DERR-1992-014776 - 0901a068805414a9

DEC 2 7 836
SCANNED
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00072-RS
ADDRESS: 493 SOUTH MAIN STREET
MONTICELLO, UTAH 84535
JANUARY 1992
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 JAN 2-1 1992
CJ RECORDS MANAGEMENT
Harry/A. Perry
Program Manager
7*
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-00072-RS:PCR-286
SFCMPLRPTS SFMS-08872
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-00072-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
Decommmissioning 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-00072-RS
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
Property Address:
Property Owner:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
MS-00072-RS
Parcel M-641, City of Monticello,
County of San Juan, State of Utah
493 South Main Street
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
March 1, 1989
Chem-Nuclear Geotech, Inc.
March 19, 1990
Sonderegger, Inc.
P.O. Box 6
Monticello, Utah
April 30, 1990
May 31, 1990
Interior: 0 cubic yards
Exterior: 34 cubic yards
88 square meters (ma)
January 1992
2
DOE ID NO.: MS-00072-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 34 cubic yards of residual radioactive material,
ranging from 8 inches to 12 inches deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix
Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities 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-00072-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 March 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 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
1.9 picocuries per gram (pCi/g), as indicated in Appendix
Table 3.1.
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on measurements representing an annual average, the
RDC was 0.0047 Working Level (WL), as indicated in Appendix
Table 3.2. Appendix Figure 2.1 shows the measurement
location on the ground floor (the lowest habitable level of
the structure).
4
DOE ID NO.: MS-00072-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 493 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.
Applicability
Habitable Structures
Exposure Rate:
Certification Data Summary
Standards
Shall not exceed 20 /iR/h
above background.*
Survey Results
Range for the ground
floor was 11 /iR/h to
13 /jR/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
0.0047 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 m'.
The soil sample result
was 1.9 pCi/g.
*The background exposure rate is approximately 15 /jR/h.
**The background radium-226 concentration is approximately 2.0 pCi/g.
5
DOE ID NO.: MS-00072-;
4.0 APPENDIX
Appendix Tables:
*>*• 3.1 Po.t-EKc.,ation ^ple/Me„uteTOnt Reauits
Appendix Figure:
Pi9UCe EXtent °f °-*-i»ti« - KAOXo^^
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00072-RS
Address: 493 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 (/jR/h) Ticket No. (pCi/g) (pCi/g) (pCi/g)
V-l 14 - 18' MDG 356 1.9 ± 0.4 15.9 ± 4.9 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-00072-RS
Address: 493 South Main Street, Monticello, Utah
Instrument Type: Terradex Radtrak^ Detector
Detector
Number Start Date End Date
Tracks Per
mm2
Radon
Concentration
(pCi/1)
Average
Working
Level (WL)
3142017
3142716
3142049
09-12-90
09-12-90
09-12-90
09-04-91
09-04-91
09-04-91
7.5
8.0
7.6
0.91
0.97
0.92
0.0046
0.0049
0.0046
Annual Average: 0.0047
See Appendix Figure 2.1 for the measurement location.
DHW-VPF:12-10-91
MS-00072-RS:PCR-286 WS 5.5
REV051791
8
10
30
28 -
26 -
24
22
20
18
16
14
12 14
i—r
16
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18
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20
T
22 24
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26
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28 30 32
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34 36 38
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12
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SHED SHED
v-1
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V-1 11-13:
ONE STORY FRAME
WITH CRAWL SPACE
6-17 14-15
RDC
RDC Q
6uR/h
777
O
©•
so
LEGEND
ALL DEPTHS IN;INCHE-S
ALL EXPOSURE! RATES' IN '/iR/h .;:
A)! ASSESSED AREA IDENTIFIER^I j
I <6)i AVERAGE:DEPTH OF ASSESSED CONTAMINATION
AR EA. D.F. |.AS.SE$S ED. .C!Q NTAMJ NANTjS j
12-15 POST REMEDIAL ACTION EXPOSURE—RATE RANGE
BOUNDARY OF EXCAVATION i
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT
OFiCONTAMINATION
40
VERIFICATION SOIL SAMPLE AREA IDENTIFIER \
AND EXCAVATION EXPOSURE-RATE RANGE
POST REMEDIAL ACTION RADON DECAY-PRODUCT
CONCENTRATION MEASUREMENT LOCATION
ASSESSED CONTAMINANTS NOT FOUND AT
TIME OF REMEDIAL ACTION ':
RADIOLOGICAL AS-BUILT
EXTERIOR iEXTENT OF CONTAMINATION
21
26
24
22
20
18
16
O
z
12 Y
4
SCALE' fN FEET'
_L 10L-
' 10
: 20 :
J L
IO :' "0 ;:" 20 ":'
i i i i
40
THIS.DRAWING, PREPARED.FOR THE:DECONIAMIN AXIOM AMD...:.
DECOMMISSIONING PROGRAM, IS FOR THE SOLE USE OF THE :
U.S. DEPARTMENT^ ENERGY AND fTS CONTRACTORS; IT IS \
NOT A LAND SURVEY PUT, UTIUTY LOCATION PLAT, OR OTHER:
IMPROVEMENT SURVEY PLAT AND IS'NOT TO BE RELIED UPON '•
FOR THE ESTABLISHMENT OF FENCE; BUILDING, OR OTHER ':'
FUTURE IMPROVEMENT LINES.
i i i i I L J I I L
NO. DATE
RESIDENCE—NO. OF OCCUPANTS
NON-RESIDENCE—MAN-HRS./WK.
INSTRUMENT NO. SURVEYOR
SURVEY DATE
VERIFICATION
14
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE, COLORADO
1 493 SOUTH MAIN STREET
MONTICELLO, UTAH
12
DATE APPROVAL DOE
MS-00072-RS
N^-B00072-M4SHT 1 OF 1
12 14 16 18 20 22 24 26 28 30 32 34 36 38 40
DOE ID No.: MS-00072-RS
Property Address: 493 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] [ ]
[ ]
[ ]
[ ]
[ ]
[ ]
[ ]
[>] [ ]
[V] [ ]
IA [ I
[ ] [X
I 1
[ ]
[ ]
[ ]
[ ]
Ly] [ ] [ ]
*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-00072-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.
. Buthefus \ > Date lichael C. Buthi
Manager, Monticello Programs
MACTEC-ERS
DOE Evaluation
On the basis of the Property Completion Report evaluation, this property
[X] Should be certified by DOE.
[ ] Should be certified by DOE with the concurrence of the U.S. Nuclear Regulatory
Commission because supplemental standards were applied according to 40 CFR 192.21.
> Ms ft-
Certification Official Date
U.S. Department of Energy
Work performed under DOE Contract No. DE-AC 13-95GJ87335, Task Order No. 96-05.02.14
2 of 2
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00185-RS
ADDRESS: SOUTH 2ND EAST STREET
MONTICELLO, UTAH 84535
JANUARY 1992
Prepared for
Decontamination and Decommissioning Program
Division of Facilities and Site Decommissioning
Department of Energy
JAN 10V8S2
by
Chem-Nuclear Geotech, Inc.
P.O. Box 14000
RECORDS MANAGEMENT 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-00185-RS:PCR-283
SFCMPLRPTS SFMS-08185
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-00185-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-00185-RS
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
Property Address:
Property Owners:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
MS-00185-RS
Parcel No. M-70, Lot 2B, Block 11,
City of Monticello, County of San
Juan, State of Utah
South 2nd East Street
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
September 19, 1989
Chem-Nuclear Geotech, Inc.
April 9, 1990
Sonderegger Construction, Inc.
P.O. Box 6
Monticello, Utah
May 21, 1990
June 14, 1990
Interior: 0 cubic yards
Exterior: 147 cubic yards
413 square meters (m2)
January 1992
2
DOE ID NO.: MS-00185-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 49 cubic yards of
contamination, 6 inches deep, within the property. The remedial
action process included the removal of approximately 147 cubic yards
of residual radioactive material, ranging from 6 inches to 18 inches
deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix
Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities 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-00185-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 1989, as described in the final
REA dated April 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 12 microroentgens per
hour {uR/h) to 22 ^R/h (Appendix Figure 2.1). The results of
analyses for radium-226 in five composite soil samples ranged
from 2.7 picocuries per gram (pCi/g) to 4.3 pCi/g (Appendix
Table 3.1).
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
RDC measurements were not taken in the structure due to
excessive ventilation caused by missing windows and holes in
the roof; therefore, the structure was verified according to
exterior standards.
4
DOE ID NO.: MS-00185-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 2nd 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 /jR/h
above background.
Not applicable:
uninhabitable
structure.
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:
uninhabitable
structure.
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 2.7 pCi/g
to 4.3 pCi/g.
*The background radium-226 concentration is approximately 2.0 pCi/g.
5
DOE ID N°-
MS-00185-RS
4.0 APPENDIX
Appendix Table SndiX " ^/Measurement Results
Table 3.1 Fo.t-*cava*io» Sample/Measu
Appendix Figure: _ RADIOLOGICAL
, , Exterior Extent of Contamination
Fig»r. 2.1
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-0O185-RS
Address: South 2nd 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 (pR/h) Ticket No. (pCi/g) (pCi/g) (pCi/g)
V-l 14 -
V-2 14 -
V-3 14 -
V-4 14 -
V-5 14 -
18 MLT 210
18 MLT 211
19 MLT 212
18 MLT 213
22 MLT 214
3.6 ± 0.5 14.5
3.2 ± 0.5 15.5
4.3 ± 0.6 14.1
2.7 + 0.4 15.2
4.2 ± 0.5 14.4
± 3.3 1.1 ± 0.3
± 3.4 0.8 ± 0.2
± 3.3 1.3 ± 0.3
± 3.5 1.1 ± 0.3
± 3.4 1.0 ± 0.3
See Appendix Figure 2.1 for the verification areas.
MM-VPF:11-18-91
MS-00185-RS:PCR-283 WS 5.5
REV051791
7
in
V-1
14-18
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8
V-2 V-4
H-18 14-18
10 10 Hr. 10
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• •1 BRICk AND:STUCCO —
*HOUSE:
13-16
15
12-16
18
; 12-116
10
SCALE' IN FEET'
•:-20-:-r0-:
J I L
20 '40"
NORTH;
J L
THIS DRAWING, PREPARED TOR THE^ DECONTAMINATION AND '•
DECOMMISSIONING PROGRAM. IS FOR THE SOLE USE OF THE :
U.S. DEPARTMENT. OF ENERGY AND ITS CONTRACTORS. IT IS :
HOT A LANP..SURVEY PLATJ:UTIM.TY.|..OCATIPH.P.LAT..OR OTHER:'.
IMPROVEMENT SURVEY PLAT AND IS NOT TO BE RELIED UPON :
FOR THE ESTABLISHMENT OF FENCE. BUILDING. OR OTHER
j^UTURE yiPROVEjlENT LINp j j
18 26
LEGEND
ALL DEPTHS INilNCHES
ALL EXPOSURE; RATES IN ^R/h:: ""
; (A); ASSESSEb AREAJDENjriFIERj\ \
\ <f); AVERAGE! DEPTH OF ASSESSED CONTAMINATION
i..H>.i..:.AREA.OEASSESSED.O:QNIAMINA^ j
j12-15 POST REMEDIAL ACTION EXPOSURE-RATE RANGE
i—1- -60UNOAR-YGF- EXCAVATION I - I I ••••
12 AVERAGE!EXCAVATED DEPTK FOR THE DEPOSIT
P.FiCQNTAMINATION ...: • j • j.
VERIFICATION SOIL SAMPLE AREA IDENTIFIER !
AND EXCAVATION EXPOSURE—RATE RANGE
ASSESSED CONTAMINANTS NOT FOUND AT
TIME OF REMEDIAL ACTION !
40
RADIOLOGICAL ASH-BUIUT
: EXTERIOR -EXTENT OF CONTAMINATION
NO. DATE
RESIDENCE —NO. OF OCCUPANTS
NON-RE SIDE NCE —MAN-HRS.'WK.
INSTRUMENT NO. SURVEYOR
SURVEY DATE
VERIFICATION
A.E. APP. NO. DATE
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE, COLORADO
SUBMITTED:
SOUTH 2ND EAST STREET
MONTICELLO, UTAH
Geotech,Inc.
DATE APPROVAL DOE
MS-00185-RS
^-BOOISS-MS^T 1 nF 1
30 39
DOE ID No.: MS-00185-RS
Property Address: South Second 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 pR/h above
background in any occupied or
habitable structure.
The radon decay-product
concentration in any occupied or
habitable structure is < 0.02 WL or, at
most, 0.03 WL.
Supplemental standards were applied
in accordance with EPA standard
40 CFR 192.21.
Hot spot criteria met as outlined by
DOE guidelines for FUSRAP
(Rev.2, March 1987)
Yes No Not Taken Yes No Not Taken
[XT [ ]
[X] [ ]
[ ] [ ]
[ ] [ ]
[ ] [X]
[X] [ ]
[ ]
[ ]
[X]b
[X]b
[ ]
[ ]
[A I ]
IA I I
[ ] [ ]
[ ] [ ]
[ ] I*
[ ]
[ ]
LA
[ ]
MM [ 1
aThe excavations were backfilled with materials that were measured at the source indicating that the Ra-226
concentrations are in the range of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
"Uninhabitable structure.
1 of 2
DOE ID No.: MS-00185-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.
C Buthe ic ae
Manager, Monticello Program^
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.
tds a
Date
Work performed under DOE Contract No. DE-AC13-95GJ87335, Task Order No. 96-05.02.14
Certification Official
U.S. Department of Energy
2 of 2
DOE ID NO. : MS- OO I S& ~ \J L~
Property Address: 6S "Soot^ SeCQ^cf £eX^T SfreeC
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 m^. >*J [ ] [ ] t/1 [ 1 t 1
In-situ [ ] Lab -Jx]
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). [ ] [ ] tX] [ ] [ ] [*]
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.
•mn mm
SFCERTIFED SFMS-09158
t ] [ ] [X]
(Vacant Lot)
( ] [ ] [X]
(Vacant Lot)
[ ] txJ [ ]
t ] [ ] LX1
( ] [ ] tX]
[ ] IX) [ ]
DOE ID NO.: MS- £>£>/58 '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.
S3
arry ry Decontamination and Decommissioning Program Manager
Chem-Nuclear Geotech, Inc.
Date
DOE EVALUATION
fxi 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-00158-VL
ADDRESS: 65 SOUTH SECOND EAST STREET
MONTICELLO, UTAH 84535
FEBRUARY 1992
Prepared for
Decontamination and Decommissioning Program
Division of Facilities and Site Decommissioning
Department of Energy
FEB 21 1992
RECORDS MANAGEMENT
by
Chem-Nuclear Geotech, Inc.
P.O. Box 14000
Grand Junction, Colorado 81502-5504
mm FEB 21 199?
rj
RECORDS MANAGEMENT
Harp^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.
111111,11111 mmm MS-00158-VL:PCR-288
mm
SFOCPLRPTS SFMS-09021
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
1
DOE ID NO.: MS-00158-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-00158-VL
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
MS-00158-VL
Parcel No. M-173-1; beginning at the NW corner of Lot 2, Block 21,
Plat A; south 114.5 feet, east 142 feet, north 114.5 feet, west 142 feet
to beginning, City of Monticello, County of San Juan, State of Utah
Property Address:
Property Owner:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
65 South Second East Street
Monticello, Utah 84535

Vacant Lot (VL)
Oak Ridge National Laboratory
July 25, 1990
Chem-Nuclear Geotech, Inc.
June 21, 1991
Sonderegger, Inc.
P.O. Box 6
Monticello, Utah
August 23, 1991
September 17, 1991
Interior: 0 cubic yards
Exterior: 19 cubic yards
77 square meters (m1)
February 1992
2
DOE ID NO.: MS-00158-VL
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of exterior residual
radioactive material (Appendix Figure 2.1). Once excavation was
complete, the affected areas were resurveyed for possible remaining
residual radioactive material and, upon attaining satisfactory
results, were backfilled with uncontaminated material. The property
was restored to a condition comparable to that which existed prior
to remedial action activities.
2.2 Previously Unidentified Contamination
The original radiological assessment identified 6 cubic yards of
contamination, 6 inches deep, within the property. The remedial
action process included the removal of approximately 19 cubic yards
of residual radioactive material, ranging from 6 inches to 9 inches
deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix
Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities 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-00158-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 May 1990, as described in the final REA
dated June 1991. 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 (juR/h) to 18 juR/h (Appendix Figure 2.1). The result of
analysis for radium-226 in one composite soil sample was
2.4 picocuries per gram (pCi/g), as indicated in Appendix
Table 3.1.
4
DOE ID NO.: MS-00158-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 G5 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
:3=S3SSIB=SS=C=3SSSSSESES:Se
Standards Survey Results
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Shall not exceed 20 /iR/h
above background.
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Not applicable:
vacant lot.
Not applicable:
vacant lot.
Land
Radium-226 Concentration
in Surface Soil:
Radium-226 Concentration
in Subsurface Soils:
Shall not exceed 5 pCi/g
above background* in
the 15-cm surface layer,
averaged over 100 m*.
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 result
was 2.4 pCi/g.
*The background radium-226 concentration is approximately 2.0 pCi/g.
5
DOE ID NO.: MS-00158-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-00158-VL
Address: 65 South Second 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 (/iR/h) Ticket No. (pCi/g) (pCi/g) (pCi/g)
V-l 13 - 18 NAH 705 2.4 ± 0.4 19.2 ± 4.2 1.2 ± 0.3
See Appendix Figure 2.1 for the verification area.
MM-JEK:0l-28-92
MS-00158-VL:PCR-288 WS 5.5
REV051791
7
12 14 10 16 20 22 18 24 28 26 30
14-16 14-16
LU
LU 12-15 rr
C/J
12 LU
Z
16-17
to.
3
O V-1
tO:
13-18
14-16
/
•g
HO. OATE
SCALE!IN FEET
Y
A 20 tO 20 40
TIME
X i
I I I
32 34 36 38
i—i—i—i—i—i—T
ALL DEPTHS IN
ALL EXPOSURE
LEGEND
INCHES
RATES IN
ASSESSED AREA IDENTIFIER
AVERAGE! DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINANTS.
POST REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION
AVERAGE
OF CONTAMINATION
EXCAVATED DEPTH FOR THE DEPOSIT
40
28
26
24
22
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE-RATE RANGE
ASSESSED CONTAMINANTS NOT FOUND AT
TIME OF REMEDIAL ACTION
RADIO
EXTERIOR
LOGICAL AS-BUILT
FTGIL)RE:Z:T
EXTENT OF CONTAMINATION
20
18
16
NOftTH
j i i
:THIS DRAWINC. PREPARED: FOR THE- DECONTAMINATION ANP. :
;bEC6MM)SSi6NINC PROGRAM. IS FOR THE SOLE USE :OF THE :
:U.S. DEPARTMENT OF ENERGY AND ITS CONTRACTORS. IT IS :
:NOT A L*ND SURVEY PLAT; UTILITY ;LOCATION PLAT, 0R OTHER
IMPROVEMENT SURVEY PLAT AND IS NOT TO:BE RELIED UPON
TOR- THC ESTABLISHMENT OF' FENCE'.' BUILDING-.' 0* OTHER'' '
rFUTURE IMPROVEMENT LINES.
RESIDENCE —NO. OF OCCUPANTS
NON-RESIDENCE —MAN-HRS. WK
INSTRUMENT NO. SURVEYOR
SURVEY DATE
VERIFICATION
14
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE. COLORADO
DATE
9t
PRSJWNG
SUBMITTEO
65 S. SECOND E. STREET
MONTICELLO, UTAH
12
f. Geotech, Inc.
DATE APPROVAL OOE
MS-00158-VL
DWG. NO. 3-B00158-G1sHT 1 + 10 12 14 16 18 20 22 24 26 28 30 32 34 36 38 40
OAK RIDGE NATIONAL LABORATORY
OPERATED BY MARTIN MARIETTA ENERGY SYSTEMS, INC.
GRAND JUNCTION OFFICE
RO. BOX 2567
GRAND JUNCTION, COLORADO 81502
Jacob V. Gatrell
Office of Environmental Restoration
Southwestern Area Programs Division
U.S. Department of Energy
EM-451/GTN/D-247
Washington, DC 20545
Dear Mr. 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, indoor radon daughter
concentration, and indoor gamma exposure rate at this property.
Therefore, this property is recommended for certification by the U.S. Depart-
ment of Energy.
Sincerely,
Wilson
Pollutant Assessments Group
SEP 2 5 1PP?
Marv J.
Location Number: MS00158-VL
Location Address: 65 South 2nd East Street
Monticello. Utah 84535
Property Owner: Black Oil Company
Roberta B. King. President
Owner Address: P. 0. Box 607
Monticello. Utah 84535
Attachments
HEALTH AND SAFETY RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
65 SOUTH 2ND EAST STREET
MONTICELLO, UTAH (MS0015&-VL)
G. K. Stowe
September 1992
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
UST OF TABLES v
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VER1PICATION 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 5
2 Results of ORNL analysis of Geotech soil samples from 65 South 2nd East Street,
Monticello, Utah (MS00158-VL) 6
v
ACXNOWI^LXJMENTS
Research for this project was sponsored by the Division of Facility and Site
Decommissioning Projects, U.S. Department of Energy. The author wishes to
acknowledge G. A. Pierce for analysis of soil samples and E. P. Schlauger 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 1991, Chem-Nuclear Geotech, the remedial action contractor
designated by DOE, performed remedial action on the vicinity property at 65
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 in the Pollutant Assessments Group Procedures Manual.
ix
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 65 SOUTH 2ND EAST STREET
MONTICELLO, UTAH (MS00158-VL)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the U.S. government through the
Defense Plant Corporation to provide vanadium during World War 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 1991, Chem-Nuclear Geotech, Inc. (Geotech), the remedial action contractor
(RAC) designated by DOE, performed remedial action on the vicinity property that is the
subject of this report, a vacant lot located at 65 South 2nd East Street, Monticello, Utah.
