ML20141F477
| ML20141F477 | |
| Person / Time | |
|---|---|
| Site: | 07000734 |
| Issue date: | 11/11/1985 |
| From: | GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER |
| To: | |
| Shared Package | |
| ML19276D143 | List: |
| References | |
| 26074, NUDOCS 8601090379 | |
| Download: ML20141F477 (85) | |
Text
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GA reunio,vvi..
REPORT ON DECONTAMINATION AND DECOMMISSIONING OF GA TECHNOLOGIES' OLD WASTE PROCESSING FACILITY AND SURROUNDING AREAS PHASE I By GA Technologies Inc.
P.O. Box 85608 San Diego, California 92138 And AWC, Inc.
4335 West Tropicana Las Vegas, Nevada 89103 l
November 11, 1985 2667V B601090379 85111974]
ADOCK 07
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CONTENTS 1.
INTRODUCTION..
1 1.1.
Areas to be Released to Unrestricted Use.
1 I
1.2.
Site Description......
2 1.3.
Obj ectives...
3 2.
SUMMARY
5 3.
TARGET CRITERIA FOR UNRESTRICTED RELEASE.
7 3.1.
Facility and Equipment 7
3.2.
Direct Radiation.
7 3.3.
Inhalation Pathway..................
7 3.4.
Ingestion Pathway 10 3.5.
Summary of Limiting Concentrations for Direct Radiation and Inhalation Dose Limits.
10 4.
RADIATION DETECTION INSTRUMENTATION 13 4.1.
Ludlum Model 19 MicroR Meter.....
13 4.2.
Ludlum Model 3 GM Survey Meter............
13 4.3.
Eberline Model R0-2 Ion Chamber 13 4.4.
Eberline E-520 GM Survey Meter............
13 4.5.
Eberline PAC 4S Alpha Survey Meter.
14 4.6.
Davidson Multi-Channel Analyzer 14 4.7.
Canberra Model 2404 Alpha, Beta, Gamma Systeta 14 4.8.
Germanium-Lithium-Ge(Li) Detector System.
14 4.9.
Instrument Calibration................
14 5.
PERSONNEL PROTECTION.
17 5.1.
Protective Clothing 17 5.2.
Personnel Monitoring.................
17 5.3.
Air Sampling..
17 5.4.
Personnel Surveys 17 5.5.
In Vivo Total Body Counts 18 iii
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6.
INITIAL SURVEY AND SOIL SAMPLING.
19 6.1.
Natural Background Assessment 19 6.2.
External Radiation Survey Procedures..
19 6.3 Soil Sampling 20 7.
DECONTAMINATION METHODS 23 i
7.1.
Facilities and Equipment 23 7.2.
Decontamination of Soil in Areas B, C, and D.
25 7.3.
Decontamination of Soil in Area A 26 8.
COMPLIANCE WITH THE TARGET CRITERIA 29 8.1.
Facilities and Equipment 29 8.2.
Direct Radiation..
29 8.3.
Inhalation of Particulates.
30 8.4.
Ingestion of Vegetation 31 9.
RADIOACTIVE WASTE SUMHARY 33 9.1.
Radionuclide Concentrations and Volumes 33 10.
CONCLUSION.
35 APPENDIX 1: SOIL SAMPLES TAKEN PRIOR TO DECONTAMINATION 37 APPENDIX 2: RESULTS OF SOIL SAMPLES COLLECTED AFTER CLEANUP 45 Table 2-A: Area "A" Soil Sample Results.
47 Table 2-B: Area "B" Soil Sample Results.
48 Table 2-C: Area "C" Soil Sample Results.
49 Table 2-D: Area "D" Soil Sample Results....
50 APPENDIX 3: FINAL SOIL SAMPLE RESULTS 51 l
Table 3-A: Final Area "FA" Soil Sample Results 53 Table 3-B: Final Random "FR" Soil Sample Results 56 APPENDIX 4: AIR SAMPLE DATA 57 APPENDIX 5: WIPE SURVEYS.............
59 APPENDIX 6: SR-90 RESULTS OF SOIL SAMPLES PRIOR TO DECONTAMI-NATION.
63 APPENDIX 7: ANALYSIS OF VEGETATION (BRUSH) FROM WASTE YARD l
PONDS AND CANYON.
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l APPENDIX 8: RELEASE OF CONCRETE FROM EVAPORATION PONDS AS l
NON-RADIOACTIVE 67 l
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FIGURES 1A.
Principal area to be released 89 IB.
Areas to be released in Phase I and Phase II.
91 2.
Initial survey readings 93
(}3. Initial soil sample locations 95 (4. Cleanup areas "A,"
"B,"
"C," and "D" 97
~.)
SA.
Final survey reading for Phase I...
99 5B.
Final survey readings for Phase I 101 l 6.
Cleanup soil sample locacions 103
'Y.
Final soil sample locations 105
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TABLES 1.
Acceptable surface contamination levels.
8 2.
Individual concentration in soil resulting in an annual inhalation dose of 20 mres to the lung and 60 mrea to the bone 9
3.
Dose commitment resulting from ingestion (vegetable, beef, silk) of radionuclides from contaminated vegetation (brush, weeds, etc.)
11 4.
Derived annual limiting concentrations for various groups of radionuclides 12 5.
Soil volumes and radionuclide concentrations 33 6.
Total activities of major radionuclides in the soil removed...............
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INTRODUCTION 1 1.
AREAS TO BE RELEASED TO UNRESTRICTED USE The GA Technologies Inc. (GA) old Waste Processing Facility (WPF) and the surrounding canyon and ridge areas have been selected for decon-tamination and decommissioning (D&D) under the requirements specified in NRC Docket 70-734: Plan For Obtaining Release of Certain Areas to Unrestricted Use, herein referred to as the Plan.
The decontamination project was started by GA in July 1984 and a contract was issued to AWC, Inc. to provide additional support beginning November 1984.
The principal area to be released to unrestricted use is shown in Figure IA.
The area includes the Waste Processing Facility, the associ-ated canyen area and other land (mainly hillsides and canyons) surround-ing the facility. Due to the complexity of the project, it was deter-mined that the work efforts for release of this area would be handled in two phases.
The work performed under Phase I of the project was to prepare the area within the boundary shown in Figure IB, except the areas indicated as Phase II, for release to unrestricted use.
This report provides information on the decontamination /
decommissiocing conducted for Phase I of this project. The target criteria for_ unrestricted release, the method used, and the data showing compliance with the target criteria, are provided.
NRC Docket 70-734: Plan for Obtaining R'elease of Certain Areas to 4
Unrestricted Use, GA submittal letter 696-8023.
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1.2.
SITE DESCRIPTION Figure 1A shows the specific area enclosed within the boundary to I
be prepared for release to unrestricted use. This portion of GA's site represents about 80 acres. Due to the complex operations required to handle and dispose of the large volume of contaminated soil, the work
)
efforts preparing this area for release to unrestricted use will be conducted in two phases.
The work conducted under Phase I includes the area within the boundary shown in Figure IB except the three areas designated Phase II.
The Phase I area contains approximately 78 acres.
i 1.
The contaminated (affected) areas in Phase I represent about two acres of land. These affected areas are designated Area A (canyon area below the Waste Processing Facility), Area B (canyon area below the evaporation ponds), Area C (area north of ponds) and Area D (evaporation ponds). Figure 4 shows these areas in greater detail. The Phase II areas shown in Figure 1B are the incinerator site, the old Waste Processing Facility and a small area where asphalt contaminated with low levels of uranium and thorium was buried in 1974 under GA's Radioactive Material License issued by the State of Cali-fornia. The Waste Processing Facility site and the incinera-tor site are covered with concrete or asphalt and are being used as staging areas for the contaminated soil removed from i
the affected areas. A brief description of the contaminated areas is provided below.
2.
The canyon areas (Area A) is the ~3/4 acre area adjacent to i
and below the old Waste Processing Facility. Water runoff from the facility enters the canyon area.
3.
The canyon area is a one acre area adjacent to the solar evap-oration ponds, Waste Processing Facility and incinerator pad.
2
A spill in 1972 from the evaporation ponds contaminated part of this canyon area directly below the ponds with approxi-mately 100 gas of enriched uranium along with thorium, Cs-134, Cs-137, Co-60 and Sr-90.
4.
The hillside above the ponds, (Area C) is on a ~1/2 acre area which contained discrete localized plots of contaminated soil.
5.
The Solar Evaporation Ponds consisted of four sets of three 20 ft x 20 ft concrete ponds 1 ft deep designed to contain contaminated liquid which in turn is evaporated by solar energy. Three sets of ponds were used for liquid waste con -
taining enriched uranium and thorium. The fourth pend con-tained liquid waste contaminated with mixed fission and acti-vation products. Through the years there was some cross contamination of the ponds necessitated by one or the other set of ponds being full when there was a need to place addi-tional liquid waste in the ponds.
Sludge was periodically removed, packaged and disposed of to an approved radioactive waste land burial site.
1.3.
OBJECTIVES The objective of this project was to remove all sources of radia-tion and contamination so that the area meets the requirements for release to unrestricted use, as specified in the Plan.
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2.
SUMMARY
The decontamination / decommissioning of GA's old Waste Processing Facility and surrounding area is being conducted in two phases. This report documents the activities conducted under Phase I.
Phase I areas are the Solar Evaporation Ponds, the canyon areas below the Waste Processing Facility and the solar evaporation ponds, and the areas of raw land (mainly canyons and hillsides) surrounding these areas. Phase I consists of ~78 acres, approximately two of which con-tained soil contamination exceeding the target criteria for release to unrestricted use as described in the GA Plan. These affected areas (i.e., contaminated) were decontaminated as part of the Phase I ef fort.
Every location was decontaminated to:
1.
Meet the license criteria for release of a facility or equip-ment to unrestricted use.
2.
Remove any contaminated soil until the residuals meet the NRC policy (SECY 81-576) Option 1 eriteria.
Approximately 82,000 cu ft of soil containing about 480 millicuries of activity was removed for disposal at an approved radioactive waste land burial site.
All the areas within the Phase I boundary were decontaminated below the target criteria for release to unrestricted use.
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3.
TARGET CRITERIA FOR UNRESTRICTED RELEASE The following target criteria are taken from the U.S. Nuclear Regu-latory Commission (USNRC) approved decontamination plan for release of certain areas to unrestricted use.
3.1.
FACILITY AND EQUIPMENT Table 1 is taken from USNRC's criteria for releasing facilities and equipment to unrestricted use. This table was used for releasing proc-ess equipment or buildings to unrestricted use.
It has been incorpo-rated into our SNM-696 license. Ponds, tanks, etc., were treated as process equipment. The above criteria will not be atilized for soils.
3.2.
DIRECT RADIATION External radiation (ganma dose rate in air one meter above ground level) shall not exceed 10 UR/hr above background for a diffuse source
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area (a contaminated area greater.than 30 ft x 30 ft) and shall not 3.
exceed 20 pR/hr above background for a discrete area (a contaminated area smaller than 30 ft x 30 ft).
3.3.
INHALATION PATHWAY Table 2 containe values of soil contamination (pCi/ge) shich if residing on the~ surface and inhaled would not lead to an exposure exceeding the Option I acceptability limit. Soil contamination above these Table 2 values may be acceptable under certain circumstances but only if a specifically analyzed intrusion scenario shows that any individual will not be exposed to radiation levels greater than those appropriate for NRC/ EPA Option I.
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TAhLE 'l ACCEPTABtE SURTACE C0i TAHINATI0ll LEELS NUCLILE58 AVERAGEb c -f yn gyugh d f REMOVABLEbef U-nat. U-235. U-238 and 2
associateil decay products 5.000 dem e/100 cm 15.000 dem /100 cm2 1.000 dpa e/100 cm2 Transuranics. Ra-226. Ra-220 Th 239. Th-220, pa-231 100 dpm/100 cm2 300.ips/100 cm2 20 dan /100 cm2 Ac-227. 1-125. 1-129 Th-nat. Ih 232. Sr 90 Pa 223. Ra-224. U-232. 1-126, 1000 dpe/100 cm2 3000 c'pe/100 ce2 200 dem/100 cm2 1-131. 1-131 Beta ganes cealtters (nucildes with decay sedes other than alpha emission or spontaneous 5004 Jpm sy/100 cm2 15.000 dpa sy/100 cm2 1000 dpa sy/100 c 2 Co fission) except Sr-90 and others noted above.
a t.cee surf ace contamination by both alpha-and beta-gaasne-emitting nuclides exists, the Ilmits estabitshed for alpha-and beta gaerna-ewf tting a
- uclides should apply independently, b s used in this table, dpg (disintegrations per minute) means the rate of emission by radinactive riaterial as determined by correcting the A
counts e,er minute observed by an appropriate detecter for background, ef ficiency and geoenetric far.tnis associated with the Instrw'ienta tion.
(ficasuserents of average contaminant should not be averaged over riore than I square meter. Far objects of less surface area, the average sho eld I,e der tved for each such object.
dIhe snaalmum contamination level applies to an area of not more than 100 cm2 2
'Ihe aawmat of renovable radt.aactive material per 100 cra of surface area should be deterslaed by wiping that area with dry filter or sof t absorbent paper, ag. plying moderate gis essure, and assessing the amount of radioactive material on the wipe with an appropriate instrument of nro m etficiency. 1; hen removable contamination on objects of less surface area is determined, the pertinent levels should be reduced proportionally and the entire surface should be wiped.
Ilhe avesage and maaleman radiation levels associated with surface contaniination resulting from beta-ginsna emitters should not esceed 0.2 erad/hr at I cm and 1.0 maad/hr at I cm. respectively. measured through not more than 7 milligrams per square centlecter of total al.saiber.
TABLE 2 INDIVIDUAL CONCENTRATION IN SOIL RESULTING IN AN ANNUAL INHALATION DOSE OF 20 area TO THE LUNG (a) AND 60 mrem TO THE BONE (b)
Derhed Concentration (pCUg)
Solubility Radionculide Classification Lung (20 mrem)
Bone (60'erem)
U-238 Y
35 1.2 x 10 2
3 U-238 W
3.2 x 10 3.9 x 10 4
3 U-238 D
1.9 x 10 1.2 x 10 U-235 Y
35 1.2 x 10 2
3 U-235 W
3.2 x 10 3.9 x 10 4
3 U-235 D
1.9 x 10 1.2 x 10 U-234 Y
30 1.0 x 10 2
3 U-234 W
2.8 x 10 3.6 x 10 4
3 U-234 D
1.7 x 10 1.1 x 10 Th-232 Y
35 2.6x10{
2 Th-232-W 3.3 x 10 1.0 x 10 Ra-228 W
3.3 x 10 2.9 x 10 Th-228("}
3 Y
20 1.8 x 10 I
2 2
Th-228 W
1.3 x 10 3.3 x 10 Co-60(d) 6 Y
1.2 x 10 1.6 x 10 6 Co-60 W
1.2 x 10 5.8 x 10 Cs-137(d) 6 D
9.6 x 10 1.8 x 10 Sr-90(d)
Y 1.8 x 10 2.6 x 10'4 Sr-90 D
1.6 x 10 2.8 x 10
- Pulmonary lung (570 ga); consistent with EPA's Transuranics Guidance.
Bone means osseous tissue, (5,000 ga); consistent with EPA's fransuranic Guidance.
The daughters of Th-228 and Ac-228 do not contribute significantly to the inhalation dose bertuse of their comparatively short half-lives.
Solubility classifications are based on ICRP-30.
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3.4.
INGESTION PATHWAY Tha GA site is located within a semi arid region zoned for light industry and Research and Development. The area is not, nor will likely be, allowed any residential or agricultural land usage. There is no potable water on the site or sus environs. A brackish water table is approximately 275 to 300 ft deep at about the same level as the nearby salt water backwater and marshes. Therefore, the pathway for ingestion of any residual contamination via any food or water is highly improb-able.
However, vegetation (brush, weeds, etc.) removed from the GA site for unrestricted disposal could possibly enter the ingestion pathway.
Therefore, the contamination levels of such vegetation must satisfy the target criteria for ingestion exposure (as well as the target criteria for direct radiation and inhalation exposure).
t The target criteria for food ingestion exposure is 30 mres/yr to the bone (NRC Policy Issue SECY-81-576). The dose commitment resulting j
from ingestion (vegetation, beef, milk) of radionuclides from contami-nated vegetation are shown in Table 3.
These values are based upon a unit concentration of 1 pCi/ gram of each radionuclide in the vegetation.
l 3.5.
SUMMARY
OF LIMITING CONCENTRATIONS FOR DIRECT RADIATION AND INHALATION ?OSE LIMITS Table 4 summarizes the derived limiting concentrations of various groups of radionuclides for the compliance of the direct radiation and inhalation dose limits. Meeting the target criteria in Table 4 will indicate that the residuals satisfy the Option I acceptability criteria.
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TABLE 3
- DOSE COMMITMENT RESULTING FROM INGESTION (VEGETATION, BEEF, MILK) 0F RADIONUCLIDES FROM CONTAMINATED VEGETATION (BRUSH, WEEDS, ETC.).
FIGURES BASED ON A UNIT CONCENTRATION OF 1 pCi/g 0F EACH NUCLIDE IN THE VEGETATION.
Bone Dose Radionuclides (mrem /yr)
U-238 1.9E-0 U-235 1.9E-0 U-234 2.2E-0' Th-232 2.1E-0 Th-230 2.0E-0 4
Th-228 4.0E-1 Ra-228 4.5E-0 Ra-226 8.9E-0 Sr-90 6.1E-0 Cs-137 2.3E-1 Pu-239 5.6E-2
Reference:
NRC's Docket No.70-820 - United Nuclear Corporation Resources Company " Soil Decontamination Criteria for the Decommissioning of the UNC's Facility." Scrap Recovery Junction, Rhode Island.
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TAELE 4 DERIVED ANNUAL LIMITING CONCENTRATIONS FOR VARIOUS GROUPS OF RADIONUCLIDES Derived Limiting Concentration (PCi/g)
Rad a on(*
Inhalation Radionuclide Lung (20 area)
Bone (60 ares)
(10 pR/hr)
Depleted uranium U-238, U-234 (Y) 35 2
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U-238, U-234 (W) 3.2 x 10 2
U-238, U-234 (D) 8.0 x 10 High-enriched uranium U-234, U-235 (Y) 30
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2 U-234, U-235 (W) 2.8 x 10 2
U-234, U-235 (D) 8.0 x 10 Natural Thorium Th-232, Th-228 (Y) 10 Th-232, Th-228 (W) 10 Cobalt Co-60 (Y) 8 Co-60 (W) 8 Cesium Cs-137 (D) 15 Strontium Sr-90 (Y) 1.8 x 10 4
Sr-90 (D) 2.8 x 10
(*}GA prefers to use an instrument (microR meter) to demonstrate compliance of 10 pR/hr above background at one meter for dif fuse areas.
