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                  #. . ,,o * * %,i.                                        UNITED STATES NUCLEAR REGULATORY COMMISSION
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JUN I 21988
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IMUF: EYS DOCKET N0:    f0-734 LICENSEE:      General Atomics (GA)
FACILITY:      Fuel Fabrication Facility San Diego, California
 
==SUBJECT:==
EVALUATION FOR AMEN 0 MENT APPLICATION DATED MARCH 4, 1988, RE:    GA'S DECONTAMINATION EFFORT BACKGROUND By letters dated November 16, December 6, December 21, 1984; October 1, 1985; and December 15, 1986, GA Technologies, Inc. (now General Atomics) informed the Nuclear Regulatory Commission (NRC) that GA had decided to decontaminate a portion of the facility so it could be deleted from the license and released for unrestricted use. GA's decontamination plan consists of several phases of activities (Phases I, II, and III) which have been approved by NRC.1 At present, GA has completed the decontamination efforts for Phases I, II, and III and NRC's contractor, Oak Ridge Associated Universities, has completed the final confirmatory surveys. By letter dated March 4,1988, GA applied for license amendment to authorize the release for unrestricted use of approximately 277 areas of land decontaminated under the Phases I, II, and III program. Following is the staff's evaluation of GA's decommissioning effort for the release of land and property for unrestricted use.
EVALUATION OF GA'S DECONTAMINATION EFFORT A.      Description of GA's Decontamination Activities Decontamination of Phase I activities was completed in late 1985 and consisted of areas encompassing the Solar Evaporation Pond, surroundings of the former Waste Processing Facility and Incineration Pad, a previous burial sito for contaminated asphalt, the hillside and canyon below the waste handling facilities, and undeveloped land surrounding the waste processing facilities (see Fig. 1).
In December 1985, a confirmatory survey performed by NRC's contractor, Oak Ridge Associated Universities (0RAU), identified small isolated areas in need of addicional cleanup.2 GA has made further efforts to clean these areas to acceptable levels (discussed below). During July and August 1987, GA conducted decommissioning activities of the Phase II areas which included the former Waste Processing Facility and the Incineration Pad. In September 1987, ORAU conducted a radiological confirmatory survey of the Phase II areas, which confirmed that GA has met the NRC's criteria for unrestricted release of the Phase II areas. The areas of Phases I and II occupy about 80 acres of the GA e806300102g$0 MOM 34 PDR                      PDR C
 
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                        \                                        \          pH ASC n f                                AREA e h    swAsg n, N q                                      n 4
FIGURE 1            Areas of Different Decomnissioning Phases and E:Aluded Areas
 
General Atomics (GA)                  site. The Phase III decontamination activities consist of approximately 215 acres (see Fig. 1) of primarily undeveloped land surrounding the main GA plant site. GA records and individuals familiar with the facility history indicate that radioactive material uses in the Phase III area have been limited to a few small locations. Portions of the Phase III area (B1, 82, and 83 as shown in Fig. 1) have been excluded and will be decontaminated at a later date. B1 is approximately 15 acres of steep, rough hillside located generally west and north of GA's TRIGA Reactor facility; B2 is a small sewage pump station; and B3 is about 3 acres consisting of an abandoned city sewage treatment facility (also known as Callan Ponds). By letter dated March 4, 1988, GA requested that the areas of Phases I, II, and III (excluding B1, B2, and 83) be released for unrestricted use. Areas B1 and 82 are immediately adjacent to GA's main site, therefore, access for purposes of decontamination is assured. In the case of area 83, which is surrounded by non-GA land, GA assures access by means of a ground lease.3 Until it is released for unrestricted use, GA will control access to B3 (Callan Ponds). The ORAU confirmatory survey findings of the Phase III areas (excluding B1, 82, and B3) indicate that the areas have been decontaminated to acceptable levels for unrestricted release.
B. Radiological Characteristics of Contamination and Potential Doses to Persons From GA's past operations and measurements conducted by GA and ORAU, the potential radiological contaminants are enriched uranium, thorium, and longer half-life fission and activation products, such as Co-60, Cs-137, and Sr-90.
These radionuclides emit alpha, gamma, and beta radiation. The potential radiation doses to persons using the land, buildings, and equipment are from inhalation, direct gamma radiation, and ingestion pathways. The GA site is located within a semi-arid r:gion zoned for light industry and research and development. The area is not likely to be used for agriculture. In addition, the topography and cost of the land make it highly unlikely to be used for agricultural purposes in the future. There is no potable water on the site or its environs. A brackish water table is approximately 275-300 ft deep at about the same level as the nearby salt water backwater and marshes. Thereforc, the pathway for ingestion of any residual contamination via food or water is judged to be unrealistic.
C. Criteria for Unrestricted Release
: 1. Facility & Equipment The NRC has established guidelines for the decontamination of facilities and equipment prior to release for unrestricted use. The guidelines provide acceptable surface contamination levels for byproduct, source, or special nuclear materials. The guidelines which are applicable to GA's decontamination activities for facilities and equipment are shown in Table 1.
 
TABLE I ACCEPTABLE SURFACE CONTAMINATION LEVELS MAX 1i10Mbdf                              REMOVABLEbef NUCL10[5 d                            AVERAGEbcf U-nat. U-235, U.238, and                                                          15,000 den /100 cm2                    1,000 den ./100 (=2 4
associated decay products                  5,000 dpa a/IDO cm2                                                                  6 4
1ransuranics. Ra-226. Ra-228.                                                    300 dps/100 cm2                        20 dpe/100.cm2 th-230. Ih-228, pa-231,                    100 dpm/100 cm2                                                                            ,
l    Ac-227. 1-125. 1-129 Th-nat. Th-232, Sr-90,                                                            3000 dps/100 cm2                        200 dpe/100 cm2 Ra-223, Ra-224. U-232, 1-126,            1000 dpe/100 cm2
;    l-131. 1-133 f    Beta-ganea cimitters (nuclides
!    with decay codes other than                                                      15,000,dpm sy/100 cm2                  1000 dpa 8v/100 cm2 alpha cialssion or <oontaneous            5000 dpm sy/100 cm2 fissinn) catept Sr-90 and                                                                                                                      .
l      ulhers noted abave.
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      *there surface contamination by both alpha- and beta-gasuna-emitting nuclides exists, the limits established for alpha- and beta nuct ". des should apply independently.
.I b As  used in this table, dpm (dististegrat.ons per minute) means the rate of emission by radioactive saterial as determined by correcting the l        counts per minute observed by an appropriate detector for background, ef ficiency, and geometric factors associated with the instrume 4
i                                                                                                        For objects of less surface area, the avt rage CMeasurements of average contaminant should not be averaged over more than 1 square meter.                    .
should be derived for each such object.
  ]      d ihe  maximum contamination level applies to an area of not more than 100 c.2, 2 of surface area should be determined by wiping that area with dry filter or sof t f
        'The anount of removable radioactive material per 100 cm absorb.nt paper, applying moderate pressure, and assessing the amount of radioactive asterial on the wipe with an appropriate instruaien known efficiency. When removable contamination on objects of less surface area is determined, the pertinent levels should be reduced proportionally and the entire surface should be wiped.
I The    average and maximum radiation levels associated with surface contamination resulting from beta-gamma emitters. should not I cm and 1.0 mrad /hr at I cm, respectively, measured through not more than 7 milligrams per square centimeter of 0.2 mrad /hr at                                                                                                ~
total absorber.                                                                  .
                                                                                                            .            g
 
General-Atomics (GA)                                                                        2. Contaminated Soil The NRC issued a Branch Technical Position (BTP) setting forth soil decontamination limits for unrestrictive release of land contaminated with uraiiium and thorium.4 These soil limits in the BTP which had been concurred by the U. S.
Environmental Protection Agency 5 shall be aoplied to the GA site.
However, at the GA site, there are otro    radionuclide contaminants consisting of fission products or acti.- lon products. Using the dose limits established in Option 1 of the Branch Technical Position, staff has provided GA with cleanup criteria for all radionuclides involved. The Option 1 criteria for unrestricted release of land are shown in Table 2.
The target criteria used for open land cleanijp can be compared with other existing criteria or guidance in Table 2. The NRC requires the licensee to clean contaminated land to below the target criteria.      Any alternative higher than the target criteria is not acceptable without a detailed cost-benefit consideration or unless unusual circumstances exist.
D. Compliance With t'.he Target Criteria Given below are the target criteria for direct radiation and inhalation pathways. Both criteria must be met prior to release of the area for unrestricted use.
: 1. Direct Radiatio)
The direct radiation level of 10 pR/hr above background is intended as a target criterion for open land cleanup. The dose rate shall be measured using calibrated micro-R meters accurate enough to
;                                                              differentiate background.
To demonstrate compliance with the direct radiation limit, the affected areas will be dhided into grids about 30' x 30' for surveying purposes. In order to meet the target criterion, the
,                                                                following condition has to be met:
External radiation (gamma dose rate in air 1 meter above ground level) shall not exceed 10 pR/hr above background for a diffuse source area (a contaminated area greater than 30' x 30') and shall not exceed 20 pR/hr above backgrounf. for a discrete area (a contaminated area less than 30' x 30').
Land surrounding the affected areas, but within the boundaries of the principal area for release to unrestricted use, shall be surveyed for external radiation by a "walkover" survey at 30-foot intervals.
 
General Atomics (GA)                                Table 2 Criteria for soil decontamination at the GA site Exposure      ,
Target                Other existing pathway      -
criteria              criteria or guidance External Radiation        10 pR/hr              20 pR/hr indoor (b) -EPA cleanup (whole body)              (35 mrem /yr) a)      standard for Inactive Uranium (13 mrem /yr)          Processing Site; 500 mrem /yr-10 CFR 20; 170 mrem /yr-FRC Guicance; 400-900 mrem /yr-Sur-geon General's Guidance for in-door exposure; 25 mrem /yr 40CFR190and40CFR61{,)
Inhalation of Partic-    1 mrad /yr(ig)        1500 mrem /yr-10 CFR 20(d) ulates (lung, bone)      (20 mrem /yr)          25 mrem /yr-40 CFR 190; 75 aem/yr-40 CFR 61 3 mrad /yr (bone)      1 mrad /yr (lung), 3 mrad (bone)
(60 mrem /yr)          EPA Transuranic Guidance (a) This value does not include background, the 35 mrem /yr (realistic dose) includes a shielding factor of 0.3 from a residential home with residence time of 80 percent. For commercial use, the gamma doie will be reduced to about 13 mrem /yr based on 30 percent occupancy time.
(b) 40 CFR Part 192 - Federal Register, April 22, 1980.
(c) Based on quality factor of 20 as originally intended for alpha emitted from the transuranic elements.
(d) Designated in or derived from 10 CFR 20.
(e) Clean Air Act - Federal Register, February 5,1985.
The above technique can be used to demonstrate compliance for soil contaminated at the surface. For subsurface contamination at depth, the limiting soil concentrations equivalent to 10 pR/hr for Co-60 and Cs-137 are 8 pCi/g and 15 oCi/g, respectively. These limiting concentrations are provided in case there is subsurface burial and the 10 pR/hr limit cannot be demonstrated using micro-R meters.
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General Atomics (GA)                      2. Inhalation of_Particulates Table 3 summa''izes the derived limit ng soil concentration for each i
inhaled radionuclide. It is noted that Table 3 soil limits are for individual radionuclides. If a mixture.of these radionuclides exists in soil, the following formula will be applied to show compliance:
the sum of Ci/Lig 1 where Ci = the average soil concentration of radionuclide i, and Li = the derived maximum soil limit for radionuclide i (from Table 3).
Table 3 Derived limiting concentration for inhaled radionuclides Concentration limit above Radionuclide                          background (pCi/g)
Enriched Uranium                      30 Thorium (Natural)                    10 Co-60                                1.2 x 10 4 Cs-137                                9.6 x 10 5 Sr-90                                1.0 x 10 3 To demonstrate compliance with the limits established for the inhalation pathway, the following has to be met:
Representative soil samples shall be collected at each grid (30' x 30')
from the first inch (1") of soil and analyzed for the various isotopes.
To demonstrate compliance with the target criteria given in Table 3, isotope concentrations can be averages of any four adjacent grids.
The derived concentrations in Table 3 also apply to subsurface soil contamina-tion. Therefore, subsurface soil samples will also be collected. After decon-tamination has resulted in the above condition being met for surface soil, compliance with the subsurface requirement will be demonstrated by analyzing a random 5 percent of the subsurface soil samples.
If a subsurface random sample exceeds the limit, the four adjacent 30' x 30' subsurface samples will be analyzed and the results averaged. If the average is below the limits, the inhalation dose target criteria will have been met.
If the averaged result is above the limits, further decontamination will be conducted.
 
General Atomics (GA)                                                                                                    l In the affected areas where it can be demonstrated with adequate data that meeting the 10 pR/hr above background limit will also meet the inhalation dose limit, direct radiation measurements will be used to demonstrate compliance for both pathways. In this case, soil samples of 5 percent      of the grids will be randomly collected and analyzed to confirm compliance.
E. ORAU's Confirmatory Survey After each phase of the decommissioning activities was completed, NRC's Regional Office (Region V) contracted ORAU to perform radiological surveys to certify that the areas had been cleaned to below the NRC criteria prior to the release for unrestricted use.
: 1. Phase I Confirmatory Survey In November 1985, GA submitted a report documenting that the Phase I activities were completed. In December 1985, ORAU performed a confirmatory survey which consisted of direct gamma measurements and soil sampling and analysis of radionuclides under a grid system in the affected areas. The soil sampling included surface and subsurface sampling. In addition, background and baseline measurements were made in GA's surrounding areas. The survey report 2 identified 49 small isolated areas of residual contamination in the vicinity of the previous waste storage pad, evaporation ponds, and incinerator. Although these are small areas, NRC required GA to further cleanup these areas to meet the as low as reasonably achievable (ALARA) requirement. Subsequently, GA made further efforts to cleanup these areas and in March 1987, a followup confirmatory survey was conducted by ORAU certifying that the Phase I areas were acceptable for unrestricted release (see Appendix).
: 2. Phase II Confirmatory Survey In August 1987, GA completed the Phase II activities and submitted a report to the NRC. In September 1987, ORAU conducted a confirmatory survey of the Phase II areas which consisted of gamma, beta gamma, and alpha scans; exposure rate measurements, measurements of total and removable surface contamination; and measurements of radionuclide concentrations in surface and subsurface soils.
The survey identified several small areas of residual contamination, which were pr*:Maptly recleaned by GA and resurveyed by ORAU. The enclosed ORAU Report (Appendix) concludes that the Phase II areas have been decontaminated properly to meet NRC release criteria.
!. Phase III Confirmatory Survey By letter dated August 12, 1987, GA informed NRC that the Phase III decommissioning was completed except for the B1, 82, and B3 areas and requested a confirmatory survey. In September 1987, ORAU conducted a confirmatory survey of the Phase III areas consisting of primarily
 
General Atomics (GA)                          undeveloped land surrounding the GA site and included the shipping and receiving area of Building 5. An ORAU Report was issued in February 1988 certifying that the' Phase III areas had been decontaminated to acceptable levels for unrestricted release.
Copies of the ORAU confirmatory survey reports on the Phases I, II, and III are enclosed in the Appendix.
F. Environmental Impact on Released Buildings and Land ihe licensee has decontaminated buildings and equipment below the NRC guidelines for release for unrestricted use.      For open land cleanup, the licensee has made reasonable effort to clean the Phases I, II, and III areas well below NRC's established criteria. It is recognized that the dose limits (target criteria) in Option 1 of the BTP apply to the decontamination of large areas. The licensee has generally used a small gridding system (i.e.,
30' x 30') to facilitate detailed soil cleanup to ensure doses from residual contamination are well below the target criteria.        In addition, the staff had used conservative parameters to derive the soil concentration limits to provide reasonable assurance that the target criteria will be met without additional measurements, and the land can be released immediately once the soil concentra-tion limits are met.
The derived soil Concentration limits provide no allowance for soil dilution or backfill which may be applied in future potential land use. Therefore, the staff believes that the realistic doses to persons from the release of portions of the GA property are well below the NRC's target criteria for unrestricted use, and the environmental impacts are negligible.
G. Environmental Impact from GA's Future Operations Although cleaning portions of the GA site should eventually reduce the existing impact to the general public, the reduction of the site's boundaries may have more impact to the general public living closer to the site. In June 1983, NRC issued an Environmental Impact Appraisa18 (EIA) in connection with GA's license renewal. In the EIA, NRC conducted a dose assessment for the continued operation of the GA facilities.      Most of the offsite environmental impact is from the radioactive effluent releases at the GA TRIGA reactor and fuel fabrication plant at Sorrento Valley (see Fig. 1). At present, the nearest residences are about 0.75 mile northwest of the Sorrento Valley site and 1.15 miles north-northwest of the main site. The annual dose from GA's routine operation is about 0.26 mrem to the whole-body; 0.74 mrerr and 0.58 mrem to the bone and lung, respectively. Reduction of GA's site boundary will affect the dose calculation substantially, particularly the site boundary reduction around the TRIGA reactor. The staff, therefore, evaluated the atmospheric dispersion factors at various distances (EIA, Appendix A). Depending on the future loca-tion of rssidences, the atmospheric dispersion factors (X/Q) could be increased by a factor of 10. However, because of the minute releases from the GA plant, even an increase of the above doses by a factor of 10 would not result in annual doses exceeding the EPA's Clean Air Act environmental radiation standards (25 mrem /yr to the whole body and 75 mrem /yr to other organs).7
 
L General Atomics (GA)                                                                                                                                                                    t Staff also reviewed potential accidents and the effects of the change of boundaries. In the EIA, staff had used a distance of 600 ft as the closest distance for the dose assessment for the fuel fabrication plant's criticality accident. The staff assumed a worker at the manufacturing plant (600 ft from the accident site) could be exposed during the accident. This individual (as a surrogate for the nearest resident) was also assumed to be the nearest member of the public to be potentially affected by the accident. The whole body dose was calculated to be 0.2 rem and the thyroid dose to be 0.86 rem. Staff considers that not only would an accidental criticality event be extremely unlikely, but any attendant consequences would also be acceptably small. GA's current site boundary reduction would not affect the fuel fabrication plant at the Sorrento Valley site (see Fig. 1). However, it has some effect on the site boundary at the TRIGA reactor site. GA may have to modify the technical specification in
                              .the TRIGA reactor operation to provide means for mitigating adverse effects for potential accidents which are considered to be highly unlikely. In addition, GA may have to provide-an easement area west of TRIGA extending to the B-1 area which is presently excluded from unrestricted release. The current land release
* frem this license amendment should not affect future requirements. Based on the above assessment, release of portions of their land for unrestricted use is not expected to have a significant impact to the general public.                                              ,
H. Conclusion                                                                                          i Staff has evaluated GA's decontamination activities conducted under Phases I, II, and III and concludes that GA has decontaminated these areas well below NRC's target criteria. Any contaminated materials or soil generated have been properly disposed by transporting to a licensed burial site.            Therefore, it is recommended that the approximately 277 acres as described in GA's letter dated March 4, 1988, be released for unrestricted use.                                                          !
                                                                                            ,      3                              g e          - "' %                    h        ?
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OFFICIAL RECORD COPY
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General Atomics (GA)                                    References        .
: 1. Evaluation of GA's Proposed Decontamination Plan - Occket No. 70-734, November,26, 1985.
: 2. Confirmatory Survey of Phase I Decommissioning, Former Waste Processing Facility, GA Technologies, San Diego, California - J.D. Berger, Oak Ridge Associated Universities, July 1986.
3    Letter from GA (Keith Asmussen) to NRC (L.C. Rouse) March 4, 1988, Docket No. 70-734.
: 4. Disposal or Onsite Storage of Thorium or Uranium Wastes from Past Operations - Nuclear Regulatory Commission, Federal Register, Vol. 46, No.
205, 52061, October 23, 1981.
: 5. Letter from Paul C. Cahill (U.S. Environmental Protection Agency) to Ralph G. Page (NRC) dated March 31, 1982.
: 6. Environmer.tal Impact Appraisal Related to Special Nuclear Materials License No. SNM-696 - GA Technologies, Inc. (GA) Fuel Fabrication Facility, Docket No. 70-734, U.S. Nuclear Regulatory Commission, June 1983, NUREG-0994.
: 7. National Emission Standard for Radionuclide Emission from Facilities Licensed by the Nuclear Regulatory Commission (NRC) and Federal Facilities Not Covered by Subpart H - U.S. Environmental Protection Agency - Fed.
Register 50FR5195 February 5, 1985.
 
Gonoral Atomics (GA)                                                                  ,            APPEN0lx ORAU Confirmatory Survey Reports of Phases I, 11, and 111 Activities
 
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FOLLOW-UP Prepared by 18;?,,^$$ciat'd                                    CONFIRMATORY SURVEY Prepared for U.S. Nuclear Qp So''"E'i i!n s                                      PHASE I DECOMMISSIONING Region V Office Sponsored by                                FORMER WASTE PROCESSING FACILITY Oivision of industrial and Medical Nuclear Safety GA TECHNOLOGIES SAN DIEGQ, CALIFORNIA P.R.COTTEN Radiological Site Assessment Program Manpower Education, Research, and Training Division FINAL REPORT MARCH 1988
                                                \,$
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O R AUi8, C.129 FOLLOU-UP CONT:RMATORY SURVEY OF PRASE I DECOMMISSIONING FOR.WR WASTE PROCESSING FACILITY
                  .                    CA TECHNOLOGIES
              .                    SAN DIEGO, CALIFORNIA Prepared by P.R. COTTEN Radiologic;al Site Assessment Program Manpower Education, Research, and Training Division Oak Ridge Associated Universities i                                Oak Ridge, TN 37831-0117 i
Project Staff J.D. Berger            R.C. Rookard
;                            R.D. Condra            C.F. Weaver G.L. Murphy Prepared for Division of Industrial and Medical Nuclaar Safety U.S. Nuclear Regulatory Commission Region V Office Final Report March 1988 This report is based on work pe rf ormed under Interagency Agree me nt DOE No. 40-816-83 NRC Fin. No. A-9076 between the U.S. Nuclear Regulatory Commission ad the U.S . Department of Energy.        Oak Ridge Associated Universities performs complementa ry work under contract number DE-AC05-760R00033 with          r.h e U. S.
Department of Energy.
 
i TABLE OF CONTENTS Page List of Figures . ...........................                                                          l 11 List of Tables    . ........................... iii Introduction    . . ...........................                                              1 Procedures    . .. ...........................                                                1 Results .  . . ...... .....................,.                                                2 Summary . . . . . . . . . . . . . .          ............. . . . . .                          3 References  . . . ...........................                                              17 Appendices                                                                .
Appendix At Major Sampling and Analytical Equipment Appendix B: Measurement and Analytical Procedures Appendix C: Decommissioning Guidelines for the CA Technologies Weste Processing Facility l
i e
l I
i i                                                      !
 
LIST OF FfGURES Page FIGURE la Man of San Diego Area. Indicating the Location of the GA Technologies Facilities . . . . . . . . . .                                                            ,.....      4 FIGURI 2 -Area of GA Technologies Plant. Illustrating the Phase I Decommissioning Area . . . .        ...........,...                                                                    5 FIGURE 3: Vaste Processing Facility Area. Indicating the Grid System Used for Survey Reference      .... ............                                                                      6 FIGURI 4: Locations Where December 1985 Survey Indicated Soil Concentrations Exceeding Guideline Levels. ........                                                                    7 FIGURE 5: Sampling Locations - Phase I Followup.                                  ..........                                      8 FIGURE 6:  Locations of Measurement and Sampling Locations Alon Canyon Floor . . . . . . . . . . . . . . . . . . . .g the                                                        ... 9 FIGURI 7: Locations of Background Measurements and Baseline Soil Samples from the Vicinity of GA Technologies . ......                                                                  10 4
11
 
L83T OF TABLES
                                                                        ?3?e TABLE lAt Background Radiation Levels  .............. ..                11 TABLE 13:  Baseline Radionuclide Concentrations in Soil . . . . . . . . 12 TABLE 2T  Exposure Rates at Sampling Locations . . . . . . . . . . . . 13 TASLE 3:  Radionuclide Concentrations in Soil From Remediated Areas. . 14 TABLE 4:  Radionuclide Concentrations in Soil From the Canyon Floor. . 15 TABLE 5:  Rt.dionuclide Concentrations in Composite Soil Samples. . . . 16 iii
 
FOLLOW-UP CONTfRMATORY SURVEY OF PHASE I DEC0KMIS$10NING FORMER UASTE PROCESSING TACILITY CA TECHNOLOGIES SAN DIEGO, CALITORNIA
                .                          INTRODUCTION In aid 1984, CA Technologies, Inc. (CA) of San Diego, California, initiated Phase I decommissioning activities of the Forme r Waste Processing Facility (Figures 1-3).      Phase I includes the Solar Evaporation Pond Area, the areas immediately surrounding the Former Uaste Processing Facility and Incinerator Pad, a previous burial site for contaminated asphalt, the hillside and canyon below the waste handling facilities, and undeveloped land surrounding the Waste Processing Facilities.      During Decembe r 10-17,    1985 a confirmatory survey of Phase I remediation was performed by the Radiological Site Assessment Program of Oak Ridge Associated Universities (OR U). The survey identified 49 small isolated areas (Figure 4) of residual contamination; these ' areas were primarily east and north of the Waste Processing Facility, and in the vicinity of the former Solar Evaporation Ponds.I During 1987. GA Technologies performed additional remedial actions to remove contamination. identified by the December 1985 ORAU survey. A report, prepared by CA indicates that this remedial action was effective in reducing residual contamination to within the guidelines established for the site.2 At the request of the Nuclear Regulatory Commission's Region V Office, a followup survey of these reeleaned areas was pe rf ormed by ORAU during September 1987            This report describas the procedures and results of that survey.
PROCEDURES
: 1. The licensee's grid system was reestablished at JO ft (9.1 m) intervals to provide reference points f or measurements and sampling.
L
 
l
: 2.      A walkover surface gamma scan was conducted at 1-2 m intervals throughout :Me remediated area, using portable countrate instruments with NtI(T1) p .2 2 scintillation detectors and audible indicators.                              A scan of the canyr.
drainage area, southeast of the Waste Processing Facilities, was also p e r f o r me d'.
: 3. Exp'osure rates were measured at the surface and 1 m above the surface at seven locations (Figure 5), where additional remedial action had been performed.                        These locations represented those areas which were noted by the 1985 survey to have higher levels of contamination.                          Measurements were also performed at four locations in the Canyon (Figure 6).
4    Surface                        soil  samples  were  collected  at  locations  of  exposure  rate D
                                                                                                                                              -p w
measurements.
NN'ij
: 5. Samples and data were returned to Oak Ridge, Tennessee for analyses and evaluation.                          Appendices A and B contain additional information regarding equipment and procedures. Results were compared to guidelines established for decommissioning of this facility (Appendix C).
RESUI.TS Walkover gamma scans did not identify any locations of significantly elevated direct radiation levels in the remediated area or along the canyon floor.                            Gamma exposure rates measured in these areas are presented in Tabla 2.                                    In the remediated area these rates ranged f rom 16 to 23 uR/h at surface contact and from 15 to 18 uR/h at I a above the surface. Measurements along the canyon floor ranged f rom 15 to 18 uR/h at the surf ace and f rom 14 to 16 uR/h at i e above the surface. For comparsson, the background exposure rates in the vicinity of the GA Technologies f acility averages about 9.7 uR/h at 1 m above the surface (Table 1A). The guideline for decommissioning retquires that the average exposure rate te less than 10 uR/h above background, which would be a total of 19.7 J/h. All exposure levels measured at 1 m above the surface during this survey were less than 19.7 uR/h and theref ore this guideline is satisfied.
2
 
Tables 3 and 4 present the concentrations of ga tea emitting radionuclides.
measured in surf ace soil collected from the remediated and canyon floor stess.
Ranges of concentrations in these samp'.es were Co-60, <0.05 to 1.78 pC1/g; Cs-137, 0.28 to 11.9 pCi/g; Ra-226, 0.83 to 1.57 pCi/g; U-235, <0.23 to 1.69 pCi/g; U-238,
                                                                <0.78 to 3.45 'pci/g; Th-228, 1.03 to 9.57 pCi/g; Th-232, 0.98 to 7.46 pCi/g.
Concentrations    of  Sr-90    and  isotopic uranium    in  two  composite  samples, representing the remediated area and canyon area, are listed in Table 5.              The Sr-90 concentrations ne 0.32 and 2.20 pCi/g; the highest uranium levels are U-238, which are 3.29 and 4.42 pCi/g. On the basis of the U-234/U-238 ratios, it appears that the uranium is depleted in the U-235 and U-234 isotopes.
With exception ~of the total thorius (Th-228 and Th-232) concentration, in the sample f rom location 1055, all radionuclide levels were below the guideline values in Appendix C and most were in the range of baseline concentrations (see Table 15). The thorium concentration in sampla 1058 was 17.55 pCi/g, or 15.26 pCi/g above the average backgewnd level.        This is slightly higher than the guideline value of 10 pCi/g above background.      Surf ace scans in this area did not identify    '
                                                                .<fe,;'icant)* elevated direct radiation levels, and sampling during the 1985            i su . indicaced that soils at L td intersections in the vicinity of this location were well within the guideline levels.        Contamination at grid coordinate 7695N.
9550E is therefore an isolated small area, and averaging over adjacent soil will result in a concentration which satisfies the 10 pCL/g guideline.
 
==SUMMARY==
 
During September      1987, Oak Ridge Associated Universities          performed  a radiological survey of areas within the Phase 1 Decossissioning activities of CA Technologies in San Diego, California.
The survey included locations, which had
)
been remediated, following their identification by a December 1985 ORAU survey, and a section of canyon area in the drainage pathway f rom the Waste Processing p
Facility. Survey activities consisted of walkover gasaa scans, exposure rate l                                                              measurements, and soil sampling and analyses.          Findings identified no areas exceeding the decommissioning guidelines, authorized by the Nuclear Regulatory Commission f or this site.      Based on these results it is ORAU's opinion that the radiological data, as presented by the licensee, is adequate and accurate and that the radiological conditions satisfy the established guidelines for release for unrestricted use.
3
 
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FIGURE 3:        Waste Processing Faci!ity Area, indicating the Grid Systern used for Survey Reference 6
 
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!                                                      L                      l k
                                                                        \
MILES              y 0    1      2    3      4  5  j l  I      f    !      !  !
I i i i i I I I i 0      2      4        5    S KILCMETERS FIGURE 7: Locations ( e ) of Background Measurements and Baseline Soil Somptes from the Vicinity of GA Tecnnoiogies 10 i
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TABLE 1A BACKCROUND RADIATION LEVELS CA TECHNOLOGIES
                            ,            SAN DIEGO, CALIFORNIA Camma Exposure Rates Gamma Exposure Rates Locationa        . at I a Above the Surface              at the Surface (pR/h)                        (ia/h) 1                                    7                            8 2                                    8                            8 3                                    7                            7 4                                  10                            10 5                                  13                            15 6                                  ,13                            15 RANCE                              7 TO 13                        7 TO 15 AVERAGE                              9.7                          10.5 aRefer to Figure 7.
11
 
TABLE IB BASELINE RADIONUCLIDE (X)NCENTRATi(NS IN S0lt GA TEOm0LOGIES SAN DIEGO, CALIF 0HNIA                                    6 4
Location 8                                                                                RadionuclIde Concentrations (pCl/g)
Co-60          Cs-137              Ra-226            U-235          U-238  Th(228 & 232)      K-40 I                            <0.03          <0.02            0.59 1 0.14 b      <0.17        I.6 i I.2  1.34 1 0.46    14.0 1  1.7 2                              <0.05      0.16 1 0.11          0.5310.22          <0.20        3.6 1 1.5  1.98 1 0.86    25.0 1  3. 3 3                              <0.04          <0.04            0.79 1 0.20      0.39 1 0.24    1.1 1 0.5    2.24 1 0.62    10.4 1  1.7 4                              <0.08          <0.05            1.20 1 0.29        <0'.32        <1.l      3.06 1 0.79    29.0 t  3.4 5                              <0.05          <0.05            1.23 1 0.22      0.69 1 0.55    1.3 1 0.6    3.20 1 0.00    24.5 t  2.7 6                              <0.05          <0.05            0.65 1 0.16        <0.22        1.0 1 0.9  I.92 1 0.78    30.2 1  2.9 RANGE                                        <0.03 to <0.08 <0.02 to <0.16        0.53 to I.23    <0.17 to 0.69    I.0 to I.6  1.34 to 3.20  13.4 to 30.2 N                                            AVERAGE                                        <0.05          <0.06                0.85            <0.33          1.5          2.29          22.2
* Refer to Figure 7 b
uncertainties represent the 955 confidence levels, based only on counting statistics; additional laboratory uncertainties of 6 to 105 have not been propagated in these data.
 
TABLE 2 EXPOSURE RATES AT SAMPLING LOCATIONS PHASE I FOLL0tJ-UP GA TECHNOLOGIES
                  .                SAN DIEGO, CALIFORNIA
        ~'
Grid Locationa          Coordinate                      Exposure Rate (uR/h)
ID              N        E            Contact        I a Above Surface 100B          7160      9620                16                15 101B          7240      9646                16                15 102B          7532    9660                16                16 1035          7432    9645                20                18 1045          7611    9541                23                16 1055          7688    9550                20                15 1065, 7528    9544                20                16 270B          Canyon Floor                  18                16 ,
2715          Canyon Floor                  16                15 272B          Canyon Floor                  15                14 2735          Canyon Floor                  16                14 aRefer to Figures 5 and 6.
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TABLE 3 HAD10NCullDE CO M ENTR',TIONS IN S0lt FRON RENEDIATED AREAS PHASE I FOLLOW-UP GA TEO940LOGIES                              I
^
SAN DIEGO, CAlliORNIA                                        6 l                  i
                                                                                                                                                                                                                                                        !                  i Sample                    ,                                      Radionuclide Concentrailons (pCI/gl No.        Locationa        Co-60              Cs-137                    Ra-226            U-235    U-238    Th-228          Th-232 1
i 1000      7 860N,%20E        <0.05          0.28 1 0.12      1.17 1 0.25                    <0.23    <0.8      1.59 1 0.42      1.61 1 0.47 1018      7290N,%46E    I.78 1 0.27b      9.9710.44        1.17 1 0.40                    <0.38  3.5 1 0.9  2.10 1 0.42      1.96 1 0.55 1020      7532N,%60E        <0.08          1.78 1 0.19    1.50 1 0.33                    <0.32    <0.9      3.9510.48        2.03 1 0.70 1058      74 32N,%45E    0.52 1 0.15        2.9212.51        1.30 1 0.23                    <0.28    <0.8      2.76 1 0.45      f.% 1 0.55
!                                                                                                                                                          1048      76tlN,954tE        <0.06          1.52 1 0.17    1.57 1 0.25                    <0.26  3.0 1 0.7  1.62 1 0.48      2.06 1 0.50
                                                                                                                                    *-                      1056      7688N,9550E        <0.06          0.3210.14        I.07 1 0.32                1.69 1 0.86  <l.5      9.57 1 0.88      7.46 i O.87 1068      7528N,9544E    1.5010.28          11.85 1 0.50    0.83 1 0.33                    <0.31    <0.9      1.26 1 0.48      1.40 1 0.57 mRefer to Figure 5 b uncertaintles represent the 95S confidence levels based 5 ty on comting statistics; additional laboratory scortainties of 6 to 101 have not been propagated lato these data.
 