The remedial action plan required excavation of all exterior contamination. When the
excavation was completed, the property was resurveyed, including soil sampling, to ensure
the removal of all contamination, backfilled with uncontaminated material, and restored to
a condition comparable to that which existed prior to remedial action.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 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 6 yd3 of mill tailings
6 inches deep. However, during the actual removal process, a total of 19 yd3 of
contaminated earth and uranium mill tailings, 6 to 9 inches deep were removed from a 77
m2 area.
A post-excavation survey was performed by Geotech prior to backfilling of the
excavated areas. This survey consisted of a surface scan of the exterior and soil sampling.
Samples representative of the bottom 15-cm (6-in.) soil layers of four excavated areas
were collected and blended to form a representative composite soil sample for the
verification area.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation
levels have not been subtracted. Similarly, background concentrations have not been
subtracted from radionuclide concentrations in soil samples. Applicable DOE guidelines
for protection against radiation are given in Table 1.
Gamma Measurements
Exterior surface gamma measurements taken from the excavated areas prior to
backfilling ranged from 13 to 18 pR/h.
Soil Sample Analysis
Prior to backfilling, Geotech collected soil samples representative of the excavated
areas from the bottom 15-cm (6-in.) soil layers. These samples were blended to form a
composite soil sample representative of an average over the exterior verification area.
Geotech's analysis of this sample showed ^Ra concentrations of 2.4 pCi/g in the
composite sample. ORNL PAG obtained this soil sample and performed a confirmatory
analysis, which showed ^Ra concentrations from of 2.2 pCi/g. These values are below the
DOE guideline value of 15 pCi/g for soil layers >15 cm below the surface (Table 1).
Results of Geotech and ORNL soil sample analyses are given in Table 2.
CONCLUSION
Results of Geotech soil sample analysis and confirmatory split soil sample analysis by
ORNL show that radionuclide concentrations are within applicable DOE guidelines.
Based upon the results of the post-remedial-action data, which are confirmed by the
verification assessment data, these radiological measurements fall below the limits
prescribed by DOE guidelines. It is concluded that the site successfully meets the DOE
remedial action objectives.
4
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.
Z Geotech, Property Completion Report for Monticello Vicinity Property Remedial Action
for DOE ID NO: MS00158-VL, Address: 65 South 2nd East Street, Monticello, Utah
84535, Geotech, Grand Junction, Colorado, February 1992.
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 trom Uuidelmes for Residual Radioactive Matenal at tormerty
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 Geotech soil samples
from 65 South 2nd East Street, Monticello Utah (MS00158-VL)
— wKa concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No." No* (cm)
X-l NAH-705 15-30 2.2 2.4
" An X-type sample is a split of the sample taken by the remedial action contractor.
b Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated
areas were taken by Geotech, and these samples were blended to form a composite
soil sample, which represents an average over one of the verification areas.
I/'
DEC 2 7 1996
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00195-CS
ADDRESS: EAST THIRD SOUTH STREET
MONTICELLO, UTAH 84535
FEBRUARY 1992
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
Harjjy 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-00195-CS:PCR-288
SFCMPLRPTS SFMS-08195
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
1 ..••xVi^i---'-'-- ••'
DOE ID NO.: MS-0O195-CS
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-00195-CS
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-00195-CS
Parcel No. M-219, Lot 2B, Block 28,
City of Monticello, County of San Juan,
State of Utah
East Third South Street
Monticello, Utah 84535

Commercial Structure (CS)
Oak Ridge National Laboratory
October 23, 1989
Chem-Nuclear Geotech, Inc.
October 17, 1990
Sonderegger, Inc.
P.O. Box 6
Monticello, Utah
August 28, 1991
September 24, 1991
Interior: 0 cubic yards
Exterior: 34 cubic yards
115 square meters (ma)
February 1992
DOE ID NO.: MS-00195-CS
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 20 cubic yards of
contamination, 6 inches deep, within the property. The remedial
action process included the removal of approximately 34 cubic yards
of residual radioactive material, ranging from 8 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-00195-CS
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by Chem-Nuclear
Geotech, Inc., during August 1990, as described in the final
REA dated October 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 (A<R/h) to 22 pR/h (Appendix Figure 2.1). The results of
analyses for radium-226 in two composite soil samples were
3.4 picocuries per gram (pCi/g) and 6.5 pCi/g (Appendix
Table 3.1).
4
DOE ID NO.: MS-00195-CS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property
to the extent required by the EPA standards (40 CFR 192.12,
192.20-23) as indicated in the Certification Data Summary below.
Therefore, the property located at East 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 /^R/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
more than 15 cm below the
surface, averaged over
100 m*.
The soil sample results
were 3.4 pCi/g and
6.5 pCi/g.
*The background radium-226 concentration is approximately 2.0 pCi/g.
5
DOE ID NO.: HS-00195-CS
4.0 APPENDIX
Appendix Table:
Table 3.1 Post-Excavation Sample/Measurement Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00195-CS
Address: East 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 - 22 NAH 706 6.5 ± 0.9 15.5 ± 3.6 0.9 ± 0.3
V-2 13 - 19 NAH 707 3.4 ± 0.5 18.6 ± 4.0 0.6 ± 0.2
See Appendix Figure 2.1 for the verification areas.
MM-JEK:01-27-92
MS-00195-CS:PCR-287 WS 5.5
REV051791
7
ho 12 14 16
301 i—i—i—i—i—r
18
i—r
20 22
i—r
24 26
i—r
28
"i—r
30 32 34 36 38
i i i—i—i—i—i—i—i—r
40
28
26
24
22
20
r V.v.v.v;
V.v.
: 15-16
:-1 5-16
V-1
: I 13-22 4 : .1 UJ
15
00
X
LO 15-16 o 13 19 10 00 N.
Q 0 DC : I
0 I:
oo: 15-16 SI
ami
18
2£
2e
24
22
20
16
•LEGEND
ALL DEPTHS.IN INCHES ";
ALL EXPOSURE RATES WlfiR/h':
16
14
<D
12-15
•ASSESSED AREA IDENTIFIER:
AVERAGE DEPTH OF ASSESSED jC0NTAMINAT30N
AREA OF ASSESSED CON'fAMTNAINTS"';j
POST REMEDIAL ACTION EXPOSURE-RATE RANGE
12
;BOUNPARY OF EXCAVATION
iAVERAGE EXCAVATED DEPTH FOR THE DEPOSIT
•;OF CONTAMINATION \ •
V-1
16-17
^VERIFICATION SOIL SAMPLE AREA IDENTIFIER
...:AND EXCAVATION EXPOSURE-RATE RANGE-;...
lASSESSED CONTAMINANTS NOT FOUMO AT !
:TiME OF REMEDIAL ACTION
R A CD 101_0 01 CAL ASTB O lIT 16
FIGURE
EXTERIOR EXTENT OF
27T;'
CONTAMINATION
12
10
SCALE' fN; FEET'; Y Cr. A O
20 10 20 : 40
X
JH(S. DRAWING, PREPARED. FOR .THE. DjtC.QNTAMtNATI.QH 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. UTILITY LOCATION PLAT, OR OTHER
IMPROVEMENT SURVEY PLAT AND IS NOT TO BE: RELIED UPON
• FOR" THE ESTABUS^ENY OF' FEN'CEY BUiLbiNG • OR OTHER
FUTURE IMPROVEMENT UNES;
I
10 12 14 16 18 20 22
J i j L
24 26
I
28
RESIDENCE-NO. OF OCCUPANTS
NON-RESIDENCE —MAN-HRS./WK.
INSTRUMENT NO. SURVEYOR
SURVEY OATE
VERIFICATION
APP. NO. OATE REVISIONS
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE, COLORADO
1^
DAT DESIGNED
DRAWN
CH
u NO
SUBMITTED
EMPIRE ELECTRIC SUBSTATION
EAST THIRD SOUTH STREET
MONTICELLO, UTAH
30 32
Geotech, Inc.
"34
DOE ID NO.
APPROVAL DOE
MS-00195-CS
OWO. NO.
36
3-D00195-G^T, 1 QP 1
38 40
OAK RIDGE NATIONAL LABORATORY
OPERATED BY MARTIN MARIETTA ENERGY SYSTEMS, INC.
GRAND JUNCTION OFFICE
RO. BOX 2567
GRAND JUNCTION, COLORADO 81502
SEP 2 5 1332
Jacob W, Gatrell
Office of Environmental Restoration
Southwestern Area Programs Division
U.S. Department of Energy
EM-451/GTN/D-247
Washington, DC 20545
Dear Mr. 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,
'rryL/oj A . (JJJJUO*-
Mary J. Wilson
Pollutant Assessments Group
Location Number: MS00195-CS
Location Address: East 3rd South Street
A000000C002B
Monticello. Utah 84535

Vacant Lot
Property Owner:
Owner Address:
Tenant Name:
Attachments
HEALTH AND SAFETY RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
EAST 3RD SOUTH STREET, AOOOOOOC002B
MONTICELLO, UTAH (MS00195-CS)
G. K. Stowe
September 1992
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
CONCLUSION 3
REFERENCES 4
iii
LIST OF TABLES
1 Applicable guidelines for protection against radiation 5
2 Results of ORNL analysis of Geotech soil samples from East 3rd South Street,
A00O00OC002B, Monticello, Utah (MS00195-CS) 6
v
ACKNOWIJEDGMENTS
Research for this project was sponsored by the Division of Facility and Site
Decommissioning Projects, U.S. Department of Energy. The author wishes to
acknowledge G. A. Pierce for analysis of soil samples and E P. Schlauger 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 1991, Chem-Nuclear Geotech, the remedial action contractor
designated by DOE, performed remedial action on the vicinity property at East
3rd South Street, A000000C002B, 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 in the Pollutant Assessments Procedures Manual.
ix
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT EAST 3RD SOUTH STREET, A000000C002B
MONTICELLO, UTAH (MS00195-CS)*
INTRODUCTION
The mill at Monticello, Utah, was built in 1942 by the U.S. government through the
Defense Plant Corporation to provide vanadium during World War II. Various
government agencies operated the mill until 1947. In 1948 the Atomic Energy
Commission (AEC) obtained the mill and operated it under contract through 1959 to
provide both uranium and vanadium. Mill operations were terminated on January 1, 1960.
In 1961 the mill tailings piles were leveled and graded, covered with rock and soil, and
seeded with native grasses. During 1974 and 1975, the ore stockpiles were removed from
the site, and the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city
of Monticello, in San Juan County, Utah. The site is bordered on the south and southeast
by land held by the U.S. Bureau of Land Management Other boundaries are the city of
Monticello and private property.
During the AEC era, the mill processed approximately one million tons of uranium
ore. Vanadium and uranium were the only substances extracted in the milling process.
Other constituents of the ore remained in the tailings and were not separated prior to
disposal. During the years of active mill operation, the mill tailings were normally moist,
so erosion was minimal. However, throughout the mill's operating period, area residents
used these tailings as fill material and as aggregate in mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy
(DOE) initiated the Surplus Facilities Management Program (SFMP) in 1978 to ensure
the safe caretaking and decommissioning of government facilities that had been retired
from service but still had radioactive contamination. In 1980 the mill site at Monticello
was accepted into the SFMP, and the Monticello Remedial Action Project (MRAP) was
established to restore the government-owned mill site to safe levels of radioactivity, to
dispose of or contain the tailings in an environmentally safe manner, and to perform
remedial actions on off-site (vicinity) properties that had been contaminated by radioactive
material resulting from mill operations. The Monticello mill site and the tailings remain in
the custody of the DOE Grand Junction, Colorado, Projects Office. In 1983 remedial
actions for vicinity properties were separated from MRAP with establishment of the
Monticello Vicinity Properties (MVP) Project.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 1991, Chem-Nuclear 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 transformer station located at East 3rd South Street,
A000000C002B, 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 East 3rd South
Street, A0O0O00C0O2B 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 20 yd3 of mill tailings
6 inches deep. However, during the actual removal process, a total of 34 yd3 of
contaminated earth and uranium mill tailings, 14 inches deep were removed from a 115 m2
area.
A post-excavation survey was performed by Geotech prior to backfilling of the
excavated areas. This survey consisted of a surface scan of the exterior and soil sampling.
Samples representative of the bottom 15-cm (6-in.) soil layers of four 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
Surface gamma measurements taken from the excavated areas prior to backfilling
ranged from 13 to 22 /iR/h.
Soil Sample Analysis
Prior to backfilling, Geotech collected soil samples representative of the excavated
areas from the bottom 15-cm (6-in.) soil layers. These samples were blended to form a
composite soil sample representative of an average over the two exterior verification areas.
Geotech's analysis of these samples showed ^Ra concentrations of 3.4 and 6.5 pCi/g in
the composite sample. ORNL PAG obtained these soil samples and performed a
confirmatory analysis, which showed ^Ra concentrations of 3.4 and 5.0 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.
CONCLUSION
Results of Geotech soil sample analysis and confirmatory split soil sample analysis by
ORNL show that radionuclide concentrations are within applicable DOE guidelines.
Based upon the results of the post-remedial-action data, which are confirmed by the
verification assessment data, these radiological measurements fall below the limits
prescribed by DOE guidelines. It is concluded that the site successfully meets the DOE
remedial action objectives.
4
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: MS00195-CS, Address: East 3ni South Street, A000000C002B,
Monticello, Utah 84535, Geotech, Grand Junction, Colorado, February 1992,
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.
Table 2. Results of ORNL analysis of Geotech soil samples
from East 3rd South Street, A000000C002B, Monticello Utah (MS00195-CS)
-^Ka concentration (pU/g)
ORNL Geotech ~~
sample sample Depth ORNL Geotech
No." No.' (cm)
X-l NAH-706 15-30 5.0 6.5
X-2 NAH-707 15-35 3.4 3.4
" An X-type sample is a split of the sample taken by the remedial action contractor.
* Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated
areas were taken by Geotech, and these samples were blended to form a composite
soil sample, which represents an average over one of the verification areas.
DOE ID No.: MS-00195-CS
Property Address: East Third South Street
VICINITY PROPERTY CERTIFICATION SUMMARY AND RECOMMENDATION
SUMMARY EVALUATION
U.S. Department
Rust Geotech of Energy (PQE)—
YES NO NOT TAKEN YES NO NOT TAKEN
Ra-226 is < 5 pCi/g
above background in top
15-cm layer of soil
averaged over 100 m2. [X]* [ ] [ ] [?r] [ ] [ ]
In-situ [X] Lab [ ]
Ra-226 is ^ 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m2. [X] [ ] [ ] Mill]
In-situ [ ] Lab [X]
Interior gamma is <s 20 jt/R/h
above background in any
occupied or habitable
structure.
The radon decay-product
concentration in any
occupied or habitable
structure is ^ 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21.
Hot spot criteria met as
outlined by DOE
guidelines for FUSRAP
(Rev. 2, March 1987). [X] [ ] [ ] Mil U
COMMENTS: *The excavations were backfilled with materials that were
measured at the source showing that the Ra-226 concentrations are in the range
of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
[ ] [ ] [X] [ ] [ ]
(Vacant Lot)
[ ] [ ] [X] [ ] t ] ia
(Vacant Lot)
[ ] [X] [ ] [ } [V] [ ]
DOE ID No.: MS-00195-CS
RUST GEOTECH RECOMMENDATION
Based on the Rust evaluation, I recommend this property for:
[X] Certification by the U.S. Department of Energy.
[ ] Certification by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Vvanda S. Bosby
Manager, Monticello Programs
Rust Geotech
DOE EVALUATION
[)(] Should be certified by the U.S. Department of Energy.
[ ] Should be certified by the U.S. Department of Energy with application of
supplemental standards per 40 CFR 192.21.
Certification Official
U.S. Department of Energy
Date
Date
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00156-RS
ADDRESS: 64 EAST FOURTH SOUTH STREET
MONTICELLO, UTAH 84535
MARCH 1992
Prepared for
Decontamination and Decommissioning Program
Division of Facilities and Site Decommissioning
Department of Energy
by
Chem-Nuclear Geotech, Inc.
P.O. Box 14000
RECORDS MANAGEMEbrand Junction, Colorado 81502-5504
HarrVA. 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-00156-RS:PCR-287
SFOCPLRPTS
SFMS-08156
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-00156-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-00156-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-00156-RS
Parcel No. M-14, Block 3, west half of
Lot 4, City of Monticello, County of
San Juan, State of Utah
64 East Fourth South Street
Monticello, Utah 84535

Residential Simple (RS)
Not applicable; spillover inclusion
requested by the Remedial Action
Contractor
June 26, 1987
Chem-Nuclear Geotech, Inc.
November 18, 1987
Eldon Ray Contracting
P.O. Box 10
Moab, Utah
August 19, 1988
September 20, 1988
Interior: 0 cubic yards
Exterior: 414 cubic yards
1,351 square meters (ma)
March 1992
DOE ID NO.: MS-00156-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 291 cubic yards of
contamination, ranging from 6 inches to 12 inches deep, within the
property. The remedial action process included the removal of
approximately 414 cubic yards of residual radioactive material,
ranging from 9 inches to 10 inches deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix
Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities 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-00156-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 November 1987. 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 14 microroentgens per
hour (pR/h) to 18 ^/R/h (Appendix Figure 2.1). The results of
analyses for radium-226 in 15 composite soil samples ranged
from 0.9 picocurie per gram (pCi/g) to 2.8 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 0.0084 Working Level (WL), as indicated in Appendix
Table 3.2. Appendix Figure 2.1 shows the measurement
location on the ground floor (the lowest habitable level of
the structure). The basement was uninhabitable.
4
DOE ID NO.: MS-00156-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 64 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.
Applicability
Certification Data Summary
Standards Survey Results
Habitable Structures
Exposure Rate: Shall not exceed 20 pR/h
above background.*
Range for the ground
floor was 14 /jR/h to
15 uR/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
0.0084 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 m*.
The soil sample results
ranged from 0.9 pCi/g
to 2.8 pCi/g.
*The background exposure rate is approximately 16 /jR/h.
**The background radium-226 concentration is approximately 2.0 pCi/g.
5
DOE ID NO.: MS-00156-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-00156-RS
Address: 64 East Fourth South Street, Monticello, Utah
The analytical uncertainties in the table are reported at the 95-percent
confidence interval. A less-than sign (<) indicates that the minimum
detection limit based on Compton background was reached.
Area
Exposure-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
16 - 18
16 - 18
16 - 18
15 - 16
15 - 17
15 - 16
15 - 16
15 - 16
16 - 17
16
14 - 16
15 - 17
15 - 16
15 - 16
15 - 17
MNK 226
MNK 227
MNK 228
MNK 229
MNK 230
MNK 231
MNK 232
MNK 233
MNK 234
MNK 235
MNK 236
MNK 237
MNK 238
MNK 239
MNK 240
0.9
1.1
2.5
2.5
2.8
1.7
2.3
0.4
0.4
0.4
0.3
0.4
0.3
0.2
0.3
0.2
0.2
0.4
0.4
0.5
0.3
0.4
17.3
18.1
18.8
19.3
16.6
19.1
20.1
18.1
16.8
17.5
17.9
18.3
16.0
17.1
16.1
3.5
3.6
3.7
3.6
3.4
3.7
3.8
3.5
0.
1.
0.
1.
1.
0.
1.
0.8
1.2
1.1
1.2
0.2
0.9
0.2
1.2
0.2
0.3
0.3
0.3
0.3
0.2
0.3
± 0.3
See Appendix Figure 2.1 for the verification areas.
7
Table 3.2
Radon Decay-Product Concentration (RDC) Measurement Results
DOE ID No.: MS-00156-RS
Address: 64 East Fourth South Street, Monticello, Utah
Instrument Type: Terradex Radtrak® Detector
Detector
Number Start Date End Date
Tracks Per
ram1
Radon
Concentrat ion
(PCi/1)
Average
Working
Level (WL)
1255686
1272257
1271971
03-13-90
03-13-90
03-13-90
03-11-91
03-11-91
03-11-91
14.5
14.2
13.2
1.74
1.71
1.59
0.0087
0.0086
0.0080
Annual Average: 0.0084
See Appendix Figure 2.1 for the measurement location.
MM-KMA:01-27-92
MS-00156-RS:PCR-287 WS 5.5
REV051791
8
10 12 14 16 18 20 22 24 26 28 30 32 34 36 38 40
18
16
I 1 1 1 1 1 I I 1 I I 1 1 I I I I I I ! ! I 1 ! I 1
7.
10
IYYYYYYYYYY.
V-4 V-3 V-5 V-6 V-10
16itR/h
V-13
15-16 15-16 16-18 15-17 15-16 V-11
2( 14-16 •••N ZYYYY.G ^:-/7^YYQYYYYYY:Y<> j-'YY:
oc [•:••• V-2 CO
^MM'^M^ 10 16-18 x 2< 3 14-15
ONE STORY
HOUSE W/
UNINHAB.
BASEMENT
V-7 V-9 O SHED to 15-16 16-17
V-14 DC 12
3 15-16 O 2'c U.