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4.
RADIATION DETECTION INSTRUMENTATION The following radiation detection instruments were used for radia-.
tion surveys:
4.1.
LUDLUM MODEL 19 MicroR METER The microR meter used for radiation surveys was manufactured by Ludlum Measurements (Model 19) and was used for direct measurements of external gamma radiation. The instrument has five linear ranges: 0 to 25 pR/hr, O to 50 pR/hr, O to 250 pR/hr, O to 5000 pR/hr.
4.2.
LUDLUM MODEL 3 CM SURVEY METER Tha geiger counter used was manufactured by Ludlum Measurements and has a Model 3 count rate meter with a Model 44-9 pancake probe used for field monitoring of low icvel beta / gamma radiation. The " pancake" GM detector has a window thickness of less than 7 ag/cm.
The instrument has four ranges: 0 to 500 cpa, O to 5000 cpa, O to SD,000 cps, and 0 to 500,000 cpm.
4.3.
EBERLINE MODEL RO-2 ION CHAMBER An ionization chamber manufactured by Eberline (Model R0-2) was used in one small area of the pond where the gamma readings exceeded 5 mR/hr. The instrument has four scales: 0 to 5 mR/hr, O to 50 mR/hr, O to 500 mR/hr and 0 to 5000 mR/hr.
4.4.
EBERLINE E-520 GM SURVEY METER Another geiger counter, the Eberline E-520 count rate meter with HP-260 " Pancake" GM detector having a window density thickness of less 13
,y.
.-.. ~., - -.-... - _.-
was used for field monitoring of low level beta / gamma than 7 ag/cm radiation. The instrument has five ranges: 0 to 250 cpa, O to 6
2500 cpa, O to 25,000 cpe, O to 250,000 epa, and 0 to 2.5 x 10 cpa.
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.4.5.
EBERLINE PAC 4S ALPHA SURVEY METER I
Alpha Survey meters manufactured by Eberline (Model PAC 4S) were 4
j used for field monitoring of T.ow level alpha radiation. The instrument v
0 has two logarithmic ranges of 0 to 20,000 cpa and 0 to 2 x 10 cpa.
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4.6.
DAVIDSON MULTI-CHANNEL ANALYZER l
j The Davidson Model 4106 Multi-Channel Analyzer (MCA) and 3 in. x 3'in. NaI detector were used for well logging gamma esitting radionu-clides. The analyzer and detector were calibrated using naturally occurring radioactive isotopes present in the soil and comparisons with i
soil sample analysis.
i 4.7.
CANBERRA MODEL 2404 ALPHA, BETA, GAMMA SYSTEM 4
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A Low Level Alpha, Beta, Gamma Counting System manufactured by l
Canberra Industries, Inc. (Model 2404) was used to count air samples, l
wipes, and soil samples taken during the decontamination project.
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4.8.
GERMANIUM-LITRIUM-Ge(L1) DETECTOR SYSTEM l
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Two Ge(Li) detector systems were used to perfore the gamma spectrum I
analysis on the soil samples.
Results have been stored permanently on magnetic tape at GA.
4.9.
INSTRUMENT CALIBRATION All instruments were maintained and properly calibrated. Three microt meters were calibrated by the manufacturer (Ludlum Measurements, Inc.) prior to starting the decontamination efforts. Three GA and two 14 l
AWC microR meters were checked for consistent readings every two days.
The five instruments all read within 11.5 pR/hr.
All instruments (except microR meters) are calibrated on a six month schedule and were checked daily using a check source to verify proper instrument response.
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PERSONNEL PROTECTION 5.1.
PROTECTIVE CLOTHING During the removal and stockpiling of contaminated soil, asphalt and concrete, all personnel were kept out of the dust generated to every extent possitte. The requLrement for protective clothing was relaxed after the first week since no contamination had been found on air samples, hands, shoes, or clothing.
5.2.
PERSONNEL MONITORING All personnel permanently assigned to the Waste Processing Facility decontamination effort were assigned appropriate personnel monitoring devices by GA.
5.3.
AIR SAMPLING Air samples were collected during the removal and stockpiling of contaminated concrete, asphalt, and soil. One air sampler was stationed downwind from each primary work area. Air samples were allowed to decay for at least a 24 hr period prior to counting to nilow the naturally occurring daughters of radon to decay. Results of these air samples are shown in Appendix 4.
Results show airborne radioactivity concentrations l
were relatively low.
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5.4.
PERSONNEL SURVEYS All personnel involved in the decontamination effort were surveyed prior to coffee breaks, lunch break, and before leaving the area at the end of each work day. These personnel surveys verified that proper i
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I contamination control procedures were in place and effective in all work areas.
5.5.
IN VIVO TOTAL BODY COUNTS Personnel that were scheduled for steady work on the project were given an in vivo total body count before starting the work project. At the completion of the project after the contaminated soil is disposed of and the Phase II cleanup completed, they will again be given an in vivo total body count to compare with the initial one.
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6.
INITIAL SURVEY AND SOIL SAMPLING 6.1.
NATURAL BACKGROUND ASSESSMENT For the purposes of the decontesination and final radiation survey of the WPF and surrounding areas, the background to be subtracted from
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the gross radiation measurements was determined based on numerous meas-urements taken adjacent to and within 1/2 mile of the WPF. The back-ground varied from 13 to 18 pR/hr, theref ero it was decided to use 15 DR/hr as background.
6.2.
EXTERNAL RADIATION SURVEY PROCZDURES The external radiation surveys were conducted using a microR meter to measure direct radiation exposure.
The initial survey was a " walkover" survey, consisting of random readings taken in order to locate affected areas. Readings were recorded for any location whenever they exceeded 10 pR/hr above back-ground at one meter above the surface.
The affected areas were identified and surveyed on a 10 f t x 10 f t grid. These areas were later identified as Area A (below the Waste Processing Area), Area B (canyon below the evaporation ponds), Area C (north of evaporation ponds) and Area D (ponds). These areas are shown in Figure 4.
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Measurements at each grid intersection were recorded. If the level did not exceed 10 pR/hr above background measured at one meter above the surface, the surveyor moved to the next grid intersection.
If the level exceeded 20 pR/hr above background (at one meter), a surface reading was also taken. The readings are shown in Figure 2.
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6.3.
SOIL SAMPLING After the affected areas were identified, soil samples were col-lected to identify the radionuclides present and their quantities to j
assist in characterizing the site. Core samples were obtained in the solar evaporation ponds (Area D), the spill area below the ponds (Area B), the canyon floor, and north of the solar evaporation ponds (Area C), to evaluate the extent of subsurface contamination.
Samples were collected in Area A at various depths at 6 to 12 in.
increments to a maximum depth of 4 ft.
Beyond this depth soil sample radionuclide concentrations were below the target criteria.
The samples were collected, prepared, and analyzed as described below.
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Collection.
a.
The surface vegetation (brush and weeds) were removed by cutting off at ground level, not uprotted.
b.
Surface samples (0 to 1 in.) were collected; approxi-mately 2 kilograms of soil sample.
c.
A composite soil sample O to 6 in., 1 in. to 6 in. or 1 in. to 12 in were collected based on the area and estimated depth of contamination.
d.
If subsurface soil contamination was found, then addi-l tional samples (e.g., core samples) were taken at suffi-cient depths to provide an estimate of the extent of contamination.
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Preparation.
a.
The soil samples were free of vegetation and rocks.
b.
The samples were dried to remove moisture.
c.
The sample was ground to a fine powder with no " clumping" (clumping would be due to excess moisture), or were crushed and mixed to eliminate clumping and to homoge-nize.
Analysis.
1 a.
The soil samples were analyzed by gamma ray spectroscopy using Ge(Li) detector systems. The analyses were per-formed to written procedures. All gamma emitting radio-nuclides were identified and their concentrations were dete.rmined. The Th-232 value was obtained based on the concentrations of the daughter radionuclides. Th-232 was assumed to be in equilibrium with its daughters.
b.
Wet chemistry was performed on selected soil samples to measure concentrations of Sr-90.
Soil samples from every affected area were analyzed for Sr-90.
Figure 3 shows the soil sample collection locations.
The analytical results are provided in Appendix 1.
The gamma ray spectroscopy results showed that the predominant radionuclides present were Cs-137, Co-60, U-235 and Th-232. The Sr-90 concentrations are pro-vided in Appendix 6.
The highest levels were foun' so Area D, the solar evaporation ponds. Sr-90 was found in areas vbe 9
-60 and Cs-137 was u-also present, therefore, the cleanup of arety eit h. -137 and Co-60 con-tamination would also clean up Sr-90 contamination.
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7.
DECONTAMINATION METHODS 7.1.
FACILITIES AND EQUIPMENT Concrete from the twelve solar evaporation ponds was released for unrestricted disposal on August 23, 29, 30 and 31, 1984 based on the following:
1.
Surveys of the concrete remaining af ter surface scabbling showed calculated disintegrations per minute per 100 cm areas of the ponds were within the limits provided in Table 1.
2.
Instruments used in the survey were calibrated against standards and efficiencies and correction factors uere determined.
3.
Corrections for background radiation were conservative.
The method used, instruments and data associated with the grid surveys of the concrete surf aces was summarized in a report prepared and submitted to the NRC in October 1984. This report is provided in Appendix 8.
In addition to the concrete from the twelve (12) solar evaporation ponds, an additional 3200 cu f t of asphalt and concrete were surveyed by AWC, Inc. and released to unrestricted use.
Surfaces had been scabbled or jackhammered if contamiration was detected. Any material found with detectable contamination was transferred to the soil staging area (Phase II) for later disposal at an approved radioactive waste land bur-ial site. The " clean" material was segregated and a request made to the NRC for release of the material as non-radioactive.
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Radiation surveys consisted of the following:
1.
A GM survey with pancake probe to detect surfaces contaminated with beta emitting radionuclides. The pancake probe was placed within 1/2 in. of the surface and mov'ed sufficiently slow to detect any radiation above background.
2.
Where surf aces required an alpha survey, an alpha scintilla-tion probe was used. The scintillation probe was placed on the surface to be surveyed for 10 to 15 seconds and the reading observed.
3.
For gamma radiation surveys, a microR meter was used to meas-ure radiation levels at a given point. The meter was held at the desired position above the measured surface for 5 to 10 seconds or until the meter reading stabilized. Measure-ments were taken at one meter above the surface or at contact, as indicated in the survey results.
4.
Wipe samples were taken inside and outside all the buildings on the floors, walls, and ceilings and counted for beta and alpha radiation. All equipment used was also wipe surveyed before leaving the area. The results of these surveys are shown in Appendix 5.
The minimum detection limits for the instruments used to survey the asphalt and concrete are:
alpha:
10 dpm/100 cm area 2
beta / gamma:
1500 dpm/100 cm area gamma:
3 pR/hr.
4 24
7.2.
DECONTAMINATION OF SOIL IN AREAS B, C, AND D The soil in affected Areas B, C, and D identified in Figure 4 was contaminated primarily with Cs-137 and Co-60, with lesser concentrations of Sr-90, U-235 and Th-232.
Because of this, direct radiation measure-ments were used to demonstrate compliance for both the external radia-tion dose and inhalation criteria.
9 The highest levels of contamination were located with the microR meter. All the soil with contamination levels exceeding 10 pR/hr above background at approximate ground contact was removed with a large back-hoe (Grade All) and transferred by truck to the soil staging areas.
When the cleanup was completed and verified based upon detecting less than 10 pR/hr above background at one meter above the surf ace, soil samples were collected and analyzed to confirm compliance. The first foot of soil was collected, prepared, and analyzed to:
1.
Verify the correlation between the pR/hr readings and the soil contamination concentrations.
2.
Check compliance with the inhalation criteria for these areas.
The locations of these soil samples are shown in Figure 6.
The results of the analyses are provided in Tables 2-B, 2-C, and 2-D of Appendix 2.
The samples were analyzed by gamma ray spectroscopy using a Ge(Li) detector system, and for gross beta concentrations by counting a sample on a low-level alpha-beta counting system. These results provide maximum values for Sr-90 if it is assumed that all the beta activity is Sr-90.
Since the inhalation dose limit for Sr-90 is 1800 pCi/g (Table 4) and the gross beta values are well below this level, compli-ance with the inhalation dose limit is demonstrated, even when the doses from the other radionuclides are added to the total dose. For example, a level of 100 pCi/g would only add ~6% to the total lung dose limit of 25
20 mrem /yr. All gross beta results in the soil samples from these areas were <100 pCi/g.
7.3.
DECONTAMINATION OF SOIL IN AREA A The same decontamination method described above for Areas B, C, and D was used to remove soil in Area A to levels which met the release criteria.
Soil was removed until the pR reading was less than 10 pR/hr above background at one meter. Then eight (8) soil samples were collected, prepared, and analyzed. Two (2) of the eight (8) samples (A-2 and A-8) showed U-235 levels above the inhalation dose limits. Additional soil was removed in these two locations until the rationuclide concentrations met the inhalation dose limit. The results are provided in Table 2-A of Appendix 2 and the soil sample locations are shown in Figure 6.
Since the pR meter readings were not the controlling criterion in this area, i.e., a correlation did not exist between pR meter readings and the results of soil sample analyses to meet both the inhalation and direct radiation pathway limits, additional soil sampling was conducted.
A correlation did not exist due to the relatively high levels of U-235 in comparison to Cs-137 and Co-60.
Representative soil samples were then collected at each 30 ft x 30 ft grid from the first inch (1 in.) of soil and analyzed. The sub-surface soil (1 in, to 12 in.) was also collected to determine the extent of subsurface contamination. Although, only 5% of the subsurface samples needed to be analyzed according to GA's Plan, at least 98% of them were analyzed to determine subsurface contamination levels.
When results indicated contamination levels exceeding the inhala-tion dose limit concentrations, additional soil was removed until further soil sampling showed the limit was met.
26
Initial analysis of Sr-90 concentrations in soil samples collected in Area A prior to decontamination indicated no Sr-90, therefore it was conservatively assumed that Sr-90 was present at the level of detection.
i.e., <5.5 pCi/g.
Section 8.3 provides further information on the results of the soil samples.
27
8.
COMPLIANCE WITH THE TARGET CRITERIA 8.1.
FACILITIES AND EQUIPMENT Asphalt and concrete from the evaporation ponds, retaining walls and other areas around the Waste Processing Facility were surveyed for contamination. The results were compared to the release limits in Table 1.
Material found with detectable contamination was placed in the contamination soil staging areas for later shipment to an approved radioactive waste land burial site. The " clean" material was segregated and the NRC was requested to release the material for unrestricted dis-posal, e.g.,
ship to landfill.
8.2.
DIRECT RADIATION The direct radiation level of 10 DR/hr above background was intended as a target criterion for open land cleanup. The radiation level was measured using calibrated microR meters capable of distin-guishing from background levels.
Upon completion of soil decontamination, a final survey was made of the waste processing and canyon areas. The purpose of this survey was to verify all significant contamination had been removed and the area meets the target criteria.
To demonstrate compliance with the direct radiation limit, r.he affected areas were divided into grids about 30 f t x 30 f t for surveying purposes and the following conditions had to be met:
External radiation (gamma dose rate in air one meter above ground level) could not exceed 10 pR/hr above background for a diffuse source area (a contaminated l
29 I
area greater than 30 ft x 30 ft) and could not exceed 20 pR/hr above background for a discrete area (a contaminated area smaller than 30 ft x 30 ft).
The affected areas (Areas A, E, C, and D) were surveyed on a 10 ft x 10 ft grid. The results of the survey are shown in Figure SA.
All radiation levels were <10 pR/hr above background, measured at one meter above ground level.
Land surrounding the affected areas but within the Phase I boundary was surveyed for external radiation by a " walkover" survey at 30 f t intervals. The results of this survey are shown in Figure 5B.
All radiation levels were less than 10 pR/hr above a 15 pR/hr background.
In general, the levels in Figure SB are a few microR/hr above the back-ground selected for this area. However, soil samples collected from several locations remote from the affected areas and analyzed for the various radionuclides did not confirm the presence of contamination in the soil. Thus it appears that a higher background may have been more appropriate with regard to the direct radiation measurements.
8.3.
INHALATION OF PARTICULATES Table 2 summarizes the derived soil contamination limits for each inhaled radionuclide, which result in a committed dose of 20 ares /yr to the lung and 60 area /yr to the bone.
It is noted that Table 2 soil limits are for individual radionuclides. When a mixture of these radio-nuclides existed in soil, the following formula was applied to show compliance:
1 the sum of Ci/Li i 1 where Ci = the average soil concentration of radionuclide i, Li = the derived maximum soil limit for radionuclide i i
(from Table 2).
30 l
In Areas B, C, and D, a correlation existed between the microR meter readings and the results of soil sample analyses due to the rela-tively high concentrations of Cs-137 and Co-60 as compared to U-235.
The results are provided in Tables 2-B, 2-C, and 2-D of Appendix 2.
These results established that both the inhalation and direct radiation pathway limits were met when using the direct microR meter readings.
In Area A, final soil samples were collected after decontamination was completed, on a 30 ft x 30 ft grid. The top one icch (1 in.) of soil was collected and analyzed for the various radionuclideo to demon-strate compliance with the target criteria given in Table 3.
The loca-tions of the soil samples collected are shown in Figure 7 and the results of the analyses are provided in Table 3-A of Appendix 3.
Since the derived concentrations in Table 2 also apply to subsurface soil con-tamination, samples were collected at each location from one inch to one foot (1 in. to 1 ft) and analyzed to determine the extent of subsurface contamination. The results of these analyzes are also provided in Table 3-A of Appendix 3.
Although GA's Plan specified that only 5% of the subsurface samples needed to be analyzed, about 98% of the samples were analyzed. Both the surface and subsurface soil radionuclide concentrations are within the inhalation dose pathway limits.
Eighteen random surface soil samples were also collected from 4
Areas A, B, C, and D, representing about 8% of the grid locations.
These results are provided in Table 3-8 of Appendix 3 and also meet the criteria.
8.4.