4 l
l TABLE 4 4
RADIONCULIDE 'DNCENTRATIONS IN SOll. FRON THE CANYON FLOOR PHASE I FOLL01s4P CA TEONOLOGIES                                    I SAN DIEGO, CALIF 0HNIA                                  3 Sample
* Radlonuclide Concentrations (pCl/g)
No.                Cc-6C              Cs-137        Ra-226              W235            U-238      Th-228            Th-232 2700              0.15 1 0.IO b      0.97 1 0.16    1.0 1 0.2        0.57 1 0.12    1.7 1 0.6    3.62 1 0.44      2.00 1 0.57 2710              0.18 1 0.20        0.68 1 0.15    1.4 1 0.3        0.27 1 0.14        <l.0    1.03 1 0.50      0.98 1 0.37 2720                <0.05          0.15 1 0.09    I.4 1 0.3        0.20 1 0.06    2.4  1 0.67 1.50 1 0.28      1.50 1 0.53 2738              0.17 1 0.12        1. 3 1 0.2      1.3 1 0.2        0.41 1 0.13    0.94 i 1.7  1.64 1 0.39      1.6010.47  ;
9 W
u i
aRefer to Figure 6 b
l uncertainties represent the 955 confidence levels based only on <xm4 ting statistics; additional laboratory incertaintles of 6 to 105 have not been propagated lato these data, i
1
 
Ta8LE 5 AADIONUCLICE CONCENTRATIONS IN CC@01lTE Soll SAWLES PwASE I FOLLCw s9
                              .                      GA TEC* 0LOGIES
                          -                        SAN Ol EG0, CAL I FORN I A Sample                                          Redlonuellde Concentrations (pCI /c) 10                                  Sr-90                  U-234            L) 235        U-238 Composite Aa                        0.32 2 0.12 D        1.85 2 0.26        0.13 1 0.08  4.42 2 0.40 Composite B                          2.20 t 0.30          1.74 2 0.24        0.07 1 0.06  3.29 2 0.34 a$ ample Identification numbers:
Composite A          (2708; 2718; 27283 2738)
Compoelte 8: (729(N, 9646E; 7432N, 9645E; 7611N, 9541E; 7828N, 9544E) buncertaintles represent the 955 confidt'ce levels, based only on counting statistics; additional lacoratory mcortaintles of 2 6 to 105 u 5 not been props 9ated into these data.
e l
16 i
1
 
REFERENCES
: 1. "Confirmatory Survey of Phase I Decommissioning Former flaste Processing Facility," CA Technologies, San Diego, California, Oak Ridge Associated Universi. ties, July 1986.
: 2. Letter ,f rom K.E. Asmussen (CA Technologies Inc.) to R. R. Thomas (U.S. Nuclea r Regulatory Commission, Region V), Reference "License SNM-696, Docket 70-1734" August 12, 1987.
4 17 1
 
      =O 4
APPENDIX A PLIM AND ANALYTICAL EQUIPMENT h
1 1
 
APPEND!X A MAJOR SAMPLING AND ANALYTICAL EQUIPMENT The dispiay or description of a specific product is not to be construed as an endorsement of that product or its manufacturer by the authors or their employer.
A. Direct Radiation Measurements
            ~
Eber1ine '1ASCAL" Portable Ratemeter-Scaler Model PRS-1 (Eberline, Sante Fe, NM)
Eberline PRM-6 Portable Ratemeter (Eberline, Sante Fe, NM)
Victoreen NaI Scintillation Detector Model 489-55 (Victoreen, Cleveland, OH)
Reuter-Stokes Pressurized Ionization Chamber Model RSS-111 (Reuter-Stokes, Cleveland, OH)
: 8. La.boratory Analyses Automatic low-background Alpha-Beta Counter Model LBS110-2080 (Tennelee, Inc., Oak Ridge, TN)
High-Purity Germanium Detector Model CMX-23195-S, 23% efficiency (EG&G ORTEC, Oak Ridge, TN)
Used in conjunction with:
Lead Shield, G-16 (Gamma Products Inc., Palos Hills, IL)
High Purity Germanium Coaxial Well Latector Model GwL-110210-PWS-S, 23% Efficiency (EGGG ORTEC, Oak Ridge, TN)
Used in conjunction with:
Lead Shield Model C-16
( Applied Physical Technology, Atlanta, GA)
High Purity Germanium Detector Model IGC25, 25% Efficiency (Princeton Gamma-Tech, Princeton, NJ)
A-1
                                          - , - , - , - - - , + .- , - -
 
Used in conjunction with:
Lead Shield (Nuclear Data, Schaumburg, IL)
        !!ultichannel Analyzer ND-66/N0-680 System (Nuclear Data Inc., Schaumburg, IL)
Alpha Spectrometry System Tennalec Electronics (Tennelec, Oak Ridge, TN)
Surf ace Barrier Detectors (EG&G ORTEC, Oak Ridge, TN)
Multichannel Analyzer Model ND-66 (Nuclear Data, Schaumburg, IL)
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9 APPENDIX B MEASUREMENT AND ANALYTICAL PROCEDURES l
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APPENDIX 3 Measurement and Analytical Procedures Camma Surface Scans Walkover surf ace ~ scans were performed at approximately 1-2 m intervals using Eberline Model PRM-6 portable ratemeters with Victoreen Model 489-55 gamma scintillation probes containing 3.2 cm X 3.8 cm NaI(T1) scintillation crystals.
Relative count rates were monitored using earphones and increased rates above the ambient background levels were noted.
Exposure Rate Measurements Measurements of gamma e,xposure rates were performed using an Eberline PAM-6 portable ratemeter with a Victoreen Model 489-55 gamma scintillation probe containing a 3.2 cm x 3.8 cm NaI(T1) scintillation crystal.        Count rates were converted to exposure rates (uR/h) by cross-calibrating with a Reuter Stokes model RSS-111 pressurized ionization chamber.
Soil Sample Analysis Camma Spectroscopy Soil samples were dried, mixed, and a portion sealed in 0.5-liter Marinelli i-  beaker. The quantity placed in the beaker was chosen to reproduce the calibrated counting geomet ry and typically ranged from 600 to 800 g of soil. Net soil l
weights were determined and the samples counted using intrinsic germanium and Ce(Li) detectors coupled to a Nuclear Data Model ND-680 pulse height analyzer system. Background _ and Compton stripping, peak search, peak identification, and concentration calculations were        performed using the computer capabilities
  . inherent in the analyzer system. Ene rgy peaks used for determination of radionuclides of concern were:
B-1
 
Co 1.173 MeV Cs-137 - 0.662 MeV Ra-226 - 0.609 MeV from B1-214 (secular equilibrium assumed)
U-235- - 0.144 MeV U-238 - 0.094 MeV f rom Th-234 (secular equilibrium assumed)
              - Th-228 - 0.583 MeV from T1-209 (secular equilibrium assumed)
Th-232 - 0.911 MeV from Ac-228 (secular equilibrium assumed)
The spectra were also reviewed for the presence of other radionuclides.
Strontium-90 Analysis                          ,
Aliquots of soil were dissolved by pyrosulfate fusion and the strontium precipitated as a sulfate.        Successive treatments with EDTA preferentially removed lead and excess calcium and returned the strontius to solution. Ferric and other insoluble hydroxides was precipitated at a pH of 12 to 14        Strontium was reprecipitated as a sulfate.      Barium was removed as a chromate using DTPA.
The final precipate of strontium carbonate was counted using a low-background Tennelee alpha-beta proportional counter.
Alpha Spectrometry for Isotopic Uranium Aliquots of soil were dissolved by pyrosulf ate fusion and precipitated by barius sulfate. The barium sulf ate precipitate was redissolved and uranium was separated by liquid-liquid extraction. The uranium was then precipitated with a cerium fluoride carrier and counted using surface barrier detectors (ORTEC),
alpha spectrometers (Tennelec), and an ND-66 Multichannel Analyzer (Nuclear Data).
  . Uncertainties and Detection Limits The uncertainties associated with the analytical data presented in the i    tables of this report, represent the 95% confidence levels for that data. These uncertainties were calculated based on both the gross sample count levels and the associated background count levels. When the net sample count was less than the l    95: itacistical deviation of the background count, the sample concentration was l    reported as less than the detection capability of the measurement procedure.
t B-2 1
 
Because  of    variations  in    background          levels,          sample volumes or weights, ;
measurement efficiencies, and Compton contributions f rom other radionuclides in samples, the detection limits differ from sample to sample and instrument to ins t rume nt. , Additional uncertainties of            6 to 10%, associated with sampling and laboratory procedures, have not been propagated into the data presented in this report.
Calibration and Ouality Assurance Laboratory and field survey procedures are documented in the following manuals, developed specifically for the Oak Ridge Associated Universities' Radiological Site Assessment Program:                "Survey Pro,;edures Manual," Revision 3, May 1987; "Laboratory Procedures Manual", Revision 3, May 1987 and "Quality Assurance Manual", Revision 1, June 1987.
With the exception of the measurements conducted with portable gamma scintillation survey meters,            ins t rume nt s were calibrated with' NBS-traceable standards. The calibration procedures for the portable gamma ins t rume nts are performed by comparison with an NBS calibrated pressurized ionization chamber.
Quality control procedures on all instruments included daily background and check-source measurements to confirm equipment operation within acceptable statistical fluctuations.        The ORAU laboratory participates in the EPA and EML Quality Assurance Programs.
B-3
 
9 4 .
APPENDIX C DECOMMISSIONING CUIDELINES FOR THE CA TECHNO,LOGIES WASTE PROCESSING FACILITY l
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APPENDZX C Deconnissioning Guidelines for the CA Technologica Vaste Processing Facility Target criteria for unrestricted release of the GA Technologies' Uaste Processing Facility and surrounding areas are presented in the licensee's final report and are as follows:
External Radiation The gamma exposure rate at 1 m above the ground surf ace shall not exec _d 10    uR/h    above    background    f> c  an    area  of    greater  than 30 ft (9.1 m) : 30 ft (9.L m) and shall not exceed 20 uR/h above background foranydiscretearea(i.e. less than 30 ft (9.1m)x30ft9.1m)).
Inhalation and Ingestion Concentrations of radionuclides in soil shall be such that inhalation and ingestion are not expected to result in annual dose equivalents exceeding 20 area to the lung or 60 mram to the bone.
Limiting soil concentrations were derived to satisfy these external and internal target criteria.        The concentration limits are presented in the following Table.
Radionuclide              Concentration Limit Above Background (pCi/g)
Depleted Uranium                                  35 Enriched Ur,,anium                                30 l
Thorium (Natural)                                10 l      Co-40                                              8
,      Cs-137                                            15 3
Sr-90                                          1.8 x 10 Where more than one radionuclide is present, the sum of the ratios of the individual radionuclide concentrations to their respective concentration limits shall not exceed 1.
C-1 l
 
ORAU 88,C
        ~
: 0)      .
l Prepared by Oak Ridge Associated Universities CONFIRMATORY SURVEY Prepared for U.S. Nuclear                                                  Qf So"mi'i f!n,                        PHASE 11 DECOMMISSIONING Region V Office Sponsored by Division of FORMER WASTE PROCESSING FACILITY Industrial and Medical Nuclear Safety              .
GA TECHNOLOGIES SAN DIEGO, CALIFORNIA P. R. C OTTEN l
l Radiological Site Assessment Program Manpower Education, Research, and Training Division FINAL REPORT MARCH 1988 l ErQ#NM ww w            \c__
ys-m  \ \-~
                      @          k'
 
CONFfRMATORY SURVEY OF PRASE II DECOMMISSIONING FORMER WASTE PROCESSING FACILITY GA TECHNOLOGIES SAN DIEGO, CALIFORNIA d '
Prepared by P.R. COTTEN Radiological Site Assessment Program Manpower Education, Research, and Training Division Oak Ridge Associated Universities Oak Ridge, TN 37831-0117 Project Staff J.D. B,erger          R.C. Rookard R.D. Condra            T.J. Sowell D.A. Gibson            C.F. Weaver G.L. Murphy Prepared for Division of Industrial and Medical Nuclear Safety U.S. Nuclear Regulatory Commission Region V Office Final Report March 1988 This report is based on work performed under Interagency Agreement DOE No. 40-816-83 KRC Fin. No. A-9076 between the U.S. Nuclear Regulatory Commission and the U.S. Department of Energy. Oak Ridge Associated Universities performs complementary work under contract number OE-AC05-760R00033 with the U. S.
Department of Energy.
i 4
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TABLE OF CONTENTS Page List of Figures . ...........................
                                    ,                                                                11 List of Tables                .. .......................... iii
                                ~
Introduction and Site History . .                .. . . .. . . . . . . .......            1 Site Description ...........................                                              2 Procedares                  . . . .... .......................                              2 Results . . . .. . ...........................                                              6 Comparison of Survey Results with Guidelines                  . . . . . . .,. . . . . ,    9 Summary . . . . . ............ .. .. . . . . .......                                      10 References                  . . .. ..........................                              45 Appendices Appendix A: Major Sampling and Analytical Equipment            .
Appendix B: Heasurement and Analytical Procedures Arpendix C: Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Licenses for Byproduct, Source, or Special Nucicar Material Appendix D: Decommissioning Guidelines for the CA Technologies Waste Processing Facilities e
i
 
t LIST OF FIGURES Page FIGURE 1: Map,of San Diego Area, Indicating the Location of the CA Technologies Facilities . ..... . . . . . . . . .                                11 FIGURE 2: -GA Technologies Plant Layout        ..............                                  12 FIGURE 3: Area of CA Technologies Plant, Included in Phase II Decommissioning. ....................                                              13 FIGURE 4: Phase II Decommissioning Areas of the Former Vaste Processing Facility. .      .............. . . .                                    14 FIGURE 5: By-Products Storage Building Layout, Indicating the Reference Grid System and Locations of Contamination Measurements on the Floor and Lower Walls. . . . . . .                      .      15 FIGURE 6:  Ca' rage / Office Building Layout, Indicating the Reference and System and Locations of Contamination Measurements on the Floor and Lower Walls . . . .                  . . . . . . . . . .          16 FIGURE 7: Measurement Locations on Other Surfaces in the By-Products Storage Beilding . . . . . .. . . . . . . .                            17 FIGURE 81 Measurement Locations on Other Surfaces in the Garage / office Builing. . . .    ..............                                  18 FIGURE 9: Phase II Area, Indicating the 30 ft Crid System Used for Survey Reference .      ..... . . . . . . . . . . . .                          19 FIGURE 10: Locations of Surf ace Contamination Measurements and Samples f rom Pads and Foundations. . ... . . . . . . .                            20 FIGURE 11: Locations of Background Measurements and Baseline Soil Samples From the Vicinity of CA Technologies.                      . . . 21 FIGURE 12: Area on the By-Products Storage Building Floor, Identified By Surface Scans. . . . . . . . . . . . . . .                          22 FIGURE 13: Locations of Elevated Direct Radiation, Identified by Surface Canna Scans. . . . . . ... . .. .. . . . . .                              23 11 t                          -
 
LIST OF TABLES Page TABLE 1:  Background Radiation Levels . . . . . . . .. . . . . . . . . .                                        24 TABLE 2: , faseline Radionuclide Concentrations in Soil                            . . . . . . . .              25 TABLE 3: Summary of Surf ace Contamination Measurements in the By-Products Storage and Carage/ Office Buildings . . . . . . .                                        26 TABLE 4: Exposure Rates Measured at 30 f t Grid Intervals . . . . . . .                                          27 TABLE 5: Exposure Rates Measured in the Incinerator Pad Area . .                                        . . . 32 TABLE 6: Direct Radiation Levels Measured on Concrete Pads .                              . . . . .            33 TABLE 7: Exposure Rates Measured Af ter Remediacion of Areas Identified By Surface Scans. . .      . . . . ................                                                  34 TABLE 8: Summary of Surf ace Contamination Measurements - Concrete Pads and Foundations. . . . . . . . . . . . . . . . . . . . .                                          35 TABLE 9: Radionuclide Concentrations in Surface' Soil Samples from 30 f t Grid Intervals.      . .. . ................                                                    36 TABLE 10: Radionuclide Concentrations in Soil Samples Collected From the Incinerator Pad Area. . . ................                                '
40 TABLE 11: Radionuclide Concentrations in Soil From Beneath Concrete Pads  . .... ...... . ............. . . .                                                            41 TAB'.E 12: Radionuclide Concentrations in Surface Soil Samples Collected Following Remediation of Areas Identified by Surface Scans. .                                        42 TABLE 13: Radionuclide Concentrations in Composite Soil . . . . . . . .                                        43 l
TABLE 14: Radionuclide Concentrations in Miscellaneous Samples. . . . .                                        44 f
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CONFfRMATORY SURVEY OF PHA52 ff DECOMMfSS10NING FORMER WA3TE PROCESSING FACILITY CA TECHNOLOGIES SAN DIEGO, CALIFORNIA INTRODUCTION AND SITE HISTORY In mid 1984, CA Technologies (GA) of San Diego, California, initiated decommissioning activities for th,e purpose of releasing portions of its facilities from Nuclear Regulatory Commission (NRC) licensing restrictions.                                      Potential radiological contasinants at GA have been identified as enriched uranium, thorium, and longer half-life tission and activation products.                                  Decommissioning of these facilities was separated into three phases. Phase I activities, which encompassed the Solar Evaporation Pond Area, the areas immediately surrounding the former W.ste Processing Facility and the Incinerator Pad, a previous burial site for contaminated asphalt, the hillside and canyon below the waste handling f acilities, and undeveloped land surrounding the waste processing facilities, were completed in late 1985.        A confirmatory survey, performed by Oak Ridge Associated Universities in December 1985, identified small isolated areas in need of additional remedial action.I These areas have been addressed and discussed in a separate report. 2          Phase II consists of two major areas, the former Uaste Processing Facility and the Incinerator Ped.                                Phasa III consists of approximately 87 hectares (215 . acres) of primarily undeveloped land, surrounding the main GA Technologies plant site:                                survey findings of these areas have also been described in a separate report.3 During July and August 1987, GA conducted decommissioning activities of the Phase II facilities. A report of CA's findings, issued in August 1987, indicates that the post-decontamination radiological conditions satisfy the NRC guidelines for decommissioning."
At the request of the NRC, Region V Office, the Radiological Site Assessment Program of Oak Ridge Associated Universities (ORAU) conducted a radiological survey in September, 1987 to confirm the status of the Phase II area, relative to the NRC criteria for release for unrestricted use.
 
STTE DESCR!PT10N The GA Technologies facilities are located near the intersectic s of Interstate 5 and Genesee Road, approximately 20 km north of San Diego, CA (Figures 1, and 2).      Site activities include a wide variety of research and development programs. The Phase II area, shown in Figure 3,    is reached via the main ac ce s's road from the plant entrance gate.        This area includes the Waste Processing Facility, consisting of the upper and lower storage yards, and the Incinerator Pad site (Figure 4).      Much of this area is paved with asphalt; also included are a truck scale and several concrete pads or foundations.        Some of the original paving and pads have been removed during the decontamination operations.
Located in the lower storage yard are two small buildings            -
the By-Products Storage Building and the Garage / Office Building. The By-Products Storage Building was utilized for sample preparation and storage before and during decommissioning activities. The garage area of the other building was also ased for short-term storage of radioactive materials.      The buildings are of simple construction; the By-Products    Storage  Building  is  cons t ructed of corrugated metal and the Garage / Office Building is of wood frame. Both buildings have concrete floors.
PROCEDURES A survey of the Phase II Decommissioning area was pe rf ormed by the Radiological Site Assessment Program of ORAU during September 9-28, 1987.          This survey was in accordance with a survey plan submitted to the Region V Of fice of the NRC.5    Methofs and  r eocedures  utilized in the survey are presented in this section.
Objective,s l
The objectives of the survey were to confirm that the radiological condition of the Phase II area was as presented in the CA Technologies report and to provide information and data for evaluation of the site status, relative to VRC .aidelines for release for unrestricted use.        Radiological information collected included gamma exposure rates; location of elevated direct radiation levels; concentrations of radionuclides in surf ace soil; and surf ace contamination levels.
2 l
l _. . -          -
 
Procedures Document Review 1
The 11censee's final su^;ev repot; for the release of the Phase II area for unrestricted use and supporting docurents were reviewed by ORAU. Data presented in these, reports were compared to the established release guidelines.
9uilding Survey Gridding An alphanumeric 6 f t (1.8 m) x 6 ft (1.8 m) reference grid was established v the floor and lower walls (up to 6 f t (1.8) in each building.      The grid baseline coordinates (A,0) were located in the southwest corner of each buildir.g.
Figures 5 and 6 shuw the building layouts and reference grid systems used for this survey. Measurements on the upper walls and ceilings were referenced to the floor grid designation.
Surface Scans Alpha, beta-gamma, and gassa scans were performed on floors, using an alpha / beta  gas proportional  floor monitor  and  NaI(T1)  gamma  scintillation detectors with audible indicating scaler /ratemeters.          Scans of surfaces not accessible to the floor monitor, i.e.,  walls, ceilings, and overhead areas such as ledges, beams, piping, fixtures, and equipment were performed using portable ZnS alpha scintillation detectors and "Pancake" CM beta-gamma detectors.            Areas l
indicating elevated radiation levels were marked for additional decontamination and for further measurements.
Measurement of Surf ace Contamination Levels                                    ,
Approximately 20% of the grid blocks on the floor and lower walls of each building were randomly selected for surf ace contamination measurements. Blocks selected for these me asu re me nt s are indicated on Figures 5 and 6. In each grid
! block surveyed, direct measurements of alpha and beta-gamma contaminatien levels were systematically perf ormed at the center and four equidistant points, midway between the center and block corners.        Smears for removable alpha and beta 3
1
 
contamination were performed at that location in each grid block, where the highest direct level was obtained.
Seven -locations on upper walls, ceilings, fixtures, and equipment were selected fqr single point measurements of total and removabis alpha and beta gamma contamiriation levels. These locations are identified on Figures 7 and 8.                Direct measureme nt s and/or smears were also obtained from elevated locations identified by surf ace scans.
Outside Area Survey Gridding In the upper and lower storage yards the licensee's 10 f t (3.0 m) grid system was reestablished at 30 ft (9.1 m) intervals (Figure 9) and the licensee's 3 f t (0.9 m) grid was used on the Incinerator Pad.
Surface Scans Walkover gamma surface scans were conducted at t to 2m intervals in the upper and lower storage yard and on the Incinerator Pad, using portable NaI(Tl) gamma scinct11ation detectors and ratemeters.                The exposed surf ace of the wall; separating the upper and lower storage yards, was scanned using a "Pancake" GM detector coupled to a ratemeter.              Scans of concrete pads and some larger areas of asphalt paving were performed using the alpha / beta gas proportional floor monitor. Locations of elevated radiation identified by the scans, were brought to the licensee's attention and marked for further evaluation.
F.xposure Rate Measurements Exposure rate measurements were made at the surface and at 1 e above surface at 30 ft (9.1 m) intervals in unpaved areas of the former Waste Processing Facility, at seven locations in the Incinerator Pad area, and at locations of elevated direct radiation, identified by the surface scans.                      Portable ganea scintillation detectors,                calibrated onsite against a pressurized ionization chamber, were ueed f or these measurements.
4
 
Msasurement of Surface Contamination Levels Total and removable alpha and beta-ga=ma contamination levels were measured at nine locations, on the concrete pads (Figure 10).
Sampling Surface (0-15 cm) samples were collected from areas of exposed soil at 30 ft grid intervals throughout the area and at locations identified by surf ace scans.
Following further cleanup by the licensee, followup soil samples were obtained.
Concrete coring was performed at the location on each concrete pad, where the highest direct measu re me nt was obtained.      These locations are indicated on Figure 10. Camma mortitoring of the soil beneath the removed core was performed to identify the presence of elevated rad *ation levels and soil samples were collected f rom the exposed surface. A sample of residue waa also collected f rom a drain near the My-Products Storage Building (Figure 10).
Mackground and Baseline Measurements During a previous site visit, measurements and soil samples were obtained in the vicinity of tha CA Technologies plant to determine area background levels and baseline radionuclide concentrations for comparison purposes.        Locations of the background measurements and baseline samples are shown on Figure 11. Tables 1 and  2    present  the background exposure rates and baseline radionuclide concentrations, respectively.
t Sample Analyses and Interpretation of Results Samples werp returned to laboratories in Oak Ridge, Tennessee, for analyses.
All soil and residue samples were analyzed by gamma spectrometry.          The major radionuclides of interests were Cs-137, Co-60, U-235, U-238, Th-228, Th-232, and Ra-226; however, spectra were reviewed for the presence of other significant l
photopeaks. Selected individual samples and composite samples were also analyzed l
! for St-90 and isotopic uraniun.        Smears for the determination of removable co?.camination were analyzed for gross alpha and beta concentrations.
1                                          5 1
i
 
Additional inf orm:: tion concerning analytical equipcint and procedures is contained in Appendices A and 3.                    Results of this survey were compared to the guidelines, established by the                    NRC, for decommissioning of the CA Technologies Uaste Processing Facility. These guidelines are presented in Appendices C and D.
RESULTS Document Review ORAU's review of the survey report submitted by GA to the NRC, indicates that the procedures and instrumentation used were consistent with industry accepted practices. Sampling conducted by GA was primarily from the waste processing area, where contaminated soil was stored awaiting shipment, and in several locations where the potential for contamination was the highest, based on previous facility use history.                  The data developed by CA are within the NRC guidelines established for this decommissioning activity.
Building Survey Surface Scans                                                                        ,
Surface scans identified an area of residual contamination on the floor of the By-Products Storage Building.                      This location is indicated on Figure 12.
According to site personnel a spill had occurred at this location during f acility                  ,
operations.                    No additional areas of elevated radiatior, were noted inside the buildings.
Surf ace Contamination Measurements i
Table 3 summarises the results of surf ace contamination measurements in ene two buildings.                  The total co .tamination cata presented in this table are direct measurements                  which  include  removable    and  non-removable activity. Total contamination levels in the By-Products Storage Building were higher than in the Carage/ Office Building because the building had been used for sample preparation before and during decommissioning.                      At the floor location in the By-Products Storage Building identified by the surface scan, the highest total alpha and 2                      2
* beta-gamma levels were 10,600 dpm/100 cm                      and 17,800 dpm/100 cm , respectively.
6 l
1
 
2 These lovels vsre reduced to <27 alpha dpe/100 cm and    820 bata gamma dpm/100 e d ,
af ter additional remedial actions by the licensee.          At other locations in this building the individual alpha measurements ranged f rom <27 to 890 dps/100 cm 2and the individual beta-gamma measurements ranged from (470 to 3600 dpm/100 cm . 2 Total alpha' and beta-gamma contamination levels in the Carage/Of fice Building were generally dess than the detection sensitivity of the ins t rume nt s .        Levels for 2                        2 alpha and beta-gamma ranged from (27 dp /100 cm                to 130 dpm/100 cm        and
  '                  2                  2
    <470 dpe/100 cm to , 10 dps/100 cm , ,,,p,cggy,gy, Removable alpha and beta contamination levels were also generally less than the measurement sensitivity.      The highest level of removable alpha activity 2
detected was 27 dps/100 cm , on the floor in By-Products Storage Building; the 2
highest beta level was 12 dpm/100 cm    , on the floor in the Carage/ Office Building.
Outside Area Survey Surface Scans Eight areas of elevated direct gamma radiation were identified by the surface scans. These areas are shown on Figure 13.          The licensee pe rf o r=ed additional remedial action at these locations and follow-up scanning indicated that cleanup of these locations had been effective in removing the contaminant.
Exposure Rate Measurements Table 4 presents the results of exposure race measurements at 30 ft (9.1 m) grid  intervals. Levels ranged from 11 to 16 WR/h at 1 m above the surf ace and from 11 to 21 uR/h at surface contact. The highest levels were at grid coordinate l  7300N, 9560E. Levels in the area of the Incinerator Pad ranged f rom 15 to 20 J/h I
at 1 m above the surf ace and f rom 16 to 28 uR/h at surf ace contact. The highest levels were at grid coordinate 7585N, 9722E. Results are presented in Table 5.
Exposure rates on the concrete pads ranged f rom 13 to 16 2/h at 1 m above the surface and from 15 to 18 uR/h at contact (Table 6).
After further remediation of areas identified by surface scans, exposure j
l  rates were measured at each location. The maximum exposure race measured was 20 uR/h at 1 m and 21 uR/h at the surface. The results of these measurements are presented in Table 7.
7
 
Surf ace Contesination Measuremnes Table 8 succiarizes surface contamination c:e asu reme n t s on concrete pad foundations. Total contamination levels for alpha and beta gamma ranged from
  <27 dps/100 cm2 to 1550 dpm/100 cm2 and from 1240 dpm/100 cm2 to 5390 dpm/100 cm 2, respectively. Removable contamination levels were generally less than the detection sensitivity of the instrument.
Radionuclid'  '
strations in Soil Concentrations of gamma emitting radionuclides, measured in surface soil samples f rom 30 f t (9.1 m) grid intervals, are presented in Table 9.      Ranges of concentrations were:      Co-60, <0.03 to 0.90 pCi/g; Cs-137, <0.02 to 9.54 pCi/g; Ra-226, 0.44 to 2.23 pCi/g; U-235, 0.05 to 1.26 pCi/g; U-238, 0.3 to 3.9 pCi/g; Th-228, 0.47 to 2.80 pCi/g; and Th-232, 0.41 to 2.70 pCi/g.              Radionuclide concentrations in samples from the Incinerator Pad area are presented in Table 10. The highest levels of gamma ermitting radionuclides measured in these samples were: Co-60, 1.37 pCi/g; Cs-137, 19.28 pCi/g; Ra-226, 1.74 pCi/g; U-235 0.66 pCi/g; U-238,      1.31 pCi/g; Th-228, 2.11 pCi/g, and Th-232, 2.26 pCi/g.
Radionuclide concentrations in soil samples obtained from beneath concrete pads (Table 11) were in the ranges of concentrations in bcseline soil.
Table 12 presents the concentrations in samples f rom locations identified by surface scans, collected following further remedial action by the licensee.
l Maximun concentrations      in these  samples were    Co-60,  1.77 pCi/g;  Cs-137, 15.62 pCi/g; Ra-226, 1.32 pCi/g; U-235, 0.88 pCi/g; U-238, 2.1 pCi/g; Th-228, 2.64 pCi/g; and Th-232, 2.53 pCi/g.
Results of St-90 and isotopic uranium analyses performed on three composite samples, are presented in Table 13.        The highest concentration of Sr-90 was l
1.46 pCi/g in composite sample        B. Isotopic uranium concentrations were 1.53 to 3.83 pCi/g of U-234; 0.05 to 0.16 pCi/g of U-235; and 1.04 to 2.19 pCi/g of U-238.
l A soil sample, collected f rom beneath the concrete floor of the By-Products Storage, contained concentrations in the ranges of baseline soil.          Data are presented in Table 14 8
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Miscellaneous Samples Table 14 also presents the results of analyses or. samples of drain residue and a piece of asphalt from the location on the Incinerator Pad, exhibiting an elevated gamma level.                The Cs-137 level in the drain residuc (2.41 pCi/g) was slightly              elevated    above  baseline    concentrations. Other  radionuclide concentrations in the two samples did not differ from typical caseline levels.
COMPARISON OF SURVEY RESULTS WITH GUIDELINES l                        Guidelines for decommissioning the Forwr Uaste Processing Facilities of l        CA Technologies are presented in Appendices C and                    D. Surface contamination
!        limits, based on primary contaminants of Uranium, Cs-137, and Co-60, identified on l        this site, ares l                              31pha
!                                    5000 dpa/100 cm2 , averaged over 1 m 2 15000 dpa/100 em2 , maximum in 100 cm 2 1000 dpe/100 cm2 , removable l                              Beta-Camma 5000 dpa/100 cm2 , averaged over 1 m 2 15000 dpa/100 cm2 , maximum in 100 cm 2 1000 dpa/100 cm2 , removable Surveys of the two remaining buildings and concrete pr.ds indicate that the surf aces satisfied these guidelines, with the exception of one small area on the floor of the By-Products Storage Building.                  Additional remedial action reduced ,
this location to within the guideline levels.
Exposure rate guidelines limit the level at 1 m above the surface to 10 J/h, above background, over an area of 30 ft (9.1 m) x 30 f t (9.1 m) or greater; the guideline level for smaller areas is 20 uR/h above background.                      At the CA Technologies Site, the total exposure rate guidelines are 19.7 G/h and 29.7 J/h, i.e., 10 uR/h and 20 uR/h, respectively, plus .the average background level of 9
 
9.7 uR/h (f rom Table 1). Ona area, at ths Incinerator Psd had an associated exposure rate of 20 uR/h at 1 m above the surface.            Although this is slight'y 1bove the 19.7 uR/h average for areas in excess of 30 f t x 30 ft, this radiation was limited to, a small isolated area and the exposure rate was less than 20 uR/h above background. All other measurements were well below 19.7 LR/h. The external exposure rate target guideline has therefore been satisfied.
Most samples collected f rom the site had radionuclide concentrations in the ranges of typical baseline soils from the I.a Jolla            area. Only two samples contained radionuclide levels in excess of the guideline.            One of these was a sample of soil f rom grid coordinate 7270N, 9543E; this sample, f rom an area of elevated direct radiation identified by surf ace scans, contained 15.62 pCi/g of Cs-137, as compared to the guideline level of 15 pCi/g.                The other sample containing a concentration above guideline levels was from the Incinerator Pad area; this sample contained 19.28 pCi/g of Cs-137. At both of these locations the sxtent of contamination is limited to small isolated areas, based on results of surface gamma scans.        Also, the exposure route from Cs-137 in surf ace soil is direct radiation; exposure rates measured at these locations were within guideline limits. The elevated Cs-137 concentrations, when averaged across adjacent land areas would be well within the 15 pCi/g guideline. Radionuclide concentrations in the soil therefore satisfy the guidelines established for this decommissioning project.
 
==SUMMARY==
 
At the request of the NRC Region V Of fice, on September 7-28, 1988, Oak Ridge Associated Universities          performed    a  confirmatory  survey    of    Phase      II Decommissioning at GA Technologies, Inc. in San Diego, Californi..              The survey included    gamma,    beta gamma,    and  alpha  scans;  exposure  rate  mea su re ment s ;
measurements of ,cotal and removable surface contamination; and measurements of radionuclide concentrations in soil. The survey identified several small areas of residual contamination, which were promptly reeleaned by the licensee and resurveyed by ORAU.        Although there are several isolated locations of residual low-level soil contamination, the size of the involved areas and the associated levels are such that the concentrations can be averaged and the guidelines satisfied. It is theref ore ORAU's opinion that the decontamination efforts by the licensee have been effective in meeting the radiological conditions established for release of this site for unrestricted use.
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T TABLE 1 SACKCROUND RADIATION LEVELS CA TECHNOLOGIES SAN DIEGO, CALIFORNIA 4
                  --                  Gamma Exposure Rates    Camma Exposure Rates Locationa            at I a Above the Surface      at the Surface
( */h)                ( */h)        :
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TABLE 4 EXPOSURE RATES MEASURED AT 30 FT GRID INTERVALS PHASE II DECOMMISSIONINC CA TECHNOLOGIES SArt DIECO, CALITORNIA M
Casma Exposure Rates                                                                    Canna Exposure Rates Locations            at la above the surface                                                                    at the surface
                --              (9R/h)                                                                                  ( ut/h) 7360N, 9260E                      13                                                                                      15 7330N, 9260E                      13                                                                                      14 7300N, 9260E                      14                                                                                      14 7240N, 9290E                      11                                                                                      !!
7270N, 9290E                    ,13                                                                                      13 7310N, 9290E                      13                                                                                      14 7330N, 9290E                      13                                                                                      14 7360N, 9290E                        b 7210N, 9320E                      13                                                                                      13 7240N, 9320E                      13                                                                                      13 7270N, 9320E                      13                                                                                      12 7300N, 9320E                    -                                                                                      -
7330N, 9320E                      13                                                                                      13 7360N, 9320E                      14                                                                                      13 7390N, 9320E                    -                                                                                      -
7420N, 9320E                    -                                                                                      --
7180N, 9350E                    13                                                                                      13 7210N, 9350E                    13                                                                                      13 7240N, 9350E                    -                                                                                      -
, 7270N, 9350E                    11                                                                                      11
; 7300N, 9350E                    14                                                                                      14 7330N, 9350E                    13                                                                                      13 7360N, 9350E                    -                                                                                      -
27
 
TABLE 4 (Continued)
EXPOSURE RATES MEASURED At 30 FT GRID INTERVALS PHASE II DECOMMISSIONING
                                                                                          .                                    GA TECHNOLOGIES
                                                                                        .                                SAN DIECO, CALIFORNIA Camma Exposure Rates                            Canna Exposure Rates Location                              at la above the surface                            at the surface (pR/h)                          (uR/h) 7390N, 9350E                                                      -                              -
7420N, 9350E                                                      11                              11 7120N, 9380E                                                      11                              11 7150N, 9380E                                                      13            ,
11        ,
7180N, 9380E                                                      11                              11 7210k, 9380E                                                      13                              13 7240N, 9380E                                                      13                              12 7270N, 9380E                                                    -                                -
7300N, 9390E                                                    -                                -
7330N, 9390E                                                    -                                -
7360N, 9390E                                                    -                              --
7390N, 9390E                                                    -                              -
7420N, 9380E                                                    ~                              ~
7090N, 9410E                                                      11                              11 7120N, 941'E                                                    11                              11 7150N, 9410E                                                      11                              11 7180N, 9410E                                                    12                              12 7210N, 9410E                                                    12                              13 7240N, 9410E                                                    -                              -
7270N, 9410E                                                    -                              -
7300N, 9410E.                                                    -                              -
7330N, 9410E                                                    -                              -
7360N, 9410E                                                    -                              --
28
 
TABLE 4 (Continued)
EXPOSURE RATES MEASURED AT 30 FT GRID INTERVALS PHASE II DECOMMISSIONING CA TECHNOLOGIES SAN DIEGO, CALIFORNIA Gamma Exposure Rates                  Gamma Exposure Rates Location            at in above the surfaca                  at the surface (pR/h)                              ( uR/h) 7390N, 9410E                      -                                  -
7380N, 9410E                      13                                13 7090N, 9440E                      -                                -
7120N, 9440E                      11                                11 7150N, 9440E                    -                                  -
7180N, 9440E                    -                                  -
7210N, 9440E                    -                                  -
7240N, 9440E                    -                                  -
7270N, 9440E                    -                                  --
7300N, 9440E                    -                                  -
7330N, 9440E                    13                                  14 7360N, 9440E                    15                                  16 7390N, 9440E                    11                                13 7420N, 9440E                    -                                  -
7450N, 9440E                    -                                  --
7120N, 9470E                    13                                12 7150N, 9470E                    -                                  -
l 7180N, 9470E                    -                                  -
7210N, 9470E                    -                                  -
7240N, 9470E                    16                                16 7300N, 9410E                    -                                  -
l 7330N, 9470E                    13                                13 7369N, 9470E                    -                                  -
29 t
l
 
TABLE 4 (Continued)
EXPOSURE RATES MEASURED AT 30 FT GRID INTERVALS PHASE II DECOMMISSIONING CA TECHNOLOGIES SAN DIEGO, CALIFORNIA 4              -
Gamma Exposure Rates                Camma Exposure Rates Location              at is above the surface                at the surface (PR/h)                            (uR/h) 7390N, 9410E                        14                                13 7420N, 9470E                        13                                12 7450N, 9470E                      -                                  -
7480N, 9470E                      -                                  -
7030N, 9500E                      -                                  -
7060N, 9500E                      11                                  11 7090N, 9500E                        11                                11 7120N, 9500E                      13                                  14 7150N, 9500E                      -                                  -
7180N, 9500E                      -                                --
7210N, 9500E                      -                                  -
7240N, 9500E                      16                                17 l 7270N, 9500E                      15                                14
! 7300N, 9500E                      -                                  -
l 7335N, 9500E                      15                                15
; 7360N, 9500E                      -                                  -
l 7390N, 9500E                      -                                  -
! 7420N, 9500E                      -                                  --
7450N, 9500E                      -                                  -
l 7'40N, 9500E      -              -                                  -
7510N, 9500E                      -                                  -
7030N, 9500E                      -                                  --
7060N, 9530E                      12                                12 i
l 30 l
 
4 TABLE 4 (Continued).
EXPOSURE RATES MEASURED AT 30 FT CRID INTERVALS' PHASE II DECOMMISSIONING GA TECHNOLOGIES SAN DIEGO, CALIFORNIA Gamma Exposure Rates                  Gamma Exposure Rates Location              at is above the surface                  at the surface (uR/n)                              (uR/h) 7090N, 9530E                      11                                  11 7120N, 9530E                      13                                  13 7150N, 9530E                      13                                  13
, ?l80N, 9530E                      -                                    -
7210N, 9530E                      13                                    13 7240N, 9530E                      -                                    -
7270N, 9530E                    -                                    -
7300N, 9530E                    -                                    -
7320N, 9530E                    -                                    -
7360N, 9530E                      16                                  17 7000N, 9560E                    -                                    -
7030N, 9560E                    -                                    -
7060N, 9560E                      13                                  13 7090N, 9560E                      15                                  16 7120N, 9560E                    13                                    13 7150N, 9560E                      13                                  13 7180N, 9560E                    15                                    15 7210N, 9560E                      14                                  13 7240N, 9560E                    15                                  15 7270N, 9560E                    14                                  14 7300N, 9560E                    16                                  21 7330N, 9560E                    -                                    -
7360N, 9560E                    -                                    --
aRefer to Figure 9.
b(--) indicates measurement not performed.
31
 
TABLE 5 EXPOSURE RATES MEASURED IN THE INCINERATOR PAD AREA PHASE II DECOMMISSIONING GA TECHNOLOGIES SAN DIEGO, CALIFORNIA Gamma Exposare Rates            Gamma Exposure Rates Locationa            at I a above the surface              at the surface (uR/h)                                (uR/h) 7620N, 9715E                          16                                    18 7585N, 9722E                          20                                    28 7627N, 9675E                          16                                    16 7610N, 9670E                          15                                    16 7565N, 9690E                          16                                    20 7645N, 9658E                          16                                    18 7587N, 9710E                        . 16                                    16 aRefer ti Figure 9.
l i
i i
l 1
32 1
 
TABLE 6
  '                        DIRECT RADIATION LE7ELS MEASURED ON CONCRETE PADS PHASE II DECOMMISSIONING CA TECHNOLOGIES
                    -                    SAN DIEGO, CALIFORNIA Gamma Exposure Rates    Camma Exposure Race Locations        Description              at is above the surface    at the surface (uR/h)                  ( uR/h) 7261N, 9551E      Waste Pad                            15                      16 7197N, 9515E      By Products Storage Bldg.            13                      15 7354N, 9458E      North Waste Pad                      13                      16 7625N, 9720E      Incinerator Pad                      16                      18 aRefer to Figure 9.
l t
l                      -
l l
l l
l                                                  33 l
l
 