6-17
-mm <
. Lu
v.-.-i-.-.-. V-1 V-12
0 16-18 15-17
2C
V-8 V-15 16-17
15-16 15-17 16-17
10
•:OTO:O:O:»»>:O>:O»: 18
LEGEND
ALL DEPTHS IN ilNCHES
o
a:
14
12
10
10
20 i 10
SCALE IN FEET
i20
'ALL EXP OSU R E j R ATE'S' I N fiR/h
j (A) j ASSESSED AREA IDENjlFIER':
': \ AVERAGEjDEPTR OF ASSESSED CONTAMINATION
j..XvX.L..AREA OF ASSESSED CONTAMINANTS
h 2—1 $ POST REMEDIAL; ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION -!
" TFfGURE ;2"T";
EXTERIOR ^EXTENT OF CONTAMINATION
40 12 AVERAGE iEXCAVATED DEPTH: FOR THE DEPOSIT:
OF ICONTAMINATJON
: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' UNO' SURVEY PLAt; UTiLltY LOCATION PLAY.' QR OtHEK'
IMPROVEMENT SURVEY PLAT AND IS NOT TO SE RELIED UPON :
•FOR THC ESTABLISHMENT OF FENCE. BUILDING, OR OTHER
:FUTURE IMPROVEMENT LINES.
V-1
16-17
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE—RATE RANGE
RDC): POST REMEDIAL: ACTION RADON DECAY-PRODUCT
CONCENTRATION MEASUREMENT LOCATION
ASSESSED CONTAMINANTS NOT FOUND AT
TIME OF REMEDIAL ACTION
J I I I I L
12 14 16
J L
18 20
1 J L
22
1
24 J i i L
RESIDENCE—NO. OF OCCUPANTS
NON-RESIDENCE-MAN-HRS.'WK.
Br CK. A.E. APP. NO. DATE BY CK. A.E. APP.
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE, COLORADO
INSTRUMENT NO. SURVEYOR
SURVEY DATE
VERIFICATION
26 28 30
^CHECKED:
"KLU
JPROJ. ENG..
SUBMITTED:
32
5& 64 EAST FOURTH SOUTH STREET
MONTICELLO, UTAH
Geotech, Inc.
~34
APPROVAL DOE
MS-00156-RS
"3-B00156-G4.MT 1 0F 1
36
16
14
12
38 /in
DOE ID No.: MS-00156-RS
Property Address: 64 East Fourth South 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] [ ]
[ ]
[ ]
[ ]
[ ]
[ ]
[ ]
W [ ]
[J0 [ ]
[X] [ ]
[ ] [Jd
[VI [ ]
[ ]
[ ]
[ ]
[ ]
[ ]
[ ]
°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-00156-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.
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.
Date
Manager, Monticello Programs
MACTEC-ERS
DOE Evaluation
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
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00163-CS
ADDRESS: 264 EAST CENTER STREET
MONTICELLO, UTAH 84535
MARCH 1992
Prepared for
Decontamination and Decommissioning Program
Division of Facilities and Site Decommissioning
Department of Energy
{ l/.AP. 27 139?.
RECORDS MANAGEMENT
by
Chem-Nuclear Geotech, Inc.
P.O. Box 14000
Grand Junction, Colorado 81502-5504
Perrv' Harry^ft. 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-00163-CS:PCR-291
SFOCPLRPTS SFMS-00163
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-00163-CS
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-00163-CS
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
MS-00163-CS
Beginning 120 feet west of the NE corner, Lot 4, Block 21; south
124.0 feet, east 120.0 feet, south 11.0 feet, west 120.0 feet, south
69.9 feet, west 94.5 feet, north 104.9 feet, west 10.0 feet, north
100.0 feet, east 104.5 feet to beginning, City of Monticello, County of
San Juan, State of Utah
Property Address:
Property Owners:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
264 East Center Street
Monticello, Utah 84535

Commercial Structure (CS)
Not applicable; spillover inclusion
requested by the Remedial Action
Contractor
June 26, 1987
Chem-Nuclear Geotech, Inc.
April 23, 1990
Sonderegger Construction, Inc.
P.O. Box 6
Monticello, Utah
August 9, 1990
August 29, 1990
Interior: 0 cubic yards
Exterior: 37 cubic yards
120 square meters (m2)
March 1992
2
DOE ID NO.: MS-00163-CS
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of exterior residual
radioactive material (Appendix Figure 2.1). Once excavation was
complete, the affected areas were resurveyed for possible remaining
residual radioactive material and, upon attaining satisfactory
results, were backfilled with uncontaminated material. The property
was restored to a condition comparable to that which existed prior
to remedial action activities.
2.2 Previously Unidentified Contamination
The original radiological assessment identified 19 cubic yards of
contamination, 6 inches deep, within the property. The remedial
action process included the removal of approximately 37 cubic yards
of residual radioactive material, ranging from 8 inches to 10 inches
deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix
Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities 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-00163-CS
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by Chem-Nuclear
Geotech, Inc., during October 1989, as described in the final
REA dated April 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 12 microroentgens per
hour (pR/h) to 21 pR/h (Appendix Figure 2.1). The results of
analyses for radium-226 in two composite soil samples were
0.9 picocurie per gram (pCi/g) and 1.9 pCi/g (Appendix
Table 3.1).
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on measurements representing annual averages, the
RDCs were 0.0181 Working Level (WL) for Building 1, and
0.0046 WL for Building 2 (Appendix Table 3.2). Appendix
Figure 2.1 shows the measurement locations on the ground
floors (the lowest habitable level of each structure). RDC
measurements were not taken in Building 3 due to excessive
ventilation caused by open bay doors; therefore, the building
was verified according to exterior standards.
4
DOE ID NO.: MS-00163-CS
3 .2 Recommendation for Certification
Residual radioactive materials have been removed from this property
to the extent required by the EPA standards (40 CFR 192.12,
192.20-23), as indicated in the Certification Data Summary below.
Therefore, the property located at 264 East Center 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 uR/h
above background.*
Range was 12 /iR/h to
14 uR/h for the ground
floors of both
Building 1 and
Building 2.
Radon Decay-Product
Concentration:
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Annual averages
0.0181 WL for
Building 1 and
0.0046 WL for
Building 2.
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.
< 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 m*.
The soil sample results
were 0.9 pCi/g and
1.9 pCi/g.
*The background exposure rate is approximately 14 pR/h.
**The background radium-226 concentration is approximately'2.0 pCi/g.
5
DOE ID NO.: MS-00163-CS
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-00163-CS
Address: 264 East Center 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 15 - 21 NAF 327 1.9 ± 0.3 19.3 ± 4.1 0.9 ± 0.3
V-2 15 - 20 NAF 328 0.9 ± 0.2 21.0 ± 4.3 0.8 ± 0.3
See Appendix Figure 2.1 for the verification areas.
7
Table 3.2
Radon Decay-Product Concentration (RDC) Measurement Results
DOE ID No.: MS-00163-CS
Address: 264 East Center 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)
Building 1
3160914
3160971
3169120
12-12-90
12-12-90
12-12-90
01-07-92
01-07-92
01-07-92
30.8
31.6
33.0
3.50
3.60
3.76
0.0175
0.0180
0.0188
Building 2
Annual Average: 0.0181
3169170
3169145
3169090
12-12-90
12-12-90
12-12-90
01-07-92
01-07-92
01-07-92
7.8
8.7
8.3
0.87
0.96
0.93
0.0044
0.0048
0.0047
Annual Average: 0.0046
See Appendix Figure 2.1 for the measurement locations.
MM-VPF:03-17-92
MS-00163-CS:PCR-291 WS 5.5
REV051791
8
22 24
~i—r
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BUILDING 3 :
.STORY WAREHOUSE
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THIS DRAWINC. PREPARED FOR THE'DECONTAMINATION AND
bECOUUBSIONINO PROCRAU. IS FOR THC SOLE USE PF THE
U.S. OEPARTUENT. OF ENERCY AND ITS CONTRACTORS. IT IS
..HPT. A.UM SW«VST. PWT.i im«Tr. VOCATION XUSI..«! .«WWi
IUPROVEUENT SURVEY PLAT AND IS. NOT TO BE RELICS UPON
TOR THE:CSTABUSHUEHT OF rcNCC, SUILDING. OR OTHER
p)TURC yjPROVtyCNT LINES. j •
24 26 28 30 32
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Ali DEPTHS IN:lNCHE'S
"ALE. EXPOSURE!RATES IN "IIK/H" "\;;
ASSESSED AREA IDENTIFIER:
AVERAGE;DEPTH) OF ASSESSED CONTAMINATION
\...AR^.0F.|^.S.MSEP..CS0.NIA*jjNAI*Ti5 | j
12-15 POST REMEDIAL; ACTION EXPOSURE-RATE RANfcE
!••• BOUNDARY OF EXCAVATION •! I j I
46 48 50_|_
12 :
v-i
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AVERAGEiEXCAVATED PEPTW FOR THE DEPOSIT;
P.f. N.TAM IN AT;10 N j • j : :
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE-RATE RANGE
POST REMEDIAL- ACTION P^DON DECAY—PRODUCT!
CONCENTRATION MEASUREMENT LOCATION
ASSESSED CONTAMINANTS NOT FOlIND AT I i
TIME OF REMEDIAL ACTION :
PORTION lOF SHED REMEDIATED UNDER MS-O0200-CS
:ui
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§6
U.S. DEPARTMENT OF ENERGY
C»«NP JUNCTION MOjf CTS OFttCl COIMADO
264 EAST CENTER STREET
MONTICELLO. UTAH
Gaotach, Inc.
HI «MO
""""5-C00163-IIH.,., f,
US-O0163-CS
40 42 44 46 48 50
S330-OI
DOE ID No.: MS-00163-CS
Property Address: 264 East Center Street
Vicinity Property Certification Summary and Recommendation
Summary Evaluation
Certification Criteria MACTEC-ERS
U.S. Department
of Energy (DOE)
Ra-226 is < 5 pCi/g above
background in top 15-cm-thick layer of
soil averaged over 100 m2
In situ [X] Lab [ ]
Ra-226 is < 15 pCi/g above
background in any 15-cm-thick layer
of soil more than 15 cm below the
surface averaged over 100 m2.
In situ [ ] Lab[X]
Interior gamma is <; 20 pR/h above
background in any occupied or
habitable structure.
The radon decay-product
concentration in any occupied or
habitable structure is < 0.02 WL or, at
most, 0.03 WL.
Supplemental standards were applied
in accordance with EPA standard
40 CFR 192.21.
Hot spot criteria met as outlined by
DOE guidelines for FUSRAP
(Rev.2, March 1987)
Yes No Not Taken Yes No Not Taken
[X]a [ ]
[X] [ ]
[X] [ ]
[X] [ ]
[ ] [X]
[X] [ ]
[ ]
[ ]
[ ]
[ ]
[ ]
[ ]
[*] [ ]
[K\ I ]
[*! [ ]
[X [ ]
[ ]
[ ]
[ ]
[ ]
[ ] [ ]
DO [ ] [ ]
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.
1 of 2
DOE ID No.: MS-00163-CS
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.
6 Bcnael C. Butherus
Manager, Monticello Programs
MACTEC-ERS
r Date
DOE Evaluation
On the basis of the Property Completion Report evaluation, this property
[Y] Should be certified by DOE.
[ ] Should be certified by DOE with the concurrence of the U.S. Nuclear Regulatory
Cornmission because supplemental standards were applied according to 40 CFR 192.21.
4/* 1 A/SJ n
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
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00191-RS
ADDRESS: 165 SOUTH SECOND EAST STREET
MONTICELLO, UTAH 84535
APRIL 1992
Prepared for
Decontamination and Decommissioning Program
Division of Facilities and Site Decommissioning
Department of Energy
APR 2-1 1992
by
Chem-Nuclear Geotech, Inc.
P.O. Box 14000
RECORDS MANAGEMENT Grand Junction, Colorado 81502-5504
Harr
Pr
Perry
Jram 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-00191-RS:PCR-292
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-00191-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-00191-RS
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
MS-00191-RS
Beginning 114.5 feet north of the SW corner of Lot 2, Block 20; north
100 feet, east 145.0 feet, south 60.0 feet, west 75.0 feet, south
40.0 feet, west 70.0 feet to point of beginning, City of Monticello,
County of San Juan, State of Utah
Property Address:
Property Owner:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
165 South Second East Street
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
October 23, 1989
Chem-Nuclear Geotech, Inc.
June 26, 1990
Sonderegger Construction, Inc.
P.O. Box 6
Monticello, Utah
September 11, 1990
October 5, 1990
Interior: 0 cubic yards
Exterior: 135 cubic yards
407 square meters (m2)
April 1992
2
DOE ID NO.: MS-00191-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 81 cubic yards of
contamination, 6 inches deep, within the property. The remedial
action process included the removal of approximately 135 cubic yards
of residual radioactive material, 10 inches deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix
Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities 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-00191-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 1989, as described in the final
REA dated June 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 12 microroentgens per
hour (pR/h) to 19 pR/h (Appendix Figure 2.1). The results of
analyses for radium-226 in five composite soil samples ranged
from 2.2 picocuries per gram (pCi/g) to 5.2 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 0.0093 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-00191-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 165 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.
Certification Data Summary
Applicability Standards Survey Results
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Shall not exceed 20 /jR/h
above background.*
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Range for the basement
was 12 AiR/h to 14 /iR/h.
Annual average
0.0093 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 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 m1.
< 5 pCi/g above
background.
The soil sample results
ranged from 2.2 pCi/g
to 5.2 pCi/g.
*The background exposure rate is approximately 14 pR/h.
**The background radium-226 concentration is approximately 2.0 pCi/g.
5
DOE ID NO.: MS-00191-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-00191-RS
Address: 165 South Second 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 (pR/h) Ticket No. (pCi/g) (pCi/g) (pCi/g)
V-l 15 - 19 NAE 241 4.3 ± 0.6 19.4 ± 4.2 1.0 ± 0.3
V-2 15 - 19 NAE 242 4.0 ± 0.6 21.2 ± 4.4 1.2 ± 0.3
V-3 15 - 18 NAE 243 4.5 ± 0.7 20.6 ± 4.3 1.0 ± 0.3
V-4 15 - 18 NAE 244 5.2±0.7 19.8 ± 4.2 0.9+0.2
V-5 15 - 18 NAE 245 2.2 ± 0.4 19.3 ± 4.2 0.9 ± 0.2
See Appendix Figure 2.1 for the verification areas.
7
Table 3.2
Radon Decay-Product Concentration (RDC) Measurement Results
DOE ID No.: MS-00191-RS
Address: 165 South Second East 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)
3160932 12-12-90 01-07-92
3160889 12-12-90 01-07-92
3160905 12-12-90 01-07-92
16.7 1.88 0.0094
17.1 1.92 0.0096
15.7 1.76 0.0088
Annual Average: 0.0093
See Appendix Figure 2.1 for the measurement location.
MM-VPF:04-06-92
MS-00191-RS:PCR-292 WS 5.5
REV051791
8
— •-•(/)
to
i—i—r
14-161
14-16 ONE STORY
FRAME W/
BASEMENT'
12-14
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15-18
14-16
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;SHED<
12-14
14-16
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\ « I • I * / *
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s* %*»•»• i •
V-5
0 15-18 A V
V-4 10
15-18
V-2
15-19
SCALE- fN FEET
TO 20' '40"
NORTH ;
J L
' THIS DRAWING, PREPARED f OR THE: DECONTAMfNAf ION AND ":
DECOMMISSIONING PROGRAM. IS FOR THE SOLE USE OF THE :
U.S. DEPARTMENT! OF ENERGY AND fTS CONTRACTORS. IT IS ':
NOT A LAND SURVEY PLAT,: UTILITY LOCATION PLAT, OR OTHER
' IMPROVEMENT SURVEY PLAT AND' \$ NOT TO' B£ RELlEO' UPON:'
FOR THE ESTABLISHMENT OF FENCE, BUILDING, OR OTHER
FUTURE jMPROVEjlENT LINp. j j j
30 32
LjEGENP,
ALli DEPTHS IN ilNCHES
" ALL, EXPOSURE :RATES IN /iR/h\:""
; 0! ASSESSED AREA IDENTIFIER!
; \ AVIRAGE;DEPTH OF ASSESSED CONTAMINATION
..!;!;!;!;! .j.... AR EA OF. ASSESSED. CONTAMINANTS.; j j...
12-15 POST REMEDIAL; ACTIO;N EXPOSURE-RATE RAN&E
]-—**]....BOUNDARY OF EXCAVATION I i
12 AVERAGE TXCAVATED DEPTH: FOR THE DEPOSIT:
OF 00 NTA MIN AT3 0 N ;';;;;
VERIFICATION SOIL SAMPLE AREA TDENTIFIER I
AN P .EXCAVATION EXPOSURE-RATE RANGE
POST REMEDIAL; ACTION RADON DECAY-PRO DUCT
CONCENTRATION MEASUREMENT LOCATION
ASSESSED CONTAMINANTS NOT FOUND AT
TIM.-E OF REMEDIAL ACTION ':
RADIOS
; EXTERIOR EXTENT OF CONTAMINATION
NON-RE SIDENCE-MAN-HRS.'WK.
INSTRUMENT NO. SURVEYOR
SURVEY OATE
VERIFICATION
A.E. APP. NO. DATE A.E. APP.
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE. COLORADO
165 SOUTH SECOND EAST ST.
MONTICELLO, UTAH
£ Geotech, Inc.
14 16 18 26
APPROVAL DOE
DOETOHO MS-UU191-KS
DWG.N<3_B00191_G4 1 1
30 32
28
26
24
22
20
18
16
12
36
DOE ID No.: MS-00191-RS
Property Address: 165 South Second 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] [ ]
[ ] [X]
[X] [ ]
[ ]
[ ]
[ ]
[ ]
[ ]
[ ]
[X] [ ]
M [ I
[<*] [ ]
[X] [ ]
[ ] [>]
[ ]
[ ]
[ 1
[ ]
[ ]
[*] [ ] [ ]
''The excavations were backfilled with materials that were measured at the source indicating that the Ra-226
concentrations are in the range of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
1 of 2
DOE ID No.: MS-00191-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
[X] Should be certified by DOE.
[ ] Should be certified by DOE with the concurrence of the U.S. Nuclear Regulatory
Commission because supplemental standards were applied according to 40 CFR 192.21.
Date n
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 i i m 1/
<- 5 lb33
PROPERTY COMPLETION REPORX
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00088-RS
ADDRESS: 433 SOUTH FIRST EAST STREET
MONTICELLO, UTAH 84535
JULY 1992
Prepared for
Decontamination and Decommissioning Program
Division of Facilities and Site Decommissioning
Department of Energy
JUL 2 1992 'i|
RECORDS MA!
by
Chem-Nuclear Geotech, Inc.
P.O. Box 14000
Grand Junction, Colorado 81502-5504
Harrj^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-00088-RS:PCR-282
SFOCPLRPTS SFMS-00888
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 ... 5
3.2 Recommendation for Certification 6
4.0 APPENDIX 7
DOE ID NO.: MS-00088-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.
i
DOE ID NO.: MS-00088-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-00088-RS
Parcel Number M-7, Block 2, City of
Monticello, County of San Juan, State
of Utah
433 South First East Street
Monticello, Utah 84535

Residential Simple (RS)
Not applicable: historical inclusion
by the Department of Energy
January 27, 1984
Chem-Nuclear Geotech, Inc.
June 9, 1986
Bayless and Bayless, Inc.
1900 St. Charles Road
Pueblo, Colorado
April 26, 1989
June 12, 1989
Interior: 32 cubic yards
Exterior: 2,704 cubic yards
5,031 square meters (ma)
July 1992
DOE ID NO.: MS-00088-RS
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of interior and exterior
residual radioactive material (Appendix Figure 2.1). Once
excavation was complete, the affected areas were resurveyed for
possible remaining residual radioactive material and, upon attaining
satisfactory results, were backfilled with uncontaminated material.
The property was restored to a condition comparable to that which
existed prior to remedial action activities.
2.2 Previously Unidentified Contamination
The original radiological assessment identified 2,171 cubic yards of
contamination, ranging from 3 inches to 15 inches deep, within the
property. The remedial action process included the removal of
approximately 2,736 cubic yards of residual radioactive material,
ranging from 6 inches to 56 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.
7
DOE ID NO.: MS-00088-RS
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
Radiological surveys were conducted by Bendix Field
Engineering Corporation, during April 1984 and October 1985,
as described in the final REA dated June 1986. 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 exterior excavation were collected. These samples
were blended to form composite samples representing the
exterior verification areas (Appendix Figure 2.1).
Interior Findings: Surface exposure-rate values, determined
during the gamma scan, ranged from 13 microroentgens per
hour (pR/h) to 24 pR/h for the remediated crawl space,
and 13 pR/h to 19 pR/h for the ground floor (Appendix
Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined
during the gamma scan, ranged from 13 juR/h to 35 pR/h
(Appendix Figure 2.1). Residual radioactive material was
left in place in Areas V-6 through V-9, and V-59 to avoid
causing permanent damage to mature trees. The results of
analyses for radium-226 in composite soil samples of these
areas ranged from 11.8 picocuries per gram (pCi/g) to
24.7 pCi/g. The 100 m2 area averages ranged from 3.1 pCi/g
to 6.1 pCi/g (Appendix Table 3.1). Residual radioactive
material was left in place in Area V-58 to avoid structural
damage to the shop foundation. The result of analysis for
radium-226 in a composite soil sample of this area was
18.0 pCi/g. The 100 m2 area average was 2.4 pCi/g (Appendix
Table 3.1). Areas V-6 through V-9, V-58, and V-59 also met
the hot spot criteria (Appendix Table 3.2). The results of
analyses for radium-226 in 60 remaining composite soil
samples ranged from 1.2 pCi/g to 15.1 pCi/g (Appendix
Table 3.3).