INGESTION OF VEGETATION (Brush, weeds, etc.)
l Table 3 summarizes the derived vegetation contamination limits for each ingested radionuclide which would result in a committed dose of 30 mres/yr to the bone. The vegetation contamination limits given in l
Table 3 are for individual radionuclides.
For a mixture of these l
l l
31
radionuclides present in vegetation, the following formula was applied to demonstrate compliance:
the sum of Ci/Li < l.0 where Ci = average concentration of radionuclide i in vegetation, Li = derived limit for radionuclide i in vegetation (from Table 3).
The vegetation (brush, weeds, iceplant, etc.) was removed from Areas A, B, C, and D prior to removal of contaminated soil. The vegetation was cut at the surface level avoiding the removal of any roots and associated soil, and was placed in a staging area.
Several samples of the vegetation were collected from each of the five piles. The samples were dried and analyzed for radioactivity by gamma spectroscopy using a Ge(Li) detector system. The five samples were then composited and analyzed for Sr-90 by wet chemistry techniques.
The results are provided in Appendix 7.
The levels show compliance with the radionuclide concentrations shown in Table 3.
Samples of the vegetation were collected by the NRC for their inde-pendent analysis. Their analysis also showed compliance with the crt-l teria, and approval was given to GA to dispose of the vegetation as non-radioactive in a local sanitary landfill facility.
32
-m-_
1 I
t 9.
RADIOACTIVE WASTE
SUMMARY
4 9.1.
RADIONUCLIDE CONCENTRATIONS AND VOLUMES Table 5 lists the area, soil volume, and average concentration of the predominant radionuclides present in the soil.
TABLE 5 SOIL VOLUMES AND RADIONUCLIDE CONCENTRATIONS l
Radionuclide Concentrations (pci/g)
Soil volume Area Cu Ft Co-137 Co-60 U-235 Th-232 Sr-90 A.
10,020 2
0.1 2
24
<5.5(*)
B 14,580 46 6
1.4 5
35 C
1,350 100 3
2 3
8 D
55,755 82 39 0.4 2
69 Total Soil 81,705
(* Minimum detectable level is <5.5 pci/g.
Table 6 lists total microcuries of the radionuclides for each area.
l The total microcuries for each radionuclide is also provided.
1 '
i 4
4 33
e TABLE 6 TOTAL ACTIVITIES OF MAJOR RADIONUCLIDES IN THE SOIL REMOVED Radionuclide Activity (microcuries)
Area Cs-137 Co-60 U-235 Th-232 Sr-90 A
774 40 774 9,300
<2,130 B
25,900 3,380 788 2,800 19,705 C
5,200 156 104 156 416 D
176,000 83,000 860 4,300 148,350 Totals 207,874 86,576 2,526(*)
16,556( }
170,601
(* Equivalent to 1263 grams U-235.
( ) Equivalent to 151 kilograms Th-232.
4 1
1 e
1 34 I
u
i 4
4 i
10.
CONCLUSION
+
i The land designated as Phase I of this project has been decontasi-l.
nated to meet the target criteria for release to unrestricted use.
t i
a 1,
4 4
4 I
r 2
L i
l 1
i i
4
's i
4 1
1 I
1a-I i
35 5
4 5
f
APPENDIX 1 SOIL SAMPLES TAKEN PRIOR TO DECONTAMINATION I
1 Radionuclide Concentration (pCi/g)
Sample Location No.
ID Depth Cs-137 Co-60 U-235 Th-232(a) 1 U
0-6 in.
M(b)
M 0.2 0.9 6-12 in.
0.4 M
0.2 0.8 2
W 0-6 in.
0.2
-0.02 0.1 1.1 6-12 in.
0.1 M'
O.1 1.3 1-2 ft 0.03 M
0.1 1.1 2-3 ft 0.03 M
0.1 1.1 3
W-1 0-6 in.
1.2 0.02 0.3 2.2 6-12 in.
0.7 0.01 0.3 1.7 s
4 X
0-6 in.
0.2 0.1 0.2 2.1 6-12 in.
0.1 0.04 0.1 1.8 5
DS-134 0-1 in.
1.65 M
1.4 13.0 DS-135 6 in.
2.2 M
2.4 43.0 DS-136 12 in.
M M
1.0 16.0 6
B-23 0-1 ft 5.11 2.39 M
M 1-2 ft M
1.3 0.3 M
2-3 ft M
M 0.3 M
3-4 ft 0.91 M
M M
t 7
B-22 0-1 ft 37.1 9.8 M
M 1
1-2 ft 0.7 M
M M
2-3 ft M
M M
M 3-4.5 ft M
M M
M 8
B-10 1-2 ft M
M M
M 2-3 ft M
M M
M 3-4 ft M
M M
M 9
B-9 1-2 ft M
M M
M 2-3 ft M
M 0.3 M
3-4 ft M
M M
M 10 B-8 1-2 ft M
M M
M 2-3 ft M
M M
M 3-4 ft M
M M
M 11 8-5 1-2 ft M
M M
M 2-3 ft M
M M
M 3-5 ft M
M M
M 12 B-24 0-1 ft 2.33 M
M M
1-2 ft M
M M
M 2-3 ft M
M 0.3 M
3-4 ft M
M 0.2 M
37 I
SOIL SAMPLES TAKEN PRIOR TO DECONTAMINATION (Continued)
Radionuclide Concentration (pCi/g)
Sample Location No.
ID Depth Cs-137 Co-60 U-235 Th-232(a) 13 B-25 0-1 ft 1.26 M
0.2 M
1-2 ft M
M M
M 2-3 ft M
M M
M 3-4 ft M
M M
M 14 B-26 0-1 ft 1.09 2.83 M
M 1-2 ft M
1.79 M
M 2-3 ft M
M M
M 3-4 ft M
M 0.3 M
15 B-27 0-1 ft 3.3 4.41 M
M 1-2 ft M
24.2 0.5 M
2-3 ft M
13.5 H
M 3-4 ft M
3.0 M
M 4-5 ft M
M 0.3 M
5--6 f t M
M M
M 6-7 ft M
M M
M 7-9 ft M
M M
M 16 B-28 0-1 ft 148.46 36.1 M
M 1-2 ft 240.0 138.0 M
4.5 2-3 ft 25.8 187.0 M
2.4 3-4 ft 1.57 34.5 M
M 4-5 ft M
7.9 M
M 5-6 ft M
2.3 0.3 6-7 ft M
4.11 M
M 7-8 ft M
2.6 M
M 8-9 ft M
6.81 M
M 9-10 ft 0.63 M
M M
10-11 ft M
M 17 B-38 0-1 in.
404.0 68.2 M
M 1-2 ft 3.45 1.85 M
2-3 ft M
7.59 0.3 18 B-37 0-1 ft 105.0 14.7 0.6 M
1-2 ft M
M 2-3 ft M
M 3-4 ft 0.66 M
M M
19 B-36 0-1 ft 407.4 142.0 M
2.6 1-2 ft 1.57 10.0 M
M 2-3 ft M
1.51 M
M 3-4 ft M
M M
M 4-5 ft M
1.43 38
i i
l SOIL SAMPLES TAKEN PRIOR TO DECONTAMINATION (Continued)
Radionuclide Concentration (pCi/g)
Sample Location No.
ID Depth Cs-137 Co-60 U-235 Th-232(a) 20 B-35 0-1 ft 58.9 163.3 M
M j
1-2 ft 2.83 93.9 0.3 M
2-3 ft M
6.98 M
M 3-4 ft M
1.63 M
M 4-5 ft M
3.7 5-6 ft M
M M
6-7 ft.
M M
0.3 7-8 ft M
M 8-9 ft M
M 0.2 21 B-34 0-1 ft M
M M
M 1-2 ft M
M M
M 2-3 ft 24.7 13.9 0.4 M
4-5 ft M
M 5-6 ft M
M 6-7 ft M
M 7-8 ft M
M 0.3 22 B-7 1-2 ft 35.2 1.8 M
M 3-4 ft 0.7 M
M M
4-5 ft M
M 0.1 M
5-6 ft M
M M
M 23 B-6 1-2 ft 28.9 1.6 M
2.2 2-3 ft 4.6 1.53 M
M 3.5-5 ft 35.4 1.8 M
M 24 B-39 0-1 ft 20.4 4.19 M
M 1-2 ft 14.2 2.49 M
M 2-3 ft 4.74 5.58 M
M 4
3-4 ft M
5.15 25 DS-131 0-1 in.
648.9 455.9 4.5 DS-132 6 in.
421.7 166.9 5.0 7.3 26 B-40 0-1 ft M
M M
M 1-2 ft M
M 0.3 2-3 ft M
M M
M 3-4 ft M
M 27 B-29 0-1 ft 3.9 M
0.2 M
1-2 ft M
M M
M 2-3 f t -
M M
M M
3-4 ft M
M M
M 28 B-30 0-1 ft 4.2 M
M M
1-2 ft M
M M
M 2-3 ft M
M M
M 3-4 fc M
M M
M 39
SOIL SAMPLES TAKEN PRIOR TO DECONTAMINATION (Continued)
Radionuclide Concentration (pCi/g)
Sample Location No.
ID Depth Cs-137 Co-60 U-235 Th-232(a) 29 DS-123 0-1 in.
27.9 3.1 0.6 DS-124 1-6 in.
2.0 M
M DS-125 6-12 in.
M M
M M
DS-126 1-2 ft 0.65 M
M M
30 DS-119 0-1 in.
163.7 9.8 0.9 2.5 DS-120 1-6 in.
87.3 5.2 0.9 M
DS-121 6-12 in.
19.5 1.3 0.4 DS-122 1-2 ft 14.2 M
M 31 DS-127 0-1 in.
16.5 2.2 M
DS-128 0-6 in.
2.5 2.1 0.3 DS-129 6-12 in.
746.7 11.3 M
DS-130 1-2 ft 70.1 7.5 M
32 B-32 0-1 ft 1.3 M
M 1-2 ft M
M M
M 2-3 ft M
M M
M 3-4 ft M
M M
M 33 B-33 0-1 ft 4.21 M
M M
1-2 ft M
M 0.6 M
2-3 ft M
M M
2.0 q
3-4 ft M
M M
M 34 B-31 0-1 ft 28.5 4.7 0.5 M
1-2 ft M
M M
2-3 ft M
M M
3-4 ft M
M M
35 A
0-6 in.
33.0 19.4 0.6 3.2 6-12 in.
8.8 4.7 0.4 5.6 36 DS-76 0-1 in.
80.4 20.6 2.7 4.96 1-6 in.
23.8 2.07 6.1 3.24 37 DS-92 0-1 in.
5.7 M
0.2 M
38 DS-79 0-1 in.
13.3 M
0.4 2.6 1-6 in.
2.6 0.3 0.3 1.8 39 DS-86 0-1 in.
82.8 3.4 3.3 3.6 40 DS-87 0-1 in.
6.9 M
M M
DS-91 0-1 in.
31.5 0.8 1.0 2.5 41 DS-78 0-1 in.
71.1 3.7 4.0 22.1 1-6 in.
83.2 2.3 3.3 6.8 42 DS-77 0-1 in.
162.3 7.6 6.4 3.25 l
1-6 in.
35.9 3.5 1.2 2.04 43 DWYS-1 115.9 12.7 6.8 11.9 40
l SOIL SAMPLES TAKEN PRIOR TO DECONTAMINATION (Continued)
Radionuclide Concentration (pCi/g)
Sample Location No.
ID Depth Cs-137 Co-60 U-235 Th-232(a) 44 DWYS-2 103.5 15.0 4.2 6.7 l
45 DWYS-3 119.4 9.7 5.6 17.1 i
46 A-1 0-6 in.
42.0 17.0 4.2 5.4 6-12 in.
26.0 6.8 2.5 3.6 1-2 ft 3.9 1.0 0.5 M
3-4 ft 0.1 0.1 0.2 1.8 47 DWYS-4 17.6 1.8 0.4 2.2 48 DWYS-5 21.8 2.8 0.8 2.9 49 DWYS-6 16.8 2.5 0.3 M
50 DWYS-7 16.3 5.7 0.5 M
51 DWYS-8 26.1 3.3 0.9 2.6 52 DWYS-9 25.0 7.7 0.8 2.5 53 DWYS-10 8.9 3.7 0.3 M
54 DS-80 0-1 in.
13.4 2.6 0.4 M
DS-81 1-6 in.
1.5 M
M M
DS-82 6-12 in.
M M
M M
DS-83 1-2 ft M
M M
M 55 DS-84 0-1 in.
81.7 8.8 3.7 3.6 DS-85 1-6 in.
15.5 2.9 0.8 2.0 56 C
0-6 in.
7.8 0.3 0.5 1.0 6-12 in.
9.6 0.5 0.6 1.0 57 F
0-6 in.
0.5 0.1 0.2 1.3 6-12 in.
0.2 0.1 0.1 1.3 1-2 ft 0.1 0.01 0.1 1.2 2-3 ft 0.1 0.01 0.1 1.2 58 E
0-6 in.
16.8 1.6 0.4 2.5 6-12 in.
3.9 0.3 0.2 1.7 59 D
0-1 in.
8.2 1.5 0.2 1.8 0-6 in.
7.3 1.7 0.2 1.7 6-12 in.
3.3 0.8 0.2 1.7 60 DS-113 0-1 in.
M M
0.3 DS-114 6 in.
M M
0.4 DS-115 12 in.
M M
0.5 DS-116 1-2 ft M
M 0.4 DS-117 2-3 ft M
M 0.3 M
DS-118 3-4 ft M
M M
41
SOIL SAMPLES TAKEN PRIOR TO DECONTAMINATION (Continued)
Radionuclide Concentration (pCi/g)
S ample Location No.
ID Depth Cs-137 Co-60 U-235 Th-232(a) 61 DS-107-0-1 in.
0.52 M
M DS-108 6 in.
M M
0.3 DS-109 12 in.
M M
0.2 M
)
DS-110 1-2 ft M
M M
M DS-111 2-3 ft M
M M
M DS-112 3-4 ft M
M M
M 62 DS-133 0-1 in.
M M
0.7 2.5 63 DS-255 B-11 0-1 ft 1.0 M
0.6 2.3 1-2 ft M
M 0.2 2.0 2-3 ft M
M M
1.7 3-4 ft M
M M
1.3 64 DS-256 B-12 0-1 ft M
M 0.2 1.9 1-2 ft M
M 0.3 1.8 2-3 ft M
M M
1.9 3-4 ft M
M M
1.9 65 DS-257 B-13 0-1 ft M
M 0.3 2.6 1-2 ft M
M M
2.0 2-3 ft M
M M
2.1 66 DS-258 B-14 0-1 ft M
M M
2.0 1-2 ft M
M M
2.0 2-3 ft M
M 0.2 2.0 3-4 ft M
M M
2.0 67 DS-137 0-1 in.
56.9 2.0 26.9 25.8 68 DS-260 B-16 0-1 ft M
M 0.6 3.4 1-2 ft M
M 0.3 2.1 2-2.5 ft M
M 0.2 2.2 69 DS-259 B-15 0-1 ft M
M 0.5 2.5 1-2 ft M
M 0.3 1.9 2-3.5 ft M
M 0.3 2.3 70 DS-261 B-17 0-1 ft M
M 7.9 5.7 1-2 ft M
M 0.2 1.8 2-3 ft M
M M
1.8 3-4 ft M
M 0.2 1.7 71 DS-138 0-1 in.
M M
10.1 301.9 72 B-10 0-2 ft M
M 0.2 2.1 73 B-6 0-4 ft M
M M
1.8 74 B-9 0-2 ft M
M M
1.8 75 B-7 0-3.5 ft M
M M
1.8 42
SOIL SAMPLES TAKEN PRIOR TO DECONTAMINATION (Continued) i Radionuclide Concentration (pCi/g)
Sample Location No.
ID Depth Cs-137 Co-60 U-235 Th-232(a) 76 B-8 0-4 ft M
M M
2.3 77 I
0-6-in.
0.6 0.03 0.1 1.8 6-12 in.
0.1 0.03 0.2 1.6 78 J
0-6 in.
0.1 0.1 0.2 1.5 6-12 in.
0.8 0.04 0.2 1.5 1-2 ft 0.8 0.04 0.2 1.3 2-3 ft 2.5 0.1 0.4 1.6 3-4 ft 3.8 0.2 0.7 1.9 4-4.5 ft 0.2 0.02 0.1 1.3 4.5-5 ft M
M 0.1 1.2 79 P
0-6 in.
0.9 0.05 0.1 1.4 80 Q
0-6 in.
0.56 0.04 0.1 1.4 6-12 in.
0.58 0.04 0.1 1.4 1-2 ft 0.83 0.02 0.2 1.3
+
2-3 ft 0.15 0.01 0.1 1.5 3-4 ft 0.05 0.01 0.1 1.3 4-5 ft 0.01 0.01 0.1 1.5 81 0
0-6 in.
1.1 M
0.3 1.1 6-12 in.
0.4 M
0.2 0.8 1-2 ft 0.2 M
0.3 1.0 2-3 ft M
M 0.2 0.1 82 B-41 0-1 ft 13.4 1.90 0.4 M
1-2 ft M
M 0.3 M
2-3 ft M
M 0.2 M
3-4 ft M
M 0.3 M
4-5 ft M
M M
83 B
0-6 in.
2.1 0.1 0.2 1.0 6-12 in.
1.5 M
0.2 1.0
(*)Th-232 value obtained by assuming equilibrium with the daughters i
AC-228 and Ra-228.