TABLE 7 EXPOSURE RATES MEASURED AFTER REMEDIATION OF AREAS IDENTIFIED BY SURFACE SCANS
                                                                                                                  .                                                                    PHASE II DECOMMISSIONING CA TECHNOLOGIES SAN DIEGO, CALIFORNIA 4 "
Canna Exposur, .tates                                                                            Camma Exposure Rates Locationa                    at 1 e above the surface                                                                                                      at the surface (uR/h)                                                          (uR/h) 7240N, 9490E                                                                                                                  20                                                  20 7260N, 9480E                                                                                                                  18                                            '
18 7270N, 9480E                                                                                                                  18                                                  21 7370N, 9543E                                                                                                                  15                                                  15 7330N, 9430E                                                                                                                  14                                                  16 7260N, 9400E                                                                                                                  13                                                  13 7135N, 9455E                                                                                                  -
13                                                  11 7380N, 9360E                                                                                                                  13                                                  14 aRefer to Figure 13.
34
 
TABLE 8
                                    $UMMARY OF SURFACE CCNTAMINATION WASUREMNTS - CONCRETE PA05 440 FOUNDATICN$
PHASE 11 CECOMMIS$10NING GA TEC>NOLOGIES
                                                                                                            $AN OlEGO, CALIFORNIA TOTAL CCNTANINATION (dom /100 cm2)                                              REMOVABLE CONTAMINATlCN (dem/100 cm2, s
location            ALPHA                                                                SETA-GAM 4A          ALPHA            BETA 7620N, 9730E                  370                                                                  1240                  5              <6 7610N, 9720E                  36                                                                  1880                <3                <6 7260N, 9550E                  310                                                                  5390                <3                <6 7355N, 9455E                  <27                                                                  3420                <3                <6 7370N, 9480E                130                                                                  1330                <3                <6 D                                ---
7405, 9495E                  (27                                                                                      ---
726m , 9547E                  330                                                                  5640                <3                <6 7615N, 972SE                1550                                                                  I150                <3                <6 7624N, 9723E                930                                                                  1270                <3                <6 eRefer to Figure 10 b0 ash Indicat es nessurement not performed.
35
 
j TABLE 9 RADIONUCLlDE @NCENTRATIONS IN St#tFACE Soll SAWLES FRON 30 FT GtID INTERVALS PHASE 11 DEconostS$10NING GA TECH 40LOGIES                                  3 ,
SAN DIEGO, CALIF 0ftil A                        ,
i          .
Sample                                              Radlonuclide Concentrations (pCI/g)          '
No. Locatlona    Co-60        Cs-137          Ra- Q              U-235          U-238    Th-228        Th-232 ll4A    7360N,9260E    <0.05      0.26 1 0.07    1.14 1 0.20      0.08 1 0.10    0.8 1 0.5  1.22 1 0.22  1.24 20.53 IISA    7330H,9260E    <0.07      0.27 1 0.13    1.33 1 0.28      0.16 1 0.11    1.0 1 1.4  f.64 1 0.47  2.10 20.50 Il6A    7303N,9260E    <0.04      0.15 1 0.11    0.98 1 0.23      0.20 1 0.08    J.9 1 f.2  1.45 1 0.33  1.65 2 0.52 Il7A    7240N,929aC    <0.05      0.27 1 0.10    0.77 1 0.17      0.77 1 0.09      f.1 10.9  0.75 1 0.25  0.62 1 0.40 4
IISA    7270N,9290E    <0.05      0.14 1 0.09    0.78 1 0.19      0.12 1 0.04    0.8 1 0.5  0.89 1 0.28  0.76 1 0.48 y ll9A    7300H,9290E    <0.05        <0.04      1.52 1 0.35      0.18 1 0.10    1.4 i 1.1  1.22 1 0.39  1.81 1 0.47 120A    7350N,9320E    <0.05      0.26 1 0.09    1.03 1 0.22          <0.25      2.5 1 0.5  1.28 1 0.28  0.97 2 0.35 12tA    7210N,9320E    <0.05      0.45 1 0.11    0.75 1 0.21      0.17 1 0.09    1.0 11.0  0.64 1 0.22  0.76 1 0.32 122A    7240N,9520E    <0.15      0.45 1 0.24    1.40 1 0.46      0.06 1 0.18        <l.2    0.78 1 0.53  0.64 1 0.68 l      125A  7270N,9320E    <0.05      0.26 1 0.10    0.74 1 0.15      0.12 1 0.11    0.9 1 1.0  1.11 1 0.38  0.76 1 0.37 124A  7530N,9320E    50.05      0.4910.13      1.14 1 0.27      0.1310.10      f.5 1 0.9  1.25 1 0.31  1.3520.45 b 0.41 1 0.13 125A    7360N,9320E 0.03 1 0.15                  1.16 1 0.30      0.19 1 0.11    0.6 i 1.4  1.62 1 4.07  f.57 1 0.47 126A    7180N,9550E    <0.19      0.56 1 0.II    l.22 1 0.89      0.13 1 0.08    4.9 1 0.3  0.67 1 0.28  1.06 1 0, 56 127A  7210N,9350E    <0.54      0.11 1 0.11    I.30 1 0.24      0.18 1 0.15    0.3 2 1.0  f.II 1 0.28  0.70 2 0.51 128A    7270N,9350E    <0.04      0.22 2 0.07    0.62 1 0.25      0.09 1 0.07    0.8 1 0.8  2.56 1 0.58  0.70 2 0.40 I      129A    7500N,9550E    <0.06      0.34 1 0.10    0.9510.30        0.13 1 0.51        <0.9    1.03 1 0.47  1.16 1 0.57 ISOA    7330N,9350E    <0.09      0.68 1 0.20    1.16 2 0.51      0.07 1 0.20      1.9 2 1.0 1.39 1 0.50  I.49 ! 0.dl
 
TABLE 9 (Continued)
RADIONUCLIDE CONCENTRATIONS IN SURFACE Soll SAWLES FROM 30 FT ORIO INTERVALS PHASE II DECometSS10NING                                  I GA TECH 40LOGIES                                      6 SAN DIEGO, CALIFORNIA Saeple                                                                Radlonuclide Concentrations (pCI/g)
No.                Location      Co-60        Cs-137          Ra-226          U-235                IM38      T6-228          Th-232 13tA                          7420N,9350E    <0.06    0.s i 1 0.11    1.37 1 0.24      0.23 1 0.13            <0.8    1.47 10.%    1.30 1 0.44 152A                          7820N,9380E    <0.44    0.18 1 0.08    0.93 1 0.19      0.05 i 0.06          0.6 1 0.1  0.70 1 0.19  0.52 1 0.40 135A                        7850N,9380E    <0.05        <0.05        0.97 1 0.20      0.13 1 0.15          0.6 1 1.1  1.06 1 0.28  0.91 1 0.40 134A                        7180N,9380E    <0.06    0.52 1 0.12      0.75 1 0.26      0.07 1 0.81          0.9 1 0.9  0,53 1 0.22  0.8310.36 135A                        7210N,9380E    <0.33    0.30 1 0.20      0.78 1 0.63      0.10 1 0.18          1.5 i 1.6  0.93 1 0.81  0.87 1 0.84 136A                        7240N,9380E    <0.05    0.43 1 0.15      1.25 1 0.25      0.14 1 0.52          1.1 't 0.8 0.86 1 0.28  1.l8 1 0.45 137A                        7270N,9380E    <0.05    0.11 1 0.06      1.04 1 0.24      0.30 1 0.11          1.5 i 1.3  1.62 10.%    I.50 1 0.51 138A                        7090N,9410E    <0.04        <0.05        0.61 1 0.22      0.14 1 0.07          0.3 1 0.8  0.56 1 0.22  0.46 1 0.32 139A                        7120N,9410E    <0.06    1.30 1 0.15    0.62 1 0.20      0.10 1 0.05            <0.6'    O.47 1 0.22  0.60 1 0.32 140A                        7150rl,9410E    <0.05    0.18 1 0.12      0.7510.26        0.13 1 0.09            <0.5    0.61 1 0.38  0.40 1 0.53 14IA                        718tN,9410E    <0.06    's.38 1 0.08    0.14 1 0.27      0.12 1 0.10          1.6 1 2.7  0.81 10.M    0.88 1 0.28 142A                        7210N,9410E  0.10 1 0.10  1.05 1 0.19    0.75 1 0.19      0.26 1 7.08          1.0 1 0.9  0.70 1 0.22  1.02 1 0.54 l4 3A                      7380N,9410E  0.25 1 0.09 3.10 1 0.24      1.10 1 0.24      0.28 1 0.!2          0.4 i 1.2  1.39 1 0.33  1.41 10.55 144A                        7820N,9440E    <0.05    0.46 1 0.85      0.75 1 0.26        <0.25              1.0 1 0.5  0.75 1 0.30  0.58 1 0.39 145A                      7350N,9440E    <0.03    0.45 1 0.11      0.62 1 0.30      0.05 1 0.14            <0.7    0.97 10.33    1.15 12.0 146A                      7560N,9440E    <0.07    1.57 t 0.20    1.30 1 0.29      0.14 1 0.33          1.1 f 0.6  1.50 10.%    1.45 ! 0.4s
 
i TABLE 9 (Continued)
RADIONUCLIDE CONCENTRATIONS IN SURFACE SOIL SAWLES FRON 30 FT CRID INTERVALS PHASE il DECOseeBSS10NING                            I CA TEOte0LOGIES SAN DIEGO, CALIFORNIA i
;                                                                                                                                          Sample                                                            Radlonuclide Concentrations (pC1/q)
:                                                                                                                                            No. Location      Co-60      Cs-137                      Ra-226            U-235          U-238    Th-228        Th-232
* 147A      7390N,9440E      <0.05    0.06 1 0.04                0.44 1 0.16      0.09 1 0.09        <0.6    0.67 1 0.25  0.73 1 0.31 148A      7120N,9470E      <0.06    0.30 1 0.11                0.85 1 0.18      0.10 1 0.08        <0.5    0.86 1 0.28  0.41 1 0.45 149A      7240N,9470E  0.90 1 0.17 9.5410.41                  1.48 1 0.30      0.21 1 0.14        <0.7    1.22 1 0.36  8.44 1 0.44 ISOA      7330N,9470E  0.09 1 0.10 0.l7 1 0.09                0.69 1 0.16      0.12 1 0.10      0.9 1 1.2 1.16 1 0.30  1.18 1 0. 58
                                                                                              $                                        ISIA      7390N,9470E      <0.06    0.45 1 0.12                1.02 1 0.30          <0.25          <0.7    1.94 1 0.30  1.53 1 0.60 IS2A    74 SON,9470E    <0.05    0.52 1 0.13                  1.36 + 0.35      0.l5 1 0.II      1.1 11.0  1.45 1 0.33  1.72 1 0.48 IS3A      7060N,9500E      <0.05        <0.05                  0.70 1 0.21      0.09 1 0.09      0.7 1 0.8 0.63 1 0.22  0.79 1 0.28 IS4A    7090N,9500E      <0.04    0.05 1 0.06                0.60 1 0.21          <0.18          <0.5    0.83 1 0.20  0.88 10.27 ISSA    7120N,9500E      <0.04    0.23 + 0.11                0.86 1 0.23      0.14 1 0.08      0.5 i 1.0 0.78 1 0.19  0.85 1 0.43 lo6A    7240N,9500E  0.33 1 0.18 2.60 1 0.24                  1.00 1 0.28      0.19 1 0.12      1.8 1 1.3 f.85 1 0.42  1.72 1 0.60 IS7A    7270N,9500E  0.20 1 0.14 0.05 1 0.09                  1.15 1 0.25        <0.26          <0.8    1.72 1 0.33  1.45 1 0.44 IS8A  733$N,9500E      <0.32    2.74 1 0.28                  1.29 1 0.24      0.24 1 0.12      1.7 1 0.7 f.78 1 0.36  2.70 1 0.55 159A    7060N,9550E    <0.05    0.02 1 0.08                0.70 1 0.16      0.12 1 0.09        <0.7    0.84 1 0.27  0.95 1 0.31 160A    7090N,9530E    <0.07    0.39 1 0.13                  1.II 1 0.30        <0.24          <0.8    I.44 2 0.81  2.01 1 0.46 16tA    7120N,9550E      <0.04      <0.05                    1.48 2 0.24      0.20 1 0.09      1.4 10.5  1.17 1 0.28  1.08 2 0.42 162A    71 SON,9550E    c0.06-  0.27 1 0.13                  I.85 1 0.30      0.56 1 0.55      2.5 1 1.6 1.35 1 0.52  1.42 1 0.59
 
TABLE 9 IContinued)
RADIONUCLIOE CONCENTRATIONS IN SURFACE Soll SA WLES FRO 4 30 FT GIID INTERVALS PHASE il DEC0welSSIONING GA TECte40LOGIES 6
SAN DIEGO, CALIFORNIA 6
Saepte                                                        Radlonuclide Concentrations (pC1/q)
* No,      tocatIon        Co-60          Cs-137          Ra-226            U-235          U-238      Th-228        Th-232 163A        7%0N,9530E    , 0.61 1 0.17    6.64 1 0.31    1.18 1 0.25          <0.25          *0.7    I.08 1 0.40    1.13 10.58 164A        7060N,9%0E        <0.04        0.06 1 0.04    1.02 1 0.23      0.Il i 0.09    0.9 1 0.5  1.00 1 0.25    1.1910.45 165A        7090N,9560E        <0.04          <0.06        1.38 1 0.31      0.25 ,1 0.13    0.9 1 1.6  1.2  1 0.47  1.42 1 0.49 166A        7120H,9560E        <0.05        0.05 1 0.07    1.09 1 0.28      0.14 1 0.07      1.2 1 0.5 1.17 1 0.28    1.13 1 0.41 167A        7 8 504,9560E      <0.06          <0.06        1.27 1 0.26          <0.26          <0.8    1.86 1 0.36    1.59 1 0.58 168A        7180N,9560E        <0.05        0.47 1 0.10    1.0010.26        0.39 1 0.12    2.9 i 3.6  1.63 1 0.52    1.60 1 0.52 g                                            169A        7230N,9560E    0.24 1 0.17        <0.07        I.0310.26            <0.24          <0.8    1.11 1 0.42    1.00 10.79 170A        7240N,9560E    0.21 1 0.17    2.10 1 0.21    1.28 1 0.27      0.4110.08      3.9 1 0.8  2.8010.33      2.67 1 0.50 17tA        72704,9560E    0.17 1 0.10    2.14 1 0.20    1.05 1 0.26      0.23 1 0.13      1.7 i I.2 1.34 1 0.26    f 43 1 0.40 172A        7300N,9560E    0.29 1 0.12    3.0510.25      1.10 1 0.28      1.26 1 0.78      <0.9    3.78 i O.47    1.8610.47 I?3A      7210N,9530E    0.14 1 0,.12      <0.05        2.23 1 0.35          <0.30      3.6 1 0.8  1.50 10.36    f.30 1 0.48 aReter to Figure 9 buncertainties represent the 955 confidence levels based only on counting statistics; additional laboratory uncertalnfles of 6 to 10$ have not been propagated into these data.
 
TABLE 10 RADIONUCLIDE CONCENTRATIONS IN $0tL SAWLES COLLECTED FRG4 THE INCINERATOR PAD AREA                            6 PHASE il DE(XIeetBSS10NING GA TECHt0LOGIES SA WLES                                  6  .
SAN DIEGO, CALIFORNIA Sample                                                                    Radlonuclide Concentrations (pCl/q)
No.        Location a          Co-60                  Cs-t u            Ra-226            U-235          I)-238    Th-228          Th-232 107A      7620N. 97tSE      0.84 1 0.18 b      I.46 i          18      1.33 1 0.31      0.54 1 0.54    1.31 1 1.04 1.75 1 0.36    1.8210.51 108A      7585N. 9722E        I.37 1 0.20    19.28 1 0.56            0.97 1 0.32      0.66 1 0.78        <l.05    1.45 1 0.44    1.74 1 0.46 109A      7630N. 9680E          <0.06                  <0.04          1.27 1 0.25          <0.22          <0.75    1.50 1 0.36    1.85 1 0.38 Il0A      7610N, %70E            <0.06        0.18 1 0.08              1.12 1 0.27          <0.25      0.50 1 0.11 1.39 t 0.31    1.52 t 0.42
                                                                                                                                        ,    Illa      7565N, %90E        0.82 1 0.20      9.7810.40                1.17 1 0.27          <0.36          <0.70    1.22 1 0.36    1.56 i O.4 3 O      Il2A      7645N. 9685E      0.32 1 0.18                <0.04          I.74 1 0.30          <0.30          <0.98    2.11 1 0.44    2.26 1 0.56 II3A      758 7N, 9 7 80E        <0.06          1.05 1 0.15            0.97 1 0.21          <0.23          <0.81    1.53 1 0.36    1.39 1 0.48 aRefer to Figure 9 b
uncertainties represent the 95$ confidence levels based only on counting statistics; addditional laboratory wicertaintles of 6 to 105 have not tamen propagated into t$ese data.
 
4 TABLE il RADIONCULIDE CONCENTRATIONS IN Soll FROM BENEATH CONCRETE PADS                                  ,
PHASE la DECONMlSS10NING I
GA TEO NOLOGIES SAN OBEGO, CALIFnRNIA                                    g Sample                                                        Redlonuclide Concentratlons (pCl/g)
No.        Location
* Co-60          Cs-137          Ra-226              U-235        U-238      Th-228        Th-232 0018        726tN, 955tE        <0.10        0.29 t 0.16D    3.48 1 0.36            <0.38          <l.2    1.70 1 0.53    1.38 1 0.63 0058        7354N, 9458E        <0.05        0.03 1 0.05    0.43 1 0.10            <0.17          <0.5    0.44 t 0.20    0.39 1 0.41 0040        7625N, 9720E        <0.06        0.05 1 0.I4    0.85 1 0.19            <0.29          <0.7    0.76 1 0.40    0.8I t 0.*>0 d
                            *
* Refer to Figure 10 buncertainties represent the 955 confidence levels based only on counting statistics; addditional laboratory uncertaintles of 6 to IOS have not been propagated Into these data.
 
TABLE 12 RADIONUCLIDE CONCENTRATIONS IN SURFACE S0lt SAWLES COLLECTED FOLLOWING RENEDI ATION OF AREAS 1 DENT lF1ED 8Y SistFACE SCANS PHASE Il DECDeceBSS10NING
                                                                                                                                                                                    ~
GA .EO NOLOGIES SAN OIEGO, CALIF 0HNIA 6
Saeple                                                                                                          Radionuclide Concentrations (pCl/g)
No.          Location                                                      Co-60            Cs-137          lb-226              U-235        U-238        Th-228      Th-232 174A      724 0N,9490E                                                      0.53 1 0.19    2.94 1 0.25    1.24 1 0.28        0.24 1 0.12    2.1 1 1.7    I.7510.33    2.00 10.45 175A      72704,9480E                                                        0.8510.19      9.68 1 0.39    1.32 1 0.36        0.88 1 0.64    2.5 i 1.7    2.64 1 0.56  2.53 1 0.55 I16A      7270N,9543E                                                        I.77 1 0.27    15.62 1 0.52    1.00 1 0.40          <0.41      1.1 1 0.8    2.06 1 0.42  1.58 1 0.47 177A      7370N,9460E                                                        0.C6 1 0.19    0.63 1 0.15    1.2310.67          0.22 1 0.12    0.8 i 3.5    1.81 10.40    1.73 10.45 178A      7330N,9460E                                                          <0.04        0.12 1 0.09    1.25 1 0.7            <0.22        <0.8      1.6110.36    1.60 1 0.42 179A      7260N.9400E                                                          <0.04          <0.04        f.15 1 0.24          <0.24      1.1 10.6    1.44 1 0.31  1.27 1 0.39 e
180A      7835N,9455E                                                          <0.04        0.09 1 0.09    1.24 1 0.25        0.24 1 0.11    0.9 1 1.2    1.40 10.35    1.48 1 0.46 18tA      7380N,9360E                                                          <0.04          <0.05        0.78 1 0.18          <0.20        <0.6      1.06 1 0.28  0.77 1 0.47 "Refer to Figure 13 b
uncertaintles represent the 955 confidence levels based only on counting statistics; addith .Aal laboratory uncertaintles of 6 to 10% have not been propagated lato these data.
i
 
TABLE 13 RADIONUCLIDE CONCENTRATIONS IN COMPOSITE SOIL FRASE II DECOMMISSIONING CA TECHNOLOGIES SAN DIEGO, CALIFORNIA e a Radionuclide Concentrations (pCi/g)
Sample Type a        Depth          Sr-90            U-234        U-235        U-238 Composite A          Surface    0.72 2 0.16b 1.5820.22        0.05 2 0.04  1.04 2 0.18 Composite B                      1.46 2 0.25    3.83    0.37  0.1620.09    2.19 2 0.28 Composite C                      0.21 2 0.15      1.53 2 0.24  0.05 2 0.05  1.32 2 0.22 aSample identification numbers:
Composite A:    (7060N, 9500E; 7090N, 9500E; 7120N, 9500E; 7240N, 9500E; 7270N,9500E)
Composite B:    (7240N, 9490E, 7270N, 9480E)
Composite C:    (7261N, 9551E; 7197N, 9458E; 7354N, 9458E; 7625N, 9720E) b Uncertainties  represent the 95% confidence levels, based only on counting statistics; additional laboratory uncertainties of 6 to 10% have not been            .
propagated into these data.
l l
43 L
 
TABLE 14 RADIONUCLIDE CONCENTRATIONS IN solSCELLANE00S SA rtES PHASE il DECONNISSIONING GA TECt940LOGIES SADFLES SAN DIEGO, CALIFORNIA                                    6 Description                                                          Radlonuclide Concentra15cas (pC1/g and                            Co-60          0s-137          Ra-226          U-235          U-238    Th-228        Th-232 Location
* Soit fRON BENEATH BY-Pf4000 CTS STORACE BUILDING FLOOR (7197N, 95tSEI                        <0.06          <0.06        0.85 1 0.36b        <0.21          <0.6      <0.23        0.85 1 0.35
  $    ORAIN RESIOUE (7170N, 9562El                    0.14 1 0.26    2.48 1 0.38      1.07 1 0.58      0.24 1 0.74      <l.3      <0.46        1.89 1 0.84 ASPHALT (7587N, 9710El                        <0.05      0.48 1 0.09      1.49 1 0.24        <0.29        2.1 1 0.9  <0.26        8.78 1 0.58 aRefer to Figures 9 and 10 b
uncertaintles represent the 955 c; f tdence levels based only on counting statistics; addditional laboratory uncertainties of 6 to 105 have not been propagated into these data.
 
REFERENCES
: 1.  "Confirmatory Survey of Phase I Decommissioning Former, Waste Processing Facility, CA Technologies, San Diego, California," Oak Ridge Associated Universities, July 1986.
: 2. "Follow-Up Confirmatory Survey of Phase I Decommissioning, Former Waste Processing Facility, CA Technologies, San Diego, California," Oak Ridge Associated Universities, March 1988.
: 3. "Confirmatory Survey of Phase III Decommissioning, CA Technologies, San Diego, California," Oak Ridge Associated Universities, February 1988.
: 4. Letter f rom K. E. Asmussen (CA Technologies, Inc.) to R. D. Thomas (U.S .
Nuclear Regulatory Commission, Region V),
 
==Reference:==
"License SNM-696, Docke* 70-734", August 25, 1987.
: 5. "Proposed Confirmatory Survey Plan for Phase I (Follow-up) and Phase II of the Former Vaste Processing Facility, CA Technologies, San Diego, California," Oak Ridge Associated Universities, September 4, 1987.
45
 
O O
4 4 "
g
      = - _
W6 APPENDIX A MAJOR SAMPLING AND ANALYTICAL EQUIPMENT
{
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l APPENDEX A MAJOR SAMPLING AND ANALYTICAL EQUIPMENT The display or description of a specific product is not to be construed as an endorsement of that product or its manufacturer by the authors or their employer.
A. Direct Radiation Measurements Eberline "RASCAL" Portable Ratemeter-Scaler Model PRS-1 (Eberline, Sante Fe, NM)
Eberline PRM-6                      -
Portable Ratemeter (Eberline, Santa Fe, NM)
Ludlum Floor Monitor Model 239-1 (Ludlum, Sweetwater, TX)
Eberline Alpha Scintillation Probe Model AC-3-7 (Eberline, Sante Fe, NM)
Eberline GM Pancake Probe Model HP-260 (Eberline, Sante Fe, NM)
Victoreen Beta-Gamma "Pancake" Detector Model 489-110 (Victoreen, Cleveland, OH)
Victoreen NaI Scintillation Detector Model 489-55 (Victoreen, Cleveland, OH)
Reuter-Stokes Pressurised Ionization Chamber Model RSS-111 (Reuter-Stokes, Cleveland, OH)
B. Laboratory Analyses Automatic low-background Alpha-Beta Counter Model LB5110-2080 (Tennelee, Inc., Oak Ridge, IN)
High-Purity Germanium Detector Model CMX-23195-S, 23% efficiency (EG6G ORTEC, Oak Ridge, TN)
A-1
 
Ussd in conjunction with:
Lead Shield, G-16 (Gamma Products Inc., Palos Hills, IL)
High Purity Germanium Coaxial Well Detector Model.GWL-110210-FUS-S, 23: Efficiency (EG&G ORTEC, Oak Ridge, TN)
Ueed in conjunction with:
Lead Shield Model C-16 (Applied Physical Technology, Atlanta, CA)
High Purity Germanium Detector Model IGC25, 25% Efficiency (Princeton Gamma-Tech, Princeton, NJ)
Used in conjunction with:
Lead Shield (Nuclear Data, Schaumburg, IL)
Multichannel Analyzer ND-66/FD-680 System (Nuclear Data Inc., Schaumburg, IL)
Alpha Spectrometry System Tennelec Electronics (Tennelec, Oak Ridge, TN)
Surface Barrier Detectors (EG&G ORTEC, Oak Ridge, TN)
Multichannel Analyzer Model ND-66 (Nuclear Data, Schaumburg, IL)
A-2
 
l l
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i I
l APPENDIX B MEASUR$ MENT AND ANALYTICAL PROCEDURES e
 
APPENDZX 3 Measurement and Analytical Procedures Surface Scans
              & ~
Surf ace scans were performed by passing the probes slowly over the surf ace.
The d is t a n.ca between the probes and the surf ace was maintained at a minimum                    -
nominally about 1 ca.                  Identification of elevated levels was based on increases in the audible signal from the recording or indicating instrument.                        Alpha and beta gamma scans of large surface areas on the floor of the facility were accomplished by use of a gas proportional floor monitor, with a 600 cm2 sensitive area.        The ins t rument was slowly moved in a systematic pattern to cover 100% of the accessible area.                  Combinations of detectors and ins t rument for the scans were Beta-Camma - Pancake GM probe with PRM-6 ratemeter.
Beta-Camma - Pancake GM probe with PRS-1 scaler /ratemeter.
Camma            - NaI scintillation detector (3.2 cm x 3.8 cm crystal) with PRM-6 racemeter.
Alpha            - ZnS probo with PRS-1 scaler /ratemeter.
Alpha / Beta - Cas proportional floor monitor with 1.udium Model 2220 scale r/ ra t eme t e r.
Alpha and Beta-gamma Surface Contaminatioa Measurements Measurements of total alpha radiation level were performed using Eberline Model PRS-1 portable scaler /ratemeters with Model AC-3-7 alpha scintillation probes.          Measurements of total beta gamma radiation levels were performed using Eberline Model PRS-1 portable scaler /ratemeters with Model HP-260 thin-window "pancake" GM probes. Count rates (epm) were converted to disintegration rates 2
(dpm/100 es ) by dividing the net rate by the 4w efficiency and correcting for the active area of the detector.                      Effective window areas were 59 em2 for the ZnS detectors and 15 cm 2 for the GM detectors. The background count race for ZnS alpha probes averaged approximately 2 epm; the average background count race was approximately 40 cpm for the GM detectors.
B-1
 
Rsmovable Contaminttion Metsurestnts Smear measurements were perf ormed on numbered filter paper disks, 47 mm in diameter. See,ars were placed in labeled envelopes with the location and other pertinent information recorded.        Smears were counted on a low background proportional counter at the Oak Ridge laboratory.
  ' Exposure Rate Measurements Measurements of gamma exposure rates were performed using an Eberline PRM-6 portable ratemeter with a V ctoreen Model 489-55 gamma scintillation probe containing a 3.2 cm x 3.8 cm NaI(T1) scintillation crystal.        Count rates were converted to exposure rates (uR/h) by onsite cross-calibration using a Reuter Stokes model RSS-111 pressurized ionization chamber.
* Soil, Asphalt. and Residue Sample Analysis Camma Spectroscopy Samples were dried, mixed, and a portion sealed in 0.5-liter Marinelli beaker. The quantity placed in the bea'ker was chosa.: to reproduce the calibrated councing geometry and ranged f rom 600 to 800 g of soil. Net soil weights were determined and the samples counted using intrinsic germanium and Ce(Li) detectors coupled to a Nuclear Data Model ND-680 pulse height analyzer system. Background and Compton stripping, pesk search, peak identification, and concentration calculationr were performed usin5 the computer capabilities inherent in the analyzer system. Energy peaks used for determination of radionuclides of concern were:
Co 1.173 MeV Cs-137 - 0.662 MeV Ra-226 - 0.609 MeV from Bi-214 (secular equilibrium assumed)
U-235 - 0.144 MeV U-238 - 0.094 MeV from Th-234 (secular equilibrium assumed)
Th-228 - 0.583 MeV from T1-209 (secular equilibrium assumed)
Th-232 - 0.911 MeV from Ac-228 (secular equilibrium assumed)
Spectra were also reviewed for the presence of other radionuclides.
B-2
 
Serontium-90 Analysis A liquot s of soil were dissolved by pyrosulfate fusion and the strontium precisitated as a sulfate.        Successive treatments with EDTA preferentially remot ed lead and excess calcium and returned the strontium to solution. Ferric and ather fnsoluble hydroxides was precipitated at a pH of 12 to 14        Strontium was reprecipitated as a sulf ate. 8arium was removed as a chromate using DTPA.
The final precipitate of strontium carbonate was counted 'using a low-background Tennelee alpha-beta proportional counter.
Alpha Spectrometry for Isotopic Uranium Aliquots of soil were dissolved by pyrosulf ate fusion and precipitated with barium sulfate. The barium sulfate precipitates we re redissolved and uranium separated by liquid - liquid , extraction. Uranium was then precipitated with a cerium fluoride carrier and counted using surface barrier detectors (ORTEC),
alpha spectrometers (Tennelec), and an ND-66 Multichannel Analyzer (Nuclear Data).
Uncertainties and Detection Limits The uncertainties associated with the analytical data presented in the tables of this report, represent the 95 confidence levels for that data. These uncertainties were calculated based on both the gross sample count levels and the associated background count levels. When the net sample count was less than the 95  statistical deviation of the background count, the sample concentration was reported as less than the detection capability of the measurement procedure.
Because of variations in background levels and Compton contributions from other radionuclides in samples, the detection limits dif fer f rom sample to sample and instrument to instrument.      Additional uncertainties of 2 6 to 10%, associated with sampling and laboratory procedures, have not been propagated into the data presented in this report.
Calibration and Ouality Assurance Laboratory and field survey p r,ocedu res are documented in the following manuals, developed specifically for the Oak Ridge Associated Universities' B-3 l
 
Radiological Site Assessmsnt Program:      "Survey Procedures !!anual," Revision 3,
    !!ay 1987; "Laboratory Procedures :tanual", Revision    3, May 1987 and "Quality Assurance Manual", Revision 1, June 1987.
With the exception of the measurements conducted with portable gamma
              ^
scintillation survey meters, instruments were calibrated with NBS-traceable standards. The calibration procedures for the portable gamma instruments are performed by comparison with an NBS calibrated pressurized ionization chamber.
Quality control procedures on all instruments included daily background snd check-source measurements to confirm equipment operation withi'n acceptable statistical fluctuations. The ORAU laboratory participates in the EPA and E!fL Quality Assurance Programs.
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APTENDIX C i
i GUIDELINES FOR DEC0!ffAMINATION OF FACILITIES AND EQUIPMENT PRIOR'TO RELEASE FOR UNRESTRICTED USE OR TERMINATION OF LICENSES FOR BYPRODUCT, SOURCE OR SPECIAL NUCLEAR MATERIAL i
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    'CUIDELINES FOR DECONTAMINATION OF FACILITIES AND EQUIPMEh7 PRIOR TO RELEASE FOR UNEESTRICTED USE
  .      OR TERMINATION OF LICENSES FOR BYPRODUCT, SOURCE OR SPECIAL NUCLEAR MATERIAL U.S. Nuclear Regulatory Commission Division of Fuel Cycle & Material Safety Washington, D.C.      20555
          .                        July '.982 C-1
                                                              ,--r- - %------ - -
 
The instructions in this guide, in conjunction with Table 1, specify the radionuclides and radirtion exposure race limits which should be used in decontamination and survey of surf aces or premises and equipment prior to abandonment or release for unrestricted use. The limits in Table 1 do not apply to premises, equipment, or scrap containing induced radioactivity for which the radiological considerations pertinent to their use may be different. The release of such facilities or items from regulatory control is con,sid~ered on case-by-case basis.
: 1. The licensee shall make a reasonable effort to eliminate residual contamination.
: 2. Radioactivity on equipment or surfaces shall not be covered by paint, plating, or other covering material unless contamination levels, as determined by a survey and documented, are below the limits specified in Table 1 prior to the application of the covering.        A reasonable effort must be made to minimize the contamination prior to use of any covering.
: 3. The radioactivity on the interior surf aces of pipes, drain lines, or ductwork shall be determined by making measurements at all traps, and other apptopriate access points, provided that contamination at these locations is likely to be representative of contamination on the interior -of the pipes, drain lines, or ductwork.            Surfaces or premises, equipment, or scrap which are likely t,o be contaminated but are of such size, construction, or location as to make the surface inaccessible for purposes of measurement shall be presumed to be contaminated in excess of the limits.
: 4. Upon request, the Commission may authorize a licensee to relinquish possession or control of premises, equipment, or scrap having surfsees contaminated with materials in excess of the limits specified.        This may include, but would not be limited to, special circumstances such as razing of buildings, transf er of premises to another organization continuing  work  with  radioactive  materials,  or  conversion    of facilities to a long-term storage or standby status.        Such requests l        must 1
: a. Provide detailed, specific information describing the premises, equipment or scrap, radioactive contaminants, and the nature, extent, and degree of re'sidual surf ace contamination.
: b. Provide a detailed health and safety analysis which reflects that the residual amounts of materials on surf ace areas, together with other considerations such as prospective use of the premises, equipment or scrap, are unlikely to result in an unreasonable risk to the health and safety of the public.
: 5. Prior to release of premises for unrestricted use, the licensee shall make  a  comprehensive  radiation    survey  which  establishes    ' hat contamination is within the limits specified in Table 1.        A copy of C-2
 
the survey report shall be filed with the Division of Fuel Cycle and Material Safety. USNRC, Washington,                  D.C. 20555, and also the Administrator of the NRC Regional Office having jurisdiction.              The report should be filed at least 30 days prior to the planned date of abandonment. They survey report shall
: a. Identify the premises.
: h. Show that reasonable effort has been made to eliminate residual contamination.
: c. Describe the scope of the survey and general procedures followed.
: 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.
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TAB 12 1 ACCEPTABLE SURFACE CONTAMINATION IIVELS Nuclides*                              Averageb,c,f              ;g,xg ,,,b,d,f        Remoyableb.e f U-nat, U-235, U-238, and                    5,000 dpa e/100 cm 2    15,000 dpa a/100 cm 2  1,000 dpa a/100 cm 2 associated decay prodesets                                                                                  .
Transuranics, Ra-226,~Ra-228,                100 dpe/100 cm 2
300 dpe/100 cm 2      20 dpe/100 cm 2 Th-230 Th-228 Pa-231, Ac-227, 1-125, I-129 2
Th-net Th-232, Sr-90, Ra-223                1000 dpe/100 cm 2        3000 dpe/100 cm 2      200 dpe/100 cm Ra-224 U-232, 1-126, I-131,                                                          .
I-133 Beta games cettters (nuclides                5000 dpa Sy/100 cm 2    15,000 dpa Sy/100 cm 2 1000 dpa Sy/100 cm 2 with decay modes other than alpha emission or spontaneous
                ? fission) except Sr-90 and
* others noted above.
a IAiere surf ace cor.taelnation by both alpha- and beta-gamma-emmtting nuclides exists, the lietts established for alpha- and beta-gamma-emitting nuclides should apply independently.
b As used in this table, dpa (disintegrations per minute) means the rate of emission by radioactive material as determined by correcting the counts per minute observed by an appropriate detector for background, efficiency, and geometric factors associated with the instrumentation.
c Heasurements of average contaminant should not be averaged over more than I square meter. For objects of less surface area, the average should be derived for each such object.
d                                                                                        2 The maximum contamination level applies to en area of agt moce than 100 cm ,
e The amount of removable radioactive meteria.1 per 100 cm of surface area should be determined by                ,
wiping that area with dry filter or soft absorbent paper, applying moderate pressure, and assessing            !
the amount of radioactive material on the wipe with an appropriate instrument of known efficiency. 14 hen removable contamination on objects .i less surface area is determined, the pertinent levela should be reduced proportionally and the entire surface should be wiped.                                                t f 1he average and anximum radiation levels associated with surface contamination resulting from beta gamma emitters should not exceed 0.2 mrad /h at I ce and 1.0 mrad /h at I cm, respectively, measured through not more tlian 7 milligrams per square centimeter of total absorber.
 
