLEDGMENTS
Research for this project was sponsored by the Division of Facility and Site
Decommissioning Projects, U.S. Department of Energy. The authors wish to acknowledge
G. A. Pierce for analysis of soil samples and D. T. Redding. G. K Stowe. S. K Mather, 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 1985, 1989, and 1990, UNC Geotech, the
remedial action contractor designated by DOE, performed remedial action on the vicinity
property at 164 East 4th South Street, Monticello, Utah. The Pollutant Assessments Group
(PAG) 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 PAG found that the site successfully meets the DOE remedial action
objectives. Procedures used by the PAG are described.
ix
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 164 EAST 4TH SOUTH STREET
MONTICELLO, UTAH (MS00086)*
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 H 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 de<x>mmissioning of government facilities that had been retired from service
bat 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.1
*The verification of remedial action was performed by members of the Pollutant Assessments
Group of the Health and Safety Research Division at Oak Ridge National Laboratory under DOE
contract DE-AC05-84OR21400 with Martin Marietta Energy Systems, Inc.
During 1985, 1989, and 1990, 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 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.2
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 Pollutant Assessments Group (PAG) of Oak Ridge National Laboratory
(ORNL) has been assigned the responsibility of this task at the 164 East 4th South Street
site. This report describes the methods and results of that verification.
PROCEDURES
Objectives
The objectives ofthe verification activities were to confirm (1) that available documenta-
tion adequately and accurately describes the post-remedial-action radiological conditions of
the entire property that is to be certified and (2) that the remedial action reduced
contamination to below applicable DOE guidelines.
Document Reviews
Review of the property completion report prepared by Geotech2 indicates the property
was evaluated by DOE on the basis of Environmental Protection Agency standards3 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 194 yd3 of mill tailings
12 in. deep. However, during the actual removal process, a total of 844 yd3 of contaminated
earth and uranium mill tailings, 6 to 24 in. deep, were removed from a 1,062-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, ground-level and
basement scans ofthe building and a surface scan ofthe exterior and soil sampling. Samples
representative of the bottom 15-cm (6-in.) soil layers of nine excavated areas were collected
and blended to form representative composite soil samples for each verification area.