( )M - minimal means:
<0.1 pCi/g Cs-137
<0.1 pCi/g Co-60
<0.4 pCi/g U-235
<2.0.pci/g Th-232 43
4 I
I I
4 t
I I
APPENDIX 2 RESULTS OF SOIL SAMPLES COLLECTED AFTER CLSAN-UP 45
7ASl2 2-A AREA *A" SOIL SAMPli RESULTS Radlonuclide Concentration (pC1/g)
Sample I lung Dose ID Co-60 Cs-137 Th-228 Th-232(a) ga.226 0-238 U-235 (20 mrem /yr)
Cross Beta Al DS 279 N3 0.2 t 0.4 2.1 10.3 2.6 2 0.5 1.0 t 0.2 I t2 0.24 t 0.12 46.6 80.54 t 2.95 A2 DS 280 ND 0.52 2 0.06 4.4 t 0.4 5.5 t 0.&
l.3 t 0.2 3t2 0.32 t 0.12 1 39 88.43 t 1.47 A2-1 DS 305 8.7M '
.25 8.73 2 0.69 8.75 2 0.43 8.82 2 0.66 0.88 2 0.36 5.67 t 1.09 0.40 t 0.16 63.5 94.44 t 3.14 A2-2 DS Sol 0.00 t 00 0.Il t 0.07 1.85 t 0.47 5.79 t 0.72 1.29 t 0.47 2.66 t I.55 0.24 t 0.18 45.8
- 78. 35
- 1.rm A3 DS 288 ND 3.2 2 0.4 2.120.3 2.2 1 0.4 1.5 t 0.2 3t2 0.22 t 0.l4 49.5 102.70 t 1.12 A4 DS 282 1.0 t 0.2 2.6 t 0.3 1.8 t 0.3 2.1 t 0.4 1.0 t 0.2 8t 1
- 0. l2 t 0.09 D).7 92.H1
- 1.th A5 DS 283 ND 2.020.3 1.9 t 0.4 1.8 1 0.4 1.0 t 0.2 222 0.14 t 0.10 33.3 82.M6 ' 2.99 A6 DS 284 ND 0.4 t 0.8 8.7 t 0.3 2.1 t 0.4 1.5 t 0.3 2t2 0.18 ' O.82 19.6 77.02 t 2.M9 A7 DS 285 MD 0.3 t 0.1 1.6 t 0.3 8.7 t 0.5 1.2 t 0.2 2t2 0.5 + 0.2 12.4 15.52
- 2.35 A8 DS 286 ND 1.0 t 0.8 1.4 t 0.3 5.6 t 0.2
- 1. 5 t 0.1 6t3 5.4 t 0.4 618 19.85 ' 2.92 N
A8-1 DS 104 3.29 t 0.39 100.00 t 5.87 3.06 t 0.69 3.32 t 1.16 0.78 t 0.47 1.16 t 1.42 2.28
- 0.44 281 212.40
- 4.95 A8-2 DS 500 0.00 t 0.00 0.48 t 0.12 1.48 t 0.44 8.42 t 0.80 1.98 t 0.39 0.96 t 0.79 0.19 t 0.12 35.2 78.98 + 2.79 A9 DS 306 0.00 t 0.00 0.00 t 0.00 1.41 1 0.27 2.75 t 0.53 1.37 t 0.27 2.85 t 8.09 0.08 t 0.07 30.7 84.11
- 3.02 AIO DS 307 0.00 t 0.00 1.09 t 0.19 1,47
- 0.28 1.85 t 0.53 1.48 t 0.27 4.72 t 1.48 0.27 t 0.14 56.7 84.48
- 1.01 i
All DS 318 0.00 t 0.00 0.18 t 0.08 1.62 t 0.30 I.94 t 0.50 1.80 t 0.24 1.24 t I.08 0.15 t 0.18 11.9 75.54 ' 2.8n Al2 DS 177 0.tm ? U.tM) 0.62 ? 0.16 l.77 t0.3) 8.38 t 0.48 1.17 9 0.28 0.88 t 0.94 0.14 t 0.88 18.2 H2.66 ' 2.95 All DS 491 0.00 t 0.00 0.00 t 0.tM l.47 t 0.46 8.64 + 0.74 1.47
- 0.44 2.94 t I.48 0.04
- O.09 16.1 79.82 2.14 AI4 DS 498 0.00 ' O.00 0.00 t 0.00 1,53 t 0.46 1.50 t 0.54 1.28 t 0.40 2.53 + I.29 0.10
- 1.a re 29.9 72.62
- 2.*e l
l A15 DS 499 0.00 t0.00 0.tM t 0.00 1.60 t U.46 1.80 t 0.78 1.19 t U.45 2.09 ? 1.23 0.11 ' O.ll 17.7 78.2M ' 2.92 Alb DS S0) 0.00 t 0.00 0.00 t 0.00 1.00 t 0.45 1.56 + 0.78 0.78 9 0.42 l.94 ' 1 20 0.10 ' O.10 26.5 12.40 ' 5.02 All DS 504 0.tM t 0.00 0.71 t 0.16 1.28 t 0.38 1.48 t 0.57 1.19 9 0.18 0.94 ' O.77 0.28
- 0.11 16.4 78.M9
- 2.92 i
' Th-232 value obtained by assuming equlltbrium wlth the daughters Ac-223 and Ra-228.
l l
l t
. - ~ _
u_ - _. --- _. _
TABLE 2-s ABSA ~5* SOIL Safe'LE RESULTS Radionuclide Concentration (pC1/g)
Sample I imag Dose ID Co-60 Cs-137 Th-228 Th-232(a)
Ra-226 U-238 U-235 (20 eses /yr)
Cross meta 31 DS 287 0.2 t 0.1 ND 1.4 2 0.2 1.4 2 0.4 1.1 2 0.2 ND 0.2 2 0.1 32.6 72.70 t 2.80 82 DS 284 ND WD 2.0 t 0.3 2.2 2 0.4 1.3 2 0.2 222 0.13 t 0.09 36.5 79.82 t 2.9) 53 DS 299 ND 1.820.2 1.7 2 0.2 1.8 2 0.3 0.9 1 0.2 222 0.11 2 0.09 31.1 76.52 t 2.56 84 95 290 ND 1.1 t 0.8 1.320.2 8.6 2 0.4 0.9 t 0.3 322 0.12 1 0.8 32.6 67.58 t 2.70 85 DS 291 0.4 2 0.2 3.620.4 1.7 2 0.4 2.5 20.5 8.120.3 3t2 0.34 2 0.15 59.8 88.73 t 2.97 36 DS 292 ND 0.5 2 0.1 1.5 2 0.4 8.820.4 1.120.3 2t2 0.07 2 0.07 25.8 81.40 t 2.96 l
87 DS 293 ND 1.6 2 0.2 I.6 t 0.3 1.6 2 0.5 1.1 t 0.2 2t2 0.15 2 0.10 34.5 78.50 t 2.89 as SS 294 0.3 2 0.2 2.2 2 0.3 1.7 20.3 I.6 2 0.4 1.110.2 222 0.3320.83 54.4 81.89 t 2.97 39 DS 295 ND 0.2 2 0.1 1.6 2 0.3 8.7 2 0.4 1.0 2 0.2 2 t '2 0.15 2 0.9 30.4 69.03 e 2.73 r
BIO DS 296 ND ND I.7
- O.3 1.9 t 0.4 0.9 2 0.2 It2 0.09 t 0.08 26.4 12.67 t 2.*:
d all DS 297 0.2 2 0.1 7.920.6 1.5 t 0.3 1.6 2 0.5 0.8 t 0.2 ND 0.10 t 0.09 22.9 86.75 t 3.0%
on B12 35 298 0.2 2 0.1 8.9 2 0.2 8.2 20.4 1.4 2 0.5 0.9 2 0.3 222 0.02 2 0.08 17.9 78.40
- 2.90 583 DS 299 0.5 t 0.2 1.320.2 1.2 20.3 1.420.5 0.9 2 0.3 ItI 0.05 t 0.05 18.2 79.30
- 2.91 sie DS 406 I in.(b) 0.00 t 0.00 1.09 2 0.20 1.42 2 0.45 1.61 t 0.69 1.50 2 09.45 0.00 t 0.00 0.34 t 0.09 27.8 75.56
- 2.%
Bl4 DS 403 8 ft 0.00 t 0.00 2.95 t 0.32 1.50 t 0.40 1.72 t 0.62 0.97 2 0.35 0.99 t 0.75 0.37 t 0.56 56.8 585 DS 408 I to.
0.00 2 0.00 0.42 2 0.11 0.94 2 0.34 1.19 2 0.50 0.78 t 0.29 0.55 t 0.55 0.05 t 0.05 15.4 76.Ms t 2.19 515 DS 409 I tt 0.00 2 0.00 0.00 2 0.00 1.06 t 0.%
1.32 2 0.55 0.69 2 0.32 1.39 2 0.60 0.04 t 0.04 17.3 516 DS 405 I to.
0.00 2 0.00 B.93 t_0.24 1.25 10.36 1.% t 0.58 0.94 t 0.33 1.82 t 8.05 0.09 t 0.08 25.9
- s.42
- 2.9 Bl6 DS 402 I it 0.00 2 0.00 0.40 1 0.83 I.25 2 0.42 1.23 t 0.6l 0.70 t 0.35 0.57 t 0.59 0.05 t 0.06 16.8 587 DS 404 I ta.
l.30 t 0.24 6.11 1 0.54 1.76 2 0.48 2.13 2 0.79 0.90 t 0.38
!.45 t 8.23 0.49 2 0.17 73.3 90.41 t 3.12 i
817 DS 450 I ft 0.00 t 0.00 0.85 1 0.08 1.17 2 0.39 1.42 2 0.61 0.9320.%
2.03 t 8.24 0.08 t 0.07 24.8 BIS '
DS 44 1 to.
0.71 2 0.88 0.90 1 0.19 1.45 2 0.50 1.58 t 0.73 0.98 t 0.45 0.77 t 0.85 0.13 1 0.09 28.2 73.22 ' 2.*:
518 DS 45 I it 0.25 2 0.08 2.43 2 0.30 1.45 2 0.45 2.13 2 0.87 0.93 t 0.40 1,53 t 8.04 0.16 t 0.82 15.2 75.7 5 ' ' 2.m I
I*ITh-232 value obtatsed by assustag equilibrium with the daughters Ac-228 and Ra-22m.
(b)! in. 3 to.
I ft - I-12 In.
_.___._m._,._
-..._.m.___
.~ _- --
TAtlE 2-C AREA "C" Soll Safell RESULTS Radionuclide Concentration (pC1/g)
Sample 1 Imag pose ID Co-60 Co-137 Th-228 Th-232(a)
- n. 226 U-2 M U-235 (20 mRee/yr)
Cross Seta C-1 DS 398 0.00 1 0.00 0.05 2 0.04 I.64 2 0.41 1.72 2 0.63 0.96 2 0.15 0.92 2 0.71 0.10 t 0.08 26.9 72.43 2 2.80 C-2 DS 399 0.00 2 0.00 0.00 2 0.00 1.64 2 0.44 I.95 2 0.64 1.2I 2 0.39 0.98 1 0.96 0.24 2 0.85 43.7 C-3 DS 400 0.00 t 0.00 0.00 t 0.00 1.75 t 0.41 2.04 2 0.63 1.22 t 0.38 1.93
- 8.05 0.03 2 0.04 23.4 -
71-83 2 2.79 C-4
- DS 451 1 In.(b) 0.u0 t 0.00 0. 4
- 0.13 1.77 2 0.42 1.34 t 0.55 1.06 t 0.28 0.69 1 0.62 0.04 2 0.04 16.9 74.84 t 2.84 C-4 og 464 1 ft 0.00 t 0.00 0.00 2 0.00 1.42 t 0.33 1.91 2 0.60 0.87 2 0.31 1.M t o *2 a 18 t 0.09 29.2 69.33 t 2.74 C-5 DS 454 1 in.
0.00 t 4.0G 0.00 2 0.00 1.26 1 0.38 1.17 2 0.62 0.86 1 0.33 l.tv t 0.96 0.08 t 0.08 22 I 72.74 t 3.4l C-5 DS 416 I ft 0.00 2 0.00 0.00 t 0.00 1.17 t 0.34 1.43 t 0.52 0.79 2 0.29 0.95 t0.91 0.07 2 0.07 21.0 C-6
- DS 43 I in.
0.00 t 0.00 0.83 2 0.17. 2.22 t 0.50 2.18 2 0.75 0.92 t 0.39 2.51 t 1.26 0.58 t 0.87 80.9 79.15 t 2.92
'C-6 95 421 I ft 0.00 t 0.00 0.00 2 0.00 1.17 2 0.35 1.13 1 0.43 0.89 t 0.30 1.57 t I.01 0.08 t 0.07 22.0 12.22 t 2.79 i
l C-7 DS 459 I la.
0.00 t 0.00 0.16 2 0.07 1.40 t 0.36 1.38 1 0.57 0.92 t 0.33 0.00 t 0.00 0.11 t 0.09 23.6 60.59 t 2.95 C-7 DS 418 I ft 0.00 t 0.00 0.00 2 0.00 0.9220.32 l.18 2 0.51 0.67 t 0.30 0.74 t 0.53 0.03 t 0.03 13.1 71.67 t 2.78 C-8 DS 457 I in.
0.00 t 0.00 0.00 t 0.00 1.26 2 0.37 I.69 2 0.60 1.04 t 0.32 8.63 2 0.85 0.I4 2 0.10 31.0 76.94 e 2.89 i
C-8 DS 450 t it 0.00 t 0.00 0.00 2 0.00 1.45 t 0.40 1.M t 0.67 0.77 t 0.35 0.00 2 0.00 0.25 t 0.13 19.9 75.06 t 2.85 l
3 C-9 DS 453 1 in.
0.00 2 0.u0 0.32 2 0.09 8.16 2 0.35 1.38 2 0.57 0.82 2 0.33 0.00 t 0.00 0.15 t 0.10 26.1 75.63 t 2.86 C-9 DS40 t it 0.00 t 0.00 0.00 t 0.00 1.40 1 0.37 1.68 t 0.58 0.81 t 0.32 1.68 2 0.82 0.07 t 0.07 74.8 75.03 t 2.85 l
l I*ITh-232 value obtained by assuming equilibrium with the daughters Ac-228 and Ra-228.
l (b)g.,,,g_g g,,
9 l
t ft = l-12 te.
t e
1
(
l l
l l
l T4BLE 2-D AREA "D" Soll SAMPLE RESULTS Radionuclide Concentration (pCl/g)
Sample I Lung Dose ID Co-60 Cs-137 Th-228 Th-232(a)
Ra-226 U-238 U-235 (20 mRen/yr)
Cross Beta l
l D-I DS 417 I in.(b) 0.00 1 0.00 0.48 2 0.12 I.58 2 0.42 1.25 t 1.66 0.92 t 0.36 2.67 t 1.23 0.15 t 0.I0 35.3 70.03 t 2.74 l
l D-l DS 425 I ft 0.00 t 0.00 0.00 t 0.00 8.29 2 0.39 8.72 t 0.67 0.80 t 0.34 I.9) t 1.26 0.09 2 0.07 26.7 72.87 t 2.80 D-2 DS 419 I in, t.71 t 0.28 0.00 t 0.00 3.38 2 0.46 1,76 t 0.78 1.15 2 0.45 1.97 t 5.04 0.06 2 0.07 24.4 82.28 t 2.97 l
D-2 DS 414 I it 0.00 t 0.00 0.25
- 0.09 1.26 2 0.48 1.19 2 0.66 0.98 t 0.42 1.51 t 1.01 0.06 t 0.06 21.3 D-3 DS 4I5 I In.
14.09 e 1.13 2.32 2 0.32 1.27 t 0.48 1.98 t 0.90 0.84 t 0.42 3.09 t 1.43 0.50 t 0.19 16.5 95.24 t 3.19 D-3 DS 452 I it 0.00 t 0.00 0.22 2 0.09 I.18 2 0.39 1.28 t 0.56 0.73 t 0.34 0.00 t 0.00 0.17 t 0.12 28.3 74.54 t 2.84 D-4 DS 407 I in.
0.28 t 0.04 5.52 t0.47 1.28 2 0.37 8.64 t 0.66 0.94 t 0.35 d.63 t 0.96 0.06 t 0.05 22.5 31.95 t 2.97 D-4 DS All I it 0.00 1 0.00 0.46 t 0.12 8.35 t 0.38 1.43 t 0.58 0.86 t 0.32 1.38 t 0.63 0.13 t 0.08 28.9 D-5 DS 413 I in.
0.86 t 0.12 8.26 2 0.19 1.40 t 0.40 1.46 2 0.53 0.98 t 0. 36 0.98 t 0.74 0.17 t 0.82 33.1 79.96
- 2.9 5.
D-5 DS 412 I ft 0.00 t 0.00 0.58 t 0.14 1.36 t 0.41 1.37 2 0.64 0.94 t 0.37 1.45 t 0.97 0.07 t 0.07 22.8 D-6 DS 408 I ta.
0.52 2 0.13 0.16 t 0.07 8.43 t 0.46
- 1. 34 t 0.69 0.94 t 0.40 0.00 t 0.00 0.07 t 0.08 59.4 85.93 t 5.04 I
LP D-6 DS 424 I it 0.00 t 0.00 0.00 2 0.00 1.18 2 0.39 0.70 t 1.35 1.l* t 0.36 1.01 t 0.81 0.04 t 0.05 15.4 75.84 t 2.87 C3 i
D-7 DS 427 I in.
3.53 t 0.40 0.00 t 0.00 8.24 2 0.48 0.82 t 0.57 1.07 t 0.41 8.7 3 t 0.74 0.08 e 0.08 23.0 76.75 t 2.88 D-1 DS 422 I it 0.54 t 0.15 0.00 2 0.00 I.30 t 0.42 1.31 t 0.68 8.27 t 0.42 0.88 t 0.94 0.u9 t 0.07 22.7 79.45 ' 2.9)
D-s DS 455 1 in.
0.85 t 0.86 1.54 2 0.23 1.3I t 0.38 8.49 t 0.63 0.85 t 0.36 8.76 t 1.18 0.09 t 0.08 26.3 87.39 t 3.07 D-8 DS 420 I ft 0.00 t 0.00 0.00 t 0.00 I.50 t 0.38 8.48 t 0.55 0.83 t 0.32 2.48 t 1.03 0.04 t 0.05 23.6 71.56 t 2.78 s
D-9 DS 449 I ft 0.00 t 0.00 0.74 t 0.15 I.26 2 0.43 1.20 t 0.65 0.85 t 0.39 0.00 t 0.00 0.I4 t 0.80 25.2 60.62
- 2'.95 D-9 DS 462 I In.
0.00 t 0.00 0.00 t 0.00 1.25 t 0.48 1.4 3 t 0.60 0.89 t 0.36 2.05
- I.26 0.06 t 0.06 23.5 80.92
- 2.95 D-lo DS 468 I it 0.00 t 0.00 0.00 t 0.00 1.21 t 0.44 1.62 t 0.72 0.72 t 0.37 2.74 t 1.12 0.83 t 0.10 33.2 77.8%
- 3.46 D-10 DS 456 I in.
8.16 t 0.20 3.66 2 0.37 4.49 t 0.48 8.74 t 0.68 0.89 t 0.34 0.93
- 0.79 U.06 t 0.06 23.3 92.46 ? 1.15
(* Tk-232 value obtained by assuming equilibrine with the daughters 4c-228 and Ra-228.