APPENDIX D DECOMMISSIONING GUIDELINL FOR THE GA TECHNOLOGIES tlASTE PROCESSING FACILITY p
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APPEND 2X D Decommissioning Guidelines for the
              ,    CA Technologies Waste Processing Facilities Target criteria for unrestricted release of the CA Technologies' Waste Processing Facility and si:rrounding areas are presented in the licensee's final report and are as follows:
Extetaal Radiation The gamma exposure rate at 1 m above the ground surf ace shall not exceed 10 uR/h above background for an area of greater than 30 f t (9.1 m) x 30 ft (9.1 m) and shall not exceed 20 uR/h above background for any discrete area (i.e. less than 30 ft (9.1 m) x 30 ft (9.1 m)].
Inhalation and Ingestion Cuncontrations of radionuclides in soil shall be such that inhalation and ingestion are not expected to result in annual dose equivalents exceeding 20 mrem to the lung or 60 area to the bone.
Limiting soil concentrations were derived to satisfy these external and internal target criteria.      The concentration limits are presented in the following Table.
Radionuelide            Concentration Limit Above Background (DCi/g)
Depleted Uranium                              35 Enriched Uranium                              30 Thorium (Natural)                              10 Co-60                                          8 Cs-137                                        15 Sr-90                                      1.8 x 10 3 Where more than one radionuclide si present, the sum of the ratios of the individual radionuclide concentrations to their respective concentration limits shall not exceed 1.
D-1
 
CRAU 88/A 96
          ~
0              -
                    %upI ed Prepared by
        'i, n ,,Rid'^"
ties CONFIRM ATORY SURVEY Prepared for U.S. Nuclear OF Regulatory comm:ssion s                  PHASE Ill DECOMMISSIONING Region V Office s
* nsored bv GA TECHNOLOGIES Division of
              ''      d SAN DIEGO, CALIFORNIA b"eU*a'i E*c"i ar safety P. R. C O TT E N l
l Radiological Site Assessment Program Manpower Education, Research, and Training Division l
FINAL REPORT FEBRUARY 1988 e
l r t d % \ ' C 7 d r N N._\, 7 __
e% 6W J N \,x p CN sG T L\ QQ'
 
CONFIRMATORY S1'RVEY OF P4ASE III OEC0!!'!ISSIGNISC CA TECHNOLOGIES
                              ,              CAN DIEGO, CALIFORNIA Prepared by D.R. COTTEN Radiological Site Assessment Program Manpower Education, Research, and Training Division Oak Ridge Associated Universities Oak Ridge, TN 37831-0117 Project Staff J.D. Berger              R.C. Rookard R.D. Condra              T.J. Sowell D.A. Gibson              C.F. Heaver C.L. !!urphy Prepared for Division of Industrial and itedical Nuclear Safety U.S. Nuclear Regulatory Commission Region V Office Final Report February 1987 This    report    is    based on work pe rf ormed under Interagency Agreement DOE No. 40-816-83 NRC Fin. No. A-9076-3 between the U.S. Nuclear Regulatory Conmission and the U.S. Department of Energy. Oak Ridge Associated Universities performs complementary work under contract number DE-AC05-760R00033 with the
        !! . S. Departnent of Energy.
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TABLE OF CONTENTS Page 11 List of Figures . ' .                      ... . .. . . . . . . . . . . . .. . ......
iii'
                . Lis t of Tablet. . . .... . ........... . . . . .......
Int roduction and Site His tory . . . . . . . . . . . . . . . ......                                                                                                I 2
Site Description                        . ... ..... . . . . . .. .. . . . . ......
xi 2
Procedures                        . ... .. . . . ... . . .. . . . . . .. . . .-. . . .
5 Results .. .. .. .. . . .. . . . . . . . . . . . .. .......
                                                                                        . . . . .. .......                                                                            7 Comparisen c. Survey Results with Guidelines 8
Summary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
                                                                    . . . .. . . . . . . . . . .. . ......                                                                          50 Ref erences                      . .....
Appendices Appendix At Major Sampling and Analytical Equipment Appendix B: Measurement and Analytical Procedures Appendix C: Guidelines f or Decontamination of Facilities and Equipment Prior to Release f or Unrestricted Use or Termination of Licenses f or Byproduct. Source, or Special Nuclear Material Appendix D: Decommissioning Guidelines f or the GA Technologies Facility i
 
LIST OF FIGURES Page:
FIGURE 1: Map of' San Diego, Indicating the Location of GA Technologies Facilities . . . . .. . .. . . . . . .                              9 FIGURE 2: CV Technologies Plant Layout        . . . .. . .. . . .. . .                        10 FIGURE 3:  %reas of Different Deconmissioning Phases and Exclusion Areas. .;.....        . . . . .. . .. .... . ... .                                11 FIGURE 4:  Location of Building 5 Indicating the Shipping and Receiving Ares . .  . . . . . . . . . . . . _ . . . .. ..                          12 FIGURE 5:  Shipping and Receiving Area. CA Technologies .            .. . . .                13 FIGURE 6:  Contamination Measurement Locations on the Floor and Lower Walls of the Shipping and Receiving Area.              . . ..                14    -
FIGURE 7: Measurement Locations pn Upper Walls, Ceiling and Overhead Surfaces of the Shipping and Receiving Area .                  .          15 FIGUR? St  Phase III Property Sections . . . . . . . . .            .    ....                  16 FIGURE 9:  Locations of Exposure Rate Measurement Using a Pressurized Ionization Chamber . . . . .. . ... ... . . . . ..                                  17 FIGURE 10: Section 1 Measurement and Soil Sampling Locations .                  ..            18 FIGURE 11: Section 2 Measurement and Soil Sampling Locations .                  ..            19 FIGURE 12: Section 3 Measurement and Soil Sampling Locations .                  ..            20 FIGURE 13: Section 4 Measurement and Soil Sampling Locations .                  ..            21 FIGURE 14: Section 5 Measurement and Soil Sampling Locations .                  ..            22 FIGURE 15: Section 6 Heasurement and Soil Sampling Locations .                  ..            23 FIGURE 16: Section 7 Measurement and Soil Sampling Locations . . .                            24 FIGURE 17: Section 8 Measurement and Soil' Sampling Locations . . .                            25 FIGURE 18: Section 9 Measurement and Soil Sampling Locations                ...                26 FIGURE 19: Section 10 Measurement and soil Sampling Locations .                ..            27 FIGURE 20: Section 11 Measurement and Soil Sampling Locations .                ..            28 FIGURE 21: Section 12 Measurement and Soil Sampling Locations .                ..            29 FIGURE 22 Section 13 Measurement and Soil Sampling Locations .                  ..            30 l
11                                                      ,
e,-- a ,    - -
 
LIST OF FIGURES (Continued)
Page FIGURI 23: Section 14 Measurement and Soil Sampling Locations .                              . . 31 FIGURE 24: Section 15 Measurement and Soil Sampling Locations                              . . . 32 FIGURE 25: Section 16 ?teasurement and Soil Sampling Locations .                              . . 33 FIGURE 26: Section 17 !!easurement and Soil Sampling Locations . . .                              34 FIGURE 27: Section 18 Measurement and Soil Sampling Locations .                              . . 35 FIGURE 28: Section 19 Measurement and Soil Sampling Locations . . .                                36 FIGURE 29: Section 20 Measurement and Soil Sampling Locations . . .                                37 FIGURE 30: Locations of Backgrouad !!easurements and Baseline Soil Sample: from the Vicinity of GA Technologies .                            . . . . . 38 iii
 
LIST OF TABLES Page TABLE 1: Background Radiation Levels . . . . . . . . . . . . . . . . .            39 TABLE 2: Ba eline hdionuclide Concentrations in Soil          . . . . . . . . 40 TABLE 3: Summary of Surf ace Contamination Steasurements, Building i Shipping and Receiving Area  . . . . . . . . . . . . . . . . .          41 TABLE 4: Direct Radiation Levels .  . . . . . . . . . . . . . . . . . .            42 TABLE 5: Radionuclide Concentrations in Soil .      . . . . . . . . . . . .        46 TABLE 61 Radionuclide Concentrations in Composite Soil . .            . . . . . . 49 iv
 
CONFIRt!ATORY SURVEY OF
                                                                -PHASE III DEC050tISSIONING GA TECHNOLOGIES SAN DIEGO, CALIFORNIA k
                                                .            INTRODUCTION AND SITE HISTORY In nid 1984, GA Technologies. Inc. (GA) of San Diego, California, initiated decommissioning activities          for the purpose of      releasing portions of    thuir facilities from Nuclear Regulatory Commission (NRC) licensing restrictions.. The decommissioning is being accomplished in separate phases.                Phase I activities, which    encompassed the        Solar Evaporation Pond area,        the areat    immedistely surrounding the former Uaste Processing Facility and the Incinerator Pad, a previous burial site for contaminated asphalt, the hillside and canyon below the waste handling f acilities, and undeveloped land surrounding the waste processing facilities, were completed in late 1985. A confirmatory survey, performed by Oak Ridge Associated Universities, (ORAU) in December 1985, identified small isolated areas in need of additional remedial action.1 These areas have been addressed and resurvey findings will be discussed in a separate report.            Phase II areas are the former Uaste Processing Facility itself, and the incinerator pad; survey findings of these areas will also be described in a separate report. Phase III consists of approximately 87 hectares (215 acres) of primarily undeveloped land, surrounding the main GA Technologies plant site. GA recorda and individuals familiar with the facility history indicate that radioactive material uses in the Phase III area have been limited to a few small locations.            Portions of the Phase III area, have been  excluded        and have    been  identified    for  evaluation under    a  separate decommissioning activity.          These are the San Diego Gas and Electric Company's Torrey Pines substation, an abandcned sewage treatment facility, a pump station for the municipal sewage system, shipping and receiving and of fice facility, and several areas of asphalt paving.          Potential radiological contaminants at GA have been identified as enriched uranium, thorium, and longer half-life fission and activation products.
At the request of the Nuclear Regulatory Commission (NRC), Region V office, the Radiological Site Assessment Program of Oak Ridge Associated Universities (ORAU) conducted a radiological survey to confirm the status of the Phase III area, relative tu the NRC criteria for release for unrestricted use.
I
 
i SITE DESCRIPTION The- CA Technologies factitties are        located near the      intersections of Interstate 5 and. Genesee Road, approximately          2') km north of San Diego, CA (Firures I and 2).        Site activities include a wide variety of research and
      - developnent p rograms . The Phase III area-is. illustrated in Figure 3. Most of the area has remained undeveloped. The terrain consists primarily of extremely heavy brush, steep cills, and canyons; accessibility is limited. There are also several areas of asphalt paving, which include parking lots, roads, and storage areas.
The Phase III survey also includes the shipping and receiving area of Sluilding 5.      This facility consists of a small room, approximately 2 m x 3          m, which contained an exhaust hood, a large receiving room, and a smaller shipping room with package preparation area.
tiithin the Phase III boundaries are several areas in which CA decommissioning activities have not yet been completed. These areas, shown in Figure 3, have been excluded from the survey and will be addressed at a later date.            Area Bl is the Canyon Area to the Uest and below the "200 meter" storage butiding, the TRICA Reactor and Hot Cell facilities.      Area B2 includes a liquid storage tank, the CA sewage pumphouse, and contractor sheds.          Area B3, a sewage t rea t me nt facility known ss Callon Ponds, is surrounded by a security fence.
PROCEDURES l
A survey of the Phase III decommissioning area was performed by the l      Radiological Site Assessment Program of ORAU during September 9-28, 1987.              Ihis survey cas in accordance with a servey plan submitted to the Region V office of I      *he NRC.'      Methods and procedures utilized in the survey are presented in this section..
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i      objectives l
The ob.ectives of the survey were to confirm that the radiological condition l
i of the Phase III area was as presented in the CA Technologies report and to provide information and data for evaluation of the site status, relative to NRC guidelines for      elease for unrestricted use.3 Radiological information collected i                                                  2 l
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included gamma exposure rates; location of elevated direct rid t at ion leve l s ; and concentrations of radionuclides in surface soil.
Procedures _      ,-
Document Regfew The licensee's survey report for the release of the Phase III area for unrestricted use and other supporting documents were reviewed by ORAU.              Data presented in these reports were compared to the established release guidelines.
The licensee investigated the history of radiological use in the Phase II area.
Several areas were identifled with a potential for residual contamina!. ton and were excluded f rom this phase of the decommissioning project.
Facility Survey The location of building 5, which houses the shipping and receiving f acility, is indicated on Figure 4      Shipping and receiving is a small area located in the southwest portion of this building.          The total enclosed area is approximately 6.3 m x 15 m (refer to F!,gure 5).
Surface Scans Alpha, beta gamma, and gamma scans were pe rf ormed on floors, using an alph./hta      gas proportional  floor  monitor    and  NaI(T1)  gamma  scintillation detectors with audible indicating scaler /ratemeters.        A cursory scan of surf aces not accestible to the floor monitor,        i.e.,  walls, ceilings, and overhead areas such as ledges, beams, piping, fixtures, counter tops, equipment, and ductwork was performed using portable ZnS alpha scintillation and "pancake" CM beta-gamma detectors.
Measurement of Surface Contamination Levels Sixteen single point measurements were collected on the floor and lowcr walls of the shipping and receiving area.            Locations (Figure 6) were referenced to building features. At each location, direct measurements of alpha and beta-gamma      l contamination levels were performed and smears for removable alpha and beta I
contamination were collected.
3
 
Ten single point measurements for total and removable alpha and bet i-g r a contamination levels on uppe- walls, ceilings, fixtures, and equipment .ere 314s performed. These locations are identified on Figure 7.
Outside Area Survey Survey Reference System 3ecause the history of use of the Phase III property did not identify a significant potential for radiological contamination, a grid system was not established for survey reference.        Instead, the property was divided into 20 sections (Figure 8) using identifiable landmarks      (i.e.,  fence and property lines, parking lots and roads). Radiological measurement and sampling locations were referenced to surface features and landmarks.
P Surface Scans walkover surf ace scans were conducted at 5 to 20 m intervals over accessible areas of each section.      Portable NaI(Tl) gamma scintillation detectors with audible indicating ratemeters, were used to perform these scans.
Exposure Rate Measurements Exposure rates were measured at the surface and at 1 e above the surface at 2 to 7 randomly selected locations in each of the 20 sections, using NaI gamma scintillation detectors, cross-calibrated onsite with a pressurized ionization chamber.    'feasurements were also performed at 9 locations, directly with the pressurized ionization chamber. Measurement locations are indicated on Figures 9 through 29.
i l
Sampling Surface (0-15 cm) soil samples were collected at locations of exposure rate measurement throughout each section of the Phase III area. Sample locations l
l are indicated on Figures 10 through 29.
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Rackereund and Raseline !!oasurer.ents During a previous site visit, background measurements and soil sanples were            [
collected to determine area background and to provide casaline radionuclide                  ,
concentrations for comparision purposes. Locations of the background measure ents        -
and baselinef samples are shown on Figure 30.          TTbles 1 and 2 present the            j hackground exposure rates and baseline radionuclide concentrations, respectively.
Sample Analyses and Interpretation of Results Samples were returned to laboratories in Oak Ridge, Tennessee, 'or analyses.
All samples were analyzed by ga mma spectrometry.          The major radiotuclides of interest were Cs-137, Co-60, U-235, U-238, (fron Th-234 or Pa-234m), Th-232 (from Ac-228), and Ra-226 (f rom Ri-214); however, spectra were reviewed for the presence            .
of other significant photopeaks.          Selected individual samples and composite samples were also analyzed for Sr-90 and isotopic uranium. Additional information concerning analytical equipment and procedu res is contained in Appendices A and R. Results of this survey were compared to the guidelines, established by the            ;
NRC, for decommissioning of the GA Technologit's Uaste Processing Facility. These guidelines are presented in Appendices C and D.                                              ,
RESULTS i
Document Rtviev ORAU's review of the survey report submitted by CA to the NRC, indicates that          f i
the procedures and instrumentation used were consistent with industry accepted practices.      The survey, however, provi hd only a limited number of samples as          ,
representative of the radionuclide concentrations in the Phase III area. The
~
shipping and receiving area of Building 5 was included as part of the task af ter ORAU had begun the final survey of the Phase III area.          Data f rom GA were not available for review.      Data developed by CA are within the NRC guidelines, established for this site.                                                                  ,
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Facility Survey                                                                              !
I            Surface Scans                                                                            ,
Surface scans did not identify any locations of elevated alpha, beta-ganma, or gamas cousmination, which would have suggested residual contamination.
Surface Contamination Measurements Table 3 summarizes the results of surf ace contamination measurements.              The total contamination data presented in this cabic are direct measurements which include removable and non-removable activity.          Alpha and beta-gamma le vels were generally less than the detection sensitivity of the ins t rume nt s .      The maximun 2
alpha and beta gamma levels were 75 dps/100 cm and 680 dpm/100 em 2 ,,,p,,ggy,1y, Renovable alpha activity ranged f ron <3 to 7 dpm/100 cm 2and <6 to 7 dpm/100 cm 2 respectively.
r e
Outside Area Survey                                                                          >
Surface Scans The gamma scan of the area did not identify any areas of gross elevated direct gamma radiation,                                                                      i i        Exposure Rate Measurements I
i i
Exposure rates measured are presented in Table 4. Direct radiation levels ranged f rom 8 to 23 Jt/h. The highest level was found in Section 19.
t Radionuclide Concentration in Soil                                                            l r
I 1            Table 5 presents the concentrations of gamma emitting radionuclides, measured            j in surface soil collected in each of the 20 sections. Ranges of concentrations in            7
)        these samples were    Co-60, <0.03 to 1.13 pCi/g; Cs-137, <0.03 to 1.77 pCi/g; Ra-226,  <0.14  to 1.69 pCi/g; U-235,      <0.15    to 0.46 pCi/g; U-238,    <0.15      to 2.02 pCi/g; Th-228 <0.16 to 1.66 pCi/g; and Th-232, <0.21 to 2.15 pCi/g.                These .
l 6
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cencentrattons are in the ranges of bas e .' i ne samples. The highest radianueLLde concentrations were identif ied in 9ection 5, which is along the south boundary af the main plant site.
Results of    Sr-90 and is otopic uranium analyses, perf ormed on selected compos ite Sa.:piiles , are presented in Table 6. The highest concentration of Sr-90 in a composite sample was 0.48 pCi/g .                                                                                                                  Because this composite was prepared f rom !
individual samples, the maximum level possible in any individual sample would be 2.4  pCi/g. Other compos ites had Sr-90 concentratt e ranging f ron 0.09 to 0.28 pCi/g.
Isotopic uranium analyses                                                                                                      indicate concentrations                that are well below regulatory guidelines for surf ace sofi. Concentrations ranged from 0.88 to 1.33 pCi/g of U-238; 0.10 to 0.18 pCi/g of U-235; and 1.34 to 1.50 pct /g of U-234.      Results of the analysis are presented in Table 6. The highest total uranium concentration was <3.0 pC1/g.
COMPARISION OF SURVEY RESULTS WITH GUIDEl.INES The guidelines f or decommissioning the GA Technologies Phase III property (ref er to Appendices C and D) allow an exposure rate of 10 4/h, above background, at 1 m above the surf ace and over an area of 30 ft (9.1 m) x 30 ft (9.1 m) or The guideline level f or smaller areas is 20 -R/h above background.                                                                                                                          At greater.
the CA Technologies site, the total exposure rate guidelines would be 19.7 4/h and 29.7 R/h, i.e. 10 4/h and 20 4/h, respectively, plus the average background level of 9.7 R/h (f rom Table 1). One measurement in Section 19 had an exposure rate of 23 4/h, which exceeds the 10 4/h above  - background average guideJine. This was a small isolated area and the exposure rate was less than 20 R/h above background. All other measurements were well below 19.7 4/h. The external exposure rate target guideline has been satistied.
Radionuclide concentrations in samples collected f rom the Phase III area were in the range of concentrations measured in baseline samples from the I.a Jolla area. All concentrations were well sithin the guidelines es tablis hed for this decommissioning project.
7
 
Surf ace contamination levels, measured in the Shipping and Receiving f acili;y of Building ' 5 ' were also all within es tablished ' NRC guidelines for unrestricted use.
 
==SUMMARY==
 
4 -
At the request of the NRC Region V of f ice, on September 7.through 28, Oak Ridge Associated Universities perf ormed a conf irmatory survey of 87 hectares of property at GA Technologies, Inc. in San Diego, Calif ornia. The area surveyed is known as the Phase III portion of the overall site decommissic      .g project. The survey included surf ace gamma, be t a-gamma , and alpha scans , meas urement of total and removable surf ace contamination, measurements of direct radiation levels, and measurements of radionuclide concentrations in soil. The findings indicated no areas of residual contamination, exceeding the guidelines established by the NRC for release of the property, and conf irmed the adequacy and accuracy of the radiological measurements perf ormed by the licensee.
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                                                                                                      ,    245A MEASUREMLNi Af4D SAMPt tilG L OCAilOtJS u
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TABLE 2                                                                      ;
i
                                                                                                                                                                                  ~
BASELINE HADIONUCLlDE CONCfNTRATIONS IN Soll GA TECHNOLOGIES SAN DliGO, CAltf0RNIA 6
1 Lccation*
Co-60            Cs-137 Radlonuclide Concentrations (pCl/g)
R3-226            U-235              U-238 Th(228 & 252)        K-40 t
I                                        <0.05            <0.02            L*.59 2 0.14 D        <0.17        1.64 f 1.22    1.54 10.46    14.0 t 8. 7 2                                          <0.05          0.16 ? O.11          0.55 t 0.22          <0.20        1.59 t 1.48    I.98 1 0.86    25.0 t 5. 5 3                                          <0.04            <0.04            0.79 1 0.20        0.59 ! 0.24      1.07 ! 0.48    2.24 ! 0.62    10.4 t 1. 7 4                                          <0.08            <0.05              1.20 1 0.29          <0.52            <0.08      3.08 t 0.79    29.0 t 5.4
;                    5                                          <0.05            <0.05            1.23 1 0.22        0.69 1 0.55      1.28 1 0.62    5.20 1 0.80 -  24.5 t 2. 7 1                    6                                          <0.05            <0.05            0.65 1 0.16          <0.22        1.05 t0.85    .1.92 1 0.78    30.2 ! 2.9
$                  RANGE                                    <0.05 to <0.08 <0.02 to <0.16          0.55to 1.23      <0.17 to 0.69    t.05 to 1.64  1.54 to 3.20  10.4 to 50.2 I
i 1                  AVERAGE                                      <0.05            <0.06                  0.85            <0.35              1.28        2.29          22.2      '
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)
't aRefer *o Figure 30
{              buncertalntles represent the 955 confidence level based only on counting statistics; additional analytical uncertainties of 2 6 to 105 have not been propagated in these data.
B 1
t t
I
 
                                      ~_.          . . .
k i
TABLE 's
 
==SUMMARY==
OF SURFACE CO*4TAMINAT10N MEASURfM[NTS
.                                                          BUILDING 5 SHIPPING AND RECEIVING AREA PHASE 111 GA TECHNOLOGIES l                                                                    *, Art DIEGO, CALIFORNIA 6,
i TOTAL CONTAMINATION (dpm/100 cm )          REMOVA8LE CONTAMINATION (dph/ LOO 'cm )
!          Location8                      Number of        AIpha    _
Beta-Gamma          AIpha            Beta-Gamma 1
j                                      Measurements      Range of                        Range, of        Range of          Range of Measuremenis                  Measurements      Measurements        Measuremen t s H. P. Hood Room Floors / lower walls                3              <27                            <465              <4                    <6 Upper malls /cellings              2              <27                            <465              <3                    <6 Vents, flutures, equip.                b            _                                _                _                    _
j Shipping Area c.
      ~
r Floors / lower walls                4            <27 - 75                      <465 - 818            <3                    <6 Upper malls /cellings                I              <27                            <465              <3                    <6 Vents, flutures, equip.            -                -                                -                -                    -
a 1^
ReceiwIng Area l        Floors / lower walls                7            <27 - 45                      <465 - 757        <3 - 7                <6 - 7 4
a      bpper malls /cellings                3              <27                            <465              <3                    <6 s
a        Vents, flutures, equip.              3              <27                        <465 - 485            <3                    <6 4
1 Dock Area 1
Floors / lower walls                2              <27                            <465              <3                    <6
;      Equipment                            I            <27                            <465              <3                    <6 j
i i
aRefer to Figures 5 and 6 b(~) Indicates measurement not performed.
4 I
i
 
TABLE 4 DIRECT RADIATION LEVELS          *
                ,              PHASE III GA TECHNOLOGIES SAN DIECO, CALIFORNIA
          ^
Gamma Exposure Rates      Camma Exposure Rates Sample  ID Locationa  at I c: Above the Surf ace  At the Surface (uR/h)                    (tR/h) 182 A    SEC 4                  10                        11 183 A    SEC 4                  10                        10 184 A    SEC 4                  10                        10 185 A    SEC 4                  13                        15
'.86 A    SEC 4                  10                        10 187 A    SEC 2                  9                          9 188 A    SEC 2                  10                        10 189 A    SEC 2                  9                          9 190 '. SEC 2                  10                        10 191 A    SEC 2                  8                          8 192 A    SEC    1              8                          9 193 A    SEC    1              8                          9 194 A    SEC    1              8                          9 195 A    SEC 1                  9                          9 196 A    SEC    1              12                        12 197 A    SEC 7                  8                          9 198 A    SEC ?                  9                          9 199 A    SEC 3                  9                          9 200 A    SEC 3                  9                          9 201 A    SEC 3                  8                          7 202 A    SEC 3                  9                        10 203 A    SEC 7                  9                        10 204 A    SEC 7                  8                          8 42
 
TABLE 4 (continued)
DIRECT RADIATION LEVELS PHASE III GA TECHNOLOGIES S AN DIEGO, CALIFORNI A
                ~
Camma Exposure &ctes    Camma Exposure Rates Sample ID Locationa  at 1 m Above the Surface  At the Surface
( tR/h )              ( tR/h) 205 A  SEC 7                    9                    10 206 A  SEC 7                    8                    9 207 A  SEC 7                    9                    10 208 A  SEC 8                    9                      9 209 A  SEC 8                    9                    10 210 A  SEC 8                  10                    10 211 A  SEC 8                  10                    10 212 A  SEC 5                  13                    13 213 A  SEC 5                  13                    13 214 A  SEC 5                  13                    13 215 A  SEC 6                  10                    10 216 A  SEC 6                  13                    13 217 A  SEC 6                  11                    11 218 A  SEC 6                  10                    12 219 A  SEC 6                  11                    11 221 A  SEC 10                  13                    13 22? A  SEC 10                  11                    12 223 A  SEC 10                  8                      9 224 A  SEC 9                  11                    13 225 A  SEC 9                  12                    12 226 A  SEC 15                  12                    13 227 A  SEC 15                  13                    15 228 A  SEC 15                  13                    13 229 A  SEC 15                  12                    13 43 l
l l
l
 
TABLE 4 (continued)
DIRECT RADIATION LEVELS PHASE III
              .              CA TECHNOLOGIES S AN DIEGO, CALIFORNI A Gamma Exposure Rates    Gamma Exposure Rates Sample  ID Locationa  at I m Above the Surf ace  At the Surface
( :a/h)              (tR/h) 230 A    SEC 12                    15                  15 231 A    SEC 12                    15                  15 232 A    SEC 11                    16                  16 233 A    SEC 11                    12                    12 234 A    SEC 11            ,
16                  16 235 A    SEC 13                    15                  15 236 A    SEC 13                    14                  15 237 A    SEC 13                    15                  15 238 A    SEC 13                    16                  15 239 A    SEC 14                    15                  15 240 A    SEC 14                    13                  15 241 A    SEC 13                    13                  14 242 A    SEC 19                    14                  15 243 A    SEC 19                    15                  16 244 A    SEC 17                    12                  14 245 A    SEC 17                    11                  11 246 A      b                        b                    b 247 A    SEC 17                    11                  13 248 A    SEC 17                    11                  12 249 A    SEC 18                    10                  10 250 A    SEC 20                    13                  13 251 A    SEC 20                    11                  10 252 A    SEC 16                  11                    11 44
 
TABLE 4 (continued)
DIRECT RADIATION LEVELS MEASURED ON PHASE III PROPERTIES Gamma Exposure Rates          Gamma Exposure Rates Sample        ID Location a    at 1 o Above the Surface        At the Surface
( $/h)                        ( 2/h) 253 A            SEC 16                  13                            13 254 A            SEC 16                  13                            15 255 A            SEC 18                  11                            13 256 A            SEC 18                  13                            15 257 A            SEC 18                  13                            15 258 A            SEC 18                  13                            15 259 A            SEC 19                  16                            13 260 A            SEC 19                  13                            11
  - 261 A              b                      b                              b 262 A            SEC 19                  23                            20 263 A            SEC 20                  13                            13 264 A            SEC 19                  18                            16 265 A              b                      b                              b 266 A            SEC 16                  13                            13 267 A            SEC 16                  13                            15 aRefer to Figures 10 to 29.
b Measurement not performed.
I l
l l
l 45 I
l
 
TABLE 5 RADIONCUllDE (X)NCENTRATIONS IN S0lt PHASE lll GA TECHNOLOGIES SAN DIEGO, CALIFORNIA 6
1 Sample                                          Radlonuclide Concentrations (pCl/g)                          ,
No. Location a    Co-60      Cs-137          Ra-226          6-235          u-238      Th-228            Th- 232 182A    SEC    4      <0.04    1.77 1 0.20D    0.70 1 0.11        <0.22          <0.50      <1.80              <0.27 18 5A  SEC    4  0.17 1 0.80 0.10 1 0.07    0.90 t 0.21        <0.27      0.28 t 1.6  0.64 1 0.05    0.86 t 0.52 184A    SEC    4      <0.05    0.1210.09      1.0 t 0.18        <0.21      0.45 t I.3      <0.28        1.26 ? 0.42 185A    SEC    4      <0.06        <0.04        1.16 t 0.26      <0. 50      0.87 ! 0.90    <0.26        1.24 ? 0. 50 '
186A    SEC    4      <0.05    0.16 1 0.09    0.83 1 0.28 0.08 1 0.10        1.5510.72    0.89 t 0.29      1.14 1 0.55 18 7A  SEC    2      <0.04    0.08 1 0.08    0.73 1 0.12        <0.15          <0.45      <l.59        0.77 ? 0.27 IB8A    SEC    2      <0.05    0.25 1 0.10    0.96 1 0.24        <0.19          <0.44      <0.18        1.02 t 0.50 189A    SEC    2      <0.05    0.25 2 0.07    0.70 2 0.18 0.10 1 0.08        0.61 1 0,81  0.59 1 0.24    3.70 t 0.45 190A    SEC    2      <0.05    0.26 1 0.10    0.95 1 0.28        <0.18          <0.54      <0.25        0.79 t 0.28 19 tA  SEC    2      <0.05    0.17 1 0.08        <0.14    0.46 1 0.50          <0.4l      <0.17        0.57 t 0. 58 192A    SEC    1    <0.04    0.85 1 0.11    0.68 1 0.12 0.10 t 0.08        1.14 1 2.72  0.85 1 0.22    0.60 t 0.24
  $[  195A  SEC    I    <0.05    0.14 1 0.12      1.08 1 0.20      <0.21          <0.61      <0.25              <0.24 194A  SEC    l    <0.05        <0.05      0.62 1 0.16        <4.19          <0.43      <0.16        0.50 ! O.50 195A  SEC    1    <0.05    0.45 1 0.10    0.71 1 0.20 0.10 1 0.10        1.16 ! 2.66 C.58 t 0.11    0.72 10.55 196A  SEC    I      0.06        <0.07          <0.18          <0.25          <0.74      <0.50'            <0.51 19 7A  SEC    7    <0.04        <0.05      0.86 1 0.17        <0.88          <0.47      <0.21        0.87 1 0.48 198A  SEC    3    <0.05        <0.05      0.65 1 0.24 0.15 2 0.07        0.60 t 0.74  1.66 1 0.85    0.60 ! 0.50 199A  SEC    3    <0.04        <0.05          <0.14          <0.16      1.76 e 1.12    <0.10              <0.25 200A    SEC    3    <0.05    0.07 1 0.04    0.76 1 0.12        <0.17      0.82 ? 0.52    <0.16        0.62 t 0.57 201A    SEC    5    <0.05        <0.05      0.40 2 0.11 0.07 2 0.08        0.98 i 0.70  0.40 t 0.20    0. 54 ? 0.20 202A    SEC    3    <0.05    0.05 t 0.15    0.76 1 0.17        <0.19          <0.52      <0.22        0.92 1 0.54 205A    SEC    7    <0.05        <0.05      0.78 ? 0.17        <0.19      0.60 1 0.44    <0.17        1.15 ! 0. 56 204A    SEC    7    <0.04    0.23 ! 0.85    0.60 t 0.17 0.08 t 0.08        0.88 1 0.84  0.71 ! 0.20    0.90 ! 0.51 205A    SEC    7    <0.04        <0.04      0.78 1 0.15        <0.18          <0.50      <0.28              <0.24 206A    SEC    7    <0.04        <0.05      0.61 t 0.15        <0.18      0.59 1 0.75    <0.16        0.49 ! 0.28 20 7A  SEC    7    <0.04    0.58 1 0.11    0.70 t 0.17        <0.20          <0.57      <0.19        1.07 ! 0.?>
208A    SEC    8    <0.05    1.01 1 0.16    0.80 t 0.20        <0.18          <0.54      <0.21        0.75 ! 0.40 209A    SJC    8    <0.04    0.48 1 0.15    0.84 t 0.19        <0.20      0.77
* 0.70    <0.17        1.15 t 0. 56
~_                                              -
 
                                                                ~
i TABLE 5 (Continued)
HADIONrut.1DE ONCENTRATIONS IN SOtt PHASF 111 GA TEOP 40LOGIES SAN 01 EGO, CALIFORNIA 6
1 Sample                                    Radionuclide Concentrations rJI/ql                    ,
No. Locationa Co-60    Cs-137            Ra-226          U-255      U-238    Th-228          Th- 252 210 A  SEC    8 <0.04 0.58 1 0.05      0.85 ! 0.24        <0.20        <0.60    <0.19      0.89 t0.55 218 A  SEC    8 <0.04 0.15 1 0.10      1.08 1 0.20        <0.20        <0.67    <0.25            <0. 50 212 A  SEC    5 <0.06 0.44 1 0.16      1.48 1 0.50        <0.32    1.20 1 0.64  <0. 50    1.61 ! 0.54 215 A  SEC    5 <0.06 0.2920.09        1.25 t 0.25        <0.51        <0.91    <0.27
* 5'
* 1.45 214 A  SEC    5 <0.05 0.0210.11        1.56 1 0.28        <0.24    2.02 1 1.18  <0. 50    1.80 t0.40 215 A  SEC    6 <0.04 0.04 1 0.07      0.57 1 0.16 0.25 1 0.25      0.59 1 0.40  <l.68      0. 51 !0.24 216 A  SEC    6 <0.06 0.11 f 0.06      1.50 f 0.25        <0.27        <0.85    <0.05      1.21 1 0.48 217 A  SEC    6 <0.05    <0.04        0.51 1 0.16        <0.14        <0.55    <0.20      0.46 ! 0. 55 218 A  SEC    6 <0.05    <0.04        1.56 1 0.25        <0.28    0.84 1 1.25  <0.29      f.69 ! 0.42 219 A  SEC    6 <0.05    <0.04          1.0 1 0.22        <0.26        <0.75    <0.25      0.89 !0.55
: c. 220 A  SEC    9 <0.04    <0.04        1.05 1 0.22        <0.22        <0.69    <0.27      1.25 ! 0.44 221 A  SEC    10 <0.04 0.05 1 0.09      1.15 t 0.26        <0.25        <0.59    <0.25      1.27 ! 0.57 222 A  SEC    10 <0.05 0.15 1 0.09      1.11 1 0.25        <0.26    f.40 1 1.45  <0.25      1.68 ! 0.57 225 A  SEC    10 <0.04 0.10 1 0.09      0.65 1 0.20        <0.17        <0.55    <0.19      0.72 10.52 224 A  SEC    10 <0.04    <0.04        1.28 f 0.22        <0.25    1.07 i O.59  <0.25      8.75 t 0.48 225 A  SEC    9 <0.05 0.1810.11        0.92 10.25        <0.26        <0.85    <0.28      1.12 10.14 226 A  SEC    15 <0.07    <0.05        1.16 1 0.29        <0.25        <0.88    <0.52            <0.40 227 A  SEC    15 <0.06 0.08 1 0.10      1.55 t 0.28 0.51 1 0.44        <0.70    <0.50      1.71 ! 0.56 228 A  SEC    15 <0.05    <0.06        1.5820.24          <0.52        <0.95    <0.55      2.00 ! 0.52 229 A  SEC    15 <0.06 0.05 f 0.10      1.10 1 0.26        <0.25        <0.79    <0.27      1.06 ! O.50 250 A  SEC    12 <0.05 0.06 t 0.11      1.16 t 0.24        <0.26    0.68 1 1.62  <0.25      1.5010.42 231 A  SEC    12 <0.06 0.49 1 0.14      1.52 1 0.25        40.26        <0.85    <0.52      1.92 10.57 252 A  SEC    11 <0.04    <0.04        1.59 1 0.27        <0.29    0.65 1 0.87  <0.26      1.50 t 0. 50 255 A  SEC    11 <0.07 I.01 1 0.16      0.64 ! 0.20        <0.28        <0.64    <0.22      0.64 20.40 254 A  SEC    11 <0.06 0.0520.09        1.10 t 0.17        <0.29        <0.86    <0. 50    1.46 t 0.45 255 A    SEC  15 <0.04 0.06 1 0.08      1.04 1 0.26        <0.25    0.86 2 1.26  <0.29      2.02 ' O.49 2 56 A  SEC    15 <0.05 0.08 ! 0.06      1.25 t 0.22        <0.28    0.89 ! 0.69  <0.27      1.50 ? 0.47 257 A  SEC  15 <0.07 0.21 ! 0.07      1.55 t 0.25        <0.29        <0.82    <0.55      3.73 ' 0.rW
 