A
DOE ID NO.: MS-00088-RS
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on measurements representing an annual average, the
RDC was 0.0029 Working Level (WL), as indicated in Appendix
Table 3.4. Appendix Figure 2.1 shows the measurement
location on the ground floor (the lowest habitable level of
the structure). The partial basement was uninhabitable.
c
DOE ID NO.: MS-00088-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 First East Street, j.n
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.*
Ranges were 13 fjR/h
to 24 /jR/h for the
remediated crawl space,
and 13 uR/h to 19 yR/h
for the ground floor.
Radon Decay-Product
Concentration:
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Annual average
0.0029 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.
The soil sample results,
averaged over 100 m2
areas, ranged from
2.4 pCi/g to 4.4 pCi/g.
The soil sample results
ranged from 1.2 pCi/g
to 15.1 pCi/g. Another
soil sample result,
averaged over a 100 m2
area, was 6.1 pCi/g.
*The background exposure rate is approximately 16 fiR/h.
**The background radium-226 concentration is approximately 2.0 pCi/g.
DOE ID NO.: MS-00088-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 Interior and Exterior Extent of Contamination
RADIOLOGICAL AS-BUILT
7
Table 3.1
Calculations of Average Radium Concentrations Over 100 m2 Areas
DOE ID No.: MS-00088-RS
Address: 433 South First East Street, Monticello, Utah
Where:
(cp x Ap) + (Cr x (1,076 - Ap)]
Cavg ~
1,076
Ca = Radium-226 concentration in pCi/g averaged over a 100 m2
(1,076 ft2) area.
Cp = Radium-226 concentration in pCi/g of the residual radioactive
material left in place.
Ap = Area in ft2 of the residual radioactive material left in place.
Cr = Radium-226 concentration in pCi/g for the remainder of the
100 m2 area, including excavated and unexcavated areas.
1,076 = Total area in ft2 over which the EPA guideline is applied.
Meas./ Depth Cp Ap Cr Cfivg EPA
Sample Interval Standard
Area Type* (Inches) (pCi/g) (ft2) (pCi/g) (pCi/g) (pCi/g)
V-6 SS 00 -
V-7 SS 00 -
V-8 SS 00 -
V-9 SS 00 -
V-58 SS 00 -
V-59 SS 06 -
06 11.9 128
06 11.8 25
06 14.0 90
06 13.2 105
06 18.0 30
12 24.7 88
3.4** 4.4 7.0
4.2** 4.4 7.0
3.5** 4.4 7.0
2.0*** 3.1 7.0
2.0*** 2.4 7.0
4.4**** 6.1 17.0
Therefore, the averaged radium-226 concentrations do not exceed the EPA
standard.
*SS = Soil Sample
**Areas V-6, V-7, and V-8 were averaged in the same 100 ma area, based on
833 ft2 of background area at 2.0 pCi/g.
***Background radium-226 concentration.
****Weighted average, based on 630 ft2 of Area V-65 at 5.4 pCi/g, 130 ft2 of
V-54 at 2.4 pCi/g, 90 ft2 of V-61 at 2.8 pCi/g, and 138 ft2 of V-10
at 2.5 pCi/g.
Table 3.2
Hot Spot Calculation Results
DOE ID No.: MS-00088-RS
Address: 433 South First East Street, Monticello, Utah
shg = tSg x (10° / A> 1 + Bko
Where:
Sfig = Hot Spot Limit of radium-226 concentration in pCi/g.
Sg = Authorized Limit of radium-226 concentration in pCi/g
(S = 5.0 pCi/g for surface soil and 15.0 pCi/g for
subsurface soils).
100 = Total area in m2 over which the Hot Spot Limit guideline is
applied.
A = Area in m2 of the hot spot.
Bkg = Background radium-226 concentration in pCi/g (Bkg = 2.0 pCi/g for
Monticello).
Meas./ Depth A Sg Sfig Radium-226 in
Sample Interval Hot Spot Area
Area Type* (Inches) (m2) (pCi/g) (pCi/g) (pCi/g)
V-6 SS 00 - 06 11.89 5.0 16.5 11.9
V-7 SS 00 - 06 2.32 5.0 34.8 11.8
V-8 SS 00-06 8.36 5.0 19.3 14.0
V-9 SS 00 - 06 9.75 5.0 18.0 13.2
V-58 SS 00 - 06 2.79 5.0 31.9 18.0
V-59 SS 00 - 12 8.18 15.0 54.4 24.7
Therefore, the radium-226 concentrations in the hot spot areas do not exceed
the Hot Spot Limits.
*SS = Soil Sample
q
Table 3.3
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00088-RS
Address: 433 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)
EXTERIOR
V-l
V-2
V-3
V-4
V-5
V-6*
V-7*
V-8*
V-9*
V-10
V-ll
V-12
V-13
V-14
V-15
V-16
V-17
V-18
V-19
V-20
V-21
V-2 2
V-2 3
16
16
16
18
17
18
19
18
19
13
13
13
16
15
17
17
15
15
15
15
21
17
16
21
22
26
26
26
35
24
24
24
19
18
24
24
26
24
22
22
21
26
18
26
24
22
MNK 266
MNK 267
MNK 268
MNK 269
MNK 270
MNK 251
MNK 252
MNK 253
MNK 255
MKQ 500
MNK 273
MNK 274
MNK 275
MNK 302
MNK 303
MNK 304
MNK 305
MNK 306
MNK 307
MNK 308
MNK 325
MNK 376
MNK 377
1.5
3.3
7.6
8.5
7.7
11.9
11.8
14.
13,
2.5
1.4
1.7
3.8
1.2
14.5
11.3
4.0
0.3
0.5
1.1
1.3
1.2
1.8
1.7
2.1
1.9
0.4
0.3
0.9
0.5
0.7
0.8
0.8
0.6
0.3
0.6
0.3
2.2
1.7
0.6
17.2
16.4
17.4
19.1
8.8
13.1
14.8
14.9
15.6
14.9
15.7
16.6
17.0
17.6
17.3
16.4
15.9
14.9
13.6
17.2
20.0
19.3
6.0
3.0
2.9
3.0
3.2
3.3
2.5
2.8
2.9
2.8
4.2
4.1
3.9
3.9
1.0
1.0
1.2
0.9
0.9
0.9
1.1
0.7
0.5
1.4
1.2
0.8
1.1
1.3
0.2
0.3
0.3
0.2
0.2
0.2
0.3
0.2
0.3
0.2
0.3
0.3
0.2
0.3
0.3
0.2
0.3
0.3
0.3
•Composite soil sample of residual radioactive material left in place.
10
Table 3.3 (continued)
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00088-RS
Address: 433 South First East Street, Monticello, Utah
Area
Exposure-Rate
Range (pR/h)
Soil Sample
Ticket No.
Radium-226
(pCi/g)
Potassium
(pCi/g)
Thorium
(pCi/g)
V-2 4
V-2 5
V-2 6
V-2 7
V-2 8
V-29
V-30
V-31
V-32
V-33
V-34
V-35
V-3 6
V-37
V-3 8
V-3 9
V-40
V-41
V-42
V-43
V-44
V-45
V-46
16
16
20
20
13
22
20
17
14
20
18
16
14
14
13
13
13
1.3
13
13
14
16
18
24
24
26
26
24
24
24
22
22
24
22
22
21
18
22
21
17
20
18
20
17
21
24
MNK
MNK
MNK
MNK
MNK
MNK
MNK
MNK
MNK
MNK
MNK
MNK
MNK
MNK
MNK
MNK
MNK
MNK
MNK
MNK
MNK
MNK
MNK
378
380
381
382
383
384
385
386
387
388
389
390
391
392
409
410
411
412
413
414
415
416
417
5.0
6.7
14.3
12.8
8.6
15.1
12.4
10.4
9.
11.
9.
6.9
6.1
3
6
4
3
2.7
4.5
7.2
4.6
9.0
11.5
0.8
1.0
2.2
1.4
1.3
2.3
1.2
1.1
0.6
1.1
0.9
0.6
0.6
0.9
1.3
0.9
1.6
2.0
16.4
17.4
17.1
16.4
13.7
19.9
16.3
16.8
17.5
20.0
16.5
18.1
15.9
17.5
12.6
16.4
16.5
15.4
14.2
15.6
14.8
17.5
18.5
4.2
4.2
4.3
4.6
4.1
4.0
4.4
4.3
4.1
1.6
0.2
0.2
1.0
0.2
1.3
0.4
0.3
0.2
0.3
0.3
0.9
1.0
0.9
1.0
0.4
1.3
0.9
1.0
1.6
1.1
1.2
0.5
± 0.4
± 0.3
± 0.4
± 0.3
± 0.3
± 0.3
± 0.3
± 0.4
0.5
0.4
0.4
0.5
0.5
0.5
11
Table 3.3 (continued)
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00088-RS
Address: 433 South First East Street, Monticello, Utah
Area
Exposure-Rate
Range (pR/h)
Soil Sample
Ticket No.
Radium-226
(pCi/g)
Potassium
(pCi/g)
Thorium
(pCi/g)
V-47
V-48
V-49
V-50
V-51
V-52
V-53
V-54
V-55
V-56
V-57
V-58*
V-59*
V-60
V-61
V-62
V-63
V-64
V-65
V-66
V-67
14
16
15
16
15
13
15
14
15
16
15
18
18
15
13
13
13
13
13
13
24
24
24
22
19
19
17
19
21
24
20
21
35
18
18
18
18
18
19
18
MNK
MNK
MNK
MNK
MNK
MNK
MNK
MNK
MNK
MNK
MNK
MNK
MNK
MNK
MNK
MNK
MNK
MNK
MNK
MNK
418
419
420
421
422
423
424
425
426
427
428
429
430
434
435
436
437
438
439
440
11.6
10.1
4.7
7.5
4.5
4.5
3.6
2.4
4.8
7.8
3.1
18.0
24.7
8.
2.
3.
3.
4.9
5.4
3.5
2.0
1.7
0.8
1.3
0.8
0.8
0.6
0.5
0.8
1.3
0.5
2.5
3.5
1.2
0.4
0.5
0.5
0.7
0.8
0.5
16.9
19.4
17.0
16.2
15.7
15.0
16.4
16.6
17.3
12.9
19.1
18.9
17.4
20.3
19.3
18.0
17.7
19.1
16.8
15.4
4.5
4.2
3.8
3.7
3.7
3.6
3.8
3.8
3.9
3.4
3.5
3.6
3.6
3.6
3.4
3.4
3.4
3.4
3.2
3.1
0.6
1.5
0.7
1.7
1.0
0.9
0.8
1.4
1.3
0.9
1.1
0.3
0.8
1.2
1.2
1.4
1.0
1.2
1.1
1.0
0.4
0.3
0.4
0.3
0.3
0.3
0.4
0.3
0.3
0.3
0.3
0.3
0.3
0.3
0.3
0.3
0.3
0.3
13 - 24
INTERIOR
Not applicable
See Appendix Figure 2.1 for the verification areas.
•Composite soil sample of residual radioactive material left in place.
1 "5
Table 3.4
Radon Decay-Product Concentration (RDC) Measurement Results
DOE ID No.: MS-00088-RS
Address: 433 South First East Street, Monticello, Utah
Instrument Type: Terradex Radtrak® Detector
Radon Average
Detector Tracks Per Concentration Working
Number Start Date End Date mm* (pCi/1) Level (WL)
1650033 11-13-89
1652384 11-13-89
1652216 11-13-89
12-12-90 5.8
12-12-90 4.7
12-12-90 5.1
0.64 0.0032
0.51 0.0026
0.56 0.0028
Annual Average: 0.0029
See Appendix Figure 2.1 for the measurement location.
MM-JEK:11-08-91
MS-00088-RS:PCR-282 WS 5.5
REV051791
13
28 22 24 26 3? 34 30 36 38
V-64 V-60 V-6 V-58 V-6S
15-18 3-18 18-35 18-35 18-21 13-19
Si
SOUTH FIRST EAST STREET
V-61 V-10 12 14 16 12 tf-66 13-18 13-19 12 13-16
Es V-61
15-19 h2 13-18 2 V-57 18 12 BX3)-*0:--15-20
13-19
V-54 14 RDC U-19 SHOP 33 \F ONE STORY
.. HOUSE W/
UNINHABIT. UNINHABIT
PARTIAL
BASEMENT
V-25 4 V-56 V-62
16-24 16-24 13-18 18
• c.: 14 V-53 SEE DETAIL A 12 X -j; METAL' .
0)02))'.'.SHED,*.':
r< '. ':' ..'.''
EX12 15-17
:.\ .:.
V-28 V-63 18
13-2* 13-16 ;.'. .V.' V-52
V-27 13-19 12 12
20-26
GX15 V-55 12 0 12
15-21
V-26 V-39 12 :.12
12 20-26 13-21
V-9 V-3B 14
19-24 13-22
V-40
13-17 V-51
15-19 17 :• 17
V-33 V-29
17 20-24 22-24
V-42 V-35 V-44
17 : 13-18 14-17 16-22
17 : 17
V-41 V-30 V-43
13-20 20-24
13-20
V-34
17 17 18-22
V-SO 17
16-22
V-31 V-47 V-36 17 17
7-22 4-24 14-21
V-46
V-45 18-24
16-21
V-32 V-37 V-49 17
14-22 14-1E 15-24
17 • 17
V-48
16-24
THIS DRAWINC. PREPARED rOR THE DECONTAMINATION AND •
DECOMMISSIONINS PROCRAU. IS FOR THE SOLE USE OF THE U.S.
DEPARTMENT Of: ENERGYiAND nS iCONTRACTORS. II IS NOT:
A LAND: SURVEY :PLAT. UTJUTY LOCATION PLAT, OR OTHER
IMPROVEMENT SURVEY PLAT ANO IS NOT TO BE RELIED UPOH
FOR THE ESTABLISHMENT OF FENCE. BUILDING, OR OTHER ••:
FUTURE IMPROVEMENT LINES.
42 44 46
"i—i—i—i—i—r
50 |
1 1 +
I ®£>..L
12 20 ./ 1BI.>.rrrr.«. AX3
\f. 28 26
32 16 12
CRAWL SPACE
V-67
> i • • 13-24
14 12 :
|.
BASEMENT i
(JOT TQ SCALE
LEGEND
ALL DEPTHS IN INCHES
" ALI- EXPOSURE RATES' IM" ViR/h"
ASSESSED AREA IDENTIFIER
©I AVERAGE DEPTH OF ASSESSED CONTAMINATION
,. ^-.vi .ARjEA. OF; ASSESSED ..C.O.NIAtylNAIIpN. \ j
|l2-15 POST—REMEDIAL ACTION EXPOSURE-RATE RANGE
BOUNDARY OF EXCAVATION;!j -"j
AVERAGE EXCAVATED! DEPTH FOR THE DEPOSIT OF
CONTAMINATION i i \ i i 12
VERIFICATION AREA IDENTIFIER AND
16-17| EXCAVATION EXPOSURE -RATE .RANGE...;..
: (RDC): POST—REMEDIAL ACTION RADON DECAY^PRODUCT
CONCENTRATION MEASUREMENT LOCATION
AREA WITH CONTAMINATION:LEFT IN PLACE
•i i i-
jjjj FIGU REj 2; 1 j i i i
; INTERIOR AND EXTERIOR EXTENT OF] CONTAMINATION |
•tSIMNCI-MO O* OC CURIAM t(
HIIIIIUMIll MO.
•t C«. *< «r* MO. DAT I
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFF ICC. COLORADO
433 SOUTH FIRST EAST ST.
MONTICELLO. UTAH
V~~—~~ [rare!* MS-UUUBB-KV
Geottch. Inc. t.t .e 3-CD00BB-CL, 1.
40
38
36
34
32
30
28
26
24
22
20
18
16
14
12
22 24 26 28 30 32 34 36 38 40 42 44 46 48 50
nx-M
+
DOE ID No.: MS-00088-RS
Property Address: 433 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
[XT [ ]
[X] [ ]
[X] [ ]
[X] [ ]
[ ] [X]
[X] [ ]
[ ]
[ ]
[ ]
[ ]
[ ]
[ ]
[ ]
[y] [ ]
[ ] W
[x] [ ]
[ ]
[ 3
[ 1
[ 1
[ ]
[ ]
aThe excavations were backfilled with materials that were measured at the source indicating that the Ra-226
concentrations are In the range of normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
1 of 2
DOE ID No.: MS-00088-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.
^N^cr^el C. Butherus \ 1 Date
Manager, Monticello Progra
MACTEC-ERS
DOE Evaluation
On the basis of the Property Completion Report evaluation, this property
[ X] Should be certified by DOE.
[ ] Should be certified by DOE with the concurrence of the U.S. Nuclear Regulatory
Commission because supplemental standards were applied according to 40 CFR 192.21.
<2
Certification Official
U.S. Department of Energy
IL
Date
Work performed under DOE Contract No. DE-AC13-95GJ87335, Task Order No. 96-05.02.14
2 of 2
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00193-RS
ADDRESS: 264 EAST FIRST SOUTH STREET
MONTICELLO, UTAH 84535
JULY 1992
Prepared for
Decontamination and Decommissioning Program
Division of Facilities and Site Decommissioning
Department of Energy
by
9 AQQ? \\\ Chem-Nuclear Geotech, Inc.
' ' P.O. Box 14000
1L_- - —~-.r Grand Junction, Colorado 81502-5504
RECORDSMftW
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-00193-RS:PCR-295
SFOCPLRPTS
SFMS-00193
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-00193-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-00193-RS
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
MS-00193-RS
Parcel No. M-166-1 - Beginning at the northwest corner of Lot 3,
Block 20, east 122.5 feet for the point of beginning; east 70.0 feet,
south 114.5 feet, west 70.0 feet, north 114.5 feet to beginning, City of
Monticello, County of San Juan, State of Utah
Property Address:
Property Owner:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
264 East First South Street
Monticello, Utah 84535

Monticello, Utah 84535
Residential Simple (RS)
Oak Ridge National Laboratory
October 23, 1989
Chem-Nuclear Geotech, Inc.
June 26, 1990
Sonderegger Construction
P.O. Box 6
Monticello, Utah
September 11, 1990
September 26, 1990
Interior: 0 cubic yards
Exterior: 112 cubic yards
336 square meters (m2)
July 1992
2
DOE ID NO.: MS-00193-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 90 cubic yards of
contamination, ranging from 6 inches to 12 inches deep, within the
property. The remedial action process included the removal of
approximately 112 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-00193-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 1989, as described in the final
REA dated June 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 12 microroentgens per
hour (pR/h) to 20 /i/R/h (Appendix Figure 2.1). The results of
analyses for radium-226 in four composite soil samples ranged
from 2.4 picocuries per gram (pCi/g) to 4.8 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 0.0068 Working Level (WL), as indicated in Appendix
Table 3.2. Appendix Figure 2.1 shows the measurement
location on the ground floor (the lowest habitable level of
the structure).
4
DOE ID NO.: MS-00193-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 264 East First 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 fiR/h
above background.*
Range for the ground
floor was 12 juR/h to
14 piR/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
0.0068 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 2.4 pCi/g
to 4.8 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-00193-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-00193-RS
Address: 264 East First 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 (juR/h) Ticket No. (pCi/g) (pCi/g) (pCi/g)
V-l 17 - 20 NAE 250 4.3 + 0.6 20.4 ± 4.4 1.3 ± 0.3
V-2 17 - 20 NAH 448 4.8 ± 0.7 21.1 ± 4.5 1.1 ± 0.3
V-3 15 - 20 NAH 449 2.4 ± 0.4 20.9 ± 4.4 0.9 ± 0.3
V-4 15 - 20 NAH 450 3.4 ± 0.5 19.4 ± 4.3 1.1 ± 0.3
See Appendix Figure 2.1 for the verification areas.
Table 3.2
Radon Decay-Product Concentration (RDC) Measurement Results
DOE ID No.: MS-00193-RS
Address: 264 East First 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)
3246233 03-11-91 03-13-92
3246172 03-11-91 03-13-92
3249979 03-11-91 03-13-92
14.3 1.45 0.0073
11.4 1.15 0.0058
14.3 1.45 0.0073
Annual Average: 0.0068
See Appendix Figure 2.1 for the measurement location.
MM-JEK:05-18-92
MS-00193-RS:PCR-295 WS 5 . 5
REV051791
8
28 -
26
24
22
20
18
16
14
12
i—r i—i—i—r
OH J8
i—r i—i—i—i—r
EAST FIRST SOUTH STREET'
.///•
ILL.
LEGEND
ALL DEPTHS IN INCHES
ALL .-EXPOSURE RATES IN uR/\\
ASSESSED! AREA ^IDENTIFIER . \
AVERAGE DEPTH iOF ASSESSES) CONTAMINATION j
AREA OF ASSESSED CONTAMINATION
POST—REMEDIAL! ACTIOjN EXPOSURE-RATE RANGE
BOUft D AR Y: OF E j( C AVAliON : !
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION :
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
EXCAVATION: EXPOSURE'^RATE'KANdE
POST-REMEDIAL':ACTIO'N RADON DECAY-PRODUCT
CONCENTRATION MEASUREMENT LOCATION
ASSESSED ^CONTAMINATION NOT FOUND AT TIME^
OF REMEDIAL ACTION
40
.....