(b)g g,,
,,_g g,,
I ft = l-12 in.
f f
I I
)
APPENDIX 3 FINAL SOIL SAMPLE RESULTS i
l
)
51
TABLE 3-A AREA "FA* SolL SAfrLE SESULTS Radlenuellde Concentration (pCl/g)
Sample I lang Dose ID Co-60 Co-837 Th-228 Th-232 s)
Ra-226 U-238 U-235 (20 maee/yr) Cross Seta 0
FA-l DS 440 N 7155 E %55 I In.(h) 0.00 t 0.00 0.00 t 0.00 1.85 t 0.41 1.08 2 0.62 1.09 t 0.39 0.00 t 0.00 0.10 t 0.09 20.8 78.15 t 2.77 FA DS 443 N 7855 E %55 I ft 0.00 1 0.00 0.02 2 0.04 1.20 t 0.40 8.29 t 0.59 l.nl t 0.40 0.57 t 0.77 0.05 t 0.06 17.3 72.44 t *.80 FA DS 355 N 7860 E 9700 I In.
0.00 2 0.00 0.97 t 0.16 8.71 t 0.39 8.75 t 0.59 0.92 t 0.33 2.23 t 0.69 0.75 t 0.20 104 83.17 t 2.99 FA DS %4 N 7160 E 9700 1ft 0.00 t 0.00 0.79 t J.16 1.68 2 0.44 1.99 t 0.78 1.12 1 0.37 3.76 t 4.06 0.56 t 0.19 88.4 72.49 t 2.79 FA-3 DS 509 N 7170 E 9580 I In.
0.00 2 0.00 0.00 1 0.00 8.24 h 0.43 1.35 t 0.64 1.58 t 0.43 3.49 t 1.23 0.23 t 0.14 45.7 79.66 2 2.93 FA DS 439 N 1870 E 9580 i ft 0.00 t 0.00 0.60 t 0.I4 1.88 2 0.46 1.77 t 0.67 1.23 2 0.39 2.25 t 1.63 0.48 t 0.17 74.3 83.51 e 3.00 FA-4 DS 438 N 7870 E 9610 I la-0.00 t 0.00 0.31 t 0.10 1.77 t 0.48 1.69 t 0.76 1.48 t 0.46 1.86 t 3.17 0.38 t 0.89 68.7 83.02 t 2.99 FA DS 447 N 7870 E 9610 i ft 0.00 t 0.00 0.00 t 0.00 1.25 t0.49 8.3210.34 1.18 1 0.48 1.77 t 1.33 0.20 t 0.15 37.6 74.10 9 2.43 FA-5 DS 507 N 7870 E 9640 I la.
0.00 t 0.00 0.00 t 0 A0 3.15 t 0.41 1.32 t 0.67 0.70 t 0.M l.48 t 0.99 0.06.t 0.05 20.3 70.82 2 2.77
. FA DS 426 N 7170 E 9640 t it 0.00 t 0.00 0.00 t 0.00 8.23 t 0.15 1.38 t 0.51 0.87 t 0.34 0.78 t 0.% 0.11 t 0.09 24.9 75.% t 2.86 FA-6 DS 368 N 7170 E 9670 l 1;..
0.00 t 0.00 0.52 t 0.82 1.28 t 0.24 1.42 2 0.40 1.17 t 0.23 2.21 t 8.06 0.11 e u.08 28.8 71.64 ' 2.78 FA DS 381 N 7170 E 9670 I it 0.00 t 0.00 0.25 t 0.09 1.27 t 0.35 1.37 t 0.52 1.11 t 0.M l.24 t 0.80 0.11 t 0.09 26.5 FA-7 DS 371 N 7170 E 9700 8 in.
0.00 t 0.00 1.14 t 0.19 1.27 t 0.24 1.67 t 0.44 1.06 t 0.23 0.86 t 0.85 0.14 t 0.10 29.0 76.76 + 2.44 Ltt FA DS 190 N 7870 E 9700 l It 0.00 t 0.00 0.19 t 0.08 1.11 t 0.4 8 1.68 t 0.70 1.15 t 0.41 2.24 t 1.25 0.13 t 0.80 11.0 FA-8 US 430 N 72n0 E 9580 I la.
0.00 t 0.00 0.00 t 0.00 1.38 t 0.35 8.65 t 0.59 0.90 t 0.32 1.58 t 0.91 0.10 t u.08 27.2 10.96
- 2.11 '
~
FA DS 445 N 1200 E 9%0 I ft 0.00 2 0.00 0.00 t 0.00 1.49 t 0.42 I.78 t 0.65 1.8 7 ~ t 0.39 0.00 2 0.OV 0.06 t 0.07 19.6 77.27
- 2.49 ftd v DS 346 N 7200,E 9610 I la.
0.00 t 0.00 0.24 t 0.40 1.74 t 0.28 1.73 t 0.45 1.43 t 0.27 1.85 t I.25 0.27 t 0.14 54.6 75.86
- 2.84 FA DS 393 N 7200 E 9610 t it 0.0G t 0.00 0.00 t 0.00 1.56 t 0.42 2.01 t 0.65 0.92 1 0.%
[.10 t 0.84 0.10 t 0.09 27.9
%+
y l
FA-10 DS 315 N 7200 E 9640 I In.
0.00 t 0.00 0.28 2 0.II 1.70 t 0.29 1.88 t 0.51 1.47 t 0.26 2.35 t 1.01 0.24
- 0.14 48.5 14.62
- 2.34 I
FA DS M2 N 7200 E %40 I ft 0.W t 0.00 0.00 t 0.00 1.53 t 0.25 1.75 1 0.4I l.04 t 0.20 3.08 t 1.06 0.18 t 0.11 42.0 70.88 t 2.93 FA-ll DS 357 N 1200 ~ E 9670 1 in.
0.00 t 0.00 8.00 t 0.16 1.85 t 0.35 I.43 t 0.76 6.11 t 0.35 1.04 t 0.94 0.10 t 0.u9 25.9 12'.43
- 2.8u FA DS 311 N 7200 E 9670 i ft ND 0.220.1 1.6 1 0.3 1.7 t 0.4 1.2 t 0.3 1t2 0.10 t 0.09 33.2 7 5.so
- 2.4 5 FA-12 DS 319 N 7200 E 9700 t it 0.00 t 0.00< 0.00 t 0.00 1.40 t 0.46 1.37 t 0.64 1.06 t0.41 2.46 t 1.18 0.14 t 0.11 13.6 74.44 + 2.84 FA-l)
DS 314 ' N 7230 E 9610 I In.
0.00 1 0.00 '2.78 1 0.35 1.99 t 0.35 2.32 t 0.63 1.37 1 0.29 4.96 t I.% 0.30 t 0.86 60.7 92.48
- 3.16 FA DS 335 N 12 30 E 9610 i ft 0.00 1 0.00 0.00 2 0.00 1.41 t 0.42 1.89 t 0.6% 0.92 t 0.35 2.48 t 5.18 0.12 t 0.10 33.5 82.86 *. 99
,FA-14 DS M7 N 7230 E 9640 I la.
0.00 t0.00 3.05 t 0.34 8.91 t 0.32 1.85 t 0.46 1.89 t a.25 1.46 t 1.28 0.8% t 0.15 35.5 83.9# e 3.03 FA" DS 382' N 7230 E %40 i ft ND 2.4 t 0.3 8.9 t 0.3 2.2 t 0.6 l.2 t 0.2 It2 0.22 t 0.8) 50.6 80.47
- 2.9%
FA-15 DS 174 N J230 E 9670 1 in.
0.00 t 0.00 0.40 t 0.10 1.58 t 0.26 I.65 t 0.45 1.00 t 0.22 1.46 t 1.Il u.15 t 0.60 33.4 84.00 t 3.nl FA DS 396 N 1230 E 9670 1 it 0.00 2 0.00 0.00 t 0.00
- 1. 86 t 0. % 1.57 t 0.57 0.87 2 0.32 2.02 t 1.82 0.04 t 0.04 30.4 FA-16 DS 373 N 7230 E 9700 t in.
0.00 t 0.00 1.65 2 0.26 1.53 t 0.29 1.51 t 0.44 1.07 t 0.25 2.42 t 1.17 0.22 t 0.l2 44.4 16.06 t 2.87 FA
. DS 394 N 7230 E 9700 Ift 0.00 t 0.00 0.00 1 0.00 1.85 t 0.37 1.67 t 0.64 0.95 t 0.34 I.53 t 0.98 0.07 t 0.07 22.4 FA-17 DS 434 N 7245 E 9610 t in.
0.00 t 0.00 0.95 t 0.17 1.10 t 0.40 0.72 2 0.82 0.88 t 0.%
2.37 t I.83 0.07 t 0.07 21.8 58.63 t 2.64 a4 h
4."
(
y
. _~.
w, wm-
%N c
4 s.
i TA8LE 1-A (Continued)
Sadlonuclide Concentration (pCl/8)
Sample' 3 Lung pose ID Co-60 Co-437 h-228 Th-232(a)
Sa-226.
0-238 0-235 (20 stes/yr)
Cross Sete
[
i FA.
DS 429 N 7245 E 9610 I it 0.00 2 0.00 0.22 1 0.09 1.25
- 0 35 1.34 t 0.54 0.96 1 0.35 0.38 t 0.53 0.10 t 0.08 21.9 68.% t 2.72
'FA-18 DS 448 N 7260. E 9580 t In, 0.00 t 0.00 0.49 1 0.13 t.88 t 0.45 2.11 1 0.66 1.05 1 0.38 8.05 t 0.90
- 0. M i 0.15 St.6 19.84 t 2.94 FA
'DS e44 N 1260 E 9580 t it 0.00 t 0.00 0.%
- 0.12 L.70 t 0.44 2.06 2 0.67 0.96 t 0.38 0.00 t 0.00 0.31 2 0.15 48.5 79.37 t 2.93 FA-19 ' DS %9 N 7260 E 9610 t In.
0.00 2 0.00 7.% 10.67 2.32 2 0.35 2.28 2 0.61 t.17 t 0.29 3.47 t 8.38.0.52
- 0.20 60.3 90.25 t 3.14 l
FA DS M5 N 7260 E %!0 t it 0.00 t 0.00 4.12 t 0.43 - 2.80 t 0.%
2.30 t 0.53 0.99 t 0.24 1.61 t 1.34 0.28 t 0.15 53.3 74.48 t 2.43 FA-20 DS 351 N 7260 E 9640 I in.
0.00 t 0.00 7.18 1 0.62 2.12 t 0.52 2.20 t 0.76 0.98 t 0.40 2.75 t 1.35 0.28 t 0.15 55.8 10.90 t 3.12
-FA DS 348 at 7260 E M40 I ft 0.00 t 0.00 1.17 t 0.21 1.59 t 0.29 l.78 t 0.47 1.06 t 0.24 2.75 t t.23 0.14 t 0.11 17.1 77.29 t 2.48 FA-21 DS 435 N 7260 E 9670 t in.
0.00 t 0.00 2.19 t 0.27 1.58 t 0.44 1.72 t 0.67 1.06 t 0.38 0.92 t 0.84 0.18 t 0.12.
35.3 78.30 e 2.90 F4 DS 438 N 7260 E 9670 i ft 0.00 t 0.00 0.18 t 0.08 l.49 t 0.37 B.69 t 0.62 0.98 t 0.33 2.39 t 1.14 0.07
- 0.07 26.8 73.47
- 2.98 FA-22 DS 433 N 7260 E M85 1 is.
0.00 t 0.00 1.13 2 0.20 1.% t 0.44 1.48 t 0.75 1.00 t 0.40 1.48 t 8.01 0.l% t 0.l2 12.0 69.49 e 2.75 FA Da 448 N 7260 E 9685 i ft 0.00 t 0.00 0.00 t 0.00 1.55 t 0.3t 4.37 t 0.67 1.00 t 0.39 0.00 t 0.00 0.08 t 0.08 20.6 74.28
- 2.85 FA-23, DS %9 N 7260 E 9700 l In.
0.00 t 0.00 0.88 t 0.17 1.53 t 0.29 8.57 t 0.45 3.02 t 0.24 2.76 t 1.28 0.16 t 0.18 17.6 78.04
- 2.76 FA DS 389 N 7260 E 9700 1 ft 0.00 t 0.00. 0.00 t 0.00 1.28 t 0.46 1.63 t 0.70 0.99 t 0.39 1.37 t 1.02 0.12 t 0.48 28.6
.[
FA-24 DS'358 N 7290 E 9500 t la.
0.00 t 0.00 2.14 1 0.27 1.85 t 0.29 2.22 t 0.48 1.07 t 0.24 0.00 t 0.00 0.31 t 0.14 50.2 14.50
- 2.44 FA DS M6 N 7290 E 9580 t it 0.00 t 0.00 0.22 t 0.09 1.55 t 0.26. I. u t 0.42 1.03 t 0.22 0.00 t 0.00 0.12 t 0.08 26.2 FA-25 DS %0 N 7290 E %IO I in.
0.00 2 0.00 0.90 t 0.17 3.75 t 0.47 3.73 t 0.68 8.24 t 0.29 1.48 t 1.40 0.40 t 0.t8 78.9 93.6u
- 3.67 FA DS 394 N 7290 E 9610 I tt 0.00 t 0.00 0.00 t 0.00 1.43 t0.42 1.79 t 0.67 1.02 t 0.38 2.07 t I.30 0.07
- 0.07 25.8 FA-26 DS 333 N 7290 E 9640 1 In.
0.58 t 0.14 2.44 1 0.32 2.77 t 0.60 2.96 e 0.85 1.t5 t 0.46 4.9s t I.99 0.21
- o.14 59.9 90.38
- 3.12 FA DS %2. N 7290 E 9640 t it 0.00 t 0.00 0.44 t 0.14 1.59 t 0.43 1.83 t 0.M l.17 t 0.40 1.05 t 4.M 0.10 t 0.u9 33.1 81.65
- 3.la FA-27 DS 310 N 7290 E %70 t !a.
ND 1.720.3 1.8 t 0.3 1.9 t 0.5 1.1 t 0.2 i t2 0.80 e u.u9 28.0 so.84
- 2.95 FA DS 309 N 1290 E 9670 i ft ND ND l.7 t 0.3 2.0 t 0.5 1.1 t 0.2 292 0.08
- 4.u?
M.6 82.44
- 2.97 FA-28 DS 387 N 7290 E 9700 t in.
0.00 t0.00 0.39 t 0.12 1.48 1 0.45 3.35 t 0.60 1.14 t 0.37 2.25 t 4.43 0.83 t 0.84 32.5 78.16 t 2.91 FA DS 383 N 1290 E 9700 t it 0.00 t 0.00 0.00 t 0.00 1.29 t 0.38 1.45 t 0.%
t.05 t 0.35 1.54
- 1.22 u.14 t 0.12 14.8
)
FA-29 DS 352 N 7290 E 9730 I In.
0.00 t 0.00 0.98 t 0.89 1.25 t 0.45 1.51 t 0.68 1.04 t 0.41 I.90 t I.t3 0.06
- 0.47 22.9 11.04
- 2.70 FA -
DS 339 N 7290 E 9730 I ft 0.00 t0.00 0.00 t 0.00 8.68 t 0.38 t.96 t 0.54 1.19 t 0.27 0.43 t 0.54 0.85 t u.tl 32.1 77.h2 + 2.90 FA-M DS 508 N 7300 E 9570 t in.
0.00 t 0.00 1.93 t 0.25 2.08 t 0.45 2.54 t 0.73 1.05 t 0.%
l.06 t t.00 0.26
- 0.13 49.4 79.85 e 2.94 FA DS 4e6 N 7300 E 9570 t is 0.00 t 0.01 0.83 t 0.17 1.44 t 0.42 8.76 t 0.65 0.89 t 0.35 1.63 t 0.85 0.23 e 0.8) 42.5 79.15 e 2.92 FA-31 DS %0 N 7300 E 9600 1 In.
0.00 t 0.00 2.99 t 0.35 1.83 t 0.M 2.04 t 0.53 1.09 t 0.24 1.29 t t.83 0.21
- 0.t3 23.4 76.79 e 2.48 FA US 179 N FMO. E 9600 I ft 0.00 t 0.00 0.46 t 0.14 B.87 t 0.32 1.95 t 0.53 1.81 t 0.26 1.68 t 8.27 0.21 t 0.l) 43.5 FA-32 DS 432 N 7320 E 9570 t in.
0.00 t 0.00 l.11 t 0.20 2.12 1 0.48 2.66 t 0.73 0.78 t 0.3% 3.28 t 4.24 0.39 9 0.16 10.7 7 5. 8 %
- 3.u 7 FA-DS 423 N 7320 ~ E 9570 i ft 0.00 t 0.00 0.00 t 0.00 1.30 t 0.51 l.71 1 0.75 0.12 t 0.45 8.12 t 0.89 0.88 t 0.11 24.7 71.78 e 2.79
- FA-33 DS 4% N 7329 E 9580 1 In.
0.00 t 0.00 0.00 t 0.00 1.38 t 0.43 1.42 t 0.67 0.97 t 0.39 0.00 t 0.00 0.84 t 0.1%
2h.9 75.18
- 2.84 t
y r-
m I
l TA8LE 3-A (Continued 7 l
l Radionuclide Concentration (pC1/8)
Sample 3 lang Does ID Co-60 Co-117 Th-228 Th-232(*)
Ra-226 U-2 38 -
U-235 (20 maee/yr) cross meta FA DS 428 m 7320 E 9580 t it 0.00 2 0.00 0.00 1 0.00 1.54 t 0.47 1.55 1 0.76 1.17 t 0.44 0.28 t 0.68 0.08 t 0.07 20.7 80.50 t 2.93 f
l FA-34 DS 354 N 7320 E 9590 I in.
0.00 t 0.00 1.18 t 0.18 1.57 t 0.40 1.98 t 0.68 1.08 t 0.35 1.93 2 0.90 0.54 2 0.17 78.9 78.07 t 2.90 FA
' DS 385 N 7320 F,9530 'I (t 0.00 t 0.00 0.63 t 0.15 1.39 t 0.39 I.78 e 0.60 0.95 t 0.34 1.29 t'O.8% 0.44 t 0.16 64.5
[
FA-35 DS 350 N 7320 E 9610 s in.
0.00 t 0.00 0.45 t 0.13 l.30 t 0.26 1.38 t 0.44 0.96 2 0.23 0.70 t 0.73 0.88 1 0.10 32.7 63.27 t 2.6l I
FA DS 382 N 7320 E 96'J I ft 0.00 t 0.00 0.00 1 0.00 1.12 t 0.34 1.38 t 0.52 1.0320.34 1.56 t 8.19 0.04 t 0.04 18.4 FA-36 DS 345 N 7230 E 'e640 I in.