TABLE 5 (Continued)
RADIONCULIDE (DNCENTRA110NS IN SolL PHASE III GA TECHNOLOGIES SAN DIEGO, CALIFORNIA Sample                                                                        Radlonuclide Concentrations (pCl/g)                  ',
No.        Location a      Co-60                              Cs-157            Ra-226          U-235      6-2 58    Th-228        Th- 252 2 58 A        SEC    15        <0.06                            3.11 1 0.09      0.99 i 0.19        <0.27        <0.77      <0.25      1.48 ?0.59 259 A        SEC    14        <0.04                              <0.04        1.5610.16          <0.19        <0.54      <0.22      1.17 ! O. 58 240 A        SEC    14        <0.06                              <0.06        1.54 1 0.54        <0.51        <0.94      <0.51      1.60 t 0.44 24l A        SEC    15        <0.07                            0.0210.10        1.55 i 0.28        <0.27        <0.90      <0. 54    1.94 t0.55 242 A        SEC    19        <0.06                            0.56 i 0.11      1.16 t 0.24        <0. 50      <0.84      <0.29      1.28 t 0.49 24 5 A        SEC    19        <0.06                            1.15 1 0.20      1.52 10.55          <0.28        <0.15      <0.55      1.45 ! 0.49 244 A        SEC    17        <0.05                            0.16 1 0.10      0.98 1 0.17        <0.27        <0.85      <0.28      1.10 t0.46 245 A        SEC    17        <0.06                              <0.05        0.75 t 0.22        <0.22    1.90 i 1.58  <0.52      1.44 ?0.58 247 A        SEC    17        <0.07                            0.02 1 0.10      1.15 1 0.26        <0.26        <C.80      <0.28      2.15 1 0.56 248 A        SEC    17        <0.06                            0.05 1 0.09      0.91 i 0.24        <0.21        <0.66      <0.27      1.19 1 0.40 249 A        SEC    18        <0.05                            0.21 2 0.10      0.o5 1 0.15        <0.22        <0.65      <0.20      1.09 ? 0. 59
[l 250 A        SEC    20        <0.08                            0.11 ! 0.12      1.15 10.25        <0.27        <0.97      <0. 54    1.52 !0.54 251 A        SEC    20        <0.05                              <0.05        0.57 1 0.17        <0.20        <0.60      <0.21 '    O.52 t 0.27 252 A        SEC    16        <0.05                            0.62 1 0.16      0.89 1 0.25        <0.27        <0.86      <0.35      1.21 !0.48 253 A        SEC    16        <0.04                            0.48 1 0.12      1.20 1 0.25        <0.24    1.54 1 0.60    <0.25      1.40 t 0.55 254 A        SEC    16        <0.07                            0.29 1 0.21      1.51 ? 0.25        <0.31        <0.96      <0.51      1.27 ! 0.49 255 A        SEC    18        <0.07                              <0.06        1.56 1 0.26        <0.27        <0.85      <0. 58    1.91 ! 0.56 256 A        SEC    18        <0.04                            0.02 2 0.11      1.42 1 0.55        <0.29    0.78 1 0.67    <0.50      1.95 t0.47 257 A        SEC    18        <0.06                              <0.04          1.40 ! 0.55        <0.51        <0.92      <0.55      1.45 t0.51 258 A        SEC    18        <0.06                              <0.10          1,69 1 0.35        <0. 50      <0.89      <0.57          <0.4I 259 A        SEC    19    1.15 1 0.21                        0.91 1 0.16      0.47 i 0.18        <0.22    0.4 5 t 1. 58  <0.17          <0.21 260 A        SEC    19        <0.04                            0.04 1 0.08      0.29 i 0.16        <0.19        <0.55      <0.19      0.47 1 0.55 262 A        SEC    19      <0.05                            0.08 1 0.12      1.59 t 0.27        <0.25        <0.85      <0.50      1.57 ?0.42 265 A        SEC    20        <0.07                            0.07 i 0.15      0.88 i 0.25        <0.25        <0.64      <0.25      1.12 ! 0.45 264 A        SEC    19      <0.05                            0.11 i 0.10      1.46 1 0.26        <0. 50  1.76 1 1.27    <0.27      1.11 ! 0.45 265 A        SEC    19      <0.06                            0.35 1 0.17      0.86 1 0.25        <0.25        <0.71      <0.27      I.45 ? 0 . 58 266 A        SEC    16      <0.05                            0.15 ! 0.09      l.16 ! 0.29        <0.26    1.55 ! 0.92    <0.25      1.0  ?0.40 8
Refer to figures 10 through 29 b
uncertainties represent the 951 confidence levels, based only on counting statistics; additional la t>>ra t or y uncertaint.es of ! 6 to 105 have not tenen propagated into these data.
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TABLE 6 RADIONUCLICE CONCENNATICNS IN CoueOSITE Soll PHASE fil GA TECHNOLOGIES SAN OlEGO, CALIFORNIA Radlonuclide Concentrations (eCl/g)
Sample lype 8                  Sr-90                V-234          U-235            U-238 Compostto A                0.48 ! 0.18 D        1.50 t 0.20    0.08 2 0.05      1.03 ! 0.'I7 ComposIto B                0.09 1 0.09          1.34 !0.24    0.16 ! 0.10      1.33 ! 0.24 Composite C                0.28 1 0.10          1.33 ! 0.30    0.18 ! 0.12      0.88 ! 0.24 ComposIto 0                0.22 2 0.10          1.31 2 0.25    0.10 t 0.07      1.26 1 0.22 a$aaple Identification numbers:
Composite A: (182A, 183A, 184A, 185A, 186A )
Composite 8: (222A, 223A, 224A)
Composite C: (242A, 243A, 259A, 260A)
Coeposite 0: (250A, 251A,'263A)
D Uncertaintles represent the 955 confidence levels, based only on counting statisticsl additional laboratory uncertainties of f 6 to 101 have not been propcgated into these data.
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REFERENCES
: 1. Be rge r, J.D. , "Confiroatory Survey of Phase I Decommissioning Former b'aste Processing Facility, CA Technologies, San Diego, California," Oak Ridge Associated Universities, July 1986.
: 2. "Proposed Confirmatory Survey Plan for 215 Acres at the CA Technologies Site, CA Tecnhologies, San Diego, California," Oak Ridge Assoc'sted Universities, September 8, 1987
: 3. Letter from K. E. Asmussen (CA Technologies, Inc.) to R. D. Thomas (U.S.
      '!uclear Regulatory Commission, Region V),
 
==Reference:==
    "Licens e SN't-696, Docket 70-734", Augitst 12, 1987.
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* APPENDIX A MAJOR SAMPLING AND ANALYTICAL EQUIPMENT l
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APPENDIX A MAJOR SAMPLING AND ANALYTICAL EQU1PMTNT The display or description' of a specific product is not to be construed as an' endorsemgdt of' that product or its manufacturer by the . authors or their employer.
A. Direct Radiation Measurements Eberline "RASCAL" Portable Ratemeter-Scaler
                                -Model PRS-1 (Eberline, Sante Fe, NM)
Eberline PRM-6 Portable Ratemeter (Eberline, Sante Fe, NM)
Ludlum Floor Monitor Model 239-1
              .                  (Ludlum, Sweetwater, TX)
Eberline Alpha Scintillation Probe Model AC-3-7                                                                                      i (Eberline, Sante Fe, NM)
Eberline GM Pancake Probe Model HP-260 (Eberline, Sante Fe, NM) f Victoreen Beta-Gamma "Pancake" Detector Model 489-110 1                                (Victoreen, Cleveland, OH) i Victoreen NaI Scintillation Detector Model 489-55 (Victoreen, Cleveland, OH)
Reuter-Stokes Pressurized Ionization Chamber
"                                Model RSS-Ill 4
(Reuter-Stokes, Cleveland, OH)
B. Laboratory Analyses Automatic low-background Alpha-Beta Counter Model LB5110-2080 (Tennelec, Inc., Oak Ridge, TN)
High-Purity Germanium Detector Model GMX-23195-S, 23% efficiency
( EC&G ORTEC, Oak Ridge, TN)
A-1                            ,
 
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Used in conjunction with:
Lead Shield, G                                (Gamma Products Inc. , Palos Hills , IL)
                            ~ High Purity'$ermanium Coaxial Well Detector Model GWL-110210-PWS-S, 23% Ef f iciency (EC&G ORpEC, Oak Ridge, TN)
Used in - conjunction with:
Lead Shield Model C-16 (Applied Physical Technology, Atlanta, GA) 1 High Purity Germanium Detector Model IGC25, 25% Ef ficiency (Petnceton Gamma-Tech, Princeton, NJ)
Used in conjunction with:
Lead Shield (Nuclear Data, Schaumburg, IL)
Multichannel Analyzer ND-66/ND-680 Sys tem (Nuclear Data Inc., Schaumburg, IL)
Alpha Spectrometry System Tennelec Electronics (Tennelec, Oak Ridge, TN)                                                            ;
Surf ace Barrier Detectors                                                          '
(EG&G ORTEC, Oak Ridge, TN)
Multichannel Analyzer Model ND-66 (Nuclear Data, Schaumburg, IL) l i
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                          .- APPENDIX B 1                MEASUREMENT AND ANALYTICAL PROCEDURES 5.
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APPENDIX B Me as u reme n t and Analytical Procedures Su rf a ce Sca ns- ,
Surf ace' scans in the -f acility were perf ormed by passing the _ probes slowly over the surf ace. The distance between the probes and the surf ace was maintained at a minimum - nominally about I cm.                  Identification of elevated levels was based on increases in the audible signal f rom the recording or indicating- ins trument.
Alpha and beta-gamma scans of large surf ace areas on the floor of i the f acility                          ,
we re accomplis hed by use of a gas proportional floor monitor, with a 600 cm' sens itive area. -The instrument was slowly moved in a systematic pattern to cover 100% of the accessible area.                Combinations of detectors and ins trument for the scans were:
    -            Beta-Gamma - Pancake G-M probe with PRM-6 ratemeter.
Beta-Gamma - Pancake G-M probe with PRS-1 scaler /ratemeter.
Gamma          - NaI scintillation detector (3.2 cm x 3.8 cm crystal) with PRM-6 ratemeter.
Alpha          - ZnS probe with PRS-1 scaler /ratemeter.
Alpha / Beta - Gas proportional floor monitor with Ludium Model 222-s cale r/ rat eme te r .
Alpha and Beta-gamma Surf ace Contamination Measurements Meas urements of total alpha radiation level were pe rf ormed using Eberline Model PRS-1 portable s cale r/ratemete rs with Model AC-3-7 alpha scintillation probes.      Measurements of total beta-gamma radiation levels were perf ormed using Eberline Model PRS-1 portable s caler/ratemeters with Model HP-260 thin-window
  .        "pancake" G-M probes . Count rates (cpm) were converted to disintegration rates (dpm/100 ca#) by dividing the net rate by the 4 4 ef ficiency and correcting f or the active area of the detector.                  Ef f ective window areas were 59 cm' f or the ZnS detectors and 15 cm' f or the G-M detectors . The background count rate for ZnS alpha probes averaged approximately 2 cpm; the average background count rate was approximately 40 cpm f or the G-H detectors.
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Removible Contamination Meaourerents Smear  easurements were perf ormed on nunbered filter paper disks, 47 en in dianeter. Smears were placed in labeled envelopes with the location and other pertinent information recorded.      The smears were counted on a iov background proportional,tounter at the Oak Ridge laboratory.
Exeosure Rate Measurements
        'feasurements of gamma exposure rates were performed using an Eberline PRM-6 portable ra t eme t e r with a Victoreen Model 489-55 gamma scintillation probe containing a 3.2 cm x 3.8 cm NaI(TI) scintillation crystal.        Count rates were converted to exposure rates ( L2/h) by onsite cross-calibration with a Reuter Stokes model RSS-111 pressurized ionization chamber.
Soil Sample Analvsis  _
Camsa Spectroscopy soil samples were dried, mixed, and a portion sealed in 0.5-liter Marinelli beaker. The quantity placed in the beaker was chosen to reproduce the calibrated counting geometry and ranged from 600 to 800 g of soil. Net soil weights were determined and the samples counted using intrinsic germanium and Ce(Li) detectors coupled to a Nuclear Data Model ND-680 pulse height analyzer system. Background and Compton stripping,      peak search, peak identification, and concentration calculations were performed using the computer capabilities inherent in the analyzer system. Energy peaks used for determination of radionuclides of concern were:
Co 1.173 MeV Cs-137 - 0.662 MeV Ra-226 - 0.609 MeV from Bi-214 (secular equilibrium assumed)
U-235 - 0.144 MeV U-238 - 0.094 MeV f rom Th-234 (secular equilibrium assumed)
Th-228 - 0.583 MeV from T1-209 (secular equilibrium assumed)
Th-232 - 0.911 MeV from Ac-228 (secular equilibrium assumed)
Spectra were also reviewed for the presence of other radionuclides.
B-2
 
i Strontium-90 Analysis Aliquots of, soil were            dissolved by pyrosulfate fusion and the strontium-precipitated a's a sulfate.                Successive treatments with EDTA preferentially removed lead and excess calcium and returned the strontium to solution.                                                                          Ferric and other . insoluble hydroxides was _ precipitated at a pH of 12 to 14.                                                                    S t ront ium was reprecipitated as a sulfate.                Barium was re oved as a chromate using DTPA.
The final precipitate of strontium carbonate ' was counted using a low-background Tennelee alpha-beta proportional counter.
fd Alpha Spectrometry for Isotopic Uranium Aliquots of soil were dissolved by pyrosulf ite fusion and precipitated ' with -
barium sulfate.                The barium sulfate precipitates were redissolved and uranium separated b,c liquid - liquid extraction.                                                                        Uranium sas then precipitated with a cerium fluoride carrier and counted using surface barrier detectors (ORTEC),
alpha spect rome te rs (Tennelec), and an ND-66 Multichannel Analyzer (Nuclear Data).
Uncertainties and Detection Limits The uncertainties associated with the analytical data presented in the tables of this report, represent the 95% confidence levels for that data. These uncertainties were calculated based on both the gross sample count levels and the associated background count levels. When the net sample count was less than the 95% statistical deviation of the background count, the sample concentration was reported as less than the detection capability of the measurement procedure.
Because of variations in background levels and Compton contributions from other radionuclides in samples, the detection limits dif f er f rom sample to sample and instrument to ins t rument . Additional uncertainties of 26 to 10%, associated with sampling and laboratory procedures, have not been propagated into the data presented in this report.
Calibration and Quality Assurance Laboratory and field survey procedures are documented in the following
::anuals , developed specifically for the Oak Ridge Associated Universities' B-3
 
Radiological Site As s ess ;_,n t Program:    "Survey Procedures Manual,' Revisi m 3  j May 1987; "Laboratory Procedures Manual", Re vis ion 3, May 1987 and "Quality
  -  Assurance Manual", Revision 1, June 1987.
With the. exception of      the meas u reme nts conducted with portable gamma    j scintillation survey meters,        ins t rume nts were calibrated with NBS-traceable s tanda rds . The calibration procedures for the portable gamma instruments are perf ormed by comparison with an NBS calibrated pressurized ionization chamber.
Quality control procedures on all ins truments included daily background au    d che ck-s our ce meas urements  to conf irm equipment operation within acceptable s tatis tical f luctuations . The ORAU laboratory participates in the EPA and EML Quality Assurance Programs .
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APPENDIX C GUIDELINES FOR DECONTAMINATION OF FACILITIES AND EQUIPMENT PRIOR TO RELEASE FOR UNRESTRICTED USE OR TERMINATION OF LICENSES FOR BYPRODUCT, SOURCE OR SPECIAL NUCLEAR MATERIAL l
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CUIDELINES FOR DECONTAMINATION OF FACILITIES AND EQUIPMENT
        .        PRIOR TO RELEASE FOR UNRESTRICTED USE
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OR TERMINATION OF LICENSES FOR. BYPRODUCT, SOURCE OR SPECIAL NUCLEAR MATERIAL U.S. Nuclear Regulatory Cocenission 4
Division of Fuel Cycle & Material Safety l                                    Washington, D.C.      20555 1
July 1982 l
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The instructions in this guice, in conjunction with Table 1 specify the radionuclides and radiation exposure rate limits which should be used in decontamination and survey of surfaces or premises and equipment peior to abandonment or release for unrestricted use. The limits in Table 1 do not apply to premises, equipment, or scrap containing induced radioactivity for which the radiological considerations pertinent to their use may be different. .The release of such f acilities or items f rom regulatory cont rol is conside~ red on case-by-case basis.
: 1. The licensee shall make a reasonable effort to eliminate residual contamination.
: 2. Radioactivity on equipment or surfaces shall not be covered by paint ,
plating, or other covering material unless contamination levels, as determined by a survey and documented, are below the limits specified in Table 1 prior to the application of the covering.        A reasonable effort must be made to minimize the contamination prior to use of any covering.
: 3. The radioactivity on the inrerior surf aces of pipes, drain lines, or ductwork shall be determined by making measurements at all traps, and other appropriate access points, provided that contamination at these locations is likely to be representative of contamination on the interior of the pipes, drain lines, or ductwork.            Surfaces or premises, equipment, or scrap which are likely to ba contaminated but are of such size, construction, or location as to make the surface inaccessible for purposes of measurement shall be presumed to be contaminated in excess of the limits.
: 4. Upon request, the Commission may authorize a licensee to relinquish possession or control of premises, equipment, or scrap having surfaces contaminated with materials in excess of cne limits specified.      This may include, but would not be limited to, special circumstances such as razing of buildings, transfer of premises to another organization continuing  work with radioactive materials, or        conversion    of facilities to a long-t e rm storage or standby status. Such requests must:
: a. Provide detailed, specific information describing the premises, i
equipment or scrap, radioactive contaminants, and the nature, extent, and degree of residual surf ace contamination.
"        b. Provide a detailed health and safety analysis which reflects that the residual amounts of materials on surface areas, together with other considerations such as prospective use of the premises, equipment or scrap, are unlikely to result in an unreasonable risk to the health and safety of the public.
: 5. Prior to release of premises for unrestricted use, the licensee shall make  a  comprehensive  radiation  survey  which  establishes that contamination is within the limits specified in Table 1. A copy of C-1
 
the <urvey report shall be filed with the Division of Fuel Cycle and Material Safety, USNRC, '4a sh ing t on , D.C.                              20555, and also the Administrator of the NRC Regional Office having jurisdiction.                                          The report sho,uld be filed at least 30 days prior to the planned date of abandonment. They survey report shall:
: a.  ,Identif y the premises.
: b. Show that reasonable effort has been sade to eliminate residual contamination.
: c. Describe the scope of the survey aad general procedures followed.
: d. State the findings of the survey in units specified in the instruction.
Following review of the report, the KRC will consider visiting the facilities to confirm the survey.
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                                                                                    ~
4, TARIE I ACCEPTABIE SURFACE CONTAMINATION LEVEL.S Nuclidesa                        Averageb,c,f            Maximumb,d,f              Removableh,c,f U-nat, U-235 U-238, and                      5,000 dpa a/100 cm 2 15,000 dem a/100 cm 2    1,000dpmh100cm 2 associated decay products                                                                                      ,
2                        2                      2 Transuranics, Ra-226, Ra-228,                100 dpm/100 cm          300 dpm/100 cm            20 dpe/iOO cm Th-230, %-228, Pa-231, Ac-227, 1-125, 1-129 2                      2 Th-nat, Th-232, Sr-90, Ra-223                1000 dpm/100 cm 2      3000 den / LOO cm        200 dpm/100 cm Ra-224, U-232, I-126, 1-131, 1-133 2                            2 Beta gamena emitters (nuclides              5000 dpm Sy/100 cm      15,000 dpa 81/100 cm      1000 dpm 61/100 cm#
with decay modes other than
            ?
alpha emission or spontaneous fission) except Sr-90 and others noted above.
a Where surface contamination by both alpha- and beta-gamma-emitting nuclides exists, the limits established for alpha- and beta-gamma-emitting nuclides should apply independently.
b As used in this table, dpm (disintegrations per minute) means the rate of emission by radioact Ive material as determined by correcting the counts per minute observed by an appropriate detector for background, ef ficiency, and geometric factors associated with the instrumentation.
c Measurements of average contaminant should not be averaged over more than I square sneter.              For objects of less surface area, the average should be derived for each such object.
2 d % e maximum contamination level applies to an area of ngt smore than 100 cm              ,
e ne amount of removabic radioactive material per 100 cm of surface area should.be determined by wiping that area with dry filter or soft absorbent paper, applying m>derate pressure, and assessing the amount of radioactive material on the wipe with an appropriate instrument of known efficicucy. When removable contamination on objects of less surface area is determined, the pertinent levels should be reduced proportionally and the entire surface should be wiped.
I %e average and maximum radiation levels associated with surface contamination resulting fross beta gamm.s emitters should not exceed 0.2 mrad /h at I cm and 1.0 mrad /h at I cm, respectively, measured through not more than 7 milligrams 3,er square centimeter of total absorber.
 
        . . ~, ,_ - --. . .. - .. . _ . .                ..      .-    .  . . . . - -.. . .-
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l APPENDIX D i
DECOMMIS?IONING CUIDELINES FOR THE GA TECHNOLOGIES FACILITY
      ,                                                                                        t I
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APPENDIX D          ,
r Decommissioning Guidelines for the
                            ,            GA Technologies Facility Targe,t criteria for unrestricted release of the GA Technologies' Uaste Processing. Facility and surrounding areas are presented in the licensee's final I
report and are as follows:
External Radiation The gamma exposure rate at 1 m above the ground surf ace shall not exceed 10 LR/h above background for an a rea of greater than 30 ft (9.1 m) x 30 ft (9.1 m) and shall not exceed 20 $/h above background for any discrete area (i.e. less than 30 ft (9.1 m) x 30 ft 9.1 m)).
Inhalation and Ingestion Concentrations of radionuclides in soil shall be such that inhalation and ingestion are not expected to result in annual dose equivalents exceeding 20 mrem to the lung or 60 mrem to the bone.
Limiting soil concentrations were derived to satisfy these external and internal target criteria.        The concentration limits are presented in the following Table.
Radionuclide              Concentration Limit Above Background (pCi/g)
Depleted Uranium                                35 Enriched Uranium                              30 Thorium (Natural)                              10 Co-60                                            3 1
Cs-137                                          15 St-90                                        1.8 x 10 3 l
Uhere more than one radionuclide is present, the sum of the ratios of the individual radionuclide concentrations to their respective concentration limits shall not exceed 1.
D-1 l
l.}}

Revision as of 10:35, 13 November 2020

Evaluation Supporting Amend 9 to License SNM-696
ML20196B041
Person / Time
Site: 07000734
Issue date: 06/22/1988
From: Shum E, Swift J
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20196B002 List:
References
NUDOCS 8806300182
Download: ML20196B041 (12)
v • d • e


Text

- - _ _ _ _ .

  1. . . ,,o * * %,i. UNITED STATES NUCLEAR REGULATORY COMMISSION

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IMUF: EYS DOCKET N0: f0-734 LICENSEE: General Atomics (GA)

FACILITY: Fuel Fabrication Facility San Diego, California

SUBJECT:

EVALUATION FOR AMEN 0 MENT APPLICATION DATED MARCH 4, 1988, RE: GA'S DECONTAMINATION EFFORT BACKGROUND By letters dated November 16, December 6, December 21, 1984; October 1, 1985; and December 15, 1986, GA Technologies, Inc. (now General Atomics) informed the Nuclear Regulatory Commission (NRC) that GA had decided to decontaminate a portion of the facility so it could be deleted from the license and released for unrestricted use. GA's decontamination plan consists of several phases of activities (Phases I, II, and III) which have been approved by NRC.1 At present, GA has completed the decontamination efforts for Phases I, II, and III and NRC's contractor, Oak Ridge Associated Universities, has completed the final confirmatory surveys. By letter dated March 4,1988, GA applied for license amendment to authorize the release for unrestricted use of approximately 277 areas of land decontaminated under the Phases I, II, and III program. Following is the staff's evaluation of GA's decommissioning effort for the release of land and property for unrestricted use.

EVALUATION OF GA'S DECONTAMINATION EFFORT A. Description of GA's Decontamination Activities Decontamination of Phase I activities was completed in late 1985 and consisted of areas encompassing the Solar Evaporation Pond, surroundings of the former Waste Processing Facility and Incineration Pad, a previous burial sito for contaminated asphalt, the hillside and canyon below the waste handling facilities, and undeveloped land surrounding the waste processing facilities (see Fig. 1).

In December 1985, a confirmatory survey performed by NRC's contractor, Oak Ridge Associated Universities (0RAU), identified small isolated areas in need of addicional cleanup.2 GA has made further efforts to clean these areas to acceptable levels (discussed below). During July and August 1987, GA conducted decommissioning activities of the Phase II areas which included the former Waste Processing Facility and the Incineration Pad. In September 1987, ORAU conducted a radiological confirmatory survey of the Phase II areas, which confirmed that GA has met the NRC's criteria for unrestricted release of the Phase II areas. The areas of Phases I and II occupy about 80 acres of the GA e806300102g$0 MOM 34 PDR PDR C

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FIGURE 1 Areas of Different Decomnissioning Phases and E:Aluded Areas

General Atomics (GA) site. The Phase III decontamination activities consist of approximately 215 acres (see Fig. 1) of primarily undeveloped land surrounding the main GA plant site. GA records and individuals familiar with the facility history indicate that radioactive material uses in the Phase III area have been limited to a few small locations. Portions of the Phase III area (B1, 82, and 83 as shown in Fig. 1) have been excluded and will be decontaminated at a later date. B1 is approximately 15 acres of steep, rough hillside located generally west and north of GA's TRIGA Reactor facility; B2 is a small sewage pump station; and B3 is about 3 acres consisting of an abandoned city sewage treatment facility (also known as Callan Ponds). By letter dated March 4, 1988, GA requested that the areas of Phases I, II, and III (excluding B1, B2, and 83) be released for unrestricted use. Areas B1 and 82 are immediately adjacent to GA's main site, therefore, access for purposes of decontamination is assured. In the case of area 83, which is surrounded by non-GA land, GA assures access by means of a ground lease.3 Until it is released for unrestricted use, GA will control access to B3 (Callan Ponds). The ORAU confirmatory survey findings of the Phase III areas (excluding B1, 82, and B3) indicate that the areas have been decontaminated to acceptable levels for unrestricted release.

B. Radiological Characteristics of Contamination and Potential Doses to Persons From GA's past operations and measurements conducted by GA and ORAU, the potential radiological contaminants are enriched uranium, thorium, and longer half-life fission and activation products, such as Co-60, Cs-137, and Sr-90.

These radionuclides emit alpha, gamma, and beta radiation. The potential radiation doses to persons using the land, buildings, and equipment are from inhalation, direct gamma radiation, and ingestion pathways. The GA site is located within a semi-arid r:gion zoned for light industry and research and development. The area is not likely to be used for agriculture. In addition, the topography and cost of the land make it highly unlikely to be used for agricultural purposes in the future. There is no potable water on the site or its environs. A brackish water table is approximately 275-300 ft deep at about the same level as the nearby salt water backwater and marshes. Thereforc, the pathway for ingestion of any residual contamination via food or water is judged to be unrealistic.

C. Criteria for Unrestricted Release

1. Facility & Equipment The NRC has established guidelines for the decontamination of facilities and equipment prior to release for unrestricted use. The guidelines provide acceptable surface contamination levels for byproduct, source, or special nuclear materials. The guidelines which are applicable to GA's decontamination activities for facilities and equipment are shown in Table 1.

TABLE I ACCEPTABLE SURFACE CONTAMINATION LEVELS MAX 1i10Mbdf REMOVABLEbef NUCL10[5 d AVERAGEbcf U-nat. U-235, U.238, and 15,000 den /100 cm2 1,000 den ./100 (=2 4

associated decay products 5,000 dpa a/IDO cm2 6 4

1ransuranics. Ra-226. Ra-228. 300 dps/100 cm2 20 dpe/100.cm2 th-230. Ih-228, pa-231, 100 dpm/100 cm2 ,

l Ac-227. 1-125. 1-129 Th-nat. Th-232, Sr-90, 3000 dps/100 cm2 200 dpe/100 cm2 Ra-223, Ra-224. U-232, 1-126, 1000 dpe/100 cm2

l-131. 1-133 f Beta-ganea cimitters (nuclides

! with decay codes other than 15,000,dpm sy/100 cm2 1000 dpa 8v/100 cm2 alpha cialssion or <oontaneous 5000 dpm sy/100 cm2 fissinn) catept Sr-90 and .

l ulhers noted abave.

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  • there surface contamination by both alpha- and beta-gasuna-emitting nuclides exists, the limits established for alpha- and beta nuct ". des should apply independently.

.I b As used in this table, dpm (dististegrat.ons per minute) means the rate of emission by radioactive saterial as determined by correcting the l counts per minute observed by an appropriate detector for background, ef ficiency, and geometric factors associated with the instrume 4

i For objects of less surface area, the avt rage CMeasurements of average contaminant should not be averaged over more than 1 square meter. .

should be derived for each such object.

] d ihe maximum contamination level applies to an area of not more than 100 c.2, 2 of surface area should be determined by wiping that area with dry filter or sof t f

'The anount of removable radioactive material per 100 cm absorb.nt paper, applying moderate pressure, and assessing the amount of radioactive asterial on the wipe with an appropriate instruaien known efficiency. When removable contamination on objects of less surface area is determined, the pertinent levels should be reduced proportionally and the entire surface should be wiped.

I The average and maximum radiation levels associated with surface contamination resulting from beta-gamma emitters. should not I cm and 1.0 mrad /hr at I cm, respectively, measured through not more than 7 milligrams per square centimeter of 0.2 mrad /hr at ~

total absorber. .

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General-Atomics (GA) 2. Contaminated Soil The NRC issued a Branch Technical Position (BTP) setting forth soil decontamination limits for unrestrictive release of land contaminated with uraiiium and thorium.4 These soil limits in the BTP which had been concurred by the U. S.

Environmental Protection Agency 5 shall be aoplied to the GA site.

However, at the GA site, there are otro radionuclide contaminants consisting of fission products or acti.- lon products. Using the dose limits established in Option 1 of the Branch Technical Position, staff has provided GA with cleanup criteria for all radionuclides involved. The Option 1 criteria for unrestricted release of land are shown in Table 2.

The target criteria used for open land cleanijp can be compared with other existing criteria or guidance in Table 2. The NRC requires the licensee to clean contaminated land to below the target criteria. Any alternative higher than the target criteria is not acceptable without a detailed cost-benefit consideration or unless unusual circumstances exist.

D. Compliance With t'.he Target Criteria Given below are the target criteria for direct radiation and inhalation pathways. Both criteria must be met prior to release of the area for unrestricted use.

1. Direct Radiatio)

The direct radiation level of 10 pR/hr above background is intended as a target criterion for open land cleanup. The dose rate shall be measured using calibrated micro-R meters accurate enough to

differentiate background.

To demonstrate compliance with the direct radiation limit, the affected areas will be dhided into grids about 30' x 30' for surveying purposes. In order to meet the target criterion, the

, following condition has to be met:

External radiation (gamma dose rate in air 1 meter above ground level) shall not exceed 10 pR/hr above background for a diffuse source area (a contaminated area greater than 30' x 30') and shall not exceed 20 pR/hr above backgrounf. for a discrete area (a contaminated area less than 30' x 30').

Land surrounding the affected areas, but within the boundaries of the principal area for release to unrestricted use, shall be surveyed for external radiation by a "walkover" survey at 30-foot intervals.

General Atomics (GA) Table 2 Criteria for soil decontamination at the GA site Exposure ,

Target Other existing pathway -

criteria criteria or guidance External Radiation 10 pR/hr 20 pR/hr indoor (b) -EPA cleanup (whole body) (35 mrem /yr) a) standard for Inactive Uranium (13 mrem /yr) Processing Site; 500 mrem /yr-10 CFR 20; 170 mrem /yr-FRC Guicance; 400-900 mrem /yr-Sur-geon General's Guidance for in-door exposure; 25 mrem /yr 40CFR190and40CFR61{,)

Inhalation of Partic- 1 mrad /yr(ig) 1500 mrem /yr-10 CFR 20(d) ulates (lung, bone) (20 mrem /yr) 25 mrem /yr-40 CFR 190; 75 aem/yr-40 CFR 61 3 mrad /yr (bone) 1 mrad /yr (lung), 3 mrad (bone)

(60 mrem /yr) EPA Transuranic Guidance (a) This value does not include background, the 35 mrem /yr (realistic dose) includes a shielding factor of 0.3 from a residential home with residence time of 80 percent. For commercial use, the gamma doie will be reduced to about 13 mrem /yr based on 30 percent occupancy time.

(b) 40 CFR Part 192 - Federal Register, April 22, 1980.

(c) Based on quality factor of 20 as originally intended for alpha emitted from the transuranic elements.

(d) Designated in or derived from 10 CFR 20.

(e) Clean Air Act - Federal Register, February 5,1985.

The above technique can be used to demonstrate compliance for soil contaminated at the surface. For subsurface contamination at depth, the limiting soil concentrations equivalent to 10 pR/hr for Co-60 and Cs-137 are 8 pCi/g and 15 oCi/g, respectively. These limiting concentrations are provided in case there is subsurface burial and the 10 pR/hr limit cannot be demonstrated using micro-R meters.

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General Atomics (GA) 2. Inhalation of_Particulates Table 3 summaizes the derived limit ng soil concentration for each i

inhaled radionuclide. It is noted that Table 3 soil limits are for individual radionuclides. If a mixture.of these radionuclides exists in soil, the following formula will be applied to show compliance:

the sum of Ci/Lig 1 where Ci = the average soil concentration of radionuclide i, and Li = the derived maximum soil limit for radionuclide i (from Table 3).

Table 3 Derived limiting concentration for inhaled radionuclides Concentration limit above Radionuclide background (pCi/g)

Enriched Uranium 30 Thorium (Natural) 10 Co-60 1.2 x 10 4 Cs-137 9.6 x 10 5 Sr-90 1.0 x 10 3 To demonstrate compliance with the limits established for the inhalation pathway, the following has to be met:

Representative soil samples shall be collected at each grid (30' x 30')

from the first inch (1") of soil and analyzed for the various isotopes.

To demonstrate compliance with the target criteria given in Table 3, isotope concentrations can be averages of any four adjacent grids.

The derived concentrations in Table 3 also apply to subsurface soil contamina-tion. Therefore, subsurface soil samples will also be collected. After decon-tamination has resulted in the above condition being met for surface soil, compliance with the subsurface requirement will be demonstrated by analyzing a random 5 percent of the subsurface soil samples.

If a subsurface random sample exceeds the limit, the four adjacent 30' x 30' subsurface samples will be analyzed and the results averaged. If the average is below the limits, the inhalation dose target criteria will have been met.

If the averaged result is above the limits, further decontamination will be conducted.

General Atomics (GA) l In the affected areas where it can be demonstrated with adequate data that meeting the 10 pR/hr above background limit will also meet the inhalation dose limit, direct radiation measurements will be used to demonstrate compliance for both pathways. In this case, soil samples of 5 percent of the grids will be randomly collected and analyzed to confirm compliance.

E. ORAU's Confirmatory Survey After each phase of the decommissioning activities was completed, NRC's Regional Office (Region V) contracted ORAU to perform radiological surveys to certify that the areas had been cleaned to below the NRC criteria prior to the release for unrestricted use.

1. Phase I Confirmatory Survey In November 1985, GA submitted a report documenting that the Phase I activities were completed. In December 1985, ORAU performed a confirmatory survey which consisted of direct gamma measurements and soil sampling and analysis of radionuclides under a grid system in the affected areas. The soil sampling included surface and subsurface sampling. In addition, background and baseline measurements were made in GA's surrounding areas. The survey report 2 identified 49 small isolated areas of residual contamination in the vicinity of the previous waste storage pad, evaporation ponds, and incinerator. Although these are small areas, NRC required GA to further cleanup these areas to meet the as low as reasonably achievable (ALARA) requirement. Subsequently, GA made further efforts to cleanup these areas and in March 1987, a followup confirmatory survey was conducted by ORAU certifying that the Phase I areas were acceptable for unrestricted release (see Appendix).
2. Phase II Confirmatory Survey In August 1987, GA completed the Phase II activities and submitted a report to the NRC. In September 1987, ORAU conducted a confirmatory survey of the Phase II areas which consisted of gamma, beta gamma, and alpha scans; exposure rate measurements, measurements of total and removable surface contamination; and measurements of radionuclide concentrations in surface and subsurface soils.

The survey identified several small areas of residual contamination, which were pr*:Maptly recleaned by GA and resurveyed by ORAU. The enclosed ORAU Report (Appendix) concludes that the Phase II areas have been decontaminated properly to meet NRC release criteria.

!. Phase III Confirmatory Survey By letter dated August 12, 1987, GA informed NRC that the Phase III decommissioning was completed except for the B1, 82, and B3 areas and requested a confirmatory survey. In September 1987, ORAU conducted a confirmatory survey of the Phase III areas consisting of primarily

General Atomics (GA) undeveloped land surrounding the GA site and included the shipping and receiving area of Building 5. An ORAU Report was issued in February 1988 certifying that the' Phase III areas had been decontaminated to acceptable levels for unrestricted release.

Copies of the ORAU confirmatory survey reports on the Phases I, II, and III are enclosed in the Appendix.

F. Environmental Impact on Released Buildings and Land ihe licensee has decontaminated buildings and equipment below the NRC guidelines for release for unrestricted use. For open land cleanup, the licensee has made reasonable effort to clean the Phases I, II, and III areas well below NRC's established criteria. It is recognized that the dose limits (target criteria) in Option 1 of the BTP apply to the decontamination of large areas. The licensee has generally used a small gridding system (i.e.,

30' x 30') to facilitate detailed soil cleanup to ensure doses from residual contamination are well below the target criteria. In addition, the staff had used conservative parameters to derive the soil concentration limits to provide reasonable assurance that the target criteria will be met without additional measurements, and the land can be released immediately once the soil concentra-tion limits are met.

The derived soil Concentration limits provide no allowance for soil dilution or backfill which may be applied in future potential land use. Therefore, the staff believes that the realistic doses to persons from the release of portions of the GA property are well below the NRC's target criteria for unrestricted use, and the environmental impacts are negligible.

G. Environmental Impact from GA's Future Operations Although cleaning portions of the GA site should eventually reduce the existing impact to the general public, the reduction of the site's boundaries may have more impact to the general public living closer to the site. In June 1983, NRC issued an Environmental Impact Appraisa18 (EIA) in connection with GA's license renewal. In the EIA, NRC conducted a dose assessment for the continued operation of the GA facilities. Most of the offsite environmental impact is from the radioactive effluent releases at the GA TRIGA reactor and fuel fabrication plant at Sorrento Valley (see Fig. 1). At present, the nearest residences are about 0.75 mile northwest of the Sorrento Valley site and 1.15 miles north-northwest of the main site. The annual dose from GA's routine operation is about 0.26 mrem to the whole-body; 0.74 mrerr and 0.58 mrem to the bone and lung, respectively. Reduction of GA's site boundary will affect the dose calculation substantially, particularly the site boundary reduction around the TRIGA reactor. The staff, therefore, evaluated the atmospheric dispersion factors at various distances (EIA, Appendix A). Depending on the future loca-tion of rssidences, the atmospheric dispersion factors (X/Q) could be increased by a factor of 10. However, because of the minute releases from the GA plant, even an increase of the above doses by a factor of 10 would not result in annual doses exceeding the EPA's Clean Air Act environmental radiation standards (25 mrem /yr to the whole body and 75 mrem /yr to other organs).7

L General Atomics (GA) t Staff also reviewed potential accidents and the effects of the change of boundaries. In the EIA, staff had used a distance of 600 ft as the closest distance for the dose assessment for the fuel fabrication plant's criticality accident. The staff assumed a worker at the manufacturing plant (600 ft from the accident site) could be exposed during the accident. This individual (as a surrogate for the nearest resident) was also assumed to be the nearest member of the public to be potentially affected by the accident. The whole body dose was calculated to be 0.2 rem and the thyroid dose to be 0.86 rem. Staff considers that not only would an accidental criticality event be extremely unlikely, but any attendant consequences would also be acceptably small. GA's current site boundary reduction would not affect the fuel fabrication plant at the Sorrento Valley site (see Fig. 1). However, it has some effect on the site boundary at the TRIGA reactor site. GA may have to modify the technical specification in

.the TRIGA reactor operation to provide means for mitigating adverse effects for potential accidents which are considered to be highly unlikely. In addition, GA may have to provide-an easement area west of TRIGA extending to the B-1 area which is presently excluded from unrestricted release. The current land release

  • frem this license amendment should not affect future requirements. Based on the above assessment, release of portions of their land for unrestricted use is not expected to have a significant impact to the general public. ,

H. Conclusion i Staff has evaluated GA's decontamination activities conducted under Phases I, II, and III and concludes that GA has decontaminated these areas well below NRC's target criteria. Any contaminated materials or soil generated have been properly disposed by transporting to a licensed burial site. Therefore, it is recommended that the approximately 277 acres as described in GA's letter dated March 4, 1988, be released for unrestricted use.  !

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Edward Y. S um a h<

['b f Urarium Fuel >Section '

fW Fuel Cycle Safety Branch Division of Industrial and Medical Nuclear Safety 7

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0,f'f 4.0% j./* -

Jerry J. Swif t, Section Leader ')h RO'*d h adu t Uranium Fuel Section o . Th"Qy /W '

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OFFICIAL RECORD COPY

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General Atomics (GA) References .

1. Evaluation of GA's Proposed Decontamination Plan - Occket No.70-734, November,26, 1985.
2. Confirmatory Survey of Phase I Decommissioning, Former Waste Processing Facility, GA Technologies, San Diego, California - J.D. Berger, Oak Ridge Associated Universities, July 1986.

3 Letter from GA (Keith Asmussen) to NRC (L.C. Rouse) March 4, 1988, Docket No.70-734.

4. Disposal or Onsite Storage of Thorium or Uranium Wastes from Past Operations - Nuclear Regulatory Commission, Federal Register, Vol. 46, No.

205, 52061, October 23, 1981.