<D 14-16
12-15
...i
12
o 13r-16
o V-1
16-17
12-16 O (RDC)
r3 i V-1
O 17-20
:12-14
ONE STORY
FRAME HOUSE f: 12 V. RDC
Ij • OOO 14-16
V-4
15-20
V-2
12 17-20
RADIOLOGIC At AS-4-BUIUT •:•:•:!(•>:•:•; 12
• ^FIGURE ;211
10 EXTERIOR EXTENT OF CONTAMINATION
v-3 10 H 6 IE 15-20 NO. DATE REVISIONS AE APP. NO. OATE REVISIONS CK A.E. APP
RESIDENCE —NO. OF OCCUPANTS
NON-RESIDENCE—MAN-HRS. 'WK
DESIGNED
28
26
24
22
20
18
16
10
SCALE' (N' FEET Y ;
ii
40 .••20 "I "TO : 0 : 20
NORTH;
J l
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 |S
NOT A LAND SURVEY PLAT, UTILITY LOCATION PLAT, OR OTHER
IMPROVEMENT SURVEY PLAT AND IS NOT TO BE RELIED UPON
FOR THE ESTABLISHMENT OF FENCE, BUILDING, OR OTHER
FUTURE IMPROVEMENT LINES.
I I I I I I
10 12 14 16 18 20
J_
22
J J-
24
1 _L_
26
J L
28
INSTRUMENT NO. SURVEYOR
SURVEY DATE
VERIFICATION
14
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE, COLORADO
wm
SUBMITTED:
30 32 34
264 EAST FIRST SOUTH ST.
MONTICELLO, UTAH .
12
Geotech. Inc.
APPROVAL DOE
MS-00193-RS
'° NC3-B00193-G4S»T1 ™1
36 38 40 +
DOE ID No.: MS-00193-RS
Property Address: 264 East First South Street
Vicinity Property Certification Summary and Recommendation
Summary Evaluation
U.S. Department
Certification Criteria MACTEC-ERS of Energy (DOE)
Yes No Not Taken
[X]a [ ] [ ]
[X] [ ] [ ]
[X] [ ] [ ]
Yes No Not Taken
[X] [ ] [ ]
[/] [ ) [ ]
[yj [ ] t i
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. [X]
Supplemental standards were applied
in accordance with EPA standard
40 CFR 192.21. [ ]
Hot spot criteria met as outlined by
DOE guidelines for FUSRAP
(Rev.2, March 1987) [X]
[ ] [ ] MM [ ]
[x] [ ] [ ] \y\ [ ]
[ ] [ ] [XI [ ] [ ]
"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-00193-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.
rus lael C. Buthe
Manager, Monticello Progri
MACTEC-ERS
Date
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.
il.Jizc/ id, *
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
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00192-RS
ADDRESS: 226 EAST FIRST SOUTH STREET
MONTICELLO, UTAH 84535
SEPTEMBER 1992
Prepared for
Decontamination and Decommissioning Program
Division of Facilities and Site Decommissioning
Department of Energy
EP 25 1992
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-00192-RS:PCR-300
SFOCPLRPTS SFMS-03192
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-00192-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, mill tailings from
the Monticello millsite were removed from the site and used for
construction-related activities in the vicinity.
1.2 Criteria for Remedial Action
The Decontamination and Decommissioning Program has adopted the
"Standards for Remedial Action at Inactive Uranium Processing Sites"
(40 CFR Part 192) for all cleanup activities under the MVP project.
These standards were prepared by the U.S. Environmental Protection
Agency (EPA) to establish guidelines for the control of tailings
piles and the cleanup of buildings and open lands.
This property was evaluated on the basis of the EPA standards by the
U.S. Department of Energy (DOE) Inclusion Survey Contractor. The
DOE reviewed these evaluation results and determined that the
property contained mill tailings (residual radioactive material)
exceeding the EPA standards. The Remedial Action Contractor was
notified of the inclusion of this property into the 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-00192-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-00192-RS
Parcel No. M-166; from the NW corner
of Lot 3, Block 20, east 72.5 feet
for beginning; east 50 feet, south
114.5 feet, west 50 feet, north
114.5 feet to beginning, City of
Monticello, County of San Juan,
State of Utah
226 East First South Street
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
October 23, 1989
Chem-Nuclear Geotech, Inc.
June 26, 1990
Sonderegger Construction
P.O. Box 6
Monticello, Utah
September 11, 1990
September 26, 1990
Interior: 0 cubic yards
Exterior: 59 cubic yards
209 square meters (m2)
September 1992
DOE ID NO.: MS-00192-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 radiological assessment identified 37 cubic yards of
contamination, 6 inches deep, within the property. The remedial
action process included the removal of approximately 59 cubic yards
of residual radioactive material, ranging from 6 inches to 10 inches
deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix
Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID NO.: MS-00192-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 1989, as described in the final
REA dated June 1990. Appendix Figure 2.1 shows the extent of
assessed contamination and identifies the areas recommended
to undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted
after the removal of residual radioactive material and prior
to backfilling. Following the gamma scan, soil samples
representative of the 6-inch-thick soil layer at the bottom
of the excavation were collected. These samples were blended
to form composite samples representing the verification areas
(Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined
during the gamma scan, ranged from 13 microroentgens per
hour (pR/h) to 20 pR/h (Appendix Figure 2.1). The results of
analyses for radium-226 in three composite soil samples
ranged from 2.4 picocuries per gram (pCi/g) to 5.2 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 0.0107 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-00192-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 226 East First South Street, in
Monticello, Utah, is recommended for certification as required by
the Decontamination and Decommissioning Program guidelines, and the
appropriate records should be documented.
Applicability
Certification Data Summary
Standards Survey Results
Habitable Structures
Exposure Rate: Shall not exceed 20 pR/h
above background.*
Range for the ground
floor was 12 pR/h to
14 pR/h.
Radon Decay-Product
Concentrat ion:
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Annual average was
0.0107 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.
Soil sample results
ranged from 2.4 pCi/g
to 5.2 pCi/g.
*The background exposure rate is approximately 14 pR/h.
**The background radium-226 concentration is approximately 2.0 pCi/g.
5
DOE ID NO.: MS-00192-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-00192-RS
Address: 226 East First South Street, Monticello, Utah
The analytical uncertainties in the table are reported at the 95-percent
confidence interval.
Exposure- Soil
Rate Range Sample Meas. Radium-226 Potassium Thorium
Area (PR/h) Ticket No. Method* (pCi/g) (pCi/g) (pCi/g)
V-l 17 - 20 NAE 247 AL 5.2 ± 0.8 20.8 ± 4.4 1.2 ± 0.3
V-2 17 - 20 NAE 248 AL 2.8 ± 0.5 19.7 ± 4.3 1.1 ± 0.3
V-3 17 - 20 NAE 249 AL 2.4 ± 0.4 20.4 ± 4.3 1.2 ± 0.3
See Appendix Figure 2.1 for the verification areas.
*AL = Analytical Laboratory
7
Table 3.2
Radon Decay-Product Concentration (RDC) Measurement Results
DOE ID No.: MS-00192-RS
Address: 226 East First South Street, Monticello, Utah
Instrument Type: Terradex Radtrak® Detector
Radon Average
Detector Tracks Per Concentration Working
Number Start Date End Date mm1 (pCi/1) Level (WL)
3169141 12-12-90
3160995 12-12-90
3169098 12-12-90
01-07-92 19.9
01-07-92 19.4
01-07-92 17.8
2.23 0.0112
2.18 0.0109
1.99 0.0100
Annual Average: 0.0107
See Appendix Figure 2.1 for the measurement location.
MM-SJW:08-28-92
MS-00192-RS:PCR-300 WS 5.5
REV052592
8
I I ! ! ! ! 1 1 T
•LEGEND
ALL DEPTHS IN INCHES I i
ALL; EXPOSURE RATES IN juR/h
AS$ ESS EP AREA IDENTIFIER I ! j
AVERAGEiDEPTH OF ASSESSjED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST-REjMEDIAL ACTION EXPOSURE-RATE RANGE
BOyNDARY OF EXCAVATiON
AVERAGE EXCAVATED (DEPTH
CONTAMINATION
28 30 32 34 16 18 20 24 26 22
I
EAST FIRST SOUTH :STREET
• ; : /// ® 13-15
FA-.VI
12-15
...
rz 12
\ ONE STORY
STUCCO HOUSE V-1 6 X A 16-17
(RDC) 12-14
RDC
V-3
17-20
14-16
V-2
i /? 17-20
r--
r-.; 10 . .. ..
j
NO. DATE REVISIONS
RESIDENCE—NO. OF OCCUPANTS
NON-RESIDENCE—MAN* HRS./WK
DESIGN
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, UTILITY LOCATION PLAT; OR OTHER
IMPROVEMENT SURVEY PLAT AND IS NOT TO BE RELIED UPON
FOR THE ESTABLISHMENT OF FENCE, BUILDING. ORl OTHER
FUTURE IMPROVEMENT LINES.
INSTRUMENT NO. SURVEYOR DRAWN
vr CHECKED S*3
4> PROJ. ENGTT
SUBMITTED: 40 20 SURVEY DATE TIME
NDRTH VERIFICATION DATE
22 24 26 28 20 30 3? 34 16 18
36 38 40
FOR THE DEPOSIT OF
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE-RATE RANGE
POST-REMEDIAL ACTION RADON DECAY-JPRODUCT
CONCENTRATION MEASUREMENT LOCATION
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF:REMEDIAL ACTION ; ;
RADIOLOGICAL AS-jBUILn"
EXTERIOR EXTENT OF CONTAMINATION
A.E. APP. NO. OATE
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE, COLORADO
226 EAST FIRST SOUTH STREET
MONTICELLO, UTAH
Geotech, Inc.
APPROVAL DOE
MS-00192-RS
36
^-B00199-M4SHT1 OF1
28
26
24
22
20
18
16
14
12
3fl /in 4
DOE ID No.: MS-00192-RS
Property Address: 226 East First South Street
Vicinity Property Certification Summary and Recommendation
Summary Evaluation
Certification Criteria MACTEC-ERS
U.S. Department
of Energy (DOE)
Ra-226 is s 5 pCi/g above
background in top 15-cm-thick layer
of soil averaged over 100 m2
In situ [X] Lab [ ]
Ra-226 is ^ 15 pCi/g above
background in any 15-cm-thick layer
of soil more than 15 cm below the
surface averaged over 100 m2.
In situ [ ]Lab[X]
Interior gamma is * 20 uR/h above
background in any occupied or
habitable structure.
The radon decay-product
concentration in any occupied or
habitable structure is < 0.02 WL or, at
most, 0.03 WL.
Supplemental standards were applied
in accordance with EPA standard
40 CFR 192.21.
Hot spot criteria met as outlined by
DOE guidelines for FUSRAP
(Rev.2, March 1987)
Yes No Not Taken Yes No Not Taken
[X]a [ ]
[X] [ ]
[X] [ ]
[X] [ ]
I ] [X]
[X] [ ]
[ ]
[ ]
[ ]
[ ]
[ ]
[ ]
[A] [ ]
[X] [ ]
Pi [ ]
[X] [ ]
[ ] w
[ ]
[ ]
[ ]
[ ]
[ ]
^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-00192-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 ofthe Property Completion Report evaluation, this property
[X ] Should be certified by DOE.
[ ] Should be certified by DOE with the concurrence of the U.S. Nuclear Regulatory
Commission because supplemental standards were applied according to 40 CFR 192.21.
Date
U.S. Department of Energy
Work performed under DOE Contract No. DE-AC13-95GJ87335, Task Order No. 96-05.02.14
2 of 2
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00201-RS
ADDRESS: 381 SOUTH FIRST EAST STREET
MONTICELLO, UTAH 84535
SEPTEMBER 1992
Prepared for
Decontamination and Decommissioning Program
Division of Facilities and Site Decommissioning
Department of Energy
EP 2:> 1992
by
Chem-Nuclear Geotech, Inc.
P.O. Box 14000
Grand Junction, Colorado 81502-5504
. .; _<^5*-,
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-00201-RS:PCR-300
SFOCPLRPTS SFMS-09009
TABLE OF CONTENTS
Section Pa.ae
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-00201-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, mill tailings from
the Monticello millsite were removed from the site and used for
construction-related activities in the vicinity.
1.2 Criteria for Remedial Action
The Decontamination and Decommissioning Program has adopted the
"Standards for Remedial Action at Inactive Uranium Processing Sites"
(40 CFR Part 192) for all cleanup activities under the MVP project.
These standards were prepared by the U.S. Environmental Protection
Agency (EPA) to establish guidelines for the control of tailings
piles and the cleanup of buildings and open lands.
This property was evaluated on the basis of the EPA standards by the
U.S. Department of Energy (DOE) Inclusion Survey Contractor. The
DOE reviewed these evaluation results and determined that the
property contained mill tailings (residual radioactive material)
exceeding the EPA standards. The Remedial Action Contractor was
notified of the inclusion of this property into the 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-00201-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-00201-RS
Beginning 96 feet north of the
southwest corner of Lot 2, Block 9;
east 162.5 feet, north 69.5 feet,
west 162.5 feet, south 69.5 feet to
beginning, City of Monticello, County
of San Juan, State of Utah
381 South First East Street
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
October 23, 1989
Chem-Nuclear Geotech, Inc.
July 16, 1990
Sonderegger Construction
P.O. Box 6
Monticello, Utah
August 21, 1990
September 8, 1990
Interior: 0 cubic yards
Exterior: 102 cubic yards
513 square meters (m2)
September 1992
DOE ID NO.: MS-00201-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 radiological assessment identified contamination, 6 inches deep,
within the property. The remedial action process included the
removal of approximately 102 cubic yards of residual radioactive
material, 6 inches deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix
Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID NO.: MS-00201-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
assessed contamination and identifies the areas recommended
to undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted
after the removal of residual radioactive material and prior
to backfilling. Following the gamma scan, soil samples
representative of the 6-inch-thick soil layer at the bottom
of the excavation were collected. These samples were blended
to form composite samples representing the verification areas
(Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined
during the gamma scan, ranged from 14 microroentgens per
hour (pR/h) to 25 pR/h (Appendix Figure 2.1). The results of
analyses for radium-226 in seven composite soil samples
ranged from 1.4 picocuries per gram (pCi/g) to 5.2 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 0.0013 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-00201-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 381 South First East Street, in
Monticello, Utah, is recommended for certification as required by
the Decontamination and Decommissioning Program guidelines, and the
appropriate records should be documented.
Certification Data Summary
Applicability Standards 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 was
0.0013 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.
Soil sample results
ranged from 1.4 pCi/g
to 5.2 pCi/g.
*The background exposure rate is approximately 14 pR/h.
**The background radium-226 concentration is approximately 2.0 pCi/g.
5
DOE ID NO.: MS-00201-RS
4.0 APPENDIX
Appendix Tables:
Table 3.1 Post-Excavation Sample/Measurement Results
Table 3.2 Radon Decay-Product Concentration (RDC)
Measurement Results i^w
Appendix Figure:
Figure 2.1 Exteri
AS-BUILT or Extent of Contamination - RADIOLOGICAL
6
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00201-RS
Address: 381 South First East Street, Monticello, Utah
The analytical uncertainties in the table are reported at the 95-percent
confidence interval.
Exposure- Soil
Rate Range Sample Meas. Radium-226 Potassium Thorium
Area (pR/h) Ticket No. Method* (pCi/g) (pCi/g) (pCi/g)
V-l 14 - 16 NAH 739 AL 1.4 ± 0.3 21.3 ± 3.0 1.1 ± 0.3
V-2 14 - 20 NAH 740 AL 2.4±0.4 19.8 ± 2.8 1.3 ± 0.3
V-3 14 - 17 NAH 741 AL 2.8 ± 0.4 16.7 ± 3.1 1.4 ± 0.3
V-4 15 - 18 NAH 742 AL 3.7 ± 0.5 15.6 ± 3.0 1.3 ± 0.3
V-5 15 - 25 NAE 001 AL 3.0 ± 0.5 16.3 ± 4.0 0.5 ± 0.2
V-6 15 - 21 NAE 002 AL 1.8 ± 0.3 17.0 ± 4.1 0.9 ± 0.3
V-7 17 - 25 NAE 003 AL 5.2±0.8 16.9 ± 4.1 1.1 ± 0.3
See Appendix Figure 2.1 for the verification areas.
*AL = Analytical Laboratory
Table 3.2
Radon Decay-Product Concentration (RDC) Measurement Results
DOE ID No.: MS-00201-RS
Address: 381 South First East 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)
3142021 09-12-90
3142648 09-12-90
3142046 09-12-90
09-17-91 2.6
09-17-91 1.4
09-17-91 2.7
0.30 0.0015
0.16 0.0008
0.31 0.0016
Annual Average: 0.0013
See Appendix Figure 2.1 for the measurement location.
MM-JEK:08-12-92
MS-00201-RS:PCR-300 WS 5.5
REV052592
8
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. UTILITY LOCATION^ PLAT, OR OTHER j
IMPROVEMENT SURVEY PLAT AND IS NOT TO BE RELIED UPON : •
FOR THE ESTABLISHMENT OF FENCEJ BUILDING. OR OTHER
FUTURE IMPROVEMENT LINES.
1 I I I I I 1 L
18 14 16 12 20 22 26 30 10 28 24
30
28
26
V-7 V-6 V-3 V-4
17-25 15-21 14-17 15-18
12-5
24
7 12 O
/&•:•:•:•:
RDC V-1
14-16 16-17
x<2>1 mm / •< 6 V RDC) 22
ONE STORY i
FRAME HOUSE!
; i2-i'3 1 on mm r-
•r. a • • o n CO < 20 Lu
f.--.i 14-16
in 6 y on
3 V-2 v.v. X I... r-.I. .-. 14-20 I V-l-iv.v.. 18
to I.'Y
I • :• I 1> • \V.'.\V
•I-
16 V-5 V-1
15-25 14-16
14
NO. DATE
SCALE IN FEET
12
Y
4> 2D 40 A 20
X NORT
10
32 34
1—!—r
36 38
T~~I i—r
40
LEGEND
ALli DEPTHS IN INCHES
ALL EXPOSURE ;RATES; IN /zR:/h
ASSESSED AREA IDENTIFIER"!
AVERAGE iDEPTH OF ASSESSED CONTAMINATION
AREA OF ASSES:SED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE-RATE RANGE-
BOUNDARY OF EXCAVATION
AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT'OF-
CONTAMINATION;
VERIFICATION SOIL SAMPLE AREA IDENTIFIER ••
AND EXCAVATION EXPOSURE—RATE RANGE
POST-REMEDIAL ACTIDN RADON DECAY-I PRODUCT
CONCENTRATION MEASUREMENT LOCATION
ASSESSED CONTAMINATION NOT FOUND AT TIME
,.OF:REMEDlAL ACTION ;
RADIOLOGICAL AS-BDIUT
EXTERIOR
FTGllI RE ;27T'T
EXTENT OF CONTAMINATION
REVISIONS
RESIDENCE-NO OF OCCUPANTS
NON-RESIDENCE —MAN-HRS./WK.
INSTRUMENT NO. SURVEYOR
SURVEY DATE
VERIFICATION
on 99 94
28
26
24
22
2C
16
16
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE, COLORADO
rr Hi
381 SOUTH FIRST EAST STREET
MONTICELLO. UTAH
Geotech, Inc.
DOE ID NO.
APPROVAL DOE
MS-00201-RS
DWG. NO.
96 PR 30 39 34 .36
3-B11201-G1SHT1 OF1
38 40
DOE ID No.: MS-00201-RS
Property Address: 381 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 s 0.02 WL or, at
most, 0.03 WL.
Supplemental standards were applied
in accordance with EPA standard
40 CFR 192.21.
Hot spot criteria met as outlined by
DOE guidelines for FUSRAP
(Rev.2, March 1987)
Yes No Not Taken Yes No Not Taken
[X]a [ ]
[X] [ ]
[X] [ ]
[X] [ ]
[ ] [X]
[X] [ ]
[ ]
[ ]
[ ]
[ ]
[ ]
[ ]
[XI [ I
[y] I ]
\A [ I
[X] [ ]
[ ]
[ I
[ I
[ 1
[ I [^ [ I
[4 [ 1 [ I
^he 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-00201-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.
ael C. Butherui \ Date
Manager, Monticello Programs
MACTEC-ERS
DOE Evaluation
On the basis of the Property Completion Report evaluation, this property
[y] 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
JAN 2 tty-
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00202-RS
ADDRESS: 397 SOUTH FIRST EAST STREET
MONTICELLO, UTAH 84535
SEPTEMBER 1992
Prepared for
Decontamination and Decommissioning Program
Division of Facilities and Site Decommissioning
Department of Energy
EP 25 1992 by
Chem-Nuclear Geotech, Inc.
P.O. Box 14000
Grand Junction, Colorado 81502-5504
Harr^r 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-00202-RS:PCR-301
SFOCPLRPTS SFMS-09889
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-00202-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, mill tailings from
the Monticello millsite were removed from the site and used for
construction-related activities in the vicinity.
1.2 Criteria for Remedial Action
The Decontamination and Decommissioning Program has adopted the
"Standards for Remedial Action at Inactive Uranium Processing Sites"
(40 CFR Part 192) for all cleanup activities under the MVP project.
These standards were prepared by the U.S. Environmental Protection
Agency (EPA) to establish guidelines for the control of tailings
piles and the cleanup of buildings and open lands.