0.00 1 0.00 1.05 t 0.22 1.80 t 0.36 2.G5 t 0.53 8.J6 t 0.31 0.98 t 4.04 0.20 t 0.14 40.2 74.59
- 2.44 FA DS 380 N 7320 E 9640 I ft 0.00 2 0.00 0.46 2 0.13 1.39 t 0.48 1.84 t 0.67 1.05 t 0.37 2.98 t I.25 0.20 t 0.13 43.4 FA-37 DS 338 N 73*.0 E 9670 t in.
0.00 t 0.P0 0.60 t 0.16 I.67 t 0.33 8.71 t 0.51 1.16 1 0.27 2.29 t I.18 0.ll t 0.II 12.4 76.64 t 2.no FA DS 330 N 7320 E 9670 Ift 0.00 t %00 0.56 2 0.15 8.10 t 0.37 1.26 t 0.59 0.87 t 0.36 1.88 t I.03 0.23 e u.11 39.8 71.13
- 2.77 FA-38 DS 343 N 7320 E 9700 I in.
0.00 t 0.00 1.82 t 0.29 1.57 t 0.32 1.50 t 0.51 1.11 t 0.28 1.08 t 1.30 0.14 t 0.12
%.7 76.66
- 2.57 FA DS 570 N 7320 E 9700 1 It 0.'JO t 0.00 0.00 t 0.00 1.58 1 0.30 1.79 t 0.52 1.22 t 0.27 1.64 t 8.38 0.80 t u.09 29.0 FA-39
- s 308 N FMG E 9680 l in.
ND 0.7 t 0.2 1.4 t 0.2 1.5 t 0.4 0.9 t 0.2 2t2 0.31 t 0.83 50.5 64.42 + 2.65 s
FA' DS 344 N 7350 E Mio I ft 0.00 t 0.00 0.44 t 0.84 1.17 t 0.27 I.30 t 0.46 0.96 t 0.25 1.3I t I.85 0.89 t o.12 M.7 65.37
- 2.65 FA-40 DS 347 N 7350 E 9640 i tr.
0.00 t 0.00 0.32 t 0.13 2.75 t 0.43 2.58 t 0.58 1.23 t 0.29 1.08 t 3.10 0.20 t 0.44 46.1 7 7. 3s
- 3.u9 ww FA DS 395 N 7350 E 9640 I ft 0.00 t 0.00 0.00 t 0.00 1.27 t 0.40 1.73 t 0.63 1.25 t 0.40 1.54 t 1.00 0.15 t 0.11 12.5 FA-48 DS 338 N 7350 E 9670 I to.
0.06 1 0.04 0.96 t 0.It I.29 t 0.32 1.49 t 0.43 0.99 t 0.29 1.61 t 0.79 0.12 t 0.07 2M.6 77.29
- 2.49 FA DS 386 N 7350 E 9670 t it 0.00 t0.00 0.00 t 0.00 1.51 t 0.46 l.92 t 0.74 1.06 t 0.45 2.67
- 1.19 0.89 e 0.13 41.7 82.53
- 2.99 FA-42 DS 320 N 7350 E 9700 t in.
0.00 t 0.00 1.36 t 0.24 1.58 t 0.48 8.89 t 0.81 1.09 t 0.43 0.00 t 0.00
- 0. t 5 t u.11 30.1 42.42
- 2.9s FA DS 324 N 7350 E 9700 Ift 0.00 1 0.00 0.38 t0.12 1.53 t 0.43 8.75 t 0.68 1 01 t 0.39 I.77 t I.Il 0.14 e u.Il 33.2 7'6.64
- 2.44 FA-43 DS 328 N 7380 E 9610 l in.
0.00 t 0.00 0.79 t 0.19 8.87 t 0.33 2.84 t 0.61 1.M t 0.30 I.72 9 4.42 0.17 t 0.12 19.7 84.22
- 5.u2 FA DS 334 N 7380 E 9610 i ft 0.00 t 0.00 0.41 t 0.13 1.48 t 0.49 1.32 t 0.68 1.42 e u.48 0.8% t 0.90 0.14 e u.lu 29.5 77.29
- 2.49 FA-44 DS 129 N 1380 E %40 t in.
0.00 1 0.00 0.37 1 0.13 8.45 t 0.30 1.88 t 0.57 I.10 t 0.27 t.35 t u.96 0.18 t u.t2
%.4 69.65
- 2.7%
l FA DS 384 N 7380 E 9640 I ft 0.00 t 0.00 0.00 t 0.00 1.08 t 0.33 1.26 t 0.52 0.77 t 0.38 8.78 t 0.96 0.06 t 0.06 21.1 FA DS 341 N 7380 E 9670 I in.
0.00
- 0.00 0.89 t 0.19 l.48 t 0.30 I.84 t 0.56 1.l8 t 0.27 1.08 e 1.01 0.12 e u.10 29.6 13.8%
- 2.41 FA US 323 N 7360 E 9670 i ft 0.00 t 0.00 0.00 t 0.00 8.59 t 0.38 1.97 t 0.58 8.le t 0.27 3.80 t 1.11 0.31 t 4.10 3u.6 73.66 t 2.91 FA-46 DS 375 N 7380 E 9700 I in.
0.00 t 0.00 1.10 t 0.20 1.54 t 0.30 B.77 t 0.51 1.01 t 0.24 2.15 t t.11 0.28 t 0.13 42.8 72.e5
- 2.no FA DS 3t? N 73e0 E 9700 -1 it 0.00 t 0.00 I.30 t 0.28 8.76 t 0.51 2.00 t 0.76 1.27 t 0.44 3.0a e 1.4a 0.14 t 0.12 39.6 st.44
- 2.96 I*I Th-232 value olttained by masuming equilibrium with the daughters AC-228 and Ra-228.
(b)I in. = 0-1 in.
I ft = l-12 in.
3 9 0 4 1
5 6 8 2 6 3 8 6 9 3 3 7 8
a 8 8 8 6 0 4 8 8 0 0 0 8 8 8 2 7 9 2 te 2 2 2 2 3 2 2 2 3 3 3 2 2 2 3 2 2 3 B
t 2
t t
2 t
1 2
t t
t 1
t t
2 2
2 1
ss 7 5 3 5 2 2 9 2 8 8 8 6 6 3 5 2 8 8 o
8 1
0 1
2 0 7 3 5 9 6 2
6 2 8 2 5
3 rc 4 7 1
4 4 3 5 6 6 6 6 5 5 7 5 9 2 0 7 7 7 6 8 7 7 7
8 8 8 7 7
7 7 6 7 7
)
er sy o/
Da 8 5 7 8
1 2 3 4 2 7 5 3 8 1
5 1
4 6 e
ga 4
1 4 0 5 5 2 2 0 0 4 3 6 2 0 2 1
nm 3 3 2 1 3 2 2 2 4 6 4 2 1
2 2 2 31 3
uL0 2
1(
3 0 7
2 8 0 6 5 3 7 5 7 1
6 5 7 1
9 1
1 0
1 0
1 0 0 1
1 1
0 0 0 0 u.
1 0
5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3
2 1
1 1
t 1
1 1
t 1
2 t
t t
t t
t t
t
-U 6 4 1
8 0 1
7 4 8 6 2 7 0 5 5 7
4 2 1
1 1
1 1
1 0 0 1
3 2 0 0 0 0 0 1
1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 8 8 3 4 0 9 4 6 9 7
6 4 0 1
3 5 7
1 1
9 5 6 3 0 9 2 2 3 3 3 8 0 1
7 9 0
)g 0 o 1
0 0 0 1
0 0 1
1 1
1 1
0 1
1
/
8 1
1 3
8 C
2 t 2 2
t 1
1 2
t t
1 t
t 1
t t
t t
1 2
S p
2 T
(
U 0 7 9 5 4 0 9 3 8 9 5 7 8 5 2 3 0 1
9 3 8 7 9 0 4 9 3 9 0 6 1
0 6 8 9 0 a
L R
U n
S o
1 1
0 0 2 0 1
1 2 2 2 1
1 1
1 0
1 2
E i
d R
t n
a 3 5 0 7 7 3 5 3 2 6 1
3 9 4 2 2 4 1
a F.
r 4 3 3 3 3 4 3 4 4 4 5 4 3 3 3 3 3 3 L
t 8
P n
6 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2
M e
2 2
A c
2 2
2 2
1 1
t 1 2
t 1
1 1
t 2
t t
t t
S n
c 5
o a
0 5 6 1
6 5 3 6 9 8 6 9 8 6 1
4 0 1
A
- L C
R 4 2 0 8 2 0 0 3 0 0 0 1
0 8 8 7 9 9 3I s
O e
1 1
1 0
1 1
1 1
1 1
1 1
1 0
1 0 0 1
r ES d
e L
i t
B l
1 5 0 0 7 5 6 5 8 6 6 0 5 6 3 8 6 4 h
A "R 6 5 4 6 6 7 6 6 7 6 8 7 6 6 6 5 5 6 g
c
)
TF u
s u
n
(
0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 a
o 2
d M
i 3
t 2
2 t
1 1 2 1 2 2 t
1 t
1 1
t t
t U
d 2
e D
a 5 3 6 3 6 8 6 8 8 4 5 7 7 1
5 5 8 5 h
N R
h 4 5 2 2 2 6 6,
4 8 6 8 5 7 9 5 4 5 8 t
A T
R 1
1 1
1 2
1 1
1 1
1 1
1 1
1 1
1 1
1 h
t L
i A
2 8 0 9 4 8 9 4 6 8 7 2 2 9 8 0 8 1
w N
4 3 3 3 4 4 3 4 4 4 5 4 4 3 3 4 3 4 m
I F
8 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 u
2 i
2 2
1 1
t 1
2 1 1
2 1 2 1 t
2 2
1 t
2 r
b h
2 8 6 5 9 2 6 7 1
2 7 7 4 3 5 3 7
2 i
T 4 4 1
9 9 6 1
5 6 4 7 2 5 5 2 4 2 5 l
i 1
1 1
0 1
1 1
1 1
1 1
1 1
1 1
1 1
1 uqe 2
1 7 7 0 2 7 0 7 0 6 3 0 0 9 7 2 6 1
1 0 0 0 1
0 0 4 4 4 1
0 2 1 0 3 1
gn 7
0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 i
3 m
1 2 2 1 1 1
1 1 2 1 1 2 1 2 2 1 2
t 1 u
s s
2 6 0 9 0 7 6 0 2 6 3 7 0 2 2 4 9 4 s
C 4 3 4 1
0 3 1
0 0 4 2 3 0 3 4 1
1 8
a 0 0 0 0 0 0 0 0 5 3 4 0 0 1
1 0 3 0 y
b 0 0 0 0 0 0 0 0 0 0 3 0 0 0 2 0 0 0 d
0 0 0 0 0 0 0 0 1
1 1
0 0 0 2 0 0 0 e
n 0
0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 i
6 a
2 1 1 1 t 1 1 2 t 2 1 1 t t
1 2 2 2 t
o b
C 0 0 0 0 0 0 0 0 5 1
9 0 0 0 7 0 0 0 o
0 0 0 0 0 0 0 0 3 3 4 0 0 0 3 0 0 0 e
0 0 0 0 0 0 0 0 0 0 0 0 0 0 1
0 0 0 u
l a
4 5 6 7 1
2 3 4 5 6 7 8 9 8 6 2 0 4 v
6 6 6 6 7 7 7 7 7 7 7 7 7 8 9 9 9 9 1
1 1
1 1
1 1
1 1
1 1
1 1
4 4 4 4 4 2
3 S S S S S S S S S S S S S S S S S S 2
D D D D D D D D D D D D D D D D D D h
T e
)
l 0
1 2 3 4 5 6 7 8 pD 2 3 4 5 6 7 8 9 1
1 1
1 1
1 1
1 1
I mI a
R R R R R R R R R R R R R R R R R R S
F F F F F F F F F F F F F F F F F F f
I Y
l l
APPENDIX 4 AIR SAMPLE DATA Alpha Beta Date Sample (pCi/m3)
(pCi/m )
3 8-30-85 WY-1 1.4
<3.7 WY-2
<0.3 1.0 9-3-85 WY-3
<0.3
<0.2 WY-4
<0.1
<0.1 9-4-85 WYB-1
<0.1
<0.1 WYB-2
<0.1
<0.2 9-5-85 WYB-2
<0.7
<1.9 WYC-3
<0.1
<0.7 9-6-85 WYB-2
<0.1
<0.4 WYC-3 0.2
<0.1 9-7-85 WYB-2
<0.1 0.5 WYC-3
<0.1
<0.1 9-9-85 WYB-2
<0.1
<0.3 WYC-3
<0.1
<0.1 9-10-85 WYB-2
<0.1
<0.3 WYD-4
<0.1
<0.3 9-11-85 WYB-2
<0.1
<0.4 WYD-4
<0.1
<0.2 9-12-85 WYB-2
<0.1
<0.2 WYB-4
<0.4
<0.1 9-13-85 WYA-1
<0.1
<0.3 WYB-2
<0.1
<0.2 9-14-85 WYB-2
<0.1
<0.2 9-16-85 WYD-4
<0.1 0.2 WYB-2
<0.1 0.3 9-17-85 WYB-2
<0.2 0.3 WYD-4
<0.1 0.1 9-19-85 WYD-4
<0.1
<0.5 WYE-5
<0.1 0.5 9-20-85 WYD-4
<0.1
<0.1 WYE-5
<0.2 0.9 9-21-85 WYD-4 0.2 0.5 WYE-5 0.2 0.3 9-23-85 WYD-4
<0.1
<0.1 WYE-5
<0.2 1.3 l
57
4 AIR SAMPLE DATA (Continued)
Alpha Beta 3
3 Date Sample (pCi/m )
(pci/m )
9-24-85 WYD-4
<0.1 0.3 WYB-2
<0.1 0.3 9-25-85 WYB-2 0.2 0.7 WYD-4
<0.1
<0.1 9-26-85 WYB-2
<0.1 0.9 WYD-4
<0.1
<0.1 10-11-85 WY
<0.1
<0.4 4
10-14-85 WY
<0.1
<0.2 i
10-15-85 WY
<0.1
<0.2 2
10-16-85 WY 0.1
<0.2 10-21-85 WY 0.1 0.2 i
58
~,..
l i
APPENDIX 5 WIPE SURVEYS Alpha Beta 2
2 Sample ID (DPM/100 ce )
(DPM/100 cm )
Grade - All No. 7 CR 7-1
<0.3
<0.7 CR 7-2
<0.3
<0.7 CR 7-3
<0.3
<0.7 CR 7-4
<0.3
<0.7 CR 7-5
<0.3
<0.7 CR 7-6
<0.3
<0.7 CR 7-7
<0.3
<0.7 CR 7-8
<0.3
<0.7 CR 7-9
<0.3
<0.7 CR 7-10
<0.3 0.9 Average 0.3 0.7 Truck No. 15 TR 15-1
<0.3 0.9 TR 15-2
<0.3
<0.7 TR 15-3
<0.3
<0.7 TR 15-4
<0.3
<0.7 TR 15-5
<0.3
<0.7 TR 15-6
<0.3
<0.7 TR 15-7
<0.3
<0.7 TR 15-8
<0.3 2.5 TR 15-9
<0.3
<0.7 TR 15-10
<0.3
<0.7 Average 0.3 0.8 Propane Tank TK-1
<0.3
<0.7 TK-2
<0.3
<0.7 Average 0.3 0.7 Fence 0.9
<0.8 Fence 2
<0.3
<0.8 Average 0.6 0.8 59
WIPE SURVEYS (Continued)
Alpha Beta 2
Sample ID (DPM/100 cm )
(ppg /too e,2)
Skip Loader CF 34-1
<0.3
<0.7 CF 34-2
<0.3
<0.7 CF 34-3
<0.3
<0.7 CF 34-4
<0.3
<0.7 CF 34-5
<0.3
<0.7 CF 34-6
<0.3
<0.7 CF 34-7
<0.3
<0.7 CF 34-8
<0.3
<0.7 CF 34-9
<0.3
<0.7 CF 34-10
<0.3
<0.7 Average 0.3 0.7 Front End Loaders MF 15-1
<0.3
<0.7 MF 15-2
<0.3
<0.7 MF 15-3
<0.3
<0.7 MF 15-4
<0.3
<0.7 FM 15-5
<0.3
<0.7 Average 0.3 0.7 1 Ton Dump Truck TR 144-1
<0.3 1.2 TR 144-2
<0.3
<0.7 TR 144-3
<0.3
<0.7 TR 144-4
<0.3
<0.7 TR 144-5
<0.3
<0.7 Averaga 0.3 0.8 Coup reef
<0.3
<0.7 2x6
<0.3
<0.7 2x6
<0.3
<0.7 Plywood
<0.3
<0.7 Junction box
<0.3
<0.7 Conduit
<0.3
<0.7 Dry wall
<0.3
<0.7 Shower door
<0.3
<0.7 Tar paper
<0.3
<0.7 Dry wall No. 2
<0.3
<0.7 Shower
<0.3
<0.7 Electrical wire 0.6
<0.7 Conducit 4
<0.3
<0.7 l
Hot water heat
<0.3
<0.7 60
F, l'
WIPE SURVEYS (Continued)
Alpha Beta 2
2 Sample ID (DPM/100 cm )
(DPM/100 cm )
Truck No. 8 TR 8-1
<0.3
<0.7 TR 8-2
<0.3
<0.7 TR 8-3
<0.3
<0.7 TR 8-4
<0.3
<0.7 TR 8-5
<0.3.