5. Letter from Paul C. Cahill (U.S. Environmental Protection Agency) to Ralph G. Page (NRC) dated March 31, 1982.
6. Environmer.tal Impact Appraisal Related to Special Nuclear Materials License No. SNM-696 - GA Technologies, Inc. (GA) Fuel Fabrication Facility, Docket No.70-734, U.S. Nuclear Regulatory Commission, June 1983, NUREG-0994.
7. National Emission Standard for Radionuclide Emission from Facilities Licensed by the Nuclear Regulatory Commission (NRC) and Federal Facilities Not Covered by Subpart H - U.S. Environmental Protection Agency - Fed.

Register 50FR5195 February 5, 1985.

Gonoral Atomics (GA) , APPEN0lx ORAU Confirmatory Survey Reports of Phases I, 11, and 111 Activities

OR AU 88,C.

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FOLLOW-UP Prepared by 18;?,,^$$ciat'd CONFIRMATORY SURVEY Prepared for U.S. Nuclear Qp So"E'i i!n s PHASE I DECOMMISSIONING Region V Office Sponsored by FORMER WASTE PROCESSING FACILITY Oivision of industrial and Medical Nuclear Safety GA TECHNOLOGIES SAN DIEGQ, CALIFORNIA P.R.COTTEN Radiological Site Assessment Program Manpower Education, Research, and Training Division FINAL REPORT MARCH 1988

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O R AUi8, C.129 FOLLOU-UP CONT:RMATORY SURVEY OF PRASE I DECOMMISSIONING FOR.WR WASTE PROCESSING FACILITY

. CA TECHNOLOGIES

. SAN DIEGO, CALIFORNIA Prepared by P.R. COTTEN Radiologic;al Site Assessment Program Manpower Education, Research, and Training Division Oak Ridge Associated Universities i Oak Ridge, TN 37831-0117 i

Project Staff J.D. Berger R.C. Rookard

R.D. Condra C.F. Weaver G.L. Murphy Prepared for Division of Industrial and Medical Nuclaar Safety U.S. Nuclear Regulatory Commission Region V Office Final Report March 1988 This report is based on work pe rf ormed under Interagency Agree me nt DOE No. 40-816-83 NRC Fin. No. A-9076 between the U.S. Nuclear Regulatory Commission ad the U.S . Department of Energy. Oak Ridge Associated Universities performs complementa ry work under contract number DE-AC05-760R00033 with r.h e U. S.

Department of Energy.

i TABLE OF CONTENTS Page List of Figures . ........................... l 11 List of Tables . ........................... iii Introduction . . ........................... 1 Procedures . .. ........................... 1 Results . . . ...... .....................,. 2 Summary . . . . . . . . . . . . . . ............. . . . . . 3 References . . . ........................... 17 Appendices .

Appendix At Major Sampling and Analytical Equipment Appendix B: Measurement and Analytical Procedures Appendix C: Decommissioning Guidelines for the CA Technologies Weste Processing Facility l

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LIST OF FfGURES Page FIGURE la Man of San Diego Area. Indicating the Location of the GA Technologies Facilities . . . . . . . . . . ,..... 4 FIGURI 2 -Area of GA Technologies Plant. Illustrating the Phase I Decommissioning Area . . . . ...........,... 5 FIGURE 3: Vaste Processing Facility Area. Indicating the Grid System Used for Survey Reference .... ............ 6 FIGURI 4: Locations Where December 1985 Survey Indicated Soil Concentrations Exceeding Guideline Levels. ........ 7 FIGURE 5: Sampling Locations - Phase I Followup. .......... 8 FIGURE 6: Locations of Measurement and Sampling Locations Alon Canyon Floor . . . . . . . . . . . . . . . . . . . .g the ... 9 FIGURI 7: Locations of Background Measurements and Baseline Soil Samples from the Vicinity of GA Technologies . ...... 10 4

11

L83T OF TABLES

?3?e TABLE lAt Background Radiation Levels .............. .. 11 TABLE 13: Baseline Radionuclide Concentrations in Soil . . . . . . . . 12 TABLE 2T Exposure Rates at Sampling Locations . . . . . . . . . . . . 13 TASLE 3: Radionuclide Concentrations in Soil From Remediated Areas. . 14 TABLE 4: Radionuclide Concentrations in Soil From the Canyon Floor. . 15 TABLE 5: Rt.dionuclide Concentrations in Composite Soil Samples. . . . 16 iii

FOLLOW-UP CONTfRMATORY SURVEY OF PHASE I DEC0KMIS$10NING FORMER UASTE PROCESSING TACILITY CA TECHNOLOGIES SAN DIEGO, CALITORNIA

. INTRODUCTION In aid 1984, CA Technologies, Inc. (CA) of San Diego, California, initiated Phase I decommissioning activities of the Forme r Waste Processing Facility (Figures 1-3). Phase I includes the Solar Evaporation Pond Area, the areas immediately surrounding the Former Uaste Processing Facility and Incinerator Pad, a previous burial site for contaminated asphalt, the hillside and canyon below the waste handling facilities, and undeveloped land surrounding the Waste Processing Facilities. During Decembe r 10-17, 1985 a confirmatory survey of Phase I remediation was performed by the Radiological Site Assessment Program of Oak Ridge Associated Universities (OR U). The survey identified 49 small isolated areas (Figure 4) of residual contamination; these ' areas were primarily east and north of the Waste Processing Facility, and in the vicinity of the former Solar Evaporation Ponds.I During 1987. GA Technologies performed additional remedial actions to remove contamination. identified by the December 1985 ORAU survey. A report, prepared by CA indicates that this remedial action was effective in reducing residual contamination to within the guidelines established for the site.2 At the request of the Nuclear Regulatory Commission's Region V Office, a followup survey of these reeleaned areas was pe rf ormed by ORAU during September 1987 This report describas the procedures and results of that survey.

PROCEDURES

1. The licensee's grid system was reestablished at JO ft (9.1 m) intervals to provide reference points f or measurements and sampling.

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2. A walkover surface gamma scan was conducted at 1-2 m intervals throughout :Me remediated area, using portable countrate instruments with NtI(T1) p .2 2 scintillation detectors and audible indicators. A scan of the canyr.

drainage area, southeast of the Waste Processing Facilities, was also p e r f o r me d'.

3. Exp'osure rates were measured at the surface and 1 m above the surface at seven locations (Figure 5), where additional remedial action had been performed. These locations represented those areas which were noted by the 1985 survey to have higher levels of contamination. Measurements were also performed at four locations in the Canyon (Figure 6).

4 Surface soil samples were collected at locations of exposure rate D

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measurements.

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5. Samples and data were returned to Oak Ridge, Tennessee for analyses and evaluation. Appendices A and B contain additional information regarding equipment and procedures. Results were compared to guidelines established for decommissioning of this facility (Appendix C).

RESUI.TS Walkover gamma scans did not identify any locations of significantly elevated direct radiation levels in the remediated area or along the canyon floor. Gamma exposure rates measured in these areas are presented in Tabla 2. In the remediated area these rates ranged f rom 16 to 23 uR/h at surface contact and from 15 to 18 uR/h at I a above the surface. Measurements along the canyon floor ranged f rom 15 to 18 uR/h at the surf ace and f rom 14 to 16 uR/h at i e above the surface. For comparsson, the background exposure rates in the vicinity of the GA Technologies f acility averages about 9.7 uR/h at 1 m above the surface (Table 1A). The guideline for decommissioning retquires that the average exposure rate te less than 10 uR/h above background, which would be a total of 19.7 J/h. All exposure levels measured at 1 m above the surface during this survey were less than 19.7 uR/h and theref ore this guideline is satisfied.

2

Tables 3 and 4 present the concentrations of ga tea emitting radionuclides.

measured in surf ace soil collected from the remediated and canyon floor stess.

Ranges of concentrations in these samp'.es were Co-60, <0.05 to 1.78 pC1/g; Cs-137, 0.28 to 11.9 pCi/g; Ra-226, 0.83 to 1.57 pCi/g; U-235, <0.23 to 1.69 pCi/g; U-238,

<0.78 to 3.45 'pci/g; Th-228, 1.03 to 9.57 pCi/g; Th-232, 0.98 to 7.46 pCi/g.

Concentrations of Sr-90 and isotopic uranium in two composite samples, representing the remediated area and canyon area, are listed in Table 5. The Sr-90 concentrations ne 0.32 and 2.20 pCi/g; the highest uranium levels are U-238, which are 3.29 and 4.42 pCi/g. On the basis of the U-234/U-238 ratios, it appears that the uranium is depleted in the U-235 and U-234 isotopes.

With exception ~of the total thorius (Th-228 and Th-232) concentration, in the sample f rom location 1055, all radionuclide levels were below the guideline values in Appendix C and most were in the range of baseline concentrations (see Table 15). The thorium concentration in sampla 1058 was 17.55 pCi/g, or 15.26 pCi/g above the average backgewnd level. This is slightly higher than the guideline value of 10 pCi/g above background. Surf ace scans in this area did not identify '

.<fe,;'icant)* elevated direct radiation levels, and sampling during the 1985 i su . indicaced that soils at L td intersections in the vicinity of this location were well within the guideline levels. Contamination at grid coordinate 7695N.

9550E is therefore an isolated small area, and averaging over adjacent soil will result in a concentration which satisfies the 10 pCL/g guideline.

SUMMARY

During September 1987, Oak Ridge Associated Universities performed a radiological survey of areas within the Phase 1 Decossissioning activities of CA Technologies in San Diego, California.

The survey included locations, which had

)

been remediated, following their identification by a December 1985 ORAU survey, and a section of canyon area in the drainage pathway f rom the Waste Processing p

Facility. Survey activities consisted of walkover gasaa scans, exposure rate l measurements, and soil sampling and analyses. Findings identified no areas exceeding the decommissioning guidelines, authorized by the Nuclear Regulatory Commission f or this site. Based on these results it is ORAU's opinion that the radiological data, as presented by the licensee, is adequate and accurate and that the radiological conditions satisfy the established guidelines for release for unrestricted use.

3

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l

TABLE 1A BACKCROUND RADIATION LEVELS CA TECHNOLOGIES

, SAN DIEGO, CALIFORNIA Camma Exposure Rates Gamma Exposure Rates Locationa . at I a Above the Surface at the Surface (pR/h) (ia/h) 1 7 8 2 8 8 3 7 7 4 10 10 5 13 15 6 ,13 15 RANCE 7 TO 13 7 TO 15 AVERAGE 9.7 10.5 aRefer to Figure 7.

11

TABLE IB BASELINE RADIONUCLIDE (X)NCENTRATi(NS IN S0lt GA TEOm0LOGIES SAN DIEGO, CALIF 0HNIA 6 4

Location 8 RadionuclIde Concentrations (pCl/g)

Co-60 Cs-137 Ra-226 U-235 U-238 Th(228 & 232) K-40 I <0.03 <0.02 0.59 1 0.14 b <0.17 I.6 i I.2 1.34 1 0.46 14.0 1 1.7 2 <0.05 0.16 1 0.11 0.5310.22 <0.20 3.6 1 1.5 1.98 1 0.86 25.0 1 3. 3 3 <0.04 <0.04 0.79 1 0.20 0.39 1 0.24 1.1 1 0.5 2.24 1 0.62 10.4 1 1.7 4 <0.08 <0.05 1.20 1 0.29 <0'.32 <1.l 3.06 1 0.79 29.0 t 3.4 5 <0.05 <0.05 1.23 1 0.22 0.69 1 0.55 1.3 1 0.6 3.20 1 0.00 24.5 t 2.7 6 <0.05 <0.05 0.65 1 0.16 <0.22 1.0 1 0.9 I.92 1 0.78 30.2 1 2.9 RANGE <0.03 to <0.08 <0.02 to <0.16 0.53 to I.23 <0.17 to 0.69 I.0 to I.6 1.34 to 3.20 13.4 to 30.2 N AVERAGE <0.05 <0.06 0.85 <0.33 1.5 2.29 22.2

  • Refer to Figure 7 b

uncertainties represent the 955 confidence levels, based only on counting statistics; additional laboratory uncertainties of 6 to 105 have not been propagated in these data.

TABLE 2 EXPOSURE RATES AT SAMPLING LOCATIONS PHASE I FOLL0tJ-UP GA TECHNOLOGIES

. SAN DIEGO, CALIFORNIA

~'

Grid Locationa Coordinate Exposure Rate (uR/h)

ID N E Contact I a Above Surface 100B 7160 9620 16 15 101B 7240 9646 16 15 102B 7532 9660 16 16 1035 7432 9645 20 18 1045 7611 9541 23 16 1055 7688 9550 20 15 1065, 7528 9544 20 16 270B Canyon Floor 18 16 ,

2715 Canyon Floor 16 15 272B Canyon Floor 15 14 2735 Canyon Floor 16 14 aRefer to Figures 5 and 6.

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13 1

TABLE 3 HAD10NCullDE CO M ENTR',TIONS IN S0lt FRON RENEDIATED AREAS PHASE I FOLLOW-UP GA TEO940LOGIES I

^

SAN DIEGO, CAlliORNIA 6 l i

! i Sample , Radionuclide Concentrailons (pCI/gl No. Locationa Co-60 Cs-137 Ra-226 U-235 U-238 Th-228 Th-232 1

i 1000 7 860N,%20E <0.05 0.28 1 0.12 1.17 1 0.25 <0.23 <0.8 1.59 1 0.42 1.61 1 0.47 1018 7290N,%46E I.78 1 0.27b 9.9710.44 1.17 1 0.40 <0.38 3.5 1 0.9 2.10 1 0.42 1.96 1 0.55 1020 7532N,%60E <0.08 1.78 1 0.19 1.50 1 0.33 <0.32 <0.9 3.9510.48 2.03 1 0.70 1058 74 32N,%45E 0.52 1 0.15 2.9212.51 1.30 1 0.23 <0.28 <0.8 2.76 1 0.45 f.% 1 0.55

! 1048 76tlN,954tE <0.06 1.52 1 0.17 1.57 1 0.25 <0.26 3.0 1 0.7 1.62 1 0.48 2.06 1 0.50

  • - 1056 7688N,9550E <0.06 0.3210.14 I.07 1 0.32 1.69 1 0.86 <l.5 9.57 1 0.88 7.46 i O.87 1068 7528N,9544E 1.5010.28 11.85 1 0.50 0.83 1 0.33 <0.31 <0.9 1.26 1 0.48 1.40 1 0.57 mRefer to Figure 5 b uncertaintles represent the 95S confidence levels based 5 ty on comting statistics; additional laboratory scortainties of 6 to 101 have not been propagated lato these data.

4 l

l TABLE 4 4

RADIONCULIDE 'DNCENTRATIONS IN SOll. FRON THE CANYON FLOOR PHASE I FOLL01s4P CA TEONOLOGIES I SAN DIEGO, CALIF 0HNIA 3 Sample

  • Radlonuclide Concentrations (pCl/g)

No. Cc-6C Cs-137 Ra-226 W235 U-238 Th-228 Th-232 2700 0.15 1 0.IO b 0.97 1 0.16 1.0 1 0.2 0.57 1 0.12 1.7 1 0.6 3.62 1 0.44 2.00 1 0.57 2710 0.18 1 0.20 0.68 1 0.15 1.4 1 0.3 0.27 1 0.14 <l.0 1.03 1 0.50 0.98 1 0.37 2720 <0.05 0.15 1 0.09 I.4 1 0.3 0.20 1 0.06 2.4 1 0.67 1.50 1 0.28 1.50 1 0.53 2738 0.17 1 0.12 1. 3 1 0.2 1.3 1 0.2 0.41 1 0.13 0.94 i 1.7 1.64 1 0.39 1.6010.47  ;

9 W

u i

aRefer to Figure 6 b

l uncertainties represent the 955 confidence levels based only on <xm4 ting statistics; additional laboratory incertaintles of 6 to 105 have not been propagated lato these data, i

1

Ta8LE 5 AADIONUCLICE CONCENTRATIONS IN CC@01lTE Soll SAWLES PwASE I FOLLCw s9

. GA TEC* 0LOGIES

- SAN Ol EG0, CAL I FORN I A Sample Redlonuellde Concentrations (pCI /c) 10 Sr-90 U-234 L) 235 U-238 Composite Aa 0.32 2 0.12 D 1.85 2 0.26 0.13 1 0.08 4.42 2 0.40 Composite B 2.20 t 0.30 1.74 2 0.24 0.07 1 0.06 3.29 2 0.34 a$ ample Identification numbers:

Composite A (2708; 2718; 27283 2738)

Compoelte 8: (729(N, 9646E; 7432N, 9645E; 7611N, 9541E; 7828N, 9544E) buncertaintles represent the 955 confidt'ce levels, based only on counting statistics; additional lacoratory mcortaintles of 2 6 to 105 u 5 not been props 9ated into these data.

e l

16 i

1

REFERENCES

1. "Confirmatory Survey of Phase I Decommissioning Former flaste Processing Facility," CA Technologies, San Diego, California, Oak Ridge Associated Universi. ties, July 1986.
2. Letter ,f rom K.E. Asmussen (CA Technologies Inc.) to R. R. Thomas (U.S. Nuclea r Regulatory Commission, Region V), Reference "License SNM-696, Docket 70-1734" August 12, 1987.

4 17 1

=O 4

APPENDIX A PLIM AND ANALYTICAL EQUIPMENT h

1 1

APPEND!X A MAJOR SAMPLING AND ANALYTICAL EQUIPMENT The dispiay or description of a specific product is not to be construed as an endorsement of that product or its manufacturer by the authors or their employer.

A. Direct Radiation Measurements

~

Eber1ine '1ASCAL" Portable Ratemeter-Scaler Model PRS-1 (Eberline, Sante Fe, NM)

Eberline PRM-6 Portable Ratemeter (Eberline, Sante Fe, NM)

Victoreen NaI Scintillation Detector Model 489-55 (Victoreen, Cleveland, OH)

Reuter-Stokes Pressurized Ionization Chamber Model RSS-111 (Reuter-Stokes, Cleveland, OH)

8. La.boratory Analyses Automatic low-background Alpha-Beta Counter Model LBS110-2080 (Tennelee, Inc., Oak Ridge, TN)

High-Purity Germanium Detector Model CMX-23195-S, 23% efficiency (EG&G ORTEC, Oak Ridge, TN)

Used in conjunction with:

Lead Shield, G-16 (Gamma Products Inc., Palos Hills, IL)

High Purity Germanium Coaxial Well Latector Model GwL-110210-PWS-S, 23% Efficiency (EGGG ORTEC, Oak Ridge, TN)

Used in conjunction with:

Lead Shield Model C-16

( Applied Physical Technology, Atlanta, GA)

High Purity Germanium Detector Model IGC25, 25% Efficiency (Princeton Gamma-Tech, Princeton, NJ)

A-1

- , - , - , - - - , + .- , - -

Used in conjunction with:

Lead Shield (Nuclear Data, Schaumburg, IL)

!!ultichannel Analyzer ND-66/N0-680 System (Nuclear Data Inc., Schaumburg, IL)

Alpha Spectrometry System Tennalec Electronics (Tennelec, Oak Ridge, TN)

Surf ace Barrier Detectors (EG&G ORTEC, Oak Ridge, TN)

Multichannel Analyzer Model ND-66 (Nuclear Data, Schaumburg, IL)

I r

d l

A-2 i

m-

9 e

4 4 -

9 APPENDIX B MEASUREMENT AND ANALYTICAL PROCEDURES l

l l

i l

l l _.. _ _

APPENDIX 3 Measurement and Analytical Procedures Camma Surface Scans Walkover surf ace ~ scans were performed at approximately 1-2 m intervals using Eberline Model PRM-6 portable ratemeters with Victoreen Model 489-55 gamma scintillation probes containing 3.2 cm X 3.8 cm NaI(T1) scintillation crystals.

Relative count rates were monitored using earphones and increased rates above the ambient background levels were noted.

Exposure Rate Measurements Measurements of gamma e,xposure rates were performed using an Eberline PAM-6 portable ratemeter with a Victoreen Model 489-55 gamma scintillation probe containing a 3.2 cm x 3.8 cm NaI(T1) scintillation crystal. Count rates were converted to exposure rates (uR/h) by cross-calibrating with a Reuter Stokes model RSS-111 pressurized ionization chamber.

Soil Sample Analysis Camma Spectroscopy Soil samples were dried, mixed, and a portion sealed in 0.5-liter Marinelli i- beaker. The quantity placed in the beaker was chosen to reproduce the calibrated counting geomet ry and typically ranged from 600 to 800 g of soil. Net soil l

weights were determined and the samples counted using intrinsic germanium and Ce(Li) detectors coupled to a Nuclear Data Model ND-680 pulse height analyzer system. Background _ and Compton stripping, peak search, peak identification, and concentration calculations were performed using the computer capabilities

. inherent in the analyzer system. Ene rgy peaks used for determination of radionuclides of concern were:

B-1

Co 1.173 MeV Cs-137 - 0.662 MeV Ra-226 - 0.609 MeV from B1-214 (secular equilibrium assumed)

U-235- - 0.144 MeV U-238 - 0.094 MeV f rom Th-234 (secular equilibrium assumed)

- Th-228 - 0.583 MeV from T1-209 (secular equilibrium assumed)

Th-232 - 0.911 MeV from Ac-228 (secular equilibrium assumed)

The spectra were also reviewed for the presence of other radionuclides.

Strontium-90 Analysis ,

Aliquots of soil were dissolved by pyrosulfate fusion and the strontium precipitated as a sulfate. Successive treatments with EDTA preferentially removed lead and excess calcium and returned the strontius to solution. Ferric and other insoluble hydroxides was precipitated at a pH of 12 to 14 Strontium was reprecipitated as a sulfate. Barium was removed as a chromate using DTPA.

The final precipate of strontium carbonate was counted using a low-background Tennelee alpha-beta proportional counter.

Alpha Spectrometry for Isotopic Uranium Aliquots of soil were dissolved by pyrosulf ate fusion and precipitated by barius sulfate. The barium sulf ate precipitate was redissolved and uranium was separated by liquid-liquid extraction. The uranium was then precipitated with a cerium fluoride carrier and counted using surface barrier detectors (ORTEC),

alpha spectrometers (Tennelec), and an ND-66 Multichannel Analyzer (Nuclear Data).

. Uncertainties and Detection Limits The uncertainties associated with the analytical data presented in the i tables of this report, represent the 95% confidence levels for that data. These uncertainties were calculated based on both the gross sample count levels and the associated background count levels. When the net sample count was less than the l 95: itacistical deviation of the background count, the sample concentration was l reported as less than the detection capability of the measurement procedure.

t B-2 1

Because of variations in background levels, sample volumes or weights, ;

measurement efficiencies, and Compton contributions f rom other radionuclides in samples, the detection limits differ from sample to sample and instrument to ins t rume nt. , Additional uncertainties of 6 to 10%, associated with sampling and laboratory procedures, have not been propagated into the data presented in this report.

Calibration and Ouality Assurance Laboratory and field survey procedures are documented in the following manuals, developed specifically for the Oak Ridge Associated Universities' Radiological Site Assessment Program: "Survey Pro,;edures Manual," Revision 3, May 1987; "Laboratory Procedures Manual", Revision 3, May 1987 and "Quality Assurance Manual", Revision 1, June 1987.

With the exception of the measurements conducted with portable gamma scintillation survey meters, ins t rume nt s were calibrated with' NBS-traceable standards. The calibration procedures for the portable gamma ins t rume nts are performed by comparison with an NBS calibrated pressurized ionization chamber.

Quality control procedures on all instruments included daily background and check-source measurements to confirm equipment operation within acceptable statistical fluctuations. The ORAU laboratory participates in the EPA and EML Quality Assurance Programs.

B-3

9 4 .

APPENDIX C DECOMMISSIONING CUIDELINES FOR THE CA TECHNO,LOGIES WASTE PROCESSING FACILITY l

l t

4

APPENDZX C Deconnissioning Guidelines for the CA Technologica Vaste Processing Facility Target criteria for unrestricted release of the GA Technologies' Uaste Processing Facility and surrounding areas are presented in the licensee's final report and are as follows:

External Radiation The gamma exposure rate at 1 m above the ground surf ace shall not exec _d 10 uR/h above background f> c an area of greater than 30 ft (9.1 m) : 30 ft (9.L m) and shall not exceed 20 uR/h above background foranydiscretearea(i.e. less than 30 ft (9.1m)x30ft9.1m)).

Inhalation and Ingestion Concentrations of radionuclides in soil shall be such that inhalation and ingestion are not expected to result in annual dose equivalents exceeding 20 area to the lung or 60 mram to the bone.

Limiting soil concentrations were derived to satisfy these external and internal target criteria. The concentration limits are presented in the following Table.

Radionuclide Concentration Limit Above Background (pCi/g)

Depleted Uranium 35 Enriched Ur,,anium 30 l

Thorium (Natural) 10 l Co-40 8

, Cs-137 15 3

Sr-90 1.8 x 10 Where more than one radionuclide is present, the sum of the ratios of the individual radionuclide concentrations to their respective concentration limits shall not exceed 1.

C-1 l

ORAU 88,C

~

0) .

l Prepared by Oak Ridge Associated Universities CONFIRMATORY SURVEY Prepared for U.S. Nuclear Qf So"mi'i f!n, PHASE 11 DECOMMISSIONING Region V Office Sponsored by Division of FORMER WASTE PROCESSING FACILITY Industrial and Medical Nuclear Safety .

GA TECHNOLOGIES SAN DIEGO, CALIFORNIA P. R. C OTTEN l

l Radiological Site Assessment Program Manpower Education, Research, and Training Division FINAL REPORT MARCH 1988 l ErQ#NM ww w \c__

ys-m \ \-~

@ k'

CONFfRMATORY SURVEY OF PRASE II DECOMMISSIONING FORMER WASTE PROCESSING FACILITY GA TECHNOLOGIES SAN DIEGO, CALIFORNIA d '

Prepared by P.R. COTTEN Radiological Site Assessment Program Manpower Education, Research, and Training Division Oak Ridge Associated Universities Oak Ridge, TN 37831-0117 Project Staff J.D. B,erger R.C. Rookard R.D. Condra T.J. Sowell D.A. Gibson C.F. Weaver G.L. Murphy Prepared for Division of Industrial and Medical Nuclear Safety U.S. Nuclear Regulatory Commission Region V Office Final Report March 1988 This report is based on work performed under Interagency Agreement DOE No. 40-816-83 KRC Fin. No. A-9076 between the U.S. Nuclear Regulatory Commission and the U.S. Department of Energy. Oak Ridge Associated Universities performs complementary work under contract number OE-AC05-760R00033 with the U. S.

Department of Energy.

i 4

<-.a --. - - - . . . . - . , ,

TABLE OF CONTENTS Page List of Figures . ...........................

, 11 List of Tables .. .......................... iii

~

Introduction and Site History . . .. . . .. . . . . . . ....... 1 Site Description ........................... 2 Procedares . . . .... ....................... 2 Results . . . .. . ........................... 6 Comparison of Survey Results with Guidelines . . . . . . .,. . . . . , 9 Summary . . . . . ............ .. .. . . . . ....... 10 References . . .. .......................... 45 Appendices Appendix A: Major Sampling and Analytical Equipment .

Appendix B: Heasurement and Analytical Procedures Arpendix C: Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Licenses for Byproduct, Source, or Special Nucicar Material Appendix D: Decommissioning Guidelines for the CA Technologies Waste Processing Facilities e

i

t LIST OF FIGURES Page FIGURE 1: Map,of San Diego Area, Indicating the Location of the CA Technologies Facilities . ..... . . . . . . . . . 11 FIGURE 2: -GA Technologies Plant Layout .............. 12 FIGURE 3: Area of CA Technologies Plant, Included in Phase II Decommissioning. .................... 13 FIGURE 4: Phase II Decommissioning Areas of the Former Vaste Processing Facility. . .............. . . . 14 FIGURE 5: By-Products Storage Building Layout, Indicating the Reference Grid System and Locations of Contamination Measurements on the Floor and Lower Walls. . . . . . . . 15 FIGURE 6: Ca' rage / Office Building Layout, Indicating the Reference and System and Locations of Contamination Measurements on the Floor and Lower Walls . . . . . . . . . . . . . . 16 FIGURE 7: Measurement Locations on Other Surfaces in the By-Products Storage Beilding . . . . . .. . . . . . . . 17 FIGURE 81 Measurement Locations on Other Surfaces in the Garage / office Builing. . . . .............. 18 FIGURE 9: Phase II Area, Indicating the 30 ft Crid System Used for Survey Reference . ..... . . . . . . . . . . . . 19 FIGURE 10: Locations of Surf ace Contamination Measurements and Samples f rom Pads and Foundations. . ... . . . . . . . 20 FIGURE 11: Locations of Background Measurements and Baseline Soil Samples From the Vicinity of CA Technologies. . . . 21 FIGURE 12: Area on the By-Products Storage Building Floor, Identified By Surface Scans. . . . . . . . . . . . . . . 22 FIGURE 13: Locations of Elevated Direct Radiation, Identified by Surface Canna Scans. . . . . . ... . .. .. . . . . . 23 11 t -

LIST OF TABLES Page TABLE 1: Background Radiation Levels . . . . . . . .. . . . . . . . . . 24 TABLE 2: , faseline Radionuclide Concentrations in Soil . . . . . . . . 25 TABLE 3: Summary of Surf ace Contamination Measurements in the By-Products Storage and Carage/ Office Buildings . . . . . . . 26 TABLE 4: Exposure Rates Measured at 30 f t Grid Intervals . . . . . . . 27 TABLE 5: Exposure Rates Measured in the Incinerator Pad Area . . . . . 32 TABLE 6: Direct Radiation Levels Measured on Concrete Pads . . . . . . 33 TABLE 7: Exposure Rates Measured Af ter Remediacion of Areas Identified By Surface Scans. . . . . . . ................ 34 TABLE 8: Summary of Surf ace Contamination Measurements - Concrete Pads and Foundations. . . . . . . . . . . . . . . . . . . . . 35 TABLE 9: Radionuclide Concentrations in Surface' Soil Samples from 30 f t Grid Intervals. . .. . ................ 36 TABLE 10: Radionuclide Concentrations in Soil Samples Collected From the Incinerator Pad Area. . . ................ '

40 TABLE 11: Radionuclide Concentrations in Soil From Beneath Concrete Pads . .... ...... . ............. . . . 41 TAB'.E 12: Radionuclide Concentrations in Surface Soil Samples Collected Following Remediation of Areas Identified by Surface Scans. . 42 TABLE 13: Radionuclide Concentrations in Composite Soil . . . . . . . . 43 l

TABLE 14: Radionuclide Concentrations in Miscellaneous Samples. . . . . 44 f

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CONFfRMATORY SURVEY OF PHA52 ff DECOMMfSS10NING FORMER WA3TE PROCESSING FACILITY CA TECHNOLOGIES SAN DIEGO, CALIFORNIA INTRODUCTION AND SITE HISTORY In mid 1984, CA Technologies (GA) of San Diego, California, initiated decommissioning activities for th,e purpose of releasing portions of its facilities from Nuclear Regulatory Commission (NRC) licensing restrictions. Potential radiological contasinants at GA have been identified as enriched uranium, thorium, and longer half-life tission and activation products. Decommissioning of these facilities was separated into three phases. Phase I activities, which encompassed the Solar Evaporation Pond Area, the areas immediately surrounding the former W.ste Processing Facility and the Incinerator Pad, a previous burial site for contaminated asphalt, the hillside and canyon below the waste handling f acilities, and undeveloped land surrounding the waste processing facilities, were completed in late 1985. A confirmatory survey, performed by Oak Ridge Associated Universities in December 1985, identified small isolated areas in need of additional remedial action.I These areas have been addressed and discussed in a separate report. 2 Phase II consists of two major areas, the former Uaste Processing Facility and the Incinerator Ped. Phasa III consists of approximately 87 hectares (215 . acres) of primarily undeveloped land, surrounding the main GA Technologies plant site: survey findings of these areas have also been described in a separate report.3 During July and August 1987, GA conducted decommissioning activities of the Phase II facilities. A report of CA's findings, issued in August 1987, indicates that the post-decontamination radiological conditions satisfy the NRC guidelines for decommissioning."

At the request of the NRC, Region V Office, the Radiological Site Assessment Program of Oak Ridge Associated Universities (ORAU) conducted a radiological survey in September, 1987 to confirm the status of the Phase II area, relative to the NRC criteria for release for unrestricted use.

STTE DESCR!PT10N The GA Technologies facilities are located near the intersectic s of Interstate 5 and Genesee Road, approximately 20 km north of San Diego, CA (Figures 1, and 2). Site activities include a wide variety of research and development programs. The Phase II area, shown in Figure 3, is reached via the main ac ce s's road from the plant entrance gate. This area includes the Waste Processing Facility, consisting of the upper and lower storage yards, and the Incinerator Pad site (Figure 4). Much of this area is paved with asphalt; also included are a truck scale and several concrete pads or foundations. Some of the original paving and pads have been removed during the decontamination operations.

Located in the lower storage yard are two small buildings -

the By-Products Storage Building and the Garage / Office Building. The By-Products Storage Building was utilized for sample preparation and storage before and during decommissioning activities. The garage area of the other building was also ased for short-term storage of radioactive materials. The buildings are of simple construction; the By-Products Storage Building is cons t ructed of corrugated metal and the Garage / Office Building is of wood frame. Both buildings have concrete floors.

PROCEDURES A survey of the Phase II Decommissioning area was pe rf ormed by the Radiological Site Assessment Program of ORAU during September 9-28, 1987. This survey was in accordance with a survey plan submitted to the Region V Of fice of the NRC.5 Methofs and r eocedures utilized in the survey are presented in this section.

Objective,s l

The objectives of the survey were to confirm that the radiological condition of the Phase II area was as presented in the CA Technologies report and to provide information and data for evaluation of the site status, relative to VRC .aidelines for release for unrestricted use. Radiological information collected included gamma exposure rates; location of elevated direct radiation levels; concentrations of radionuclides in surf ace soil; and surf ace contamination levels.

2 l

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Procedures Document Review 1

The 11censee's final su^;ev repot; for the release of the Phase II area for unrestricted use and supporting docurents were reviewed by ORAU. Data presented in these, reports were compared to the established release guidelines.

9uilding Survey Gridding An alphanumeric 6 f t (1.8 m) x 6 ft (1.8 m) reference grid was established v the floor and lower walls (up to 6 f t (1.8) in each building. The grid baseline coordinates (A,0) were located in the southwest corner of each buildir.g.

Figures 5 and 6 shuw the building layouts and reference grid systems used for this survey. Measurements on the upper walls and ceilings were referenced to the floor grid designation.

Surface Scans Alpha, beta-gamma, and gassa scans were performed on floors, using an alpha / beta gas proportional floor monitor and NaI(T1) gamma scintillation detectors with audible indicating scaler /ratemeters. Scans of surfaces not accessible to the floor monitor, i.e., walls, ceilings, and overhead areas such as ledges, beams, piping, fixtures, and equipment were performed using portable ZnS alpha scintillation detectors and "Pancake" CM beta-gamma detectors. Areas l

indicating elevated radiation levels were marked for additional decontamination and for further measurements.

Measurement of Surf ace Contamination Levels ,

Approximately 20% of the grid blocks on the floor and lower walls of each building were randomly selected for surf ace contamination measurements. Blocks selected for these me asu re me nt s are indicated on Figures 5 and 6. In each grid

! block surveyed, direct measurements of alpha and beta-gamma contaminatien levels were systematically perf ormed at the center and four equidistant points, midway between the center and block corners. Smears for removable alpha and beta 3

1

contamination were performed at that location in each grid block, where the highest direct level was obtained.

Seven -locations on upper walls, ceilings, fixtures, and equipment were selected fqr single point measurements of total and removabis alpha and beta gamma contamiriation levels. These locations are identified on Figures 7 and 8. Direct measureme nt s and/or smears were also obtained from elevated locations identified by surf ace scans.

Outside Area Survey Gridding In the upper and lower storage yards the licensee's 10 f t (3.0 m) grid system was reestablished at 30 ft (9.1 m) intervals (Figure 9) and the licensee's 3 f t (0.9 m) grid was used on the Incinerator Pad.

Surface Scans Walkover gamma surface scans were conducted at t to 2m intervals in the upper and lower storage yard and on the Incinerator Pad, using portable NaI(Tl) gamma scinct11ation detectors and ratemeters. The exposed surf ace of the wall; separating the upper and lower storage yards, was scanned using a "Pancake" GM detector coupled to a ratemeter. Scans of concrete pads and some larger areas of asphalt paving were performed using the alpha / beta gas proportional floor monitor. Locations of elevated radiation identified by the scans, were brought to the licensee's attention and marked for further evaluation.

F.xposure Rate Measurements Exposure rate measurements were made at the surface and at 1 e above surface at 30 ft (9.1 m) intervals in unpaved areas of the former Waste Processing Facility, at seven locations in the Incinerator Pad area, and at locations of elevated direct radiation, identified by the surface scans. Portable ganea scintillation detectors, calibrated onsite against a pressurized ionization chamber, were ueed f or these measurements.

4

Msasurement of Surface Contamination Levels Total and removable alpha and beta-ga=ma contamination levels were measured at nine locations, on the concrete pads (Figure 10).

Sampling Surface (0-15 cm) samples were collected from areas of exposed soil at 30 ft grid intervals throughout the area and at locations identified by surf ace scans.

Following further cleanup by the licensee, followup soil samples were obtained.

Concrete coring was performed at the location on each concrete pad, where the highest direct measu re me nt was obtained. These locations are indicated on Figure 10. Camma mortitoring of the soil beneath the removed core was performed to identify the presence of elevated rad *ation levels and soil samples were collected f rom the exposed surface. A sample of residue waa also collected f rom a drain near the My-Products Storage Building (Figure 10).

Mackground and Baseline Measurements During a previous site visit, measurements and soil samples were obtained in the vicinity of tha CA Technologies plant to determine area background levels and baseline radionuclide concentrations for comparison purposes. Locations of the background measurements and baseline samples are shown on Figure 11. Tables 1 and 2 present the background exposure rates and baseline radionuclide concentrations, respectively.

t Sample Analyses and Interpretation of Results Samples werp returned to laboratories in Oak Ridge, Tennessee, for analyses.

All soil and residue samples were analyzed by gamma spectrometry. The major radionuclides of interests were Cs-137, Co-60, U-235, U-238, Th-228, Th-232, and Ra-226; however, spectra were reviewed for the presence of other significant l

photopeaks. Selected individual samples and composite samples were also analyzed l

! for St-90 and isotopic uraniun. Smears for the determination of removable co?.camination were analyzed for gross alpha and beta concentrations.

1 5 1

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Additional inf orm:: tion concerning analytical equipcint and procedures is contained in Appendices A and 3. Results of this survey were compared to the guidelines, established by the NRC, for decommissioning of the CA Technologies Uaste Processing Facility. These guidelines are presented in Appendices C and D.

RESULTS Document Review ORAU's review of the survey report submitted by GA to the NRC, indicates that the procedures and instrumentation used were consistent with industry accepted practices. Sampling conducted by GA was primarily from the waste processing area, where contaminated soil was stored awaiting shipment, and in several locations where the potential for contamination was the highest, based on previous facility use history. The data developed by CA are within the NRC guidelines established for this decommissioning activity.

Building Survey Surface Scans ,

Surface scans identified an area of residual contamination on the floor of the By-Products Storage Building. This location is indicated on Figure 12.

According to site personnel a spill had occurred at this location during f acility ,

operations. No additional areas of elevated radiatior, were noted inside the buildings.