This property was evaluated on the basis of the EPA standards by the
U.S. Department of Energy (DOE) Inclusion Survey Contractor. The
DOE reviewed these evaluation results and determined that the
property contained mill tailings (residual radioactive material)
exceeding the EPA standards. The Remedial Action Contractor was
notified of the inclusion of this property into the 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-00202-RS
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
Property Address:
Property Owners:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
MS-00202-RS
Beginning at the southwest corner of
Lot 2, Block 9; north 90 feet, east
100 feet, south 90 feet, west 100 feet
to beginning, City of Monticello,
County of San Juan, State of Utah
397 South First East Street
•Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
October 23, 1989
Chem-Nuclear Geotech, Inc.
July 16, 1990
Sonderegger Construction
P.O. Box 6
Monticello, Utah
August 22, 1990
September 8, 1990
Interior: 0 cubic yards
Exterior: 67 cubic yards
334 square meters (m2)
September 1992
2
DOE ID NO.: MS-00202-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 radiological assessment identified contamination, 6 inches deep,
within the property. The remedial action process included the
removal of approximately 67 cubic yards of residual radioactive
material, 6 inches deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix
Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
4
3
DOE ID NO.: MS-00202-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
assessed contamination and identifies the areas recommended
to undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted
after the removal of residual radioactive material and prior
to backfilling. Following the gamma scan, soil samples
representative of the 6-inch-thick soil layer at the bottom
of the excavation were collected. These samples were blended
to form composite samples representing the verification areas
(Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined
during the gamma scan, ranged from 13 microroentgens per
hour (/jR/h) to 21 pR/h (Appendix Figure 2.1). The results of
analyses for radium-226 in four composite soil samples ranged
from 3.0 picocuries per gram (pCi/g) to 6.5 pCi/g (Appendix
Table 3.1).
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on measurements representing an annual average, the RDC
was 0.0247 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-00202-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 397 South First East Street, in
Monticello, Utah, is recommended for certification as required by
the Decontamination and Decommissioning Program guidelines, and the
appropriate records 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 was 14 pR/h to
16 /iR/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 was
0.0247 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 mJ.
< 5 pCi/g above
background.
Soil sample results
ranged from 3.0 pCi/g
to 6.5 pCi/g.
*The background exposure rate is approximately 14 pR/h.
**The background radium-226 concentration is approximately 2.0 pCi/g.
5
DOE ID NO.: MS-00202-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-00202-RS
Address: 397 South First East Street, Monticello, Utah
The analytical uncertainties in the table are reported at the 95-percent
confidence interval.
Exposure- Soil
Rate Range Sample Meas. Radium-226 Potassium Thorium
Area (^R/h) Ticket No. Method* (pCi/g) (pCi/g) (pCi/g)
V-l
V-2
V-3
V-4
14
14
15
15
21
21
20
20
NAH 735
NAH 736
NAH 737
NAH 738
AL
AL
AL
AL
3.2 ± 0.5
6.5 ± 0.9
3.3 ± 0.5
3.0 + 0.4
20.5 ± 2.9
22.8 ± 3.2
21.5 ± 3.0
19.7 ± 2.8
0.9 + 0.3
0.9 ± 0.3
1.1 ± 0.3
0.7 ± 0.3
See Appendix Figure 2.1 for the verification areas.
*AL = Analytical Laboratory
7
Table 3.2
Radon Decay-Product Concentration (RDC) Measurement Results
DOE ID No.: MS-00202-RS
Address: 397 South First East 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)
3142012 09-12-90 09-04-91 39.1 4.93 0.0247
3142717 09-12-90 09-04-91 38.2 4.81 0.0241
3142048 09-12-90 09-04-91 40.3 5.08 0.0254
Annual Average: 0.0247
See Appendix Figure 2.1 for the measurement location.
MM-JEK:08-20-92
MS-00202-RS:PCR-301 WS 5.5
REV052592
8
11) 18 \Z 14 lb ZU ZZ Zb 24 Zti
30 I I 1 I I
V-1
14-21 28
/
r • v O
v>? 26 ? :
13-16
0 fc RDC
Lu
mm on 24
co
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ft : ONE"STORY"
FRAME-HOUSE V-2
to 6 V.-14-21
22
14-16
ZD
o CO V-3 •>.( 6 >.-3:
15-20
20 ML 3-16 l! •
6 y.w.v.-•
18
V-4
15-20
16
777
EAST FOURTH SOUTH STREET
14
SCALE IN FEET
12
Y
A
20 1.0 20: 40
NORTH; x; 10
T
THIS DRAWING, PREPARED FOR THE DECONTAMINATION AND
DECOMMISSIONING! PROGRAM. IS FOR THE SOLE USE OF THE
U.S. DEPARTMENT:0F ENERGY AND ITS CONTRACTORS; IT IS
NOT A LAUD SURVEY PLAT, UTILITY LOCATION- PLAT. OR OTHER
IMPROVEMENT SURVEY PLAT AND IS NOT TO BE RELIED UPON
FOR THE ESTABLISHMENT OF FENCE> BUILDING. OR OTHER
FUTURE IMPROVEMENT LINES.
.0.
LV.--.vj
12-15
12
V-1
16-17
oo oo
i—i—r
OtL 04
i—i—r
LEGEND
ALL DEPTHS IN INCHES
ALL EXPOSURERATES." IN fiR/h
ASSESSED AREA IDENTIFIER j
AVERAGE!DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST-REMEDIAL ACTION EXPOSURE-RATE RANGE
BO U NDARY OF EXCAVATI0 N
HU
AVERAGEiEXCAVATED DEPTH
"CONTAMINATION
VERIFICATION SOIL SAMPLE
FOR THE DEPOSIT OF
AREA IDENTIFIER ..; _
AND EXCAVATION EXPOSURE—RATE RANGE
POST-REMEDIAL ACTION RADON DECAY-*-PRO DUCT,
C b;N C E^ T R ATT6 N' M EAS U R EM E N t LD CATION
ASSESSED CONTAMINATION MOT FOUND AT TIME
OF. REMEDIAL ACTION'!
EXTERIOR
FIGURE
RADIOLOGICAL AS-BUILT
2.1
EXTENT OF CONTAMINATION
10 12 14 16 18 20 22 24 26 28
RESIDENCE-NO. OF OCCUPANTS
NON-RESIDENCE —MAN-HRS./WK
INSTRUMENT NO. SURVEYOR
SURVEY DATE
VERIFICATION
BY CK. A E. APP. NO. DATE CK. A.E. APP.
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE, COLORADO
ESIGNEO^L^
tr
SUBMITTED:
397 SOUTH FIRST EAST STREET
MONTICELLO, UTAH
30 32
Geotech, Inc.
~34
DATE APPROVAL DOE
MS-00202-RS
Rnnono-nosHTi OFJ.
36 38 40
DOE ID No.: MS-00202-RS
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] [ ]
[ ] [X]
[X] [ ]
[ ]
[ ]
[ ]
[ ]
[ ]
[ ]
[<] [ ]
[A I )
[X] [ ]
IX [ ]
[ ] [J?
M [ ]
[ ]
[ ]
[ I
[ ]
[ ]
[ ]
'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-00202-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.
i
ic il C. ButheruV / » Date
Manager, Monticello Programs
MACTEC-ERS
DOE Evaluation
On the basis of the Property Completion Report evaluation, this property
[X| Should be certified by DOE.
[ ] Should be certified by DOE with the concurrence of the U.S. Nuclear Regulatory
Commission because supplemental standards were applied according to 40 CFR 192.21.
Certification Official 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
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00187-RS
ADDRESS: 165 EAST FOURTH SOUTH STREET
MONTICELLO, UTAH 84535
OCTOBER 1992
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 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-00187-RS:PCR-302
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-00187-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, mill tailings from
the Monticello millsite were removed from the site and used for
construction-related activities in the vicinity.
1.2 Criteria for Remedial Action
The Decontamination and Decommissioning Program has adopted the
"Standards for Remedial Action at Inactive Uranium Processing Sites"
(40 CFR Part 192) for all cleanup activities under the MVP project.
These standards were prepared by the U.S. Environmental Protection
Agency (EPA) to establish guidelines for the control of tailings
piles and the cleanup of buildings and open lands.
This property was evaluated on the basis of the EPA standards by the
U.S. Department of Energy (DOE) Inclusion Survey Contractor. The
DOE reviewed these evaluation results and determined that the
property contained mill tailings (residual radioactive material)
exceeding the EPA standards. The Remedial Action Contractor was
notified of the inclusion of this property into the 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-00187-RS
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
MS-00187-RS
Parcel Number M-56-1: Beginning at the NW corner of Lot 1, Block 9,
south 107.25 feet to the point of beginning; south 107.25 feet, east
107.25 feet, north 107.25 feet, west to the point of beginning, City
of Monticello, County of San Juan, State of Utah
Property Address:
Property Owners:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
165 East Fourth South Street
Monticello, Utah 84535

Residential Simple (RS)
Oak Ridge National Laboratory
October 23, 1989
Chem-Nuclear Geotech, Inc.
March 29, 1990
Sonderegger Construction
P.O. Box 6
Monticello, Utah
July 12, 1990
August 14, 1990
Interior: 0 cubic yards
Exterior: 451 cubic yards
1,051 square meters (ma)
October 1992
2
DOE ID NO.: MS-00187-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 radiological assessment identified 174 cubic yards of
contamination, ranging from 6 inches to 12 inches deep, within the
property. The remedial action process included the removal of
approximately 451 cubic yards of residual radioactive material,
ranging from 8 inches to 50 inches deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix
Figure 2.1.
2.3 Unanticipated Items During Remedial Action ^
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID NO.: MS-00187-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 1989, as described in the final
REA dated March 1990. Appendix Figure 2.1 shows the extent
of assessed contamination and identifies the areas
recommended to undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted
after the removal of residual radioactive material and prior
to backfilling. Following the gamma scan, soil samples
representative of the 6-inch-thick soil layer at the bottom
of the excavation were collected. These samples were blended
to form composite samples representing the verification areas
(Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined
during the gamma scan, ranged from 13 microroentgens per
hour (^R/h) to 27 fiR/h (Appendix Figure 2.1). The results of
analyses for radium-226 in 12 composite soil samples ranged
from 1.1 picocuries per gram (pCi/g) to 6.0 pCi/g (Appendix
Table 3.1).
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on measurements representing an annual average, the RDC
was 0.0093 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-00187-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 165 East Fourth South Street, in
Monticello, Utah, is recommended for certification as required by
the Decontamination and Decommissioning Program guidelines, and the
appropriate records should be documented.
Applicability
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Certification Data Summary
Standards
Shall not exceed 20 /iR/h
above background.*
Annual average shall not
exceed 0.02 WL, to the
extent practicable, and
in no case shall exceed
0.03 WL.
Survey Results
Range for the basement
was 12 fiR/h to 14 pR/h.
Annual average was
0.0093 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 m*.
< 5 pCi/g above
background.
Soil sample results
ranged from 1.1 pCi/g
to 6.0 pCi/g.
*The background exposure rate is approximately 14 pR/h.
**The background radium-226 concentration is approximately 2.0 pCi/g.
5
DOE ID NO.: MS-00187-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-00187-RS
Address: 165 East Fourth South Street, Monticello, Utah
The analytical uncertainties in the table are reported at the 95-percent
confidence interval.
Area
Exposure-
Rate Range
(A/R/h)
Soil
Sample
Ticket No.
Meas.
Method*
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
15
16
15
15
15
15
16
16
16
16
15
15
21
25
19
19
25
21
21
21
19
20
27
25
NAA
NAA
NAA
NAA
NAA
NAA
NAF
NAF
NAF
NAF
NAF
NAF
475
476
477
478
479
480
668
669
670
671
672
673
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
2.9
2.0
1.5
1.7
1.3
1.1
1.4
1.1
2.1
2.7
6.0
5.4
0.3
0.2
0.4
0.4
0.9
0.8
22.0
21.8
21
21
21
15
14
17
13
16.2
16.5
15.8
3.0
2.9
2.9
2.9
2.8
3.9
3.8
3.9
3.7
3.9
3.9
3.8
1.2
0.7
0.7
0.7
1.1
0.9
0.7
0.9
1.1
0.7
1.0
1.1
0.3
0.2
0.2
0.2
0.3
0.2
0.2
0.2
0.3
0.2
0.3
0.3
See Appendix Figure 2.1 for the verification areas.
*AL = Analytical Laboratory
7
Table 3.2
Radon Decay-Product Concentration (RDC) Measurement Results
DOE ID No.: MS-00187-RS
Address: 165 East Fourth 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)
3160931 12-12-90 01-07-92
3160915 12-12-90 01-07-92
3160901 12-12-90 01-07-92
16.2 1.82 0.0091
17.0 1.90 0.0095
16.5 1.85 0.0093
Annual Average: 0.0093
See Appendix Figure 2.1 for the measurement location.
MM-DMN:09-18-92
MS-00187-RS:PCR-302 WS 5.5
REV052592
8
10 12 18 24
1—r
26 28
i—i—r
30 32
i—i—i—i—T
36 38
i—i—i—r
50
2il.'.^".V^".V.V'':'' "j:
V-4
15-19
8
10
10
ONE STORY
FRAME HOUSE
W/BASEMENT
10
V-3
15-19
:10
• • / « \ • ••••«,•
10
V-11
15-27
15
t: 12 V-10
16-20
VMM):-12-14
V4 15
13-15
48 48 48
12 12 12
SCALE IN FEET
;20 ;10 :20
14
J L
16
;40
18
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 1$
NOT A LAND SURVEY PLAT, UTILITY LOCATION PLAT, OR OTHER
IMPROVEMENT SURVEY PLAT AND IS NOT TO BE RELIED UPON •
FOR THE ESTABLISHMENT OF FENCE, BUILDING, OR OTHER.
FUTURE IMPROVEMENT UNES. :
12 •
; LEGEND
ALL DEPTHS IN'• INCHES.
ALL EXPOSURE: RATES IN fiR/h
ASSESSED AREA IDENTIFIER:
AVERAGE: DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION
POST- REMEDIAL ACTION EXPOSURE-RATE RANGE
BOp'N:DART OF EXCAVXtTO'N"
AVERAGE^ EXCAVATED DEPTH FOR THE DEPOSIT OF
CONTAMINATION"i!j
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVAT10.N EXP.OSURE-RATE RANGE'*"'
POST-REMEDIAL ACTION RADON DECAY-PRODUCT
CONCENTRATION MEASUREMENT LOCATIONi
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF; REMEDIAL ACTION.
28
26
24
22
20
18
RADIUMS
FTGlDRE :2: T"
EXTERIOR iEXTENT OF CONTAMINATION
16
22
I
24
J L
26 28
REVISIONS
RESIDENCE—NO. OF OCCUPANTS
NON-RESIDENCE—MAN.HRS./WK.
INSTRUMENT NO. SURVEYOR
SURVEY DATE
VERIFICATION
BY CK. A.E. APP. NO. DATE BY CK. A.i. APP.
14
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE. COLORADO
165 EAST FOURTH SOUTH ST.
MONTICELLO, UTAH
30 32
Geotech,Inc.
"34
OATE IAPPROVAL OOE
MS-00187-RS
,ONC5-B00187-M4!tHT1 n« 1
36 38
OAK RIDGE NATIONAL LABORATORY
OPERATED BY MARTIN MARIETTA ENERGY SYSTEMS, INC.
FEB 2 61993
Jacob W. Gatrell
Office of Environmental Restoration
Southwestern Area Programs Division
U.S. Department of Energy
EM-4 5l/GTN/D-2 4 7
Washington, DC 20545
Dear Mr. 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,
indoor radon daughter concentration, and indoor gamma exposure
rate at this property.
Therefore, this property is recommended for certification by the
U.S. Department of Energy.
Sincerely,
Mary J. Wilson
Pollutant Assessments Group
MS00187-RS
165 East 4th South Street
Monticello. Utah 84535

GRAND JUNCTION OFFICE
P. 0. BOX 2567
GRAND JUNCTION, COLORADO 81502
Location Number:
Location Address:
Property Owner:
Owner Address:
Attachments
HEALTH AND SAFETY RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
165 EAST 4TH SOUTH STREET
MONTICELLO, UTAH (MS00187)
S. K. Mather
February 1993
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
UST OF TABLES
AC^OWLEDGMENTS
ABSTRACT
INTRODUCTION
PROCEDURES
Objectives
Document Reviews
VERIFICATION OF REMEDIAL ACTION
Gamma Measurements
Soil Sample Analysis
Radon Measurement Results
CONCLUSION
REFERENCES
LIST OF TABLES
Applicable guidelines for protection against radiation
AOCNOWLEOXIMENTS
Research for this project was sponsored by the Division of Facility and Site
Decommissioning Projects, U.S. Department of Energy. The author wishes to acknowledge G. A.
Pierce for analysis of soil samples and A. R. Jones and G. K. Stowe 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 1990, Chem-
Nuclear Geotech, the remedial action contractor designated by DOE, performed
remedial action on the vicinity property at 165 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 in the Pollutant Assessments Group Procedures Manual (ORNL,
1992).
ix
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 165 EAST 4TH SOUTH STREET
MONTICELLO, UTAH (MS00187)*
INTRODUCnON
The mill at Monticello, Utah, was built in 1942 by the U.S. government through the
Defense Plant Corporation to provide vanadium during World War II. Various government
agencies operated the mill until 1947. In 1948 the Atomic Energy Commission (AEC) obtained
the mill and operated it under contract through 1959 to provide both uranium and vanadium.
Mill operations were terminated on January 1,1960. In 1961 the mill tailings piles were leveled
and graded, covered with rock and soil, and seeded with native grasses. During 1974 and 1975,
the ore stockpiles were removed from the site, and the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city
of Monticello, in San Juan County, Utah. The site is bordered on the south and southeast by
land held by the U.S. Bureau of Land Management. Other boundaries are the city of Monticello
and private property.
During the AEC era, the mill processed approximately one million tons of uranium
ore. Vanadium and uranium were the only substances extracted in the milling process. Other
constituents of the ore remained in the tailings and were not separated prior to disposal. During
the years of active mill operation, the mill tailings were normally moist, so erosion was minimal.
However, throughout the mill's operating period, area residents used these tailings as fill material
and as aggregate in mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy
(DOE) initiated the Surplus Facilities Management Program (SFMP) in 1978 to ensure the safe
caretaking and decommissioning of government facilities that had been retired from service but
still had radioactive contamination. In 1980 the mill site at Monticello was accepted into the
SFMP, and the Monticello Remedial Action Project (MRAP) was established to restore the
government-owned mill site to safe levels of radioactivity, to dispose of or contain the tailings in
an environmentally safe manner, and to perform remedial actions on off-site (vicinity) properties
that had been contaminated by radioactive material resulting from mill operations. The
Monticello mill site and the tailings remain in the custody of the DOE Grand Junction, Colorado,
Projects Office. In 1983 remedial actions for vicinity properties were separated from MRAP with
establishment of the Monticello Vicinity Properties (MVP) Project (Abramiuk 1989).
*The verification of remedial action was performed by members of the 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 1990, Chem-Nuclear Geotech, Inc. (Geotech), the remedial action contractor
(RAC) designated by DOE, performed remedial action on the vicinity property that is the subject
of this report, a single family residence located at 165 East 4th South Street, Monticello, Utah.
The remedial action plan required excavation of all exterior contamination. When the excavation
was completed, the property was resurveyed, including soil sampling, to ensure the removal of all
contamination, backfilled with uncontaminated material, and restored to a condition comparable
to that which existed prior to remedial action (Geotech 1990).
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 165 East 4th South Street site. This report
describes the methods and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available
documentation adequately and accurately describes the post-remedial-action radiological
conditions of the entire property that is to be certified and (2) that the remedial action reduced
contamination to below applicable DOE guidelines (DOE 1990).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1990)
indicates the property was evaluated by DOE on the basis of Environmental Protection Agency
standards (DOE 1990) 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 174 yd3 of mill
tailings 6 to 12 inches deep. However, during the actual removal process, a total of 451 yd3 of
contaminated earth and uranium mill tailings, 8 to 50 inches deep were removed from a 1051 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 12 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 to 14 /zR/h. Exterior surface gamma measurements taken from the
excavated areas prior to backfilling ranged from 13 to 27 /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 12 exterior verification areas. Geotech's
analysis of these samples showed ^Ra concentrations from 1.1 to 6.0 pCi/g in the composite
sample. These values are below the DOE guideline value of 15 pCi/g for soil layers >15 cm
below the surface (Table 1). Sample archival from Geotech was insufficient for confirmatory
analysis by ORNL.
Radon Measurement Results
Radon decay-product concentration (RDC) measurements for this site were
determined by the alpha-track method. To monitor radon levels, Geotech placed three Alpha-
track detectors on the ground floor of the residence located on this property for a period of
approximately one year (from 12/12/90 to 01/07/92). The average annual working level (WL) of
radon progeny concentration, as determined by the Tech./Ops-Landauer Corporation, was 0.0093,
which is well below the 0.03-WL guideline given in Table 1.
CONCLUSION
Results of Geotech soil sample analysis show that radionuclide concentrations are
within applicable DOE guidelines. Based upon the results of the post-remedial-action data, which
are confirmed by the verification assessment data, these radiological measurements fall below the
limits prescribed by DOE guidelines. It is concluded that the site successfully meets the DOE
remedial action objectives.