<0.7 TR 8-6
<0.3
<0.7 TR 8-7
<0.3
<0.7 TR 8-8
<0.3
<0.7 TR 8-9
<0.3 0.9 TR 8-10
<0.3
<0.7 Average 0.3 0.7 Backhoe No. 50 1
<0.9
<0.7 2
<0.9
<0.7 3
<0.9
<0.7 4
<0.9
<0.7 5
<0.9
<0.7 6
<0.9
<0.7 7
<0.9
<0.7 8
<0.9
<0.7 9
<0.9
<0.7 10
<0.9
<0.7 Average 0.9 0.7 Don's Backhoe No. 8 AWC-1
<0.3
<0.7 AWC-2
<0.3 1.2 AWC-3
<0.3
<0.7 AWC-4
<0.3
<0.7 AWC-5
<0.3
<0.7 AWC-6
<0.3
<0.7 ANC-7
<0.3
<0.7 AWC-8
<0. 3 -
<0.7 AWC-9 1.6
<0.7 Average 0.4 0.8 i
61.
l l
WIPE SURVEYS (Continued)
Alpha Beta 2
2 Sample ID (DPM/100 ce )
(DPM/100 cm )
Empty Drums 1
<0.3
<0.7 2
<0.3
<0.7 3
<0.3
<0.7 l
4
<0.3
<0.7 5
<0.3 3.0 6
<0.3
<0.7 7
0.6
<0.7 8
<0.3
<0.7 9
<0.3 1.0 10
<0.3
<0.7 11
<0.3
<0.7 12
<0.3
<0.7 13
<0.3
<0.7 14
<0.3 1.0 15
<0.3
<0.7 16
<0.3 1.2 17
<0.3
<0.7 18
<0.3
<0.7 19
<0.3
<0.7 20
<0.3 1.2 21
<0.3
<0.7 22
<0.3 8.7 23
<0.3
<0.7 24
<0.3
<0.7 25
<0.3
<0.7 Average 0.3 1.2 i
i 62 i
l-
-.,s-
.-s-4 p
-p
APPENDIX 6 Sr-90 RESULTS FOR SOIL SAMPLES TAKEN PRIOR TO DECONTAMINATION Sr-90 Concentration Sample ID Location (pCi/g)
Area A 5
DS-134, surface 0-1 in.
<5.5 DS-135, 0-6 in.
<5.5 DS-136, 6-12 in.
<5.5 Area B 25 DS-131, surface 0-1 in.
110.0 DS-132 0-6 in.
62.0 30 DS-119, surface 0-1 in.
20.0 27 B-29, 0-1 ft
<5.5 34 B-31, 0-1 ft 8.7 B-31, 2-3 ft
<5.5 43 DWYS-1 16.0 53 DWYS-10
<5.5 36 DS-76, 0-1 in.
5.5 DS-76, 1-6 in.
13.0 Area C 67 DS-137 10.0 71 DS-138 6.0 Area D (Ponds) 73 B-6, 3.5-5 ft
<5.5 76 B-8, 1-2 ft
<5.5 7
B-22, 0-1 in.
15.0 16 B-28, 0-1 ft 43.0 B-28, 1-2 f t 400.0 B-28, 2-3 ft 290.0 B-28, 3-4 ft 140.0 B-23, 4-5 ft 59.0 B-28, 5-6 ft 19.0 B-28, 6-7 ft 31.0 B-28, 7-8 ft 31.0 B-28, 9-10 ft 3.0 B-28, 10-11 f t
<5.5 19 B-36, 0-1 ft 41.0 B-36, 1-2 ft
<5.5 63
I l
I.
4 l
APPENDIX 7 ANALYSIS OF VEGETATION (BRUSH) FROM WASTE YARD PONDS AND CANYONS Isotope pCi/gm
+/- 2 Standard Deviations Pile 1 Cs-137 0.32 40%
Th-228 0.044 41%
Ra-226 0.069 41%
Ra-228 0.31 21%
Pile 2 Cs-137 0.46 29%
Th-228 0.14 36%
Ra-226 0.0045 73%
Pile 3 Cs-137 0.43 40%
Th-228 0.064 37%
Ra-226 0.045 55%
Ra-228 0.079 61%
Pile 4 Co-60 1.4 11%
Cs-137 4.9 73%
Th-228 0.13 30%
Ra-226 0.055 49%
Ra-228 0.22 29%
U-235 0.015 87%
Cs-134 0.063 45%
Pile 5 Co-60 0.39 19%
Co-137 3.8 10%
Th-228 0.40 27%
Ra-226 0.33 37%
Ra-228 0.49 39%
Th-234 0.22 69%
Sr-90 Analysis Samples from the five piles of vegation were combined and analyzed for Sr-90 using wet chemistry methods. The results were 1.3 pCi/g for both duplicate samples.
~
65 l
l l
APPENDIX 7 ANALYSIS OF VEGETATION (BRUSH) FROM WASTE YARD PONDS AND CANYONS Isotope pCi/gm
+/- 2 Standard Deviations Pile 1 Cs-137 0.32 40%
Th-228 0.044 41%
Ra-226 0.069 41%
Ra-228 0.31 21%
Pile 2 Cs-137 0.46 29%
Th-228 0.14 36%
Ra-226 0.0045 73%
Pile 3 Cs-137 0.43 40%
Th-228 0.064 37%
Ra-226 0.045 55%
Ra-228 0.079 61%
Pile 4 Co-60 1.4 11%
Cs-137 4.9 73%
Th-228 0.13 30%
Ra-226 0.055 49%
Ra-228 0.22 29%
U-235 0.015 87%
Cs-134 0.063 45%
Pile 5 Co-60 0.39 19%
Cs-137 3.8 10%
Th-228 0.40 27%
Ra-226 0.33 37%
Ra-228 0.49 39%
Th-234 0.22 69%
Sr-90 Analysis Samples from the five piles of vegation were combined and analyzed for Sr-90 using wet chemistry methods. The results were 1.3 pCi/g for both duplicate samples.
65 b
r APPENDIX 8 RELEASE OF CONCRETE FROM EVAPORATION PONDS AS NON-RADIOACTIVE 4
67
APPENDlX 8 RELEASE OF CONCRETE FROM EVAPORATION PONDS AS NON-RADIOACTIVE Concrete from the solar evaporation ponds located at the Waste Processing Facility was released for unrestricted disposal on August 23, 29, 30, and 31, 1984 based on the following:
1.
Surveys of the concrete remaining after surface scrabbling showed that calculated disintegrations per minute in 100 cm2 areas of the ponds were within the guidelines established by Federal (Attachment 1) and State (Attachment 2) regulatory agencies.
2.
Instruments used in the survey were calibrated against standards and efficiencies and correction factors were determined.
3.
Corrections for background radiation were conservative due to the area and the use of unshielded detectors.
Attached are the grid surveys of the solar evaporation pond concrete surfaces after scrabbling ponds 1 through 4 (Attachments 3 through 6).
The values given in dpm (disintegrations per minute) were determined by correcting the counts per minute of the detector used to survey the ponds for background efficiency and geometric factors.
The Instruments used were a Ludlum Geige Counter Model 3, S/N 30309 with a pancake GM detector probe, calibre.ted 7/5/84, which has a 15.2 cm2 area detector, and an Eberline Model PAC-ISA alpha counter, S/N 30353 which has a 72.5 cm2 area detector, calibrated 9-11-84.
Discussion:
Ge(LI) scans of representative samples of the concrete from each pond showed that Cs-137 was by far the major activliy contributor, therefore efficiency values for Cs-137 were used to evaluate the beta-gamma levels.
69
[
A.
Beta-Gamma Levels The counts per minute measured and recorded in the surveys were corrected as follows:
(1)
Backgrourid - A " standard" natural background of 100 cpm was subtracted from the readings while they were being taken although a higher background could be justified because of the relatively high background in the immediate area of the survey and because the detector used was unshielded.
A background of 200 epm was subtracted f rom the Pond 3C readings due to s
a 10mR/hr area caused by a large pile of concrete y
rubble from the Hot Celi pond (Pond 4) which was temporarily stored nearby. The 200 cpm reading was subtracted from the readings 0 - 3 feet away from
'a the rubble.
The background subtracted from the 1
readings during the survey was conservative.
No additional background has been subtracted f rom the readings.
(2)
Efficiency - The detector ef ficiency was determined by making measurements with a standard source.
In order to simulate the conditions on the scrabbled pond surfaces, a one-foot square area of a cement
~
block was spiked with a known amount of Cs-137:
(2.28 x 104 dpm/100 cm2 15%).
This corresponds to 3456 dpm/15.2 cm2 area.
This block then simulates the pond measurements.
Surf ace measurements of the block were taken with the Instrument simulating the pond surfaces and the results were as follows:
t 70
Gross readings (average of 5 readings)
= 1210 cpm i 50 cpm Background in area (where measurements were taken) 70 cpm i 10 cpm
=
Net reading = 1140 cpm i 51 cpm Ef fIclency = Net com/15.2 cm2 = 1140/3466 = 32.9%
dpm/15.2 cm2 (3)
Geometrv Correctron Since the values listed in
~
Table 1 of Attachments I and 2 are in dpm/100 cm2, a correction factor was applled to the values to correct for the smaller area of the detector.
The detector probe used has a 15.2 cm2 area, therefore a correction f actor of 6.58 was applied to al l the values.
(4)
The efficiency and geometry correction result in multiplying the count per minute reading by 20 to obtain disintegrations per minute.
(5)
The highest reading was an 800 cpm reading (Pond 2C) over a less than 10 cm2, which was observed where a bolt had been taken out of the concrete.
The guidelines specify maximum readings of 15,000 dpm/100 cm2 area which translates (with our calibration) to a reading of 750 cpm throughout a 100 cm2 area.
In reality, the 800 cpm measurement was made over an area much smaller (15.2 cm2) and the contamination was over an area less than 10 cm2, The local 3 ft)2 region was otherwise at a much lower count; i.e.
175 cpm /100 cm2 average.
The result is that the count rate was much lower averaged over the entire 100 cm2 area assuming that there were other " hot spots" in the 100 cm2 area which a count rate the same c: the maximum count rate in a nearby (3 ft)2 area.
This gives us a maximum of 550 cpm or 11000 dpm in this 100 cm2 area.
71
8.
Alohn Levels
' The alpha counts per minute measured and recorded in the surveys were corrected as follows:
(1)
Background - None subtracted (2)
Effielenev - During the calibration of the PAC-1SA alpha counters, the instruments are checked against a standard source and are adjusted to read in counts per minute 50% of the total dpm value.
Therefore, of ficiency is 50%.
(3)
Geometrv - The area of the detector is 72.5 an2, therefore a correction factor of 1.38 was applind to alI the values.
k (4)
The ef ficiency and geometry correction results in multiplying the counts per minute reading by 2.76 to obtain disintegrations per minute.
The maximun reading was <100 cpm which is 276 dpm in any area, well below the levels specified in Table 1 of the guidelines (Attachments 1 and 2) for U-235 or natural thorium.
The resJIt? show compilance with the guidelines for release to unrestricted use.
/
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72
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ItiES FOR DE-CO:iTAMItiAT!0ti 0F FACILITIES A.'iD EQUIPMENT PRIOR TO RELEASE FOR U.'iRESTRICTED USE OR TEPJIIt'ATI0tl 0F LICEtiSES FOR BYPRODUCT, SOURCE, OR SPECIAL NUCLEAR."ATERIAL
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U. S. Nuclear Regulatory Co mission Divisica of Fuel Cycle a.c Material Safety k'ashington, D.C.
20555 July 1932 i
73
The instructions in th'is guide, in conjunction with Table 1, soecify the radionuclides and raciation exoosure rate limits which snould be useo in decontamination and survey of surfaces or premises and equipment prior to abandonment or release for unrestricted use.
The limits in Table 1 do not acoly to oremises, ecui:: ment or scrac containing incucec radio-for wnicn tne racioiccicai cons 1cera:1cns certinent to :neir activity use mav ce di##=*=nt.
The release of sucn facilities or items trom regulatory control is considered on a case-by-case basis.
1.
The licensee shall make a reasonable effort to eliminate residual contamination.
2.
Radioactivity en equipment or surfaces shall not be covered by paint, plating, or other covering material unless contamination levels, as determined by a survey anc cocumented, are belcw tne limits specified in Table i prior to tna aoplication of :ne covering.
A reasonable effort must be made to minimize the contamination prior to use of any covering.
3.
The radioactivity on the interior surfaces of pipes, drain linet, or ductwork shall be detemined by making measurements at all traps, and other appropriate access points, provided that contam-ination at these locations is likely to be representative of r
L contamination on the interior of the pipes, drain lines, or ductwork.
Surfaces of premises, equioment, cr scrap which are
{
likely to be contaminated but are of such size, construction, or location as to make tne surface inaccecsible for purposes of measurement shall be presumed to be contaminated in excess of the limits.
4.
Upon request, the Comission may authorize a licensee to relinquish possession or control of premi,ses, equipment, or scrap having surfaces contaminated witn materials in excess of the limits scecified.
This may incluce, but would not be limited to, special circums:ances such as razing of buildings, transfer of premises go anotner organization continuing work with racicactive materials, or conversion of facilities to a long-tem storage or standby status.
Such requests must:
Provide detailed, specific information describing the pre.ises, a.
equipment or scrao, radioactive contaminants, and :ne nature, extent, and degree of residual surface contamination.
b.
Provide a detailed health and safety analysis which reflects that the residual amounts of materials on surface areas, together with c her considerations such as prospective use of the premises, ecuipment or scrap, are unlikely to result in an unreasonable risk to :he health and safety of the puolic.
74
p?
2-5.
Prior to release of premises for unrestricted use, the licensee shall make a comorehensive radiation turvey which establishes that contamination is within the limits scecified in Table 1.
A copy of the survey. report shall be filec with the Division of Fuel Cycle and Material Safety, USNRC, b'ashington, D.C.
20555, and also tne Administra:or of the NRC P.egional Office having jurisdiction.
The report should be filed at least 30 days pricr to the planned date of abandonment.
The survey report snall:
a.
Identify the premises.
b.
Show that reasonable effort has been made to eliminate residual contamination.
c.
Describe the scope of the survey and general procedures followed.
N d.
State the findings of the, survey in units specified in the instruction.
Following review of the report, the NRC will consider visiting the facilities to confirm the survey.
6 e
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75
(
ACCEPTAutE SURFACE C0llTAMINATION*tEVELS
- t AVERAGEbcf guigunb d f REMOVABLEbef Htitt.10ESa s
2 2
1,000 dpm a/100 cm
-nat U-235,(1-238, and 2
15,000 dpm a/100 cm ssociated decay products 5,000 dpm a/100 cm 2
20 d;m/100 cm2 ransuranics, Ra-226. Ra-228, 2
300 dpm/100 cm h-230, Th-220 Pa-231, 100 dpm/100 cm c-227, 1-125, 1-129 2
2 3000 dpm/100 cm2 200 dpm/100 cm sh-nat, Th-232, Sr-90,
..i-223, Ra-224. U-232, 1-126, 1000.dpm/100 cm
-131 1-133 0
eta-gann emitters (nuclides 2
1000 dpm sy/100 cm2
.Ith decay siodes other than 2
.lpha emission or spontaneous 5000 dpm sy/100 cm 15,000 dpm py/100 cm Ission) except Sr-90 and ethers noted above.
lides exists, the limits established for alpha-and beta-ganma-te.1'tting i
2'.:here surf ace contamination by both alpha-and beta-ganna-emitt ng nuc t:uclides should apply independently.
i the b s used in this table, dpm (disintegrations per minute) means the rate of emission by radioactive material as determined ins trumenta tion.
counts i.er minute observed by an appropriate detecter for background, ef ficiency, and geometric factars associated with the A
for objects of less surface area, the average titcasurer.cnts of average contaminant should not be averaged over more than i square meter, l
sho. eld be derived for each such object.
2 ihe maalmum contamination level applles to an area of not more than 100 cm,
d of surface area should be determined by wiping that area with dry filter or sof t 2
i ith an appropriate instrument of "Ihe amount of removable'rediaactive materfai per 100 cm absort.cnt paper, applying moderate pressure, and assessing the amount of radioactive material on the tr.a,.a e s t iciencye proportionally and the entire surface should be wiped.
l d
0.2 mrad /hr at I cm and 1.0 mrad /hr at I cm, respectively, measured through not mo l
t total absarber.
e s
e
AVERAGEbcf yAXIMUHbdf REMOVADLEbef NtJCLIGES" O
2 2
'1,000 dpm a/100 cm
-nat, il 235,11-230. and 2
ssociated decay products 5,000 dpm a/100 cm 15,000 dpm a/100 cm 2
300 dpm/100 cm,2 20 d;m/100 cm2 ransuranics,lla-226, na-228,
'.-230, Th-220, pa-231, 100 dpm/100 cm
-227, 1-125, 1-129 2
2 3000 dpm/100 cm2 200 dpm/100 cm h-nat, Th-232, Sr-90, n-223. Ra-224,ll-232. 1-126
.1000.dpm/100 cm
-13), 1-133 eta-gann emitters (nucildes 2
1000 dpm sy/100 cm2 eith decay aiodes nther than 2
15,000 dpm py/100 cm ilpha emission or spontaneous 5000 dpm Ay/100 cm
- Ission) except Sr-90 and sthers noted above.
1 ting
%:hcre surf ace contamination by both alpha-and beta-ganna-emitting nuclides exists, the limits estab!!shed for alpha-and b nuclIdes should apply independently.
h As used in this table, dpm (dtsintegrations per minute) means the rate of emission by radioactive r.ateria) as determined counts per minute observed by an appropriate detecter for background, ef ficiency, and gecmetric factors associated w t L
for objects of less surface area, the average C icasurer.cnts of average contaminant should not be averaged over more than i square meter.
l shoisld be derived for each such object.
2 ihe ma41 mum contamination Icvel applies to an area uf not more than 100 cm,
d 2 of surface area should be determined by wiping that area with dry filter or sof t eihe arpount of removable radlaactive material per 100 cm t of radioactive material on the wipe with an appropriate Instrument of 4hsortent paper, applying moderate pressure, and assessing the amoun1; hen removable contamination on objects of less su tr.aun efficiency.
proportionally and the entire surface should be wiped.
0.2 mrad /hr at I ca. and 1.0 mrad /hr at I cm, respectively, measured throu0h nnt m I
rotal ahtarber.
=
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9
.GUIDELI!;ES FOR DECON"'A'!!!;ATICN
^g s
OF FACILITIES AND EQUIPMI!;T
'\\ /
Cu IN PRICR 'IO PSLEASE FOR USFISTRICED USE s
Uncenditional release of radioactively c+
'a 4nated facilities and equipment requires decentamination to prevent risk to the public health and safety with subsequent unrestricted use.
Section 30298 of the California F.adiation Centrol Regulatiens specifies that the user is respensible for this decentamination.
The Depart ent will impese no conditiens with respect to future use of equipment and facilities following decentamination censistent with the following guide-lines:
(a)
The user shall make every reasonable effort to eliminate residual contaminatien.
(b)
No covering shall be applied to centaminated surfaces of equip =ent or structures by paint, plating or other near.s prior to release fer unrastricted use.