Surf ace Contamination Measurements i

Table 3 summarises the results of surf ace contamination measurements in ene two buildings. The total co .tamination cata presented in this table are direct measurements which include removable and non-removable activity. Total contamination levels in the By-Products Storage Building were higher than in the Carage/ Office Building because the building had been used for sample preparation before and during decommissioning. At the floor location in the By-Products Storage Building identified by the surface scan, the highest total alpha and 2 2

  • beta-gamma levels were 10,600 dpm/100 cm and 17,800 dpm/100 cm , respectively.

6 l

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2 These lovels vsre reduced to <27 alpha dpe/100 cm and 820 bata gamma dpm/100 e d ,

af ter additional remedial actions by the licensee. At other locations in this building the individual alpha measurements ranged f rom <27 to 890 dps/100 cm 2and the individual beta-gamma measurements ranged from (470 to 3600 dpm/100 cm . 2 Total alpha' and beta-gamma contamination levels in the Carage/Of fice Building were generally dess than the detection sensitivity of the ins t rume nt s . Levels for 2 2 alpha and beta-gamma ranged from (27 dp /100 cm to 130 dpm/100 cm and

' 2 2

<470 dpe/100 cm to , 10 dps/100 cm , ,,,p,cggy,gy, Removable alpha and beta contamination levels were also generally less than the measurement sensitivity. The highest level of removable alpha activity 2

detected was 27 dps/100 cm , on the floor in By-Products Storage Building; the 2

highest beta level was 12 dpm/100 cm , on the floor in the Carage/ Office Building.

Outside Area Survey Surface Scans Eight areas of elevated direct gamma radiation were identified by the surface scans. These areas are shown on Figure 13. The licensee pe rf o r=ed additional remedial action at these locations and follow-up scanning indicated that cleanup of these locations had been effective in removing the contaminant.

Exposure Rate Measurements Table 4 presents the results of exposure race measurements at 30 ft (9.1 m) grid intervals. Levels ranged from 11 to 16 WR/h at 1 m above the surf ace and from 11 to 21 uR/h at surface contact. The highest levels were at grid coordinate l 7300N, 9560E. Levels in the area of the Incinerator Pad ranged f rom 15 to 20 J/h I

at 1 m above the surf ace and f rom 16 to 28 uR/h at surf ace contact. The highest levels were at grid coordinate 7585N, 9722E. Results are presented in Table 5.

Exposure rates on the concrete pads ranged f rom 13 to 16 2/h at 1 m above the surface and from 15 to 18 uR/h at contact (Table 6).

After further remediation of areas identified by surface scans, exposure j

l rates were measured at each location. The maximum exposure race measured was 20 uR/h at 1 m and 21 uR/h at the surface. The results of these measurements are presented in Table 7.

7

Surf ace Contesination Measuremnes Table 8 succiarizes surface contamination c:e asu reme n t s on concrete pad foundations. Total contamination levels for alpha and beta gamma ranged from

<27 dps/100 cm2 to 1550 dpm/100 cm2 and from 1240 dpm/100 cm2 to 5390 dpm/100 cm 2, respectively. Removable contamination levels were generally less than the detection sensitivity of the instrument.

Radionuclid' '

strations in Soil Concentrations of gamma emitting radionuclides, measured in surface soil samples f rom 30 f t (9.1 m) grid intervals, are presented in Table 9. Ranges of concentrations were: Co-60, <0.03 to 0.90 pCi/g; Cs-137, <0.02 to 9.54 pCi/g; Ra-226, 0.44 to 2.23 pCi/g; U-235, 0.05 to 1.26 pCi/g; U-238, 0.3 to 3.9 pCi/g; Th-228, 0.47 to 2.80 pCi/g; and Th-232, 0.41 to 2.70 pCi/g. Radionuclide concentrations in samples from the Incinerator Pad area are presented in Table 10. The highest levels of gamma ermitting radionuclides measured in these samples were: Co-60, 1.37 pCi/g; Cs-137, 19.28 pCi/g; Ra-226, 1.74 pCi/g; U-235 0.66 pCi/g; U-238, 1.31 pCi/g; Th-228, 2.11 pCi/g, and Th-232, 2.26 pCi/g.

Radionuclide concentrations in soil samples obtained from beneath concrete pads (Table 11) were in the ranges of concentrations in bcseline soil.

Table 12 presents the concentrations in samples f rom locations identified by surface scans, collected following further remedial action by the licensee.

l Maximun concentrations in these samples were Co-60, 1.77 pCi/g; Cs-137, 15.62 pCi/g; Ra-226, 1.32 pCi/g; U-235, 0.88 pCi/g; U-238, 2.1 pCi/g; Th-228, 2.64 pCi/g; and Th-232, 2.53 pCi/g.

Results of St-90 and isotopic uranium analyses performed on three composite samples, are presented in Table 13. The highest concentration of Sr-90 was l

1.46 pCi/g in composite sample B. Isotopic uranium concentrations were 1.53 to 3.83 pCi/g of U-234; 0.05 to 0.16 pCi/g of U-235; and 1.04 to 2.19 pCi/g of U-238.

l A soil sample, collected f rom beneath the concrete floor of the By-Products Storage, contained concentrations in the ranges of baseline soil. Data are presented in Table 14 8

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Miscellaneous Samples Table 14 also presents the results of analyses or. samples of drain residue and a piece of asphalt from the location on the Incinerator Pad, exhibiting an elevated gamma level. The Cs-137 level in the drain residuc (2.41 pCi/g) was slightly elevated above baseline concentrations. Other radionuclide concentrations in the two samples did not differ from typical caseline levels.

COMPARISON OF SURVEY RESULTS WITH GUIDELINES l Guidelines for decommissioning the Forwr Uaste Processing Facilities of l CA Technologies are presented in Appendices C and D. Surface contamination

! limits, based on primary contaminants of Uranium, Cs-137, and Co-60, identified on l this site, ares l 31pha

! 5000 dpa/100 cm2 , averaged over 1 m 2 15000 dpa/100 em2 , maximum in 100 cm 2 1000 dpe/100 cm2 , removable l Beta-Camma 5000 dpa/100 cm2 , averaged over 1 m 2 15000 dpa/100 cm2 , maximum in 100 cm 2 1000 dpa/100 cm2 , removable Surveys of the two remaining buildings and concrete pr.ds indicate that the surf aces satisfied these guidelines, with the exception of one small area on the floor of the By-Products Storage Building. Additional remedial action reduced ,

this location to within the guideline levels.

Exposure rate guidelines limit the level at 1 m above the surface to 10 J/h, above background, over an area of 30 ft (9.1 m) x 30 f t (9.1 m) or greater; the guideline level for smaller areas is 20 uR/h above background. At the CA Technologies Site, the total exposure rate guidelines are 19.7 G/h and 29.7 J/h, i.e., 10 uR/h and 20 uR/h, respectively, plus .the average background level of 9

9.7 uR/h (f rom Table 1). Ona area, at ths Incinerator Psd had an associated exposure rate of 20 uR/h at 1 m above the surface. Although this is slight'y 1bove the 19.7 uR/h average for areas in excess of 30 f t x 30 ft, this radiation was limited to, a small isolated area and the exposure rate was less than 20 uR/h above background. All other measurements were well below 19.7 LR/h. The external exposure rate target guideline has therefore been satisfied.

Most samples collected f rom the site had radionuclide concentrations in the ranges of typical baseline soils from the I.a Jolla area. Only two samples contained radionuclide levels in excess of the guideline. One of these was a sample of soil f rom grid coordinate 7270N, 9543E; this sample, f rom an area of elevated direct radiation identified by surf ace scans, contained 15.62 pCi/g of Cs-137, as compared to the guideline level of 15 pCi/g. The other sample containing a concentration above guideline levels was from the Incinerator Pad area; this sample contained 19.28 pCi/g of Cs-137. At both of these locations the sxtent of contamination is limited to small isolated areas, based on results of surface gamma scans. Also, the exposure route from Cs-137 in surf ace soil is direct radiation; exposure rates measured at these locations were within guideline limits. The elevated Cs-137 concentrations, when averaged across adjacent land areas would be well within the 15 pCi/g guideline. Radionuclide concentrations in the soil therefore satisfy the guidelines established for this decommissioning project.

SUMMARY

At the request of the NRC Region V Of fice, on September 7-28, 1988, Oak Ridge Associated Universities performed a confirmatory survey of Phase II Decommissioning at GA Technologies, Inc. in San Diego, Californi.. The survey included gamma, beta gamma, and alpha scans; exposure rate mea su re ment s ;

measurements of ,cotal and removable surface contamination; and measurements of radionuclide concentrations in soil. The survey identified several small areas of residual contamination, which were promptly reeleaned by the licensee and resurveyed by ORAU. Although there are several isolated locations of residual low-level soil contamination, the size of the involved areas and the associated levels are such that the concentrations can be averaged and the guidelines satisfied. It is theref ore ORAU's opinion that the decontamination efforts by the licensee have been effective in meeting the radiological conditions established for release of this site for unrestricted use.

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Location * . Redlanuclide Concentrations (pCI/gl Co-60 Cs-137 Re-226 17-235 U-238 Th(228 4 232) K-40 i

i <0.03 <0.02 0.59 1 0.14 b <0.17 f.6 1 1.2 1.34 1 0.46 14.0 t I.7 2 <0.05 0.16 1 0.18 0.53 1 0.22 <0.20 1.6 i I.5 f.98 1 0.86 25.0 13.3 3 <0.04 <0.04 0.79 1 0.20 0.39 1 0.24 f.I i 0.5 7.24 i O.62 10.4 1 1. F 4 <0.08 <0.05 1.20 1 0.29 <0.32 <l.1 3.08 1 0.79 29.0 1 5.4 j S <0.05 <0.05 1.23 1 0.22 0.69 1 0.35 1.3 1 0.6 3.20 1 0.80 24.3 1 2.F j g 6 <0.05 <0.0S 0.65 1 0.56 <0.22 8.0 1 0.9 f.92 1 0.78 30.2 2 2.9 RANGE <0. 03 to <0.00 b <0.02 to <0.16 0.53 to 1.23 <0.37 to 0.69 f.I to 1.6 1.34 to 3.20 10.4 to 50.2 AVERAGE 40.05 <0.% 0.S3 <0.33 1.3 2.N 22.2 I

"Ref er to Figure ll.

hert elat let. represent the 955 confidence levels, based only on counting statistics; additlanet laboratory acertelaties of 6 to 105 have not been propagated In these date.

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TABLE 4 EXPOSURE RATES MEASURED AT 30 FT GRID INTERVALS PHASE II DECOMMISSIONINC CA TECHNOLOGIES SArt DIECO, CALITORNIA M

Casma Exposure Rates Canna Exposure Rates Locations at la above the surface at the surface

-- (9R/h) ( ut/h) 7360N, 9260E 13 15 7330N, 9260E 13 14 7300N, 9260E 14 14 7240N, 9290E 11  !!

7270N, 9290E ,13 13 7310N, 9290E 13 14 7330N, 9290E 13 14 7360N, 9290E b 7210N, 9320E 13 13 7240N, 9320E 13 13 7270N, 9320E 13 12 7300N, 9320E - -

7330N, 9320E 13 13 7360N, 9320E 14 13 7390N, 9320E - -

7420N, 9320E - --

7180N, 9350E 13 13 7210N, 9350E 13 13 7240N, 9350E - -

, 7270N, 9350E 11 11

7300N, 9350E 14 14 7330N, 9350E 13 13 7360N, 9350E - -

27

TABLE 4 (Continued)

EXPOSURE RATES MEASURED At 30 FT GRID INTERVALS PHASE II DECOMMISSIONING

. GA TECHNOLOGIES

. SAN DIECO, CALIFORNIA Camma Exposure Rates Canna Exposure Rates Location at la above the surface at the surface (pR/h) (uR/h) 7390N, 9350E - -

7420N, 9350E 11 11 7120N, 9380E 11 11 7150N, 9380E 13 ,

11 ,

7180N, 9380E 11 11 7210k, 9380E 13 13 7240N, 9380E 13 12 7270N, 9380E - -

7300N, 9390E - -

7330N, 9390E - -

7360N, 9390E - --

7390N, 9390E - -

7420N, 9380E ~ ~

7090N, 9410E 11 11 7120N, 941'E 11 11 7150N, 9410E 11 11 7180N, 9410E 12 12 7210N, 9410E 12 13 7240N, 9410E - -

7270N, 9410E - -

7300N, 9410E. - -

7330N, 9410E - -

7360N, 9410E - --

28

TABLE 4 (Continued)

EXPOSURE RATES MEASURED AT 30 FT GRID INTERVALS PHASE II DECOMMISSIONING CA TECHNOLOGIES SAN DIEGO, CALIFORNIA Gamma Exposure Rates Gamma Exposure Rates Location at in above the surfaca at the surface (pR/h) ( uR/h) 7390N, 9410E - -

7380N, 9410E 13 13 7090N, 9440E - -

7120N, 9440E 11 11 7150N, 9440E - -

7180N, 9440E - -

7210N, 9440E - -

7240N, 9440E - -

7270N, 9440E - --

7300N, 9440E - -

7330N, 9440E 13 14 7360N, 9440E 15 16 7390N, 9440E 11 13 7420N, 9440E - -

7450N, 9440E - --

7120N, 9470E 13 12 7150N, 9470E - -

l 7180N, 9470E - -

7210N, 9470E - -

7240N, 9470E 16 16 7300N, 9410E - -

l 7330N, 9470E 13 13 7369N, 9470E - -

29 t

l

TABLE 4 (Continued)

EXPOSURE RATES MEASURED AT 30 FT GRID INTERVALS PHASE II DECOMMISSIONING CA TECHNOLOGIES SAN DIEGO, CALIFORNIA 4 -

Gamma Exposure Rates Camma Exposure Rates Location at is above the surface at the surface (PR/h) (uR/h) 7390N, 9410E 14 13 7420N, 9470E 13 12 7450N, 9470E - -

7480N, 9470E - -

7030N, 9500E - -

7060N, 9500E 11 11 7090N, 9500E 11 11 7120N, 9500E 13 14 7150N, 9500E - -

7180N, 9500E - --

7210N, 9500E - -

7240N, 9500E 16 17 l 7270N, 9500E 15 14

! 7300N, 9500E - -

l 7335N, 9500E 15 15

7360N, 9500E - -

l 7390N, 9500E - -

! 7420N, 9500E - --

7450N, 9500E - -

l 7'40N, 9500E - - -

7510N, 9500E - -

7030N, 9500E - --

7060N, 9530E 12 12 i

l 30 l

4 TABLE 4 (Continued).

EXPOSURE RATES MEASURED AT 30 FT CRID INTERVALS' PHASE II DECOMMISSIONING GA TECHNOLOGIES SAN DIEGO, CALIFORNIA Gamma Exposure Rates Gamma Exposure Rates Location at is above the surface at the surface (uR/n) (uR/h) 7090N, 9530E 11 11 7120N, 9530E 13 13 7150N, 9530E 13 13

, ?l80N, 9530E - -

7210N, 9530E 13 13 7240N, 9530E - -

7270N, 9530E - -

7300N, 9530E - -

7320N, 9530E - -

7360N, 9530E 16 17 7000N, 9560E - -

7030N, 9560E - -

7060N, 9560E 13 13 7090N, 9560E 15 16 7120N, 9560E 13 13 7150N, 9560E 13 13 7180N, 9560E 15 15 7210N, 9560E 14 13 7240N, 9560E 15 15 7270N, 9560E 14 14 7300N, 9560E 16 21 7330N, 9560E - -

7360N, 9560E - --

aRefer to Figure 9.

b(--) indicates measurement not performed.

31

TABLE 5 EXPOSURE RATES MEASURED IN THE INCINERATOR PAD AREA PHASE II DECOMMISSIONING GA TECHNOLOGIES SAN DIEGO, CALIFORNIA Gamma Exposare Rates Gamma Exposure Rates Locationa at I a above the surface at the surface (uR/h) (uR/h) 7620N, 9715E 16 18 7585N, 9722E 20 28 7627N, 9675E 16 16 7610N, 9670E 15 16 7565N, 9690E 16 20 7645N, 9658E 16 18 7587N, 9710E . 16 16 aRefer ti Figure 9.

l i

i i

l 1

32 1

TABLE 6

' DIRECT RADIATION LE7ELS MEASURED ON CONCRETE PADS PHASE II DECOMMISSIONING CA TECHNOLOGIES

- SAN DIEGO, CALIFORNIA Gamma Exposure Rates Camma Exposure Race Locations Description at is above the surface at the surface (uR/h) ( uR/h) 7261N, 9551E Waste Pad 15 16 7197N, 9515E By Products Storage Bldg. 13 15 7354N, 9458E North Waste Pad 13 16 7625N, 9720E Incinerator Pad 16 18 aRefer to Figure 9.

l t

l -

l l

l l

l 33 l

l

TABLE 7 EXPOSURE RATES MEASURED AFTER REMEDIATION OF AREAS IDENTIFIED BY SURFACE SCANS

. PHASE II DECOMMISSIONING CA TECHNOLOGIES SAN DIEGO, CALIFORNIA 4 "

Canna Exposur, .tates Camma Exposure Rates Locationa at 1 e above the surface at the surface (uR/h) (uR/h) 7240N, 9490E 20 20 7260N, 9480E 18 '

18 7270N, 9480E 18 21 7370N, 9543E 15 15 7330N, 9430E 14 16 7260N, 9400E 13 13 7135N, 9455E -

13 11 7380N, 9360E 13 14 aRefer to Figure 13.

34

TABLE 8

$UMMARY OF SURFACE CCNTAMINATION WASUREMNTS - CONCRETE PA05 440 FOUNDATICN$

PHASE 11 CECOMMIS$10NING GA TEC>NOLOGIES

$AN OlEGO, CALIFORNIA TOTAL CCNTANINATION (dom /100 cm2) REMOVABLE CONTAMINATlCN (dem/100 cm2, s

location ALPHA SETA-GAM 4A ALPHA BETA 7620N, 9730E 370 1240 5 <6 7610N, 9720E 36 1880 <3 <6 7260N, 9550E 310 5390 <3 <6 7355N, 9455E <27 3420 <3 <6 7370N, 9480E 130 1330 <3 <6 D ---

7405, 9495E (27 ---

726m , 9547E 330 5640 <3 <6 7615N, 972SE 1550 I150 <3 <6 7624N, 9723E 930 1270 <3 <6 eRefer to Figure 10 b0 ash Indicat es nessurement not performed.

35

j TABLE 9 RADIONUCLlDE @NCENTRATIONS IN St#tFACE Soll SAWLES FRON 30 FT GtID INTERVALS PHASE 11 DEconostS$10NING GA TECH 40LOGIES 3 ,

SAN DIEGO, CALIF 0ftil A ,

i .

Sample Radlonuclide Concentrations (pCI/g) '

No. Locatlona Co-60 Cs-137 Ra- Q U-235 U-238 Th-228 Th-232 ll4A 7360N,9260E <0.05 0.26 1 0.07 1.14 1 0.20 0.08 1 0.10 0.8 1 0.5 1.22 1 0.22 1.24 20.53 IISA 7330H,9260E <0.07 0.27 1 0.13 1.33 1 0.28 0.16 1 0.11 1.0 1 1.4 f.64 1 0.47 2.10 20.50 Il6A 7303N,9260E <0.04 0.15 1 0.11 0.98 1 0.23 0.20 1 0.08 J.9 1 f.2 1.45 1 0.33 1.65 2 0.52 Il7A 7240N,929aC <0.05 0.27 1 0.10 0.77 1 0.17 0.77 1 0.09 f.1 10.9 0.75 1 0.25 0.62 1 0.40 4

IISA 7270N,9290E <0.05 0.14 1 0.09 0.78 1 0.19 0.12 1 0.04 0.8 1 0.5 0.89 1 0.28 0.76 1 0.48 y ll9A 7300H,9290E <0.05 <0.04 1.52 1 0.35 0.18 1 0.10 1.4 i 1.1 1.22 1 0.39 1.81 1 0.47 120A 7350N,9320E <0.05 0.26 1 0.09 1.03 1 0.22 <0.25 2.5 1 0.5 1.28 1 0.28 0.97 2 0.35 12tA 7210N,9320E <0.05 0.45 1 0.11 0.75 1 0.21 0.17 1 0.09 1.0 11.0 0.64 1 0.22 0.76 1 0.32 122A 7240N,9520E <0.15 0.45 1 0.24 1.40 1 0.46 0.06 1 0.18 <l.2 0.78 1 0.53 0.64 1 0.68 l 125A 7270N,9320E <0.05 0.26 1 0.10 0.74 1 0.15 0.12 1 0.11 0.9 1 1.0 1.11 1 0.38 0.76 1 0.37 124A 7530N,9320E 50.05 0.4910.13 1.14 1 0.27 0.1310.10 f.5 1 0.9 1.25 1 0.31 1.3520.45 b 0.41 1 0.13 125A 7360N,9320E 0.03 1 0.15 1.16 1 0.30 0.19 1 0.11 0.6 i 1.4 1.62 1 4.07 f.57 1 0.47 126A 7180N,9550E <0.19 0.56 1 0.II l.22 1 0.89 0.13 1 0.08 4.9 1 0.3 0.67 1 0.28 1.06 1 0, 56 127A 7210N,9350E <0.54 0.11 1 0.11 I.30 1 0.24 0.18 1 0.15 0.3 2 1.0 f.II 1 0.28 0.70 2 0.51 128A 7270N,9350E <0.04 0.22 2 0.07 0.62 1 0.25 0.09 1 0.07 0.8 1 0.8 2.56 1 0.58 0.70 2 0.40 I 129A 7500N,9550E <0.06 0.34 1 0.10 0.9510.30 0.13 1 0.51 <0.9 1.03 1 0.47 1.16 1 0.57 ISOA 7330N,9350E <0.09 0.68 1 0.20 1.16 2 0.51 0.07 1 0.20 1.9 2 1.0 1.39 1 0.50 I.49 ! 0.dl

TABLE 9 (Continued)

RADIONUCLIDE CONCENTRATIONS IN SURFACE Soll SAWLES FROM 30 FT ORIO INTERVALS PHASE II DECometSS10NING I GA TECH 40LOGIES 6 SAN DIEGO, CALIFORNIA Saeple Radlonuclide Concentrations (pCI/g)

No. Location Co-60 Cs-137 Ra-226 U-235 IM38 T6-228 Th-232 13tA 7420N,9350E <0.06 0.s i 1 0.11 1.37 1 0.24 0.23 1 0.13 <0.8 1.47 10.% 1.30 1 0.44 152A 7820N,9380E <0.44 0.18 1 0.08 0.93 1 0.19 0.05 i 0.06 0.6 1 0.1 0.70 1 0.19 0.52 1 0.40 135A 7850N,9380E <0.05 <0.05 0.97 1 0.20 0.13 1 0.15 0.6 1 1.1 1.06 1 0.28 0.91 1 0.40 134A 7180N,9380E <0.06 0.52 1 0.12 0.75 1 0.26 0.07 1 0.81 0.9 1 0.9 0,53 1 0.22 0.8310.36 135A 7210N,9380E <0.33 0.30 1 0.20 0.78 1 0.63 0.10 1 0.18 1.5 i 1.6 0.93 1 0.81 0.87 1 0.84 136A 7240N,9380E <0.05 0.43 1 0.15 1.25 1 0.25 0.14 1 0.52 1.1 't 0.8 0.86 1 0.28 1.l8 1 0.45 137A 7270N,9380E <0.05 0.11 1 0.06 1.04 1 0.24 0.30 1 0.11 1.5 i 1.3 1.62 10.% I.50 1 0.51 138A 7090N,9410E <0.04 <0.05 0.61 1 0.22 0.14 1 0.07 0.3 1 0.8 0.56 1 0.22 0.46 1 0.32 139A 7120N,9410E <0.06 1.30 1 0.15 0.62 1 0.20 0.10 1 0.05 <0.6' O.47 1 0.22 0.60 1 0.32 140A 7150rl,9410E <0.05 0.18 1 0.12 0.7510.26 0.13 1 0.09 <0.5 0.61 1 0.38 0.40 1 0.53 14IA 718tN,9410E <0.06 's.38 1 0.08 0.14 1 0.27 0.12 1 0.10 1.6 1 2.7 0.81 10.M 0.88 1 0.28 142A 7210N,9410E 0.10 1 0.10 1.05 1 0.19 0.75 1 0.19 0.26 1 7.08 1.0 1 0.9 0.70 1 0.22 1.02 1 0.54 l4 3A 7380N,9410E 0.25 1 0.09 3.10 1 0.24 1.10 1 0.24 0.28 1 0.!2 0.4 i 1.2 1.39 1 0.33 1.41 10.55 144A 7820N,9440E <0.05 0.46 1 0.85 0.75 1 0.26 <0.25 1.0 1 0.5 0.75 1 0.30 0.58 1 0.39 145A 7350N,9440E <0.03 0.45 1 0.11 0.62 1 0.30 0.05 1 0.14 <0.7 0.97 10.33 1.15 12.0 146A 7560N,9440E <0.07 1.57 t 0.20 1.30 1 0.29 0.14 1 0.33 1.1 f 0.6 1.50 10.% 1.45 ! 0.4s

i TABLE 9 (Continued)

RADIONUCLIDE CONCENTRATIONS IN SURFACE SOIL SAWLES FRON 30 FT CRID INTERVALS PHASE il DECOseeBSS10NING I CA TEOte0LOGIES SAN DIEGO, CALIFORNIA i

Sample Radlonuclide Concentrations (pC1/q)
No. Location Co-60 Cs-137 Ra-226 U-235 U-238 Th-228 Th-232
  • 147A 7390N,9440E <0.05 0.06 1 0.04 0.44 1 0.16 0.09 1 0.09 <0.6 0.67 1 0.25 0.73 1 0.31 148A 7120N,9470E <0.06 0.30 1 0.11 0.85 1 0.18 0.10 1 0.08 <0.5 0.86 1 0.28 0.41 1 0.45 149A 7240N,9470E 0.90 1 0.17 9.5410.41 1.48 1 0.30 0.21 1 0.14 <0.7 1.22 1 0.36 8.44 1 0.44 ISOA 7330N,9470E 0.09 1 0.10 0.l7 1 0.09 0.69 1 0.16 0.12 1 0.10 0.9 1 1.2 1.16 1 0.30 1.18 1 0. 58

$ ISIA 7390N,9470E <0.06 0.45 1 0.12 1.02 1 0.30 <0.25 <0.7 1.94 1 0.30 1.53 1 0.60 IS2A 74 SON,9470E <0.05 0.52 1 0.13 1.36 + 0.35 0.l5 1 0.II 1.1 11.0 1.45 1 0.33 1.72 1 0.48 IS3A 7060N,9500E <0.05 <0.05 0.70 1 0.21 0.09 1 0.09 0.7 1 0.8 0.63 1 0.22 0.79 1 0.28 IS4A 7090N,9500E <0.04 0.05 1 0.06 0.60 1 0.21 <0.18 <0.5 0.83 1 0.20 0.88 10.27 ISSA 7120N,9500E <0.04 0.23 + 0.11 0.86 1 0.23 0.14 1 0.08 0.5 i 1.0 0.78 1 0.19 0.85 1 0.43 lo6A 7240N,9500E 0.33 1 0.18 2.60 1 0.24 1.00 1 0.28 0.19 1 0.12 1.8 1 1.3 f.85 1 0.42 1.72 1 0.60 IS7A 7270N,9500E 0.20 1 0.14 0.05 1 0.09 1.15 1 0.25 <0.26 <0.8 1.72 1 0.33 1.45 1 0.44 IS8A 733$N,9500E <0.32 2.74 1 0.28 1.29 1 0.24 0.24 1 0.12 1.7 1 0.7 f.78 1 0.36 2.70 1 0.55 159A 7060N,9550E <0.05 0.02 1 0.08 0.70 1 0.16 0.12 1 0.09 <0.7 0.84 1 0.27 0.95 1 0.31 160A 7090N,9530E <0.07 0.39 1 0.13 1.II 1 0.30 <0.24 <0.8 I.44 2 0.81 2.01 1 0.46 16tA 7120N,9550E <0.04 <0.05 1.48 2 0.24 0.20 1 0.09 1.4 10.5 1.17 1 0.28 1.08 2 0.42 162A 71 SON,9550E c0.06- 0.27 1 0.13 I.85 1 0.30 0.56 1 0.55 2.5 1 1.6 1.35 1 0.52 1.42 1 0.59

TABLE 9 IContinued)

RADIONUCLIOE CONCENTRATIONS IN SURFACE Soll SA WLES FRO 4 30 FT GIID INTERVALS PHASE il DEC0welSSIONING GA TECte40LOGIES 6

SAN DIEGO, CALIFORNIA 6

Saepte Radlonuclide Concentrations (pC1/q)

  • No, tocatIon Co-60 Cs-137 Ra-226 U-235 U-238 Th-228 Th-232 163A 7%0N,9530E , 0.61 1 0.17 6.64 1 0.31 1.18 1 0.25 <0.25 *0.7 I.08 1 0.40 1.13 10.58 164A 7060N,9%0E <0.04 0.06 1 0.04 1.02 1 0.23 0.Il i 0.09 0.9 1 0.5 1.00 1 0.25 1.1910.45 165A 7090N,9560E <0.04 <0.06 1.38 1 0.31 0.25 ,1 0.13 0.9 1 1.6 1.2 1 0.47 1.42 1 0.49 166A 7120H,9560E <0.05 0.05 1 0.07 1.09 1 0.28 0.14 1 0.07 1.2 1 0.5 1.17 1 0.28 1.13 1 0.41 167A 7 8 504,9560E <0.06 <0.06 1.27 1 0.26 <0.26 <0.8 1.86 1 0.36 1.59 1 0.58 168A 7180N,9560E <0.05 0.47 1 0.10 1.0010.26 0.39 1 0.12 2.9 i 3.6 1.63 1 0.52 1.60 1 0.52 g 169A 7230N,9560E 0.24 1 0.17 <0.07 I.0310.26 <0.24 <0.8 1.11 1 0.42 1.00 10.79 170A 7240N,9560E 0.21 1 0.17 2.10 1 0.21 1.28 1 0.27 0.4110.08 3.9 1 0.8 2.8010.33 2.67 1 0.50 17tA 72704,9560E 0.17 1 0.10 2.14 1 0.20 1.05 1 0.26 0.23 1 0.13 1.7 i I.2 1.34 1 0.26 f 43 1 0.40 172A 7300N,9560E 0.29 1 0.12 3.0510.25 1.10 1 0.28 1.26 1 0.78 <0.9 3.78 i O.47 1.8610.47 I?3A 7210N,9530E 0.14 1 0,.12 <0.05 2.23 1 0.35 <0.30 3.6 1 0.8 1.50 10.36 f.30 1 0.48 aReter to Figure 9 buncertainties represent the 955 confidence levels based only on counting statistics; additional laboratory uncertalnfles of 6 to 10$ have not been propagated into these data.

TABLE 10 RADIONUCLIDE CONCENTRATIONS IN $0tL SAWLES COLLECTED FRG4 THE INCINERATOR PAD AREA 6 PHASE il DE(XIeetBSS10NING GA TECHt0LOGIES SA WLES 6 .

SAN DIEGO, CALIFORNIA Sample Radlonuclide Concentrations (pCl/q)

No. Location a Co-60 Cs-t u Ra-226 U-235 I)-238 Th-228 Th-232 107A 7620N. 97tSE 0.84 1 0.18 b I.46 i 18 1.33 1 0.31 0.54 1 0.54 1.31 1 1.04 1.75 1 0.36 1.8210.51 108A 7585N. 9722E I.37 1 0.20 19.28 1 0.56 0.97 1 0.32 0.66 1 0.78 <l.05 1.45 1 0.44 1.74 1 0.46 109A 7630N. 9680E <0.06 <0.04 1.27 1 0.25 <0.22 <0.75 1.50 1 0.36 1.85 1 0.38 Il0A 7610N, %70E <0.06 0.18 1 0.08 1.12 1 0.27 <0.25 0.50 1 0.11 1.39 t 0.31 1.52 t 0.42

, Illa 7565N, %90E 0.82 1 0.20 9.7810.40 1.17 1 0.27 <0.36 <0.70 1.22 1 0.36 1.56 i O.4 3 O Il2A 7645N. 9685E 0.32 1 0.18 <0.04 I.74 1 0.30 <0.30 <0.98 2.11 1 0.44 2.26 1 0.56 II3A 758 7N, 9 7 80E <0.06 1.05 1 0.15 0.97 1 0.21 <0.23 <0.81 1.53 1 0.36 1.39 1 0.48 aRefer to Figure 9 b

uncertainties represent the 95$ confidence levels based only on counting statistics; addditional laboratory wicertaintles of 6 to 105 have not tamen propagated into t$ese data.

4 TABLE il RADIONCULIDE CONCENTRATIONS IN Soll FROM BENEATH CONCRETE PADS ,

PHASE la DECONMlSS10NING I

GA TEO NOLOGIES SAN OBEGO, CALIFnRNIA g Sample Redlonuclide Concentratlons (pCl/g)

No. Location

  • Co-60 Cs-137 Ra-226 U-235 U-238 Th-228 Th-232 0018 726tN, 955tE <0.10 0.29 t 0.16D 3.48 1 0.36 <0.38 <l.2 1.70 1 0.53 1.38 1 0.63 0058 7354N, 9458E <0.05 0.03 1 0.05 0.43 1 0.10 <0.17 <0.5 0.44 t 0.20 0.39 1 0.41 0040 7625N, 9720E <0.06 0.05 1 0.I4 0.85 1 0.19 <0.29 <0.7 0.76 1 0.40 0.8I t 0.*>0 d
  • Refer to Figure 10 buncertainties represent the 955 confidence levels based only on counting statistics; addditional laboratory uncertaintles of 6 to IOS have not been propagated Into these data.

TABLE 12 RADIONUCLIDE CONCENTRATIONS IN SURFACE S0lt SAWLES COLLECTED FOLLOWING RENEDI ATION OF AREAS 1 DENT lF1ED 8Y SistFACE SCANS PHASE Il DECDeceBSS10NING

~

GA .EO NOLOGIES SAN OIEGO, CALIF 0HNIA 6

Saeple Radionuclide Concentrations (pCl/g)

No. Location Co-60 Cs-137 lb-226 U-235 U-238 Th-228 Th-232 174A 724 0N,9490E 0.53 1 0.19 2.94 1 0.25 1.24 1 0.28 0.24 1 0.12 2.1 1 1.7 I.7510.33 2.00 10.45 175A 72704,9480E 0.8510.19 9.68 1 0.39 1.32 1 0.36 0.88 1 0.64 2.5 i 1.7 2.64 1 0.56 2.53 1 0.55 I16A 7270N,9543E I.77 1 0.27 15.62 1 0.52 1.00 1 0.40 <0.41 1.1 1 0.8 2.06 1 0.42 1.58 1 0.47 177A 7370N,9460E 0.C6 1 0.19 0.63 1 0.15 1.2310.67 0.22 1 0.12 0.8 i 3.5 1.81 10.40 1.73 10.45 178A 7330N,9460E <0.04 0.12 1 0.09 1.25 1 0.7 <0.22 <0.8 1.6110.36 1.60 1 0.42 179A 7260N.9400E <0.04 <0.04 f.15 1 0.24 <0.24 1.1 10.6 1.44 1 0.31 1.27 1 0.39 e

180A 7835N,9455E <0.04 0.09 1 0.09 1.24 1 0.25 0.24 1 0.11 0.9 1 1.2 1.40 10.35 1.48 1 0.46 18tA 7380N,9360E <0.04 <0.05 0.78 1 0.18 <0.20 <0.6 1.06 1 0.28 0.77 1 0.47 "Refer to Figure 13 b

uncertaintles represent the 955 confidence levels based only on counting statistics; addith .Aal laboratory uncertaintles of 6 to 10% have not been propagated lato these data.

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TABLE 13 RADIONUCLIDE CONCENTRATIONS IN COMPOSITE SOIL FRASE II DECOMMISSIONING CA TECHNOLOGIES SAN DIEGO, CALIFORNIA e a Radionuclide Concentrations (pCi/g)

Sample Type a Depth Sr-90 U-234 U-235 U-238 Composite A Surface 0.72 2 0.16b 1.5820.22 0.05 2 0.04 1.04 2 0.18 Composite B 1.46 2 0.25 3.83 0.37 0.1620.09 2.19 2 0.28 Composite C 0.21 2 0.15 1.53 2 0.24 0.05 2 0.05 1.32 2 0.22 aSample identification numbers:

Composite A: (7060N, 9500E; 7090N, 9500E; 7120N, 9500E; 7240N, 9500E; 7270N,9500E)

Composite B: (7240N, 9490E, 7270N, 9480E)

Composite C: (7261N, 9551E; 7197N, 9458E; 7354N, 9458E; 7625N, 9720E) b Uncertainties represent the 95% confidence levels, based only on counting statistics; additional laboratory uncertainties of 6 to 10% have not been .

propagated into these data.

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TABLE 14 RADIONUCLIDE CONCENTRATIONS IN solSCELLANE00S SA rtES PHASE il DECONNISSIONING GA TECt940LOGIES SADFLES SAN DIEGO, CALIFORNIA 6 Description Radlonuclide Concentra15cas (pC1/g and Co-60 0s-137 Ra-226 U-235 U-238 Th-228 Th-232 Location

  • Soit fRON BENEATH BY-Pf4000 CTS STORACE BUILDING FLOOR (7197N, 95tSEI <0.06 <0.06 0.85 1 0.36b <0.21 <0.6 <0.23 0.85 1 0.35

$ ORAIN RESIOUE (7170N, 9562El 0.14 1 0.26 2.48 1 0.38 1.07 1 0.58 0.24 1 0.74 <l.3 <0.46 1.89 1 0.84 ASPHALT (7587N, 9710El <0.05 0.48 1 0.09 1.49 1 0.24 <0.29 2.1 1 0.9 <0.26 8.78 1 0.58 aRefer to Figures 9 and 10 b

uncertaintles represent the 955 c; f tdence levels based only on counting statistics; addditional laboratory uncertainties of 6 to 105 have not been propagated into these data.

REFERENCES

1. "Confirmatory Survey of Phase I Decommissioning Former, Waste Processing Facility, CA Technologies, San Diego, California," Oak Ridge Associated Universities, July 1986.
2. "Follow-Up Confirmatory Survey of Phase I Decommissioning, Former Waste Processing Facility, CA Technologies, San Diego, California," Oak Ridge Associated Universities, March 1988.
3. "Confirmatory Survey of Phase III Decommissioning, CA Technologies, San Diego, California," Oak Ridge Associated Universities, February 1988.
4. Letter f rom K. E. Asmussen (CA Technologies, Inc.) to R. D. Thomas (U.S .

Nuclear Regulatory Commission, Region V),

Reference:

"License SNM-696, Docke* 70-734", August 25, 1987.

5. "Proposed Confirmatory Survey Plan for Phase I (Follow-up) and Phase II of the Former Vaste Processing Facility, CA Technologies, San Diego, California," Oak Ridge Associated Universities, September 4, 1987.

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W6 APPENDIX A MAJOR SAMPLING AND ANALYTICAL EQUIPMENT

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l APPENDEX A MAJOR SAMPLING AND ANALYTICAL EQUIPMENT The display or description of a specific product is not to be construed as an endorsement of that product or its manufacturer by the authors or their employer.