4
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of ^Ra in soil
above background levels,
averaged over a 100-m2 area
5 pCi/g averaged over the
first 15 cm of soil below the
surface; 15 pCi/g when ave-
raged over 15-cm-thick soil
layers more than 15 cm
below the surface
Exposure to 222Rn
progeny
Average annual radon proge-
ny concentration (including
background)
0.03 WL
(DOE 1990)
5
REFERENCES
Abramiuk I. N.et al.1989. Monticello Remedial Action Project Site Analysis Report,
GJ-10, prepared by Bendix Field Engineering Corporation, Grand Junction,
Colorado, for the U.S. Department of Energy, Surplus Facilities Management
Program, Richland, Washington.
Geotech 1992, Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00187, Address: 165 East 4th South Street, Monticello,
Utah 84535, Geotech, Grand Junction, Colorado, October 1992.
U.S. DOE 1990. Verification and Certification Protocol for the Office of
Environmental Restoration, Formerly Utilzed Sites Remedial Action Programs and
Decontamination and Decommissioning Program, Revision 3, November 1990. U.S.
Department of Energy, Washington, D.C.
ORNL, 1992. Pollutant Assessments Group Procedures Manual. ORNL/TM-
6645/RI Oak Ridge National Laboratory, Grand Junction, Colorado.
DOE ID NO. : MS- OO ) % ^ " S>
Property Address: i Ea-&4 Feu* "Hi z>t>u4h 6TV~*<.-T
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.
In-situ [X] Lab [ ]
Ra-226 is < 15 pCi/g
above background in any
15-cm layer of soil
more than 15 cm below
the surface averaged
over 100 m*.
In-situ [ ] Lab [^]
Interior gamma is < 20 uR/h
above background in any
occupied or habitable
structure. [><] [ ] [ ] [yl] [ ] [ ]
The radon decay-product
concentration in any
occupied or habitable
structure is < 0.02
working level or, at
most, 0.03 working level.
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21. [ ] [y] [ ]
Hot spot criteria met as
outlined by U.S. DOE
guidelines for FUSRAP and
Decontamination and
Decommissioning
Program (Rev. 03/02/87).
COMMENTS: *The excavations were backfilled with materials that were measured
at the source showing that the Ra-226 concentrations are in the range of
normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
m* t ) [ ] r^j t i c i
tXi i i M rxi [ ] t J
tY1 t ] [ ) [*] [ ] [ ]
[ 3 ix c ]
[ ] [ ] t)0 t ] [ 3 [fl
SFCERTIFED SFMS-00187
DOE ID NO. : MS- OO 1 *D ? ~ flS
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.
Fe arry Date
Decontamination and Decommissioning Program Manager
Chem-Nuclear Geotech, Inc.
DOE EVALUATION
[)C] 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.
DecontfSmination and Decommissioning Program Dike"
Certification Official
Department of Energy
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY* PROPERTY REMEDIAL ACTION
FOR
DOE ID NO.: MS-00200-CS
ADDRESS: 264 EAST CENTER STREET
MONTICELLO, UTAH 84535
NOVEMBER 1992
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
Prdgram 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-00200-CS:PCR-305
V
TABLE OF CONTENTS
Section Page
1.0 SUMMARY 1
1.1 Basis for Remedial Action 1
1.2 Criteria for Remedial Action 1
1.3 Summary of Remedial Action 2
2.0 OPERATIONS SUMMARY 3
2.1 Abstract of Remedial Action Plan 3
2.2 Previously Unidentified Contamination 3
2.3 Unanticipated Items During Remedial Action 3
2.4 Application of Supplemental Standards 3
3.0 VERIFICATION SUMMARY 4
3.1 Radiological Survey Data 4
3.1.1 Pre-Remedial Action Survey 4
3.1.2 Post-Excavation Survey 4
3.2 Recommendation for Certification 5
4.0 APPENDIX 6
DOE ID NO.: MS-00200-CS
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, mill tailings from
the Monticello millsite were removed from the site and used for
construction-related activities in the vicinity.
1.2 Criteria for Remedial Action
The Decontamination and Decommissioning Program has adopted the
"Standards for Remedial Action at Inactive Uranium Processing Sites"
(40 CFR Part 192) for all cleanup activities under the MVP projects
These standards were prepared by the U.S. Environmental Protection
Agency (EPA) to establish guidelines for the control of tailings
piles and the cleanup of buildings and open lands.
This property was evaluated on the basis of the EPA standards by the
U.S. Department of Energy (DOE) Inclusion Survey Contractor. The
DOE reviewed these evaluation results and determined that the
property contained mill tailings (residual radioactive material)
exceeding the EPA standards. The Remedial Action Contractor was
notified of the inclusion of this property into the 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-00200-CS
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
MS-00200-CS
Location Number M-176; from the NE corner of Lot 4, Block 21,
Monticello Townsite Survey, south 135 feet for the point of beginning;
south 28.50 feet, west 79 feet, south 41.40 feet, west 41 feet, north
69.90 feet, east 120 feet to point of beginning, City of Monticello,
County of San Juan, State of Utah
Property Address:
Property Owner:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
264 East Center Street
Monticello, Utah 84535

Commercial Structure (CS)
Oak Ridge National Laboratory
October 23, 1989
Chem-Nuclear Geotech, Inc.
June 11, 1990
Sonderegger Construction
P.O. Box 6
Monticello, Utah
August 9, 1990
September 29, 1990
Interior: 0 cubic yards
Exterior: 35 cubic yards
85 square meters (ma)
November 1992
2
DOE ID NO.: MS-00200-CS
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of exterior residual
radioactive material (Appendix Figure 2.1). Once excavation was
complete/ the affected 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 radiological assessment identified 23 cubic yards of
contamination, ranging from 6 inches to 12 inches deep, within the
property. The remedial action process included the removal of
approximately 35 cubic yards of residual radioactive material,
12 inches deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix
Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID NO.: MS-00200-CS
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by Chem-Nuclear
Geotech, Inc., during October 1989, as described in the final
REA dated June 1990. Appendix Figure 2.1 shows the extent of
assessed contamination and identifies the area recommended to
undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted
after the removal of residual radioactive material and prior
to backfilling. Following the gamma scan, soil samples
representative of the 6-inch-thick soil layer at the bottom
of the excavation were collected. These samples were blended
to form a composite sample representing the verification area
(Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined
during the gamma scan, ranged from 12 microroentgens per
hour (pR/h) to 20 pR/h (Appendix Figure 2.1). The result of
analysis for radium-226 in one composite soil sample was
1.6 picocuries per gram (pCi/g), as indicated in Appendix
Table 3.1.
4
DOE ID NO.: MS-00200-CS
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property
to the extent required by the EPA standards (40 CFR 192.12,
192.20-23), as indicated in the Certification Data Summary below.
Therefore, the property located at 264 East Center Street, in
Monticello, Utah, is recommended for certification as required by
the Decontamination and Decommissioning Program guidelines, and the
appropriate records should be documented.
Applicability
Certification Data Summary
Standards Survey Results
Habitable Structures
Exposure Rate: Shall not exceed 20 juR/h
above background.
Not applicable:
vacant lot.
Radon Decay-Product
Concentrat ion:
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 background4' in
the 15-cm surface layer,
averaged over 100 ma.
< 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 m*.
Soil sample result was
1.6 pCi/g.
*The background radium-226 concentration is approximately 2.0 pCi/g.
5
DOE ID NO.: MS-00200-CS
APPENDIX
Appendix Table:
Table 3.1 Post-Excavation Sample/Measurement Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: HS-00200-CS
Address: 264 East Center Street, Monticello, Utah
The analytical uncertainties in the table are reported at the 95-percent
confidence interval.
Exposure- Soil
Rate Range Sample Meas. Radium-226 Potassium Thorium
Area (^R/h) Ticket No. Method* (pCi/g) (pCi/g) (pCi/g)
V-l 15 - 20 NAF 329 AL 1.6 ± 0.3 19.9 ± 4.1 1.4 ± 0.3
See Appendix Figure 2.1 for the verification area.
*AL = Analytical Laboratory
MM-VPF:10-29-92
MS-00200-CS:PCR-305 WS 5.5
REV052592
10 12 14 16 18 20 22 24 26 28 30
EAST CENTER STREET
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X 12-15
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NORTH 20! 10i 20: 40 TIME
X
32 34 36
i—i—i—i—r
|L££ENJ2
38
i—r
40
..;.; j ALll DEPTHS IN-INCHES
: ALL EXPOSURE :RATES jN fifi/h """:!"
® j ASSESSED AREA IDENTIFIER:
j AVERAGE iDEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION j \
12*;-15 ! Po|>T—REMEDIAL ACTION EX^OSURE-RAtE .RANGE
BOUNDARY OF EXCAVATION'!?
AVERAGE lEXCAVATED DEPTH: FOR tHE DEPOSIT
CONTAMINATION
VERIFICATION SOIL SAMPLE AREA IDENTIFIER
AND EXCAVATION EXPOSURE-RATE RANGE- "
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION.;.......:.;
OF
RADTOLODieAlI ^S- BIDILJT
IFIGURE 2.1 r
! EXTERIOR EXTENT OF CONTAMINATION
THIS DRAWING. "PREPARED FOR THE DECONTAMINATION AND
DECOMMISSIONING PROGRAM, IS FOR THE:SOLE USE OF THfc-
U.S. DEPARTMENT OF ENERGY AND ITS CONTRACTORS. IT IS:
NOT A1AND SURVEY PLAT, UTILITY LOCATION PLAT,- OR OTHEF
IMPROVEMENT SURVEY PLAT AND IS NOT TO BE RELIED UPON
FOR THE ESTABLISHMENT OF FENCE, BUILDING. OR OTHER
FUTURE IMPROVEMENT LiNES.
REVISIONS
RESIDENCE—NO. Of OCCUPANTS
NON-RESIDENCE-MAN. HRS./WK.
INSTRUMENT NO. SURVEYOR
SURVEY OATE
VERIFICATION
AE. APP. NO. OATE
U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE. COLORADO
PROJ. ENG.
SUBMITTED:
11-31 264 EAST CENTER STREET
MONTICELLO, UTAH
Geotach, Inc
DATE APPROVAL DOE
001 "> HO. MS—UU2UU —US
DWC.Ng_B0020Q-Q3gHTl
10 12 14 16 18 20 22 24 26 28 30 32 34 36 38 40
Chem-Nuclear Geotech, Inc.
P.O. Box 14000
2597 B% Road
Grand Junction. Colorado 81502-5504
303/248-6000
FAX [phone]
A Waste Management Company
November 20, 1992
Ms. Mary Wilson
Oak Ridge National Laboratory
Grand Junction Office
P.O. Box 2567
Grand Junction, Colorado 81502
SUBJECT: PROPERTY COMPLETION REPORT
Dear Ms. Wilson:
Attached is the following Property Completion Report selected by Oak Ridge
National Laboratory for independent verification.
MS-00200-CS 264 East Center Street
Should you require further information, please do not hesitate to contact me.
Sincerely yours,
Harry A. Perry
Program Manager
JEK:mm
cc: Records Management
a subsidiary ol Waste Management Environmental Services, Inc.
HEALTH AND SAFETY RESEARCH DIVISION
Waste Management Research and Developments Programs
(Activity No. EX 20 10 40 1)
RESULTS OF THE TYPE A INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION AT
264 EAST CENTER STREET
MONTICELLO, UTAH (MS00200)
S.K. Mather
February 1993
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
COhTTENTS
UST OF TABLES v
ACKNOWLEDGMENTS vii
ABSTRACT ix
INTRODUCTION 1
PROCEDURES 2
Objectives 2
Document Reviews 2
VERIFICATION OF REMEDIAL ACTION 3
Gamma Measurements 3
Soil Sample Analysis 3
CONCLUSION 3
REFERENCES 6
iii
LIST OF TABLES
1 Applicable guidelines for protection against radiation 4
2 Results of ORNL analysis of Geotech soil samples from 264 East Center Street,
Monticello, Utah (MS00200) 5
v
ACXNOWLEOXJMENTS
Research for this project was sponsored by the Division of Facility and Site
Decomniissioning Projects, U.S. Department of Energy. The author wishes to
acknowledge M.K. Jensen for analysis of soil samples and A.R. Jones and G.K. Stowe 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 1990 Chem-Nuclear Geotech, the remedial action contractor
designated by DOE, performed remedial action on the vicinity property at 264
East Center 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
in the Pollutant Assessments Group Procedures Manual (ORNL, 1992).
ix
RESULTS OF THE INDEPENDENT VERIFICATION
OF RADIOLOGICAL REMEDIAL ACTION
AT 264 EAST CENTER STREET
MONTICELLO, UTAH (MS00200)*
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 BL Various
government agencies operated the mill until 1947. In 1948 the Atomic Energy
Commission (AEC) obtained the mill and operated it under contract through 1959 to
provide both uranium and vanadium. Mill operations were terminated on January 1,1960.
In 1961 the mill tailings piles were leveled and graded, covered with rock and soil, and
seeded with native grasses. During 1974 and 1975, the ore stockpiles were removed from
the site, and the mill foundations were buried.
The Monticello mill site is a 78-acre tract along Montezuma Creek, south of the city
of Monticello, in San Juan County, Utah. The site is bordered on the south and southeast
by land held by the U.S. Bureau of Land Management. Other boundaries are the city of
Monticello and private property.
During the AEC era, the mill processed approximately one million tons of uranium
ore. Vanadium and uranium were the only substances extracted in the milling process.
Other constituents of the ore remained in the tailings and were not separated prior to
disposal. During the years of active mill operation, the mill tailings were normally moist,
so erosion was minimal. However, throughout the mill's operating period, area residents
used these tailings as fill material and as aggregate in mortar and concrete.
Under the authority of the Atomic Energy Act, the U.S. Department of Energy
(DOE) initiated the Surplus Facilities Management Program (SFMP) in 1978 to ensure
the safe caretaking and decommissioning of government facilities that had been retired
from service but still had radioactive contamination. In 1980 the mill site at Monticello
was accepted into the SFMP, and the Monticello Remedial Action Project (MRAP) was
established to restore the government-owned mill site to safe levels of radioactivity, to
dispose of or contain the tailings in an environmentally safe manner, and to perform
remedial actions on off-site (vicinity) properties that had been contaminated by radioactive
material resulting from mill operations. The Monticello mill site and the tailings remain in
the custody of the DOE Grand Junction, Colorado, Projects Office. In 1983 remedial
actions for vicinity properties were separated from MRAP with establishment of the
Monticello Vicinity Properties (MVP) Project (Abramiuk 1989).
""The verification of remedial action was performed by members of the 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 1990, Chem-Nuclear Geotech, Inc. (Geotech), the remedial action contractor
(RAC) designated by DOE, performed remedial action on the vicinity property that is the
subject of this report, a vacant lot located at 264 East Center Street, Monticello, Utah.
The remedial action plan required excavation of all exterior contamination. When the
excavation was completed, the property was resurveyed, including soil sampling, to ensure
the removal of all contamination, backfilled with uncontaminated material, and restored to
a condition comparable to that which existed prior to remedial action (Geotech 1990).
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 264 East
Center Street site. This report describes the methods and results of that verification.
PROCEDURES
Objectives
The objectives of the verification activities were to confirm (1) that available
documentation adequately and accurately describes the post-remedial-action radiological
conditions of the entire property that is to be certified and (2) that the remedial action
reduced contamination to below applicable DOE guidelines (DOE 1990).
Document Reviews
Review of the property completion report prepared by Geotech (Geotech 1992)
indicates the property was evaluated by DOE on the basis of Environmental Protection
Agency standards (DOE 1990) 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 23 yd3 of mill tailings
6 to 12 inches deep. However, during the actual removal process, a total of 35 yd3 of
contaminated earth and uranium mill tailings, 6 to 12 inches deep were removed from a 85
ro2 area.
A post-excavation survey was performed by Geotech prior to backfilling of the
excavated areas. This survey consisted of surface gamma scans with a scintillometer of the
exterior and soil sampling. A sample representative of the bottom 15-cm (6-in.) soil layers
of the one excavated area was collected and blended to form a representative composite
soil sample for the verification area.
3
VERIFICATION OF REMEDIAL ACTION
All measurements presented in this report are gross readings. Background radiation
levels have not been subtracted. Similarly, background concentrations have not been
subtracted from radionuclide concentrations in soil samples. Applicable DOE guidelines
for protection against radiation are given in Table 1.
Gamma Measurements
Exterior surface gamma measurements taken from the excavated areas prior to
backfilling ranged from 12 to 20 uR/h.
SoH Sample Analysis
Prior to backfilling, Geotech collected a soil sample representative of the excavated
area from the bottom 15-cm (6-in.) soil layers. This sample was blended to form a
composite soil sample representative of an average over the one exterior verification area.
Geotech's analysis of this sample showed ^Ra concentrations of 1.6 pCi/g in the
composite sample. ORNL PAG obtained this soil sample and performed a confirmatory
analysis, which showed ^Ra concentrations of 1.7 pCi/g. These values are below the
DOE guideline value of 15 pCi/g for soil layers >15 cm below the surface (Table 1).
Results of Geotech and ORNL soil sample analyses are given in Table 2.
CONCLUSION
Results of Geotech soil sample analysis and confirmatory split soil sample analysis by
ORNL show that radionuclide concentrations are within applicable DOE guidelines.
Based upon the results of the post-remedial-action data, which are confirmed by the
verification assessment data, these radiological measurements fall below the limits
prescribed by DOE guidelines. It is concluded that the site successfully meets the DOE
remedial action objectives.
4
Table 1. Applicable guidelines for protection against radiation
Mode of exposure Exposure conditions Guideline value
Radionuclide con-
centrations in soil
Maximum permissible con-
centration of ^Ra in soil
above background levels,
averaged over a 100-m2 area
5 pCi/g averaged over the
first IS cm of soil below the
surface; 15 pCi/g when ave-
raged over 15-cm-thick soil
layers more than 15 cm
below the surface
Exposure to 222Rn Average annual radon proge- 0.03 WL
progeny ny concentration (including
background)
(DOE 1990)
5
Table 2. Results of ORNL analysis of Geotech soil samples
from 264 East Center Street, Monticello Utah (MS00200)
^Ra concentration (pCi/g)
ORNL Geotech
sample sample Depth ORNL Geotech
No." No* (cm)
XI NAC-329 15-30 1.7 1.6
An X-type sample is a split of the sample taken by the remedial action contractor.
* Soil samples representative of the bottom 15-cm (6-in.) soil layers of the excavated
areas were taken by Geotech, and these samples were blended to form a composite
soil sample, which represents an average over one of the verification areas.
REFERENCES
Abramiuk I. N.et al.1989. Monticello Remedial Action Project Site Analysis Report,
GJ-10, prepared by Bendix Field Engineering Corporation, Grand Junction,
Colorado, for the U.S. Department of Energy, Surplus Facilities Management
Program, Richland, Washington.
Geotech 1992, Property Completion Report for Monticello Vicinity Property Remedial
Action for DOE ID NO: MS00200, Address: 264 East Center Street, Monticello,
Utah 84535, Geotech, Grand Junction, Colorado, November 1992.
U.S. DOE 1990. Verification and Certification Protocol for the Office of
Environmental Restoration, Fonmeriy Utilzed Sites Remedial Action Programs and
Decontamination and Decommissioning Program, Revision 3, November 1990. U.S.
Department of Energy, Washington, D.C.
ORNL, 1992. Pollutant Assessments Group Procedures Manual ORNL/TM-
6645/RI Oak Ridge National Laboratory, Grand Junction, Colorado.
DOE ID NO.: MS- £)£> JlOOi-C 5
Property Address: Jiietf gACT CJENTT&L 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 m2. LVJ ( 1 [ ]
In-situ [ ] Lab C^j
Interior gamma is < 20 pR/h
above background in any
occupied or habitable
structure. [ ]
The radon decay-product
concentration in any
occupied or habitable
structure is < 0.02
working level or, at
most, 0.03 working level. [ ]
Supplemental standards were
applied in accordance with
EPA standard 40 CFR 192.21. [ ]
Hot spot criteria met as
outlined by U.S. DOE
guidelines for FUSRAP and
Decontamination and
Decommissioning [ ] [ ] JX]
Program (Rev. 03/02/87).
[ ] \X)
IVftC/vnT LOT)
[ ] [XI .
[XI ( ]
LX] [ } [ ]
[/] [ ] [ ]
[ ] [ ] [ >?
[ ] [ 1 [XJ
i i iy1 [ i
[ ] i J [tf
COMMENTS: *The excavations were backfilled with materials that were measured
at the source showing that the Ra-226 concentrations are in the range of
normal background. Other surface areas were verified on the basis of gamma
exposure rates that do not exceed 30 percent above normal background.
SFCERTIFED SFMS-00200
* ~ t*- "
DOE ID NO. : MS- bkUSS ~<1 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.
arry A. Berry ' Date
Decontamination and Decommissioning Program Manager
Chem-Nuclear Geotech, Inc.
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.
zA DecoAramimiti ecommissioning Program
Certification Official
Department of Energy
Date
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DEC 231992
UJ
RECORDS MANAGEMENT
DOE ID NO.: MS-00139-MR
ADDRESS: 365 SOUTH SECOND EAST STREET
MONTICELLO, UTAH 84535
DECEMBER 1992
Prepared for
Decontamination and Decommissioning Program
Division of Facilities and Site Decommissioning
Department of Energy
DEC 23 1992
i2
by
Chem-Nuclear Geotech, Inc.
P.O. Box 14000
RECORDS MANAGEMENT
P.O. Box 14000 t _,|-pr;
Grand Junction, Colorado 81502-5504 liffiSffK \ty) -j
Harry A. Perry
Program Manager
RECORDS MAivAuri
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-00139-MR:PCR-300
SFOCPLRPTS SFMS-00139
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-00139-MR
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
U. S. Department of Energy (DOE), which determined that the property
contained mill tailings (residual radioactive material) exceeding
the EPA standards. The Remedial Action Contractor was notified of
the inclusion of this property into the 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.