Equipment =ay be released and ceated per paragraph (e) belev if it is estab-lished by. decu anted su vey that concentratiens are belew the limits specified in Table I.
(c)
The radicactivity on the interior surfa:es of pipes, drain-lines or duct work can be determined by naking measure-ments of all traps and other appr:priate a::ess points, provided conta=inatica at these locations is likely to be representative 'of centa: natien en the interier of the pipes, d
drainlines or duct work.
Surfaces of pre:ises, eqiiprent er scrap which are likely to be conta-inated but are of such size, construction er locatien as to raks the surface inaccessible for purposes of measurement sho.:ld be assumed to be centa.inated in excess of the permissable radiation limits.
(d)
In the case of facilities to be released, Section 30298 requires 30 days prior notice of intent to vacate.
This notice sust be folicwed by a report su=mari:ing the results of surveys follew-ing decentamination establishing that levels of radicactivity are within tk.e limits specified in Table I.
- fhe sur ary should be supported by sufficiently detailed survey records maintained available for inspection.
O.e Departmant must have an cpportunity to ecnfirm by spot curvey the st:.=ary report subnitted prior to granting approval for release.
78 w..
, /
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(e)
In the case of equiptent to be released, no request er report
,is required if guide limits are met.
The licensee must, however, maintain detailed survey records sufficient to justify the release.
(f)
If Califor'nia guidelines are not satisfied in a particular instance, the Department must be consulted with respect to future use of the item in question, except where there will be a transfer to a specific license.
The Department's determina-tion as to whether the item may be released will involve such factors as the practicality of further decontamination, and the likely hazard considering possible future use of the item.
Fequests for review and variance shculd provide:
(1)
Detailed and specific informatien describing the ite=, radioactive e-a-'
- - =- s and the nature, extent and degree of residual contamina icn.
(2)
A detailed health and safety analysis establishing that residual contamination is not of concern with respect to the health and safety of the public given the nature of the residue and the prospective use of the facilities or equipment.
.c
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TABLE I O
- ,e ace =. = c e.. tem ccmr.n.wn, u n c, e
- L iraLL. GUa 4 rA.a wh les aai v1: A L4 e i.a.r L.L.J WCLliE AW.PAE
- FAXImf,d EFC.R:Jf, '
b 2
(dp:V100 cm )
(dpm/100 cm')
(dpm/lC 3 e.-)
sat, U-235, U-238, and 5,000 15,000 1,000
- cciated decay p cducts insuranics, Ra-226, Pa-228, 100 300 20
-230, Th-228, Pa-231
-227, I-125, I-129 nat, Th-232, 5:-90 1,000 3,000 200
-22 3, Ra-224, C-232, L26, I-131, I-133
- a-ga-.a. emitters (nuclides 5,000 15,000 1,000
- h decay : odes other than tha emission or spontaneous
- sion) except S -90 and ters note !! a.bove.
3, C-14 except as D::A 20,000 60,000.
4,000 3 cursors f/
su:! ace conta=ination by bcth alpha-and heta-gar::a-emitting nu:lides exis:s, the li=1:s hed for alpha-and he:a-ga::.a-ed :ing nu:lides should apply independently.
ed 'in this table, dp= (disintegraticns pe: minute) means the :ste of e=issicz hy radi:a:ti-ial as de:er=ined by cc::e::ing the counts pe: minute cbserved by an app cfria:e de:e::::
tekground, e!!1ciency, and geote::Lc fac:c:s asso: Laced with che ins::crenta:icn.
- cnen:s of average contacinant should not he averaged cver more than 1 square meter.
Tc:
- s of less su:! ace a:ea, che average should he derived for-each such object.
1ximum conca=inatica level applies to an area of not :cre than 100 c=#.
cunt of :e.ovable radicactive material pe: 100 c=
of su:! ace a:ca should he dete- ' ='
ping that area with d:y filte: c: so!: ehsorben: paper, appiying :cderate p:essu:e, and sing the a:cun: of radioac:Lve ::sterial cn the wipe with an" app::. :iate ins::u ent :!.:_.:.:
Lency.
t? hen re:cvable con:amina:Lon cn objec:s of less su:! ace area is de:e:.ined, the nent levels should be reduced propo::icnally and the en:L:e surface sh:'uld he : iped.
- ecursors mean :clecules or cc= pounds that are directly incorpc:ated into the :::A.:-le:.:le
- D
- :A biosychesis, e.g. pu:ine and pyrimidine bases and their analcgs, nucleotides and asides.
The accepcable su:! ace conta=.inaticn levels for H-3 ar.d C-14 in D::A precu:sa:s 2 tabulaced in paragraph (d) for beta-ga::ma-e :itters.
Regula:ory Guide 1.36 Terminacion of 0: era:inc :.1:enses ic: ?;ucl es: Reac:c::, ;;as.-ing::
.- (June 1974)
~
t, Control of Radicactive so ! ace Ccntaminaticn on M.1:eri.1:s Ecuip.-cn and F2:llitie:
Sc Rc1 cased io: Uncon::alled User. fin.11 draic, ::Opost:d Arx::can ::a:Lcnal d:an:is:d :;-2:1, nic Induse:ial Forum, Inc., ::.Y. (June 1974) 80
/
POND IC ATTACHMENT 3, 7000 6000 8000 5000 5000 5000 5000 SURFACE CONTAMINATION LEVELS 2000 2000 2000 2000 2000 2000 2000 PONDS 1A, IB AND IC 138 138 138 138 138 166 138 5000 6000 5000 5000 5000 5000 5000 2000 2000 2000 2000 2000 2000 2000 138 138 138 138 138 138 138 Note:
5000 5000 5000 5000 5000 5000 6000 (1) Levels were taken on Pond 2000 2000 2000 2000 2000 2000 2000 concrete after scrabbling and 138 138 138 138 138 138 166 cleaning.
3000 5000 5000 6000 5000 5000 5000 (2) Each square represents a 3 foot 2000 2000 2000 2000 2000 2000 2000 square area.
138 138 138 138 13 8 138 207 (3) Upper values are in dpm and 6000 5000 5000 5000 5000 5000 5000 represent the maxi =um 2000 2000 2000 2000 2000 2000 2000 beta-gamma contamination level 138 138 138 138 138 13 8 138 in a 100 cm2 area.
6000 5000 5000 5000 5000 5000 5000 (4) Middle values are the average 2000 2000 2000 2000 2000 2000 2000 contamination levels in a 138 138 138 138 138 138 13 8 (3ft)2 area.
9000 5000 5000 5000 5000 5000 5000 (5) Lower values are the maximum 2000 2000 2000 2000 2000 2000 2000 alpha contamination levels in 2
138 138 138 138 138 138 138 dpm/100 cm,
POND 13 6000 5000 5000 5000 5000 5000 5000 2000 2000 2000 2000 2000 2000 2000 138 138 138 138 138 138 138 8000 5000 5000 5000 5000 5000 5000 2000 2000 2000 2000 2000 2000 2000 13 8 138 138 138 138 13 8 138 6000 5000 5000 5000 6000 5000 5000 2000 2000 2000 2000 2000 2000 2000 138 138 138 138 13 8 138 138 7000 5000 5000 5000 5000 5000 5000 2000 2000 2000 2000 2000 2000 2000 138 138 138 138 138 138 13 8 6000 6000 5000 5000 5000 5000 5000 2000 2000 2000 2000 2000 2000 2000 138 138 138 13 8 138 138 138 5000 5000 5000 5000 5000 5000 5000 2000 2000 2000 2000 2000 2000 2000 138 138 138 138 138 138 138 6000 5000 5000 5000 5000 5000 5060 2000 2000 2000 2000 2000 2000 2000 138 138 138 138 138 138 138 81
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f.99 JA ATTACHMENT }.
6000 5000 5000 6000 7000 5000 5000 s
2000 2000 2000 2000 2000 2000 2000 138 138 138 138 138 138 138 4-5000 6000 5000 5000 5000 5000 5000 2000 2000 2000 2000 2000 2000 2000 138 138 138 138 138 138 13 8 7000 6000 5000 5000 6000 5000 5000 2000 2000 2000 2000 2000 2000 2000 166 138 138 138 138 138 138
)
8000 6000 5000 5000 5000 6000 7000 2000 2000 2000 2000 2000 2000 2000 j
~
193 13 8 138 138 138 138 138 6000 5000 5000 5000 5000 5000 6000 2000 2000 2000 2000 2000 2000 2000 138 138 13 8 138 138 13 8 166 5000 5000 5000 5000 5000 5000 6000 2000 2000 2000 2000 2000 2000 2000 138 138 138 138 138 138 207
. 6000 5000 5000 5000 5000 6000 5000 2000 2000 2000 2000 2000 2000 2000 138 138 138 207 138 166 138 f
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l 6000 6000 6000 6000 6000 6000 6000 SURFACE CONTAMINATION LEVELS 3500' 3500 3500 3500 3500 3500 3500 PONDS 2A. 2B. AED 2C 13 8 138 138 138 138 138 13 8 6000 6000 6000 6000 6000 6000 6000 3500 3500 3500 3500 3500 3500 3500 l
13 8 138 13 8 138 138
-13 8 138 N_g3g:
6000 6000 6000 7000 6000 6000 6000 (1) Levels were taken on Pond 3500 3500 3500 3500 3500 3500 3500 concrete after scrabbling and 138 13 8 138 138 138 138 138 cleaning.
6000 6000 f6000 6000 6000 6000 6000 (2) Each square represents a 3 foot 3500 3500 3500 3500 3500 3500 3500 square area.
138 138 138 138 138 138 138 (3) Upper values are in dpa and 6000 5000 6000 6000 6000 6000 6000 represent the maximum 3500 3500
.3500 3500 3500 3500 3500 beta-gamma contamination level j
138
,138 13 3 138 138 13 8 13 8 in a 100 em2 area.
6000 0000 6000 6000 6000 6000 6000 (4) Middle values are the average 3500 3500 3500 3500 3500 3500 3500 contamination levels in a
'138 138 138 13 8 138 138 138 (3ft)2 area.
7000 6000 6000 6000 6000 6000 6000 (5) Lower values are the maximum 3500 3500 3500 3500 3500 3500 3500 alpha contamination levels in 2
13 8 138 138 138 138 13 8 13 8 dpm/100 cm,
MH 6000 6000 6000 6000 6000 6000 6000 3500 3500 3500 3500 3500 3500 3500 138 13 8 138 13 8 138 13 8 13 8 6000 6000 6000 6000 6000 6000 6000 3500 3500 3500 3500 3500 3500 3500 138 13 8 13 8 138 138 138 138 6000 6000 6000 6000 6000 6000 9000 3500 3500 3500 3500 3500' 3500 3500 138 138 13 8 138 13 8 138 138 1 6000 6000
'6000 6000 6000 6000 6000 3500 3500 3500 3500 3500 3500 3500 l
138 138 138 138 138 138 138 6000 6000 l6000 6000 6000 6000 7000 3500 3500 '3500 3500 3500 3500 3500 138 138 138
-138 138 138 138 1
6000 6000 6000 6000 6000 6000 6000 3900 3500 3500 3500 3500 3500 3500 138 138 13 8 138 13 8 138 138 7000 6000 6500 8000 6000 6000 6000 i 3500 3500 3500 3500 3500 3500 3500 138 138 138 138 138 138 138 83,
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6000 6000 6000 12000 6000 6000 7000 3500 3500 3500 3500 3500 3500 3500 138 138 13 8 138 138 138 138 7000 6000 6000 6000 6000 6000 6000
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3500 3500 3500 3500 3500 3500 3500 138 138 138 138 138 138 138 6000 6000 6003 6000 6000 6000 6000 3500 3500 3500 3500 3500 3500 3500 138 13 8 138 138 138 138 138
-8000 6000 6000 6000 6000 6000 8000 3500 3500 3500 3500 3500 3500 3500 13 8 13 8 138 13 8 138 138 13 8 7000 6000 6000 6000 6000 6000 11000*
3500 35J0 3500 3500 3500 3500 3500 138 138 13 8 138 13 8 13 8 138 6000 6000 6000 6000 6000 6000 10000 3500 3500 3500 3500 3500 3500 3500 1
138 138 138 138 138 138 138 6000 6000 7000 14000 6000 9000 6000 3500 3500 3500 3500 3500 3500 3500 138 138 138 138 138 138 138 2
- An 800 cpm spot was observed in a 10 cm area.
2 The count rate averaged over the entire 100 cm area was calculated to be 550 cpm or 11,000 dpm.
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f.ON.R 1 ATTACHMENT 1 6000 6000 6000 6000 6000 6000 7000 SURFACE CONTAMINATION LEVELS i
4000 4000- 4000 4000 4000 4000 4000 PONDS & 3B. M 1CC 276 276 276 276 276 276 276 6000 6000 6000 6000 6000 6000 8000 4000 4000 4000 4000 4000 4000 4000 1
N 11:
276 276 276 276 276 276 276 2
6000 6000 6000 6000 6000 6000 6000 (1) Levels were taken on Pond i 4000 4000 4000 4000 4000 4000 4000 concrete after scrabbling and j
276 276 276 276 276 276 276 cleaning.
7000 6000 6000 6000 6000 6000 7000 (2) Each square represents a 3 foot i 4000 4000 4000 4000 4000 4000 4000 square area.
i 276 276 276 276 276 276 276 t
(3) Upper values are in dpm and 6000 6000 6000 6000 6000 6000 6000 represent the maximum 4000 4000 4000 4000 4000 4000 4000 beta-gamma contamination level 376 276 276 276 276 276 276 in a 100 cm2 area.
6000 6000 6000 6000 6000 6000 6000 (4) Middle values are the average 4000 4000 4000 4000 4000 4000 4000 contamination levels in a 276 276 276 276 276 276 276 (3ft)2 area.
6000 6000 6000 6000 6000 6000 6000 (5) Lower values are the maximum
, 4000 4000 4000 4000 4000 4000 4000 alpha contamination levels in 2
276 276 276 276 276 276 276 dpm/100 cm,
.E9.ER 17.
6000 6000 8000 6000 6000 6000 8000 4000 4000 4000 4000 4000 4000 4000 276 276 276 276 276 276 276 8000 6000 6000 6000 6000 7000 6000
- 4000 4000 4000 4000 4000 4000 4000 276 276 276 276 276 276 276 6000 6000 6000 6000 6000. 6000 7000
+
4000 4000 4000 4000 4000 4000 4000 276 276 276 276 276 276 276 7000 6000 6000 9000 6000 6000 8000 4000 4000 4000 4000 4000 4000 4000 276 276 276 276 276 276 276 6000 6000 6000 6000 7000 10000 8000
, 4000 4000 4000 4000 4000 4000 4000 276 276 276 276 276 276 276 6000 9000 6000 6000 6000 6000 7000 4000 4000 4000-4000 4000 4000 4000 276 276 276 276-276 276 276 6000 6000 6000 6000 6000 6000 7000 4000 4000 4000 4000 4000 4000 4000 276 276 276 276 276 276 276 85.
20ER 3C ATTACHMENT 1 0
6000 6000 6000 6000 6000 6000 6000 4000 4000 4000 4000 4000 4000 4000 276 276 276 276 276 276 276 6000 6000 6000 6000 6000 6000 7000 4000 4000 4000 4000 4000 4000 4000 276 276 276 276 276 276 276 6000 6000 6000 6000 6000 6000 7000 4000 4000 4000 4000 4000 4000 4000 276 276 276 276 276 276 276 7000 6000 6000 6000 6000 6000 8000
-4000 4000 4000 4000 4000 4000 4000 276 276 276 276 276 276 276 6000 6000 6000 6000 6000 6000 8000 4000 4000 4000 4000 4000 4000 4000 276 276 276 276 276 276 276 6000 6000 6000 6000 6000 7000 9000 4000 4000 4000 4000 4000 4000 4000 876 276 276 276 276 276 276 6000 6000 6000 6000 6000 7000 9000 4000 4000 4000 4000 4000 4000 4000 276 276 276 276 276 276 276 i
l 86 2-
M.4A ATTACHMENT j.
10000 9000 8000 8000 10000 9000' 8000 SURFACE CONTAMINATION LEVELS 4000. 4000 4000 4000 4000 4000 4000 PONDS M AR H 276 276 276 276 276 276 276
.10000 8000 7000 6000 7000 8000 9000 4000 4000 4000 4000 4000 4000 4000-276 276 276 ' 276 276 276 276 N 11:
2 6
i.10000 8000 7000 7000 8000 9000 10000 (1) Levels were taken on Pond 4000 4000 4000 4000 4000 4000 4000 concrete after scrabbling and 276 276 276 276 276 276 276 cleaning.
12000 9000 7000 7000 6000 8000 11000 (2) Each square represents a 3 foot 4000 4000 4000 4000 4000 4000 4000 square area.
276 276 276 276 276 276 276 (3) Upper values are in dpm and i 11000 9000 8000 6000 7000 9000 11000 represent the maximum 4000 4000 4000 4000 4000 4000 4000' beta-gamma contamination level 276 276 276 276 276 276 276 in a 100 em2 area.
14000 10000 9000 8000 7000 7000 10000 (4) Middle values are the average 4000 4000 4000 4000 4000 4000 4000 contaministion levels in a
-276 276 276 276 276 276 276 (3ft)2 g.,,
11000 10000 9000 8000 7000 8000 9000 (5) Lower values are the maximum 4000 4000 4000 4000 4000 4000 4000 alpha contamination levels in 2
275 276 276 276 276 276 276 dpa/100 cm,
MM 8000 7000 8000 9000 8000 8000 9000 4000 4000 4000 4000 4000 4000 4000 276 276 276 276 276 276 276 9000 8000 5000 5000 6000 7000 8000 1 4000- -4000 4000 4000 4000 4000 4000 276 276 276 276 276 276 276 7000 6000 5000 6000 5000 7000 8000 4000 4000 4000 4000 4000' 4000 4000 276 276 276 276 276 276 276 4
8000 7000 5000 6000 5000 6000 7000 4000 4000 4000 4000 4000 4000 4000 276 276 276 276 276 276 276 i 9000 6000 6000 6000 6000 6000 7000 4000 4000 4000 4000 4000 4000 4000 1
276 276 276 276 276 276 276 10000 8000 7000 8000 7000 6000 6000 4000 4000 4000 4000 4000 4000 4000 276 276 276 276 276 276 276 9000 7000 8000 10000 8000 7000 8000 4000 4000 4000 4000 4000 4000 4000 276 276 276 276 276 276 276 87 i
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