DOE ID NO.: MS-00139-MR
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-00139-MR
Lot 2, Block 10, City of Monticello,
County of San Juan, State of Utah
365 South Second East Street
Monticello, Utah 84535

Major Residential (MR)
Not applicable; historical inclusion
by DOE
June 8, 1984
Chem-Nuclear Geotech, Inc.
September 29, 1987
Bayless & Bayless, Inc.
435 E. 1st
Pueblo, Colorado
September 7, 1988
September 30, 1988
Interior: 20 cubic yards
Exterior: 1,375 cubic yards
2,285 square meters (m2)
December 1992
DOE ID NO.: MS-00139-MR
2.0 OPERATIONS SUMMARY
2.1 Abstract of Remedial Action Plan
The remedial action plan involved removal of interior and exterior
residual radioactive material (Appendix Figure 2.1). Once
excavation was complete, the affected areas were resurveyed for
possible remaining residual radioactive material and, upon attaining
satisfactory results, were backfilled with uncontaminated material.
The property was restored to a condition comparable to that which
existed prior to remedial action activities.
2.2 Previously Unidentified Contamination
The original radiological assessment identified 840 cubic yards of
contamination, ranging from 51 inches deep to 36 inches high, within
the property. The remedial action process included the removal of
approximately 1,395 cubic yards of residual radioactive material,
ranging from 36 inches deep to 36 inches high.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix
Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the residual
radioactive material removal activities conducted on the property.
DOE ID NO.: MS-00139-MR
3.0 VERIFICATION SUMMARY
3.1 Radiological Survey Data
All survey data were acquired according to approved procedures.
3.1.1 Pre-Remedial Action Survey
A radiological survey was conducted by Bendix Field
Engineering Corporation during October 1985, as described in
the final REA dated September 1987. 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 conducted
after the removal of residual radioactive material and prior
to backfilling. Following the gamma scan, soil samples
representative of the 6-inch-thick soil layer at the bottom
of the exterior excavation were collected. These samples
were blended to form composite samples representing the
exterior verification areas.
Interior Findings: Surface exposure-rate values, determined
during the gamma scan, ranged from 16 microroentgens per
hour (pR/h) to 24 uR/h for the remediated portion of the
crawl space, 12 uR/h for the partial basement, 12 fjR/h
for the remediated portion of the ground floor, and 12 pR/h
to 19 uR/h for the rest of the ground floor (Appendix
Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined
during the gamma scan, ranged from 14 pR/h to 35 pR/h
(Appendix Figure 2.1). The results of analyses for
radium-226 in 25 composite soil samples ranged from
1.5 picocuries per gram (pCi/g) to 15.0 pCi/g (Appendix
Table 3.1).
3.1.3 Radon Decay-Product Concentration (RDC) Measurement
Based on measurements representing an annual average, the
RDC was 0.0129 working level (WL), as indicated in Appendix
Table 3.2. Appendix Figure 2.1 shows the measurement
location in the partial basement (the lowest habitable level
of the structure). RDC measurements were not taken in the
trailer house due to excessive ventilation caused by no
permanent foundation.
A
DOE ID NO.: MS-00139-MR
3.2 Recommendation for Certification
Residual radioactive materials have been removed from this property
to the extent required by the EPA standards (40 CFR 192.12,
192.20-23), as indicated in the Certification Data Summary below.
Therefore, the property located at 365 South Second East Street, in
Monticello, Utah, is recommended for certification as required by
the Decontamination and Decommissioning Program guidelines, and the
appropriate records should be documented.
Certification Data Summary
Applicability Standards Survey Results
Habitable Structures
Exposure Rate: Shall not exceed 20 pR/h
above background.*
Range for the remediated
portion of the crawl
space was 16 /iR/h to
24 pR/h. Exposure rate
for the partial basement
was 12 pR/h. Exposure
rate for the remediated
portion of the ground
floor was 12 pR/h. Range
for the rest of the ground
floor was 12 pR/h to
19 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 was
0.0129 WL for the
house. Not taken in
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 mJ.
< 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.
Soil sample results
ranged from 1.5 pCi/g
to 15.0 pCi/g.
*The background exposure rate is approximately 19 pR/h.
**The background radium-226 concentration is approximately 2.0 pCi/g.
DOE ID NO.: MS-00139-MR
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 Interior and Exterior Extent of Contamination -
RADIOLOGICAL AS-BUILT
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00139-MR
Address: 365 South Second East Street, Monticello, Utah
The analytical uncertainties in the table are reported at the 95-percent
confidence interval. A less-than sign (<) indicates that the minimum detection
limit based on Compton background was reached.
Exposure- Soil
Rate Range Sample Meas. Radium-226 Potassium Thorium
Area (pR/h) • Ticket No. Method* (pCi/g) (pCi/g) (pCi/g)
EXTERIOR
V-l
V-2
V-3
V-4
V-5
V-6
V-7
V-8
V-9
V-10
V-ll
V-12
V-13
V-14
V-15
V-16
V-17
V-18
V-19
V-20
V-21
14
17
16
17
17
16
17
21
22
17
17
17
17
17
16
17
16
17
15
17
16
25
22
21
28
35
28
24
24
26
24
21
21
22
23
21
20
28
21
18
30
22
MNK 179
MNK 180
MNK 181
MNK 182
MNK 183
MNK 184
MNK 185
MNK 186
MNK 187
MNK 188
MNK 190
MNK 191
MNK 192
MNK 193
MNK 194
MNK 195
MNK 196
MNK 197
MNK 198
MNK 199
MNK 200
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
AL
7.3
9.9
6
11.
14,
5
8
10.9
15.0
10.1
3.4
2.5
5.2
2
1
2
3
2.9
2.5
4.7
3.4
1.1
1.5
0.9
1.7
2.1
1.0
1.2
1.6
2.3
1.5
0.5
0.4
0.8
0.5
0.3
0.4
0.5
0.5
0.4
0.7
0.5
15.3
17.3
18.5
20.1
19.5
20.2
20.0
17.5
18.4
17.9
17.9
17.5
18.5
16.6
18.5
19.1
18.3
18.8
17.3
18.8
16.9
3.4
3.5
3.6
3.5
3.6
3.4
1.0
1.5
0.3
0.2
0.3
0.5
0.2
0.8
0.9
0.3
0.9
1.1
1.1
1.0
0.9
0.3
0.4
1.
0.
1.
1.
1.
0.
± 0.3
0.3
0.3
0.3
0.3
0.3
0.3
0.3
0.3
0.2
0.3
0.3
0.3
0.3
*AL = Analytical Laboratory
7
Table 3.1 (continued)
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00139-MR
Address: 365 South Second East Street, Monticello, Utah
Exposure- Soil
Rate Range Sample Meas. Radium-226 Potassium Thorium
Area (pR/h) • Ticket No. Method* (pCi/g) (pCi/g) (pCi/g)
EXTERIOR
V-22 17 - 21 MNK 713 AL 2.6 ± 0.4 17.6 ± 3.4 1.2 ± 0.3
V-23 17 - 21 MNK 714 AL 4.1 + 0.6 15.8 ± 3.1 0.8 ± 0.2
V-24 17 - 24 MNK 715 AL 4.8 ± 0.7 16.7 ± 3.2 0.8 ± 0.2
V-27 16 - 20 MNK 721 AL 1.7 ± 0.3 18.7 ± 3.6 1.3 ± 0.3
INTERIOR
V-25 16 - 24 Not applicable
V-26 12 Not applicable
See Appendix Figure 2.1 for the verification areas.
*AL = Analytical Laboratory
Table 3.2
Radon Decay-Product Concentration (RDC) Measurement Results
DOE ID No.: MS-00139-MR
Address: 365 South Second East 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)
526245 01/19/89
526266 01/19/89
526288 01/19/89
01/19/90 20.7
01/19/90 19.7
01/19/90 18.4
2.73 0.0137
2.59 0.0130
2.42 0.0121
Annual Average: 0.0129
See Appendix Figure 2.1 for the measurement location.
MM-KMA:08-11-92
MS-00139-MR:PCR-300 WS 5.5
REV051791
9
10 14 16 18 20 22 24 26 28 30 32 34 36 38 42 44 46
42
40
38
36
34
32
30
28
26
24
22
20
18
16
14
12 Y I
+ 10
10
. o...
Z:
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3:
• o:..
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12
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48
-7
50
' PARTIAL' BASEMENT^
CRAWL ;SPACE>
v-25
16-24
V-24
17-24
:\: v-2i ! 6 p^Z^.j^
©[36]
V-1 7
16-28 •:.:::::\-:
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:->':v:U^6;15v.v
V-26
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13-16 ; 30
'ELXJUUOLI'J,
•mm
I
16-19
12-16
CRAWL SPACE AND PARTIAL BASEMENT
DETAIL A
GROUND FLOOR -:
DETAIL-B
V-10 v-5 •15 1 5 V- •
17-24 17-35
1B
•liii ® 18 6YD 15
TWO STORY
FRAME HOUSE
W/PARTIAL
BASEMENT
15 V-4 18 V-9 15 2YE V-14 V-13 17-28 22-26 '15 17-23 17-22 I*
21YF 18 5? V-18
••>HR^51 .Y. 36[v.v V-3 V-8 17-21
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27) A AND B
21-24
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X-3; 18
MV.-.-.
V-11 18 V-6 V-1 .V.-J18 V-15 17-21 16-28 18 14-25 15 16-21
MM
h-tr i / TRAILER HOUSE
36 36 SHED 36
V-27 36 V-22 V-l 6
16-20 17-21 17-20
SCALE IN FEET
20 10 I0 20 40 •••NOSTH"
J L
THIS DRAWING. PREPARED FOR THE DECONTAMINATION AHO
DECOMMISSIONING PROCRAU. IS FOR THE SOLE USE OF THE :
U.S. DEPARTMENT OF ENERGY AND rTS CONTRACTORS. CT tS
NOT A LAND SURVEY PLAT, UTILITY LOCATION PLAT. OR OTHER:
IMPROVEMENT SURVEY PLAT AND IS NOT TO BE RELIED UPON ••
FOR THE ESTABLISHMENT OF FENCE* BUILDING. OR OTHER
FUTURE IMPROVEMENT LINES.
I I i I L
rr.vTi
•• iv.-.vt-
12-15
12
v-i
16-17
iLESENQ
ALL DEPTHS IN INCHES I
ALL EXPOSURE RATES IN /iR/h "':!:
ASSESSED AREA IDENTIFIER:
AVERAGE DEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION j j
POST—REjMEDIAj. ACTION EXPOSURE-RATE RAtiGE
"!BOUNDARY OF EXCAVATION :j||
: AVERAGE EXCAVATED DEPTH FOR THE DEPOSIT OF
••!•••• CONTAMINATION
L.. VERIFICATION AREA IDENTIFIER AND ..j j
; EXCAVATION EXPOSURE—RATE RANGE :
+
40
38
36
34
32
30
28
26
24
RDCJ""I'
[36]
POST-REMEDIAL ACTION RADON DECAY-PRODUCT _
CONCENTRATION MEASUREMENT LOCATION
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION :|[j
HEIGHT IN INCHES OF ASSESSED CONTAMINATED
ROCK WALL REMOVED.AND REPLACED j -
RADlOtom
j INTERIOR AND EXTERIOR EXTENT OFlCONTAMINATION
14 16 18 20 22 24 26 28 30
J_
U.S. DEPARTMENT OF ENERGY
OUND JUNCTION MOJCCTS OFFiCf. COLORADO
S4S365 SOUTH SECOND EAST ST iniM«l WO. ILMHrf *o*
r • MONTICELLO. UTAH
r sn G*ot*ch. Inc p*'~ 4~C0013S
32 34 36 38
22
20
18
16
14
12
40 42 44 46 48 50 +
DOE ID No.: MS-00139-MR
Property Address: 365 South Second 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] I ]
[X] [ ]
[X] [ ]
[ ] [X]
[X] [ ]
[ ]
[ ]
[ ]
[ ]
[ ]
[ ]
[A [ ]
W I ]
[>] [ ]
[ ]
[ ]
[ ]
[» [ ] [ ]
[ ] IX M
[Al U I 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-00139-MR
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
[X] Should be certified by DOE.
[ ] Should be certified by DOE with the concurrence of the U.S. Nuclear Regulatory
Commission because supplemental standards were applied according to 40 CFR 192.21.
Date
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
7 £
PROPERTY COMPLETION REPORT
FOR
MONTICELLO
VICINITY PROPERTY REMEDIAL ACTION
FOR
DEC 231992
RECORDS MANAGEMENT
DOE ID NO.: MS-00183-VL
ADDRESS: 81 EAST THIRD SOUTH STREET
MONTICELLO, UTAH 84535
DECEMBER 1992
Prepared for
Decontamination and Decommissioning Program
Division of Facilities and Site Decommissioning
Department of Energy
mm DEC 231992
_ Y-
RECORDS MANAGEMENJrand Junction, Colorado 81502-5504
Q CJ
by
Chem-Nuclear Geotech, Inc.
P.O. Box 14000
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-00183-VL:PCR-307
SFOCPLRPTS SFMS-08183
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-00183-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, mill tailings from
the Monticello millsite were removed from the site and used for
construction-related activities in the vicinity.
1.2 Criteria for Remedial Action
The Decontamination and Decommissioning Program has adopted the
"Standards for Remedial Action at Inactive Uranium Processing Sites"
(40 CFR Part 192) for all cleanup activities under the MVP project.
These standards were prepared by the U.S. Environmental Protection
Agency (EPA) to establish guidelines for the control of tailings
piles and the cleanup of buildings and open lands.
This property was evaluated on the basis of the EPA standards by the
U.S. Department of Energy (DOE) Inclusion Survey Contractor. The
DOE reviewed these evaluation results and determined that the
property contained mill tailings (residual radioactive material)
exceeding the EPA standards. The Remedial Action Contractor was
notified of the inclusion of this property into the 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-00183-VL
1.3 Summary of Remedial Action
DOE ID No.:
Legal Description:
MS-00183-VL
Parcel No. M-606; beginning 958.5 feet north and 332.5 feet east of the
W4 corner of Section 31, T33S., R24E., Salt Lake Base Meridian, east
16.5 feet, north 203.5 feet, west 16.5 feet, north 149 feet, west
118 feet, south 165.5 feet, east 118 feet, south 187 feet to beginning,
City of Monticello, County of San Juan, State of Utah
Property Address:
Property Owners:
Property Category:
Inclusion Survey Contractor:
Inclusion Notification Date:
Remedial Action Contractor:
Radiological & Engineering
Assessment (REA):
Construction Subcontractor:
Pre-Construction Conference
Record:
Notice of Final Completion
Inspection:
Volume of Material Removed:
Area Cleaned Up:
Property Completion Report
Submitted:
81 East Third South Street
Monticello, Utah 84535

Vacant Lot (VL)
Oak Ridge National Laboratory
October 23, 1989
Chem-Nuclear Geotech, Inc.
March 6, 1990
Sonderegger Construction
P.O. Box 6
Monticello, Utah
June 9, 1992
September 9, 1992
Interior: 0 cubic yards
Exterior: 697 cubic yards
2,600 square meters (m2)
December 1992
2
DOE ID NO.: MS-00183-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 radiological assessment identified 485 cubic yards of
contamination, 6 inches deep, within the property. The remedial
action process included the removal of approximately 697 cubic yards
of residual radioactive material, ranging from 6 inches to 12 inches
deep.
The differences in the extent of assessed contamination and actual
residual radioactive material removed are shown on Appendix
Figure 2.1.
2.3 Unanticipated Items During Remedial Action
No unanticipated items were encountered during the remedial action
activities conducted on the property.
2.4 Application of Supplemental Standards
Supplemental standards were not applicable to the remedial action
activities conducted on the property.
3
DOE ID NO.: MS-00183-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 assessed contamination and identifies the area recommended
to undergo remedial action.
3.1.2 Post-Excavation Survey
A surface gamma scan with a scintillometer was conducted
after the removal of residual radioactive material and prior
to backfilling. Following the gamma scan, soil samples
representative of the 6-inch-thick soil layer at the bottom
of the excavation were collected. These samples were blended
to form composite samples representing the verification areas
(Appendix Figure 2.1).
Exterior Findings: Surface exposure-rate values, determined
during the gamma scan, ranged from 13 microroentgens per
hour (pR/h) to 19 pR/h (Appendix Figure 2.1). The results of
analyses for radium-226 in 30 composite soil samples ranged
from < 1.0 picocurie per gram (pCi/g) to 5.4 pCi/g (Appendix
Table 3.1).
4
DOE ID NO.: MS-00183-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 81 East Third South Street, in
Monticello, Utah, is recommended for certification as required by
the Decontamination and Decommissioning Program guidelines, and the
appropriate records should be documented.
Applicability
Habitable Structures
Exposure Rate:
Radon Decay-Product
Concentration:
Certification Data Summary
Standards
Shall not exceed 20 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.
Survey Results
Not applicable:
vacant lot.
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
more than 15 cm below the
surface, averaged over
100 m2.
Soil sample results
ranged from < 1.0 pCi/g
to 5.4 pCi/g.
*The background radium-226 concentration is approximately 2.0 pCi/g.
5
DOE ID NO.: MS-00183-VL
APPENDIX
Appendix Table:
Table 3.1 Post-Excavation Sample/Measurement Results
Appendix Figure:
Figure 2.1 Exterior Extent of Contamination - RADIOLOGICAL
AS-BUILT
Table 3.1
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00183-VL
Address: 81 East Third South Street, Monticello, Utah
Area
Exposure-Rate
Range (/jR/h)
Soil Sample
Ticket No.
Meas.
Method*
Radium-226
(pCi/g)
V-l
V-2
V-3
V-4
V-5
V-6
V-7
V-8
V-9
V-10
V-ll
V-12
V-13
V-14
V-15
V-16
V-17
V-18
V-19
V-20
V-21
V-22
V-23
V-24
V-2 5
V-2 6
16
16
15
16
15
15
16
16
16
16
15
16
15
15
15
16
16
16
15
15
15
15
15
15
14
14
19
19
18
19
18
18
19
19
18
19
18
19
18
18
16
19
19
19
19
18
18
18
18
18
16
16
NAN
NAN
NAN
NAN
NAN
NAN
NAN
NAN
NAN
NAN
NAN
NAN
NAN
NAN
NAN
NAN
NAN
NAN
NAN
NAN
NAP
NAP
NAP
NAP
NAP
NAP
612
613
614
615
616
617
618
619
620
621
622
623
624
625
626
627
628
629
630
631
627
628
629
630
631
632
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
OCS
3.8
1.8
1.0
3.7
2.6
3.0
3.
2.
2.
5.
1.
1.
3.
3.
3.
3.6
1.0
3.5
*OCS = Opposed Crystal System
7
Table 3.1 (continued)
Post-Excavation Sample/Measurement Results
DOE ID No.: MS-00183-VL
Address: 81 East Third South Street, Monticello, Utah
Area
Exposure-Rate
Range (pR/h)
Soil Sample
Ticket No.
Meas.
Method*
Radium-226
(pCi/g)
V-27
V-2 8
V-29
V-30
14
15
13
13
18
18
18
16
NAO 355
NAO 356
NAO 357
NAR 632
OCS
OCS
OCS
OCS
1.4
3.1
1.5
3.2
See Appendix Figure 2.1 for the verification areas.
*OCS = Opposed Crystal System
MM-SJW:12-11-92
MS-00183-VL:PCR-307 WS
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ALL DEPTHS IN iNCHES
ALL EXPOSUR; RATES; IN>Ryh
ASSESSED AREA IDENTIFIER liii
AVERAGE IDEPTH OF ASSESSED CONTAMINATION
AREA OF ASSESSED CONTAMINATION .
POST-REMEDIAL ACTION EXPOSURE—RATE RANGE
BOUNDARY OF EXCAVATION i
AVERAGE 5XCAVATED DEPTKFOR THE DEPOSITOF
CONTAMINATION.
VERIFICATION SOIL SAMPLE AREA IDENTIFIER !
AND EXCAVATION EXPOSURE—RATE RANGE
ASSESSED CONTAMINATION NOT FOUND AT TIME
OF REMEDIAL ACTION.:
RADIOLOGlCAlt AS-BLilLT
!j.FIGURE 7 1 I
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U.S. DEPARTMENT OF ENERGY
GRAND JUNCTION PROJECTS OFFICE, COLORADO
"SO 2&
EnTZsTSi
»U»MITTCD.
81 EAST THIRD SOUTH STREET
MONTICELLO, UTAH
BATI lAPMbvAi Doi~
Geotech, Inc.
OOIIDM f— 1 ys-oom-vL
owa.wo. S-booiti-vi T
56 58 60 62 64 66 68 70 72 7'
DOE ID No.: MS-O0183-VL
Property Address: 81 East Third South 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] [ ]
[ ] [ ]
[ ] [ ]
[ 1 [X]
[X] [ ]
[ ]
[ ]
[X]b
[X]b
[ ]
[ ]
[/] [ ]
M [ 1
[ ] [ ]
[ ] [ ]
[ ] [Jl
[y\ [ )
[ ]
[ }
[ ]
^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.
bVacant lot.
1 of 2
DOE ID No.: MS-00183-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.
iel C. Butherus <f »
*er, Monticello Program^
Date
Manage:
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.
J °t<i?
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