A. Direct Radiation Measurements Eberline "RASCAL" Portable Ratemeter-Scaler Model PRS-1 (Eberline, Sante Fe, NM)

Eberline PRM-6 -

Portable Ratemeter (Eberline, Santa Fe, NM)

Ludlum Floor Monitor Model 239-1 (Ludlum, Sweetwater, TX)

Eberline Alpha Scintillation Probe Model AC-3-7 (Eberline, Sante Fe, NM)

Eberline GM Pancake Probe Model HP-260 (Eberline, Sante Fe, NM)

Victoreen Beta-Gamma "Pancake" Detector Model 489-110 (Victoreen, Cleveland, OH)

Victoreen NaI Scintillation Detector Model 489-55 (Victoreen, Cleveland, OH)

Reuter-Stokes Pressurised Ionization Chamber Model RSS-111 (Reuter-Stokes, Cleveland, OH)

B. Laboratory Analyses Automatic low-background Alpha-Beta Counter Model LB5110-2080 (Tennelee, Inc., Oak Ridge, IN)

High-Purity Germanium Detector Model CMX-23195-S, 23% efficiency (EG6G ORTEC, Oak Ridge, TN)

A-1

Ussd in conjunction with:

Lead Shield, G-16 (Gamma Products Inc., Palos Hills, IL)

High Purity Germanium Coaxial Well Detector Model.GWL-110210-FUS-S, 23: Efficiency (EG&G ORTEC, Oak Ridge, TN)

Ueed in conjunction with:

Lead Shield Model C-16 (Applied Physical Technology, Atlanta, CA)

High Purity Germanium Detector Model IGC25, 25% Efficiency (Princeton Gamma-Tech, Princeton, NJ)

Used in conjunction with:

Lead Shield (Nuclear Data, Schaumburg, IL)

Multichannel Analyzer ND-66/FD-680 System (Nuclear Data Inc., Schaumburg, IL)

Alpha Spectrometry System Tennelec Electronics (Tennelec, Oak Ridge, TN)

Surface Barrier Detectors (EG&G ORTEC, Oak Ridge, TN)

Multichannel Analyzer Model ND-66 (Nuclear Data, Schaumburg, IL)

A-2

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l APPENDIX B MEASUR$ MENT AND ANALYTICAL PROCEDURES e

APPENDZX 3 Measurement and Analytical Procedures Surface Scans

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Surf ace scans were performed by passing the probes slowly over the surf ace.

The d is t a n.ca between the probes and the surf ace was maintained at a minimum -

nominally about 1 ca. Identification of elevated levels was based on increases in the audible signal from the recording or indicating instrument. Alpha and beta gamma scans of large surface areas on the floor of the facility were accomplished by use of a gas proportional floor monitor, with a 600 cm2 sensitive area. The ins t rument was slowly moved in a systematic pattern to cover 100% of the accessible area. Combinations of detectors and ins t rument for the scans were Beta-Camma - Pancake GM probe with PRM-6 ratemeter.

Beta-Camma - Pancake GM probe with PRS-1 scaler /ratemeter.

Camma - NaI scintillation detector (3.2 cm x 3.8 cm crystal) with PRM-6 racemeter.

Alpha - ZnS probo with PRS-1 scaler /ratemeter.

Alpha / Beta - Cas proportional floor monitor with 1.udium Model 2220 scale r/ ra t eme t e r.

Alpha and Beta-gamma Surface Contaminatioa Measurements Measurements of total alpha radiation level were performed using Eberline Model PRS-1 portable scaler /ratemeters with Model AC-3-7 alpha scintillation probes. Measurements of total beta gamma radiation levels were performed using Eberline Model PRS-1 portable scaler /ratemeters with Model HP-260 thin-window "pancake" GM probes. Count rates (epm) were converted to disintegration rates 2

(dpm/100 es ) by dividing the net rate by the 4w efficiency and correcting for the active area of the detector. Effective window areas were 59 em2 for the ZnS detectors and 15 cm 2 for the GM detectors. The background count race for ZnS alpha probes averaged approximately 2 epm; the average background count race was approximately 40 cpm for the GM detectors.

B-1

Rsmovable Contaminttion Metsurestnts Smear measurements were perf ormed on numbered filter paper disks, 47 mm in diameter. See,ars were placed in labeled envelopes with the location and other pertinent information recorded. Smears were counted on a low background proportional counter at the Oak Ridge laboratory.

' Exposure Rate Measurements Measurements of gamma exposure rates were performed using an Eberline PRM-6 portable ratemeter with a V ctoreen Model 489-55 gamma scintillation probe containing a 3.2 cm x 3.8 cm NaI(T1) scintillation crystal. Count rates were converted to exposure rates (uR/h) by onsite cross-calibration using a Reuter Stokes model RSS-111 pressurized ionization chamber.

  • Soil, Asphalt. and Residue Sample Analysis Camma Spectroscopy Samples were dried, mixed, and a portion sealed in 0.5-liter Marinelli beaker. The quantity placed in the bea'ker was chosa.: to reproduce the calibrated councing geometry and ranged f rom 600 to 800 g of soil. Net soil weights were determined and the samples counted using intrinsic germanium and Ce(Li) detectors coupled to a Nuclear Data Model ND-680 pulse height analyzer system. Background and Compton stripping, pesk search, peak identification, and concentration calculationr were performed usin5 the computer capabilities inherent in the analyzer system. Energy peaks used for determination of radionuclides of concern were:

Co 1.173 MeV Cs-137 - 0.662 MeV Ra-226 - 0.609 MeV from Bi-214 (secular equilibrium assumed)

U-235 - 0.144 MeV U-238 - 0.094 MeV from Th-234 (secular equilibrium assumed)

Th-228 - 0.583 MeV from T1-209 (secular equilibrium assumed)

Th-232 - 0.911 MeV from Ac-228 (secular equilibrium assumed)

Spectra were also reviewed for the presence of other radionuclides.

B-2

Serontium-90 Analysis A liquot s of soil were dissolved by pyrosulfate fusion and the strontium precisitated as a sulfate. Successive treatments with EDTA preferentially remot ed lead and excess calcium and returned the strontium to solution. Ferric and ather fnsoluble hydroxides was precipitated at a pH of 12 to 14 Strontium was reprecipitated as a sulf ate. 8arium was removed as a chromate using DTPA.

The final precipitate of strontium carbonate was counted 'using a low-background Tennelee alpha-beta proportional counter.

Alpha Spectrometry for Isotopic Uranium Aliquots of soil were dissolved by pyrosulf ate fusion and precipitated with barium sulfate. The barium sulfate precipitates we re redissolved and uranium separated by liquid - liquid , extraction. Uranium was then precipitated with a cerium fluoride carrier and counted using surface barrier detectors (ORTEC),

alpha spectrometers (Tennelec), and an ND-66 Multichannel Analyzer (Nuclear Data).

Uncertainties and Detection Limits The uncertainties associated with the analytical data presented in the tables of this report, represent the 95 confidence levels for that data. These uncertainties were calculated based on both the gross sample count levels and the associated background count levels. When the net sample count was less than the 95 statistical deviation of the background count, the sample concentration was reported as less than the detection capability of the measurement procedure.

Because of variations in background levels and Compton contributions from other radionuclides in samples, the detection limits dif fer f rom sample to sample and instrument to instrument. Additional uncertainties of 2 6 to 10%, associated with sampling and laboratory procedures, have not been propagated into the data presented in this report.

Calibration and Ouality Assurance Laboratory and field survey p r,ocedu res are documented in the following manuals, developed specifically for the Oak Ridge Associated Universities' B-3 l

Radiological Site Assessmsnt Program: "Survey Procedures !!anual," Revision 3,

!!ay 1987; "Laboratory Procedures :tanual", Revision 3, May 1987 and "Quality Assurance Manual", Revision 1, June 1987.

With the exception of the measurements conducted with portable gamma

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scintillation survey meters, instruments were calibrated with NBS-traceable standards. The calibration procedures for the portable gamma instruments are performed by comparison with an NBS calibrated pressurized ionization chamber.

Quality control procedures on all instruments included daily background snd check-source measurements to confirm equipment operation withi'n acceptable statistical fluctuations. The ORAU laboratory participates in the EPA and E!fL Quality Assurance Programs.

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APTENDIX C i

i GUIDELINES FOR DEC0!ffAMINATION OF FACILITIES AND EQUIPMENT PRIOR'TO RELEASE FOR UNRESTRICTED USE OR TERMINATION OF LICENSES FOR BYPRODUCT, SOURCE OR SPECIAL NUCLEAR MATERIAL i

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'CUIDELINES FOR DECONTAMINATION OF FACILITIES AND EQUIPMEh7 PRIOR TO RELEASE FOR UNEESTRICTED USE

. OR TERMINATION OF LICENSES FOR BYPRODUCT, SOURCE OR SPECIAL NUCLEAR MATERIAL U.S. Nuclear Regulatory Commission Division of Fuel Cycle & Material Safety Washington, D.C. 20555

. July '.982 C-1

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The instructions in this guide, in conjunction with Table 1, specify the radionuclides and radirtion exposure race limits which should be used in decontamination and survey of surf aces or premises and equipment prior to abandonment or release for unrestricted use. The limits in Table 1 do not apply to premises, equipment, or scrap containing induced radioactivity for which the radiological considerations pertinent to their use may be different. The release of such facilities or items from regulatory control is con,sid~ered on case-by-case basis.

1. The licensee shall make a reasonable effort to eliminate residual contamination.
2. Radioactivity on equipment or surfaces shall not be covered by paint, plating, or other covering material unless contamination levels, as determined by a survey and documented, are below the limits specified in Table 1 prior to the application of the covering. A reasonable effort must be made to minimize the contamination prior to use of any covering.
3. The radioactivity on the interior surf aces of pipes, drain lines, or ductwork shall be determined by making measurements at all traps, and other apptopriate access points, provided that contamination at these locations is likely to be representative of contamination on the interior -of the pipes, drain lines, or ductwork. Surfaces or premises, equipment, or scrap which are likely t,o be contaminated but are of such size, construction, or location as to make the surface inaccessible for purposes of measurement shall be presumed to be contaminated in excess of the limits.
4. Upon request, the Commission may authorize a licensee to relinquish possession or control of premises, equipment, or scrap having surfsees contaminated with materials in excess of the limits specified. This may include, but would not be limited to, special circumstances such as razing of buildings, transf er of premises to another organization continuing work with radioactive materials, or conversion of facilities to a long-term storage or standby status. Such requests l must 1
a. Provide detailed, specific information describing the premises, equipment or scrap, radioactive contaminants, and the nature, extent, and degree of re'sidual surf ace contamination.
b. Provide a detailed health and safety analysis which reflects that the residual amounts of materials on surf ace areas, together with other considerations such as prospective use of the premises, equipment or scrap, are unlikely to result in an unreasonable risk to the health and safety of the public.
5. Prior to release of premises for unrestricted use, the licensee shall make a comprehensive radiation survey which establishes ' hat contamination is within the limits specified in Table 1. A copy of C-2

the survey report shall be filed with the Division of Fuel Cycle and Material Safety. USNRC, Washington, D.C. 20555, and also the Administrator of the NRC Regional Office having jurisdiction. The report should be filed at least 30 days prior to the planned date of abandonment. They survey report shall

a. Identify the premises.
h. Show that reasonable effort has been made to eliminate residual contamination.
c. Describe the scope of the survey and general procedures followed.
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.

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TAB 12 1 ACCEPTABLE SURFACE CONTAMINATION IIVELS Nuclides* Averageb,c,f ;g,xg ,,,b,d,f Remoyableb.e f U-nat, U-235, U-238, and 5,000 dpa e/100 cm 2 15,000 dpa a/100 cm 2 1,000 dpa a/100 cm 2 associated decay prodesets .

Transuranics, Ra-226,~Ra-228, 100 dpe/100 cm 2

300 dpe/100 cm 2 20 dpe/100 cm 2 Th-230 Th-228 Pa-231, Ac-227, 1-125, I-129 2

Th-net Th-232, Sr-90, Ra-223 1000 dpe/100 cm 2 3000 dpe/100 cm 2 200 dpe/100 cm Ra-224 U-232, 1-126, I-131, .

I-133 Beta games cettters (nuclides 5000 dpa Sy/100 cm 2 15,000 dpa Sy/100 cm 2 1000 dpa Sy/100 cm 2 with decay modes other than alpha emission or spontaneous

? fission) except Sr-90 and

  • others noted above.

a IAiere surf ace cor.taelnation by both alpha- and beta-gamma-emmtting nuclides exists, the lietts established for alpha- and beta-gamma-emitting nuclides should apply independently.

b As used in this table, dpa (disintegrations per minute) means the rate of emission by radioactive material as determined by correcting the counts per minute observed by an appropriate detector for background, efficiency, and geometric factors associated with the instrumentation.

c Heasurements of average contaminant should not be averaged over more than I square meter. For objects of less surface area, the average should be derived for each such object.

d 2 The maximum contamination level applies to en area of agt moce than 100 cm ,

e The amount of removable radioactive meteria.1 per 100 cm of surface area should be determined by ,

wiping that area with dry filter or soft absorbent paper, applying moderate pressure, and assessing  !

the amount of radioactive material on the wipe with an appropriate instrument of known efficiency. 14 hen removable contamination on objects .i less surface area is determined, the pertinent levela should be reduced proportionally and the entire surface should be wiped. t f 1he average and anximum radiation levels associated with surface contamination resulting from beta gamma emitters should not exceed 0.2 mrad /h at I ce and 1.0 mrad /h at I cm, respectively, measured through not more tlian 7 milligrams per square centimeter of total absorber.

APPENDIX D DECOMMISSIONING GUIDELINL FOR THE GA TECHNOLOGIES tlASTE PROCESSING FACILITY p

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APPEND 2X D Decommissioning Guidelines for the

, CA Technologies Waste Processing Facilities Target criteria for unrestricted release of the CA Technologies' Waste Processing Facility and si:rrounding areas are presented in the licensee's final report and are as follows:

Extetaal Radiation The gamma exposure rate at 1 m above the ground surf ace shall not exceed 10 uR/h above background for an area of greater than 30 f t (9.1 m) x 30 ft (9.1 m) and shall not exceed 20 uR/h above background for any discrete area (i.e. less than 30 ft (9.1 m) x 30 ft (9.1 m)].

Inhalation and Ingestion Cuncontrations of radionuclides in soil shall be such that inhalation and ingestion are not expected to result in annual dose equivalents exceeding 20 mrem to the lung or 60 area to the bone.

Limiting soil concentrations were derived to satisfy these external and internal target criteria. The concentration limits are presented in the following Table.

Radionuelide Concentration Limit Above Background (DCi/g)

Depleted Uranium 35 Enriched Uranium 30 Thorium (Natural) 10 Co-60 8 Cs-137 15 Sr-90 1.8 x 10 3 Where more than one radionuclide si present, the sum of the ratios of the individual radionuclide concentrations to their respective concentration limits shall not exceed 1.

D-1

CRAU 88/A 96

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%upI ed Prepared by

'i, n ,,Rid'^"

ties CONFIRM ATORY SURVEY Prepared for U.S. Nuclear OF Regulatory comm:ssion s PHASE Ill DECOMMISSIONING Region V Office s

  • nsored bv GA TECHNOLOGIES Division of

d SAN DIEGO, CALIFORNIA b"eU*a'i E*c"i ar safety P. R. C O TT E N l

l Radiological Site Assessment Program Manpower Education, Research, and Training Division l

FINAL REPORT FEBRUARY 1988 e

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e% 6W J N \,x p CN sG T L\ QQ'

CONFIRMATORY S1'RVEY OF P4ASE III OEC0!!'!ISSIGNISC CA TECHNOLOGIES

, CAN DIEGO, CALIFORNIA Prepared by D.R. COTTEN Radiological Site Assessment Program Manpower Education, Research, and Training Division Oak Ridge Associated Universities Oak Ridge, TN 37831-0117 Project Staff J.D. Berger R.C. Rookard R.D. Condra T.J. Sowell D.A. Gibson C.F. Heaver C.L. !!urphy Prepared for Division of Industrial and itedical Nuclear Safety U.S. Nuclear Regulatory Commission Region V Office Final Report February 1987 This report is based on work pe rf ormed under Interagency Agreement DOE No. 40-816-83 NRC Fin. No. A-9076-3 between the U.S. Nuclear Regulatory Conmission and the U.S. Department of Energy. Oak Ridge Associated Universities performs complementary work under contract number DE-AC05-760R00033 with the

!! . S. Departnent of Energy.

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TABLE OF CONTENTS Page 11 List of Figures . ' . ... . .. . . . . . . . . . . . .. . ......

iii'

. Lis t of Tablet. . . .... . ........... . . . . .......

Int roduction and Site His tory . . . . . . . . . . . . . . . ...... I 2

Site Description . ... ..... . . . . . .. .. . . . . ......

xi 2

Procedures . ... .. . . . ... . . .. . . . . . .. . . .-. . . .

5 Results .. .. .. .. . . .. . . . . . . . . . . . .. .......

. . . . .. ....... 7 Comparisen c. Survey Results with Guidelines 8

Summary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

. . . .. . . . . . . . . . .. . ...... 50 Ref erences . .....

Appendices Appendix At Major Sampling and Analytical Equipment Appendix B: Measurement and Analytical Procedures Appendix C: Guidelines f or Decontamination of Facilities and Equipment Prior to Release f or Unrestricted Use or Termination of Licenses f or Byproduct. Source, or Special Nuclear Material Appendix D: Decommissioning Guidelines f or the GA Technologies Facility i

LIST OF FIGURES Page:

FIGURE 1: Map of' San Diego, Indicating the Location of GA Technologies Facilities . . . . .. . .. . . . . . . 9 FIGURE 2: CV Technologies Plant Layout . . . .. . .. . . .. . . 10 FIGURE 3: %reas of Different Deconmissioning Phases and Exclusion Areas. .;..... . . . . .. . .. .... . ... . 11 FIGURE 4: Location of Building 5 Indicating the Shipping and Receiving Ares . . . . . . . . . . . . . . _ . . . .. .. 12 FIGURE 5: Shipping and Receiving Area. CA Technologies . .. . . . 13 FIGURE 6: Contamination Measurement Locations on the Floor and Lower Walls of the Shipping and Receiving Area. . . .. 14 -

FIGURE 7: Measurement Locations pn Upper Walls, Ceiling and Overhead Surfaces of the Shipping and Receiving Area . . 15 FIGUR? St Phase III Property Sections . . . . . . . . . . .... 16 FIGURE 9: Locations of Exposure Rate Measurement Using a Pressurized Ionization Chamber . . . . .. . ... ... . . . . .. 17 FIGURE 10: Section 1 Measurement and Soil Sampling Locations . .. 18 FIGURE 11: Section 2 Measurement and Soil Sampling Locations . .. 19 FIGURE 12: Section 3 Measurement and Soil Sampling Locations . .. 20 FIGURE 13: Section 4 Measurement and Soil Sampling Locations . .. 21 FIGURE 14: Section 5 Measurement and Soil Sampling Locations . .. 22 FIGURE 15: Section 6 Heasurement and Soil Sampling Locations . .. 23 FIGURE 16: Section 7 Measurement and Soil Sampling Locations . . . 24 FIGURE 17: Section 8 Measurement and Soil' Sampling Locations . . . 25 FIGURE 18: Section 9 Measurement and Soil Sampling Locations ... 26 FIGURE 19: Section 10 Measurement and soil Sampling Locations . .. 27 FIGURE 20: Section 11 Measurement and Soil Sampling Locations . .. 28 FIGURE 21: Section 12 Measurement and Soil Sampling Locations . .. 29 FIGURE 22 Section 13 Measurement and Soil Sampling Locations . .. 30 l

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LIST OF FIGURES (Continued)

Page FIGURI 23: Section 14 Measurement and Soil Sampling Locations . . . 31 FIGURE 24: Section 15 Measurement and Soil Sampling Locations . . . 32 FIGURE 25: Section 16 ?teasurement and Soil Sampling Locations . . . 33 FIGURE 26: Section 17 !!easurement and Soil Sampling Locations . . . 34 FIGURE 27: Section 18 Measurement and Soil Sampling Locations . . . 35 FIGURE 28: Section 19 Measurement and Soil Sampling Locations . . . 36 FIGURE 29: Section 20 Measurement and Soil Sampling Locations . . . 37 FIGURE 30: Locations of Backgrouad !!easurements and Baseline Soil Sample: from the Vicinity of GA Technologies . . . . . . 38 iii

LIST OF TABLES Page TABLE 1: Background Radiation Levels . . . . . . . . . . . . . . . . . 39 TABLE 2: Ba eline hdionuclide Concentrations in Soil . . . . . . . . 40 TABLE 3: Summary of Surf ace Contamination Steasurements, Building i Shipping and Receiving Area . . . . . . . . . . . . . . . . . 41 TABLE 4: Direct Radiation Levels . . . . . . . . . . . . . . . . . . . 42 TABLE 5: Radionuclide Concentrations in Soil . . . . . . . . . . . . . 46 TABLE 61 Radionuclide Concentrations in Composite Soil . . . . . . . . 49 iv

CONFIRt!ATORY SURVEY OF

-PHASE III DEC050tISSIONING GA TECHNOLOGIES SAN DIEGO, CALIFORNIA k

. INTRODUCTION AND SITE HISTORY In nid 1984, GA Technologies. Inc. (GA) of San Diego, California, initiated decommissioning activities for the purpose of releasing portions of thuir facilities from Nuclear Regulatory Commission (NRC) licensing restrictions.. The decommissioning is being accomplished in separate phases. Phase I activities, which encompassed the Solar Evaporation Pond area, the areat immedistely surrounding the former Uaste Processing Facility and the Incinerator Pad, a previous burial site for contaminated asphalt, the hillside and canyon below the waste handling f acilities, and undeveloped land surrounding the waste processing facilities, were completed in late 1985. A confirmatory survey, performed by Oak Ridge Associated Universities, (ORAU) in December 1985, identified small isolated areas in need of additional remedial action.1 These areas have been addressed and resurvey findings will be discussed in a separate report. Phase II areas are the former Uaste Processing Facility itself, and the incinerator pad; survey findings of these areas will also be described in a separate report. Phase III consists of approximately 87 hectares (215 acres) of primarily undeveloped land, surrounding the main GA Technologies plant site. GA recorda and individuals familiar with the facility history indicate that radioactive material uses in the Phase III area have been limited to a few small locations. Portions of the Phase III area, have been excluded and have been identified for evaluation under a separate decommissioning activity. These are the San Diego Gas and Electric Company's Torrey Pines substation, an abandcned sewage treatment facility, a pump station for the municipal sewage system, shipping and receiving and of fice facility, and several areas of asphalt paving. Potential radiological contaminants at GA have been identified as enriched uranium, thorium, and longer half-life fission and activation products.

At the request of the Nuclear Regulatory Commission (NRC), Region V office, the Radiological Site Assessment Program of Oak Ridge Associated Universities (ORAU) conducted a radiological survey to confirm the status of the Phase III area, relative tu the NRC criteria for release for unrestricted use.

I

i SITE DESCRIPTION The- CA Technologies factitties are located near the intersections of Interstate 5 and. Genesee Road, approximately 2') km north of San Diego, CA (Firures I and 2). Site activities include a wide variety of research and

- developnent p rograms . The Phase III area-is. illustrated in Figure 3. Most of the area has remained undeveloped. The terrain consists primarily of extremely heavy brush, steep cills, and canyons; accessibility is limited. There are also several areas of asphalt paving, which include parking lots, roads, and storage areas.

The Phase III survey also includes the shipping and receiving area of Sluilding 5. This facility consists of a small room, approximately 2 m x 3 m, which contained an exhaust hood, a large receiving room, and a smaller shipping room with package preparation area.

tiithin the Phase III boundaries are several areas in which CA decommissioning activities have not yet been completed. These areas, shown in Figure 3, have been excluded from the survey and will be addressed at a later date. Area Bl is the Canyon Area to the Uest and below the "200 meter" storage butiding, the TRICA Reactor and Hot Cell facilities. Area B2 includes a liquid storage tank, the CA sewage pumphouse, and contractor sheds. Area B3, a sewage t rea t me nt facility known ss Callon Ponds, is surrounded by a security fence.

PROCEDURES l

A survey of the Phase III decommissioning area was performed by the l Radiological Site Assessment Program of ORAU during September 9-28, 1987. Ihis survey cas in accordance with a servey plan submitted to the Region V office of I *he NRC.' Methods and procedures utilized in the survey are presented in this section..

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The ob.ectives of the survey were to confirm that the radiological condition l

i of the Phase III area was as presented in the CA Technologies report and to provide information and data for evaluation of the site status, relative to NRC guidelines for elease for unrestricted use.3 Radiological information collected i 2 l

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included gamma exposure rates; location of elevated direct rid t at ion leve l s ; and concentrations of radionuclides in surface soil.

Procedures _ ,-

Document Regfew The licensee's survey report for the release of the Phase III area for unrestricted use and other supporting documents were reviewed by ORAU. Data presented in these reports were compared to the established release guidelines.

The licensee investigated the history of radiological use in the Phase II area.

Several areas were identifled with a potential for residual contamina!. ton and were excluded f rom this phase of the decommissioning project.

Facility Survey The location of building 5, which houses the shipping and receiving f acility, is indicated on Figure 4 Shipping and receiving is a small area located in the southwest portion of this building. The total enclosed area is approximately 6.3 m x 15 m (refer to F!,gure 5).

Surface Scans Alpha, beta gamma, and gamma scans were pe rf ormed on floors, using an alph./hta gas proportional floor monitor and NaI(T1) gamma scintillation detectors with audible indicating scaler /ratemeters. A cursory scan of surf aces not accestible to the floor monitor, i.e., walls, ceilings, and overhead areas such as ledges, beams, piping, fixtures, counter tops, equipment, and ductwork was performed using portable ZnS alpha scintillation and "pancake" CM beta-gamma detectors.

Measurement of Surface Contamination Levels Sixteen single point measurements were collected on the floor and lowcr walls of the shipping and receiving area. Locations (Figure 6) were referenced to building features. At each location, direct measurements of alpha and beta-gamma l contamination levels were performed and smears for removable alpha and beta I

contamination were collected.

3

Ten single point measurements for total and removable alpha and bet i-g r a contamination levels on uppe- walls, ceilings, fixtures, and equipment .ere 314s performed. These locations are identified on Figure 7.

Outside Area Survey Survey Reference System 3ecause the history of use of the Phase III property did not identify a significant potential for radiological contamination, a grid system was not established for survey reference. Instead, the property was divided into 20 sections (Figure 8) using identifiable landmarks (i.e., fence and property lines, parking lots and roads). Radiological measurement and sampling locations were referenced to surface features and landmarks.

P Surface Scans walkover surf ace scans were conducted at 5 to 20 m intervals over accessible areas of each section. Portable NaI(Tl) gamma scintillation detectors with audible indicating ratemeters, were used to perform these scans.

Exposure Rate Measurements Exposure rates were measured at the surface and at 1 e above the surface at 2 to 7 randomly selected locations in each of the 20 sections, using NaI gamma scintillation detectors, cross-calibrated onsite with a pressurized ionization chamber. 'feasurements were also performed at 9 locations, directly with the pressurized ionization chamber. Measurement locations are indicated on Figures 9 through 29.

i l

Sampling Surface (0-15 cm) soil samples were collected at locations of exposure rate measurement throughout each section of the Phase III area. Sample locations l

l are indicated on Figures 10 through 29.

l 4

l I

Rackereund and Raseline !!oasurer.ents During a previous site visit, background measurements and soil sanples were [

collected to determine area background and to provide casaline radionuclide ,

concentrations for comparision purposes. Locations of the background measure ents -

and baselinef samples are shown on Figure 30. TTbles 1 and 2 present the j hackground exposure rates and baseline radionuclide concentrations, respectively.

Sample Analyses and Interpretation of Results Samples were returned to laboratories in Oak Ridge, Tennessee, 'or analyses.

All samples were analyzed by ga mma spectrometry. The major radiotuclides of interest were Cs-137, Co-60, U-235, U-238, (fron Th-234 or Pa-234m), Th-232 (from Ac-228), and Ra-226 (f rom Ri-214); however, spectra were reviewed for the presence .

of other significant photopeaks. Selected individual samples and composite samples were also analyzed for Sr-90 and isotopic uranium. Additional information concerning analytical equipment and procedu res is contained in Appendices A and R. Results of this survey were compared to the guidelines, established by the  ;

NRC, for decommissioning of the GA Technologit's Uaste Processing Facility. These guidelines are presented in Appendices C and D. ,

RESULTS i

Document Rtviev ORAU's review of the survey report submitted by CA to the NRC, indicates that f i

the procedures and instrumentation used were consistent with industry accepted practices. The survey, however, provi hd only a limited number of samples as ,

representative of the radionuclide concentrations in the Phase III area. The

~

shipping and receiving area of Building 5 was included as part of the task af ter ORAU had begun the final survey of the Phase III area. Data f rom GA were not available for review. Data developed by CA are within the NRC guidelines, established for this site. ,

i r

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Facility Survey  !

I Surface Scans ,

Surface scans did not identify any locations of elevated alpha, beta-ganma, or gamas cousmination, which would have suggested residual contamination.

Surface Contamination Measurements Table 3 summarizes the results of surf ace contamination measurements. The total contamination data presented in this cabic are direct measurements which include removable and non-removable activity. Alpha and beta-gamma le vels were generally less than the detection sensitivity of the ins t rume nt s . The maximun 2

alpha and beta gamma levels were 75 dps/100 cm and 680 dpm/100 em 2 ,,,p,,ggy,1y, Renovable alpha activity ranged f ron <3 to 7 dpm/100 cm 2and <6 to 7 dpm/100 cm 2 respectively.

r e

Outside Area Survey >

Surface Scans The gamma scan of the area did not identify any areas of gross elevated direct gamma radiation, i i Exposure Rate Measurements I

i i

Exposure rates measured are presented in Table 4. Direct radiation levels ranged f rom 8 to 23 Jt/h. The highest level was found in Section 19.

t Radionuclide Concentration in Soil l r

I 1 Table 5 presents the concentrations of gamma emitting radionuclides, measured j in surface soil collected in each of the 20 sections. Ranges of concentrations in 7

) these samples were Co-60, <0.03 to 1.13 pCi/g; Cs-137, <0.03 to 1.77 pCi/g; Ra-226, <0.14 to 1.69 pCi/g; U-235, <0.15 to 0.46 pCi/g; U-238, <0.15 to 2.02 pCi/g; Th-228 <0.16 to 1.66 pCi/g; and Th-232, <0.21 to 2.15 pCi/g. These .

l 6

4 I

i

cencentrattons are in the ranges of bas e .' i ne samples. The highest radianueLLde concentrations were identif ied in 9ection 5, which is along the south boundary af the main plant site.

Results of Sr-90 and is otopic uranium analyses, perf ormed on selected compos ite Sa.:piiles , are presented in Table 6. The highest concentration of Sr-90 in a composite sample was 0.48 pCi/g . Because this composite was prepared f rom !

individual samples, the maximum level possible in any individual sample would be 2.4 pCi/g. Other compos ites had Sr-90 concentratt e ranging f ron 0.09 to 0.28 pCi/g.

Isotopic uranium analyses indicate concentrations that are well below regulatory guidelines for surf ace sofi. Concentrations ranged from 0.88 to 1.33 pCi/g of U-238; 0.10 to 0.18 pCi/g of U-235; and 1.34 to 1.50 pct /g of U-234. Results of the analysis are presented in Table 6. The highest total uranium concentration was <3.0 pC1/g.

COMPARISION OF SURVEY RESULTS WITH GUIDEl.INES The guidelines f or decommissioning the GA Technologies Phase III property (ref er to Appendices C and D) allow an exposure rate of 10 4/h, above background, at 1 m above the surf ace and over an area of 30 ft (9.1 m) x 30 ft (9.1 m) or The guideline level f or smaller areas is 20 -R/h above background. At greater.

the CA Technologies site, the total exposure rate guidelines would be 19.7 4/h and 29.7 R/h, i.e. 10 4/h and 20 4/h, respectively, plus the average background level of 9.7 R/h (f rom Table 1). One measurement in Section 19 had an exposure rate of 23 4/h, which exceeds the 10 4/h above - background average guideJine. This was a small isolated area and the exposure rate was less than 20 R/h above background. All other measurements were well below 19.7 4/h. The external exposure rate target guideline has been satistied.

Radionuclide concentrations in samples collected f rom the Phase III area were in the range of concentrations measured in baseline samples from the I.a Jolla area. All concentrations were well sithin the guidelines es tablis hed for this decommissioning project.

7

Surf ace contamination levels, measured in the Shipping and Receiving f acili;y of Building ' 5 ' were also all within es tablished ' NRC guidelines for unrestricted use.

SUMMARY

4 -

At the request of the NRC Region V of f ice, on September 7.through 28, Oak Ridge Associated Universities perf ormed a conf irmatory survey of 87 hectares of property at GA Technologies, Inc. in San Diego, Calif ornia. The area surveyed is known as the Phase III portion of the overall site decommissic .g project. The survey included surf ace gamma, be t a-gamma , and alpha scans , meas urement of total and removable surf ace contamination, measurements of direct radiation levels, and measurements of radionuclide concentrations in soil. The findings indicated no areas of residual contamination, exceeding the guidelines established by the NRC for release of the property, and conf irmed the adequacy and accuracy of the radiological measurements perf ormed by the licensee.

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QD)

FA C/F/C P AC!nc CCEAN GEACH I MISSICN i l EEACH ma

'h t

l l

1 SAN DIEGO g l k

k i M:LES y 0 1 2 3 4 5 i i  !  ! I i A I i i i i i i i 4 0 2 4 6 8 xlLCMETERS FIGURE 30: Locations (e ) of Ecckground Measurements enc Boseline Soil Samples frorn tne Vicinity of GA Technologies 38 I

. . .. . . - - _ . - - . - - . ~ .. ,- -, -

-f TABLE I BACKGROUND RADIATION LEVELS GA TECHNOLOGIES

. SAN DIEGO, CALIFORNIA

& =

Gamma Exposure Rates. Gamma Exposure Rates Locationa at I m Above the Surface at the -Surf ace

( R/h). ( 4/h) 1 7 8 2 8 8 3 7 7 4 10 10 5 13 15 6 13 15 RANGE 7 TO 13 7 TO 15 I 9.7 10.5 AVERAGE t

aRef er to Figure 30. ,

P 6

I P

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l  ?

i .

39 l

L.

TABLE 2  ;

i

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BASELINE HADIONUCLlDE CONCfNTRATIONS IN Soll GA TECHNOLOGIES SAN DliGO, CAltf0RNIA 6

1 Lccation*

Co-60 Cs-137 Radlonuclide Concentrations (pCl/g)

R3-226 U-235 U-238 Th(228 & 252) K-40 t

I <0.05 <0.02 L*.59 2 0.14 D <0.17 1.64 f 1.22 1.54 10.46 14.0 t 8. 7 2 <0.05 0.16 ? O.11 0.55 t 0.22 <0.20 1.59 t 1.48 I.98 1 0.86 25.0 t 5. 5 3 <0.04 <0.04 0.79 1 0.20 0.59 ! 0.24 1.07 ! 0.48 2.24 ! 0.62 10.4 t 1. 7 4 <0.08 <0.05 1.20 1 0.29 <0.52 <0.08 3.08 t 0.79 29.0 t 5.4

5 <0.05 <0.05 1.23 1 0.22 0.69 1 0.55 1.28 1 0.62 5.20 1 0.80 - 24.5 t 2. 7 1 6 <0.05 <0.05 0.65 1 0.16 <0.22 1.05 t0.85 .1.92 1 0.78 30.2 ! 2.9

$ RANGE <0.05 to <0.08 <0.02 to <0.16 0.55to 1.23 <0.17 to 0.69 t.05 to 1.64 1.54 to 3.20 10.4 to 50.2 I

i 1 AVERAGE <0.05 <0.06 0.85 <0.35 1.28 2.29 22.2 '

1 i e-c3

)

't aRefer *o Figure 30

{ buncertalntles represent the 955 confidence level based only on counting statistics; additional analytical uncertainties of 2 6 to 105 have not been propagated in these data.

B 1

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TABLE 's

SUMMARY

OF SURFACE CO*4TAMINAT10N MEASURfM[NTS

. BUILDING 5 SHIPPING AND RECEIVING AREA PHASE 111 GA TECHNOLOGIES l *, Art DIEGO, CALIFORNIA 6,

i TOTAL CONTAMINATION (dpm/100 cm ) REMOVA8LE CONTAMINATION (dph/ LOO 'cm )

! Location8 Number of AIpha _

Beta-Gamma AIpha Beta-Gamma 1

j Measurements Range of Range, of Range of Range of Measuremenis Measurements Measurements Measuremen t s H. P. Hood Room Floors / lower walls 3 <27 <465 <4 <6 Upper malls /cellings 2 <27 <465 <3 <6 Vents, flutures, equip. b _ _ _ _

j Shipping Area c.

~

r Floors / lower walls 4 <27 - 75 <465 - 818 <3 <6 Upper malls /cellings I <27 <465 <3 <6 Vents, flutures, equip. - - - - -

a 1^

ReceiwIng Area l Floors / lower walls 7 <27 - 45 <465 - 757 <3 - 7 <6 - 7 4

a bpper malls /cellings 3 <27 <465 <3 <6 s

a Vents, flutures, equip. 3 <27 <465 - 485 <3 <6 4

1 Dock Area 1

Floors / lower walls 2 <27 <465 <3 <6

Equipment I <27 <465 <3 <6 j

i i

aRefer to Figures 5 and 6 b(~) Indicates measurement not performed.

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TABLE 4 DIRECT RADIATION LEVELS *

, PHASE III GA TECHNOLOGIES SAN DIECO, CALIFORNIA

^

Gamma Exposure Rates Camma Exposure Rates Sample ID Locationa at I c: Above the Surf ace At the Surface (uR/h) (tR/h) 182 A SEC 4 10 11 183 A SEC 4 10 10 184 A SEC 4 10 10 185 A SEC 4 13 15

'.86 A SEC 4 10 10 187 A SEC 2 9 9 188 A SEC 2 10 10 189 A SEC 2 9 9 190 '. SEC 2 10 10 191 A SEC 2 8 8 192 A SEC 1 8 9 193 A SEC 1 8 9 194 A SEC 1 8 9 195 A SEC 1 9 9 196 A SEC 1 12 12 197 A SEC 7 8 9 198 A SEC ? 9 9 199 A SEC 3 9 9 200 A SEC 3 9 9 201 A SEC 3 8 7 202 A SEC 3 9 10 203 A SEC 7 9 10 204 A SEC 7 8 8 42

TABLE 4 (continued)

DIRECT RADIATION LEVELS PHASE III GA TECHNOLOGIES S AN DIEGO, CALIFORNI A

~

Camma Exposure &ctes Camma Exposure Rates Sample ID Locationa at 1 m Above the Surface At the Surface

( tR/h ) ( tR/h) 205 A SEC 7 9 10 206 A SEC 7 8 9 207 A SEC 7 9 10 208 A SEC 8 9 9 209 A SEC 8 9 10 210 A SEC 8 10 10 211 A SEC 8 10 10 212 A SEC 5 13 13 213 A SEC 5 13 13 214 A SEC 5 13 13 215 A SEC 6 10 10 216 A SEC 6 13 13 217 A SEC 6 11 11 218 A SEC 6 10 12 219 A SEC 6 11 11 221 A SEC 10 13 13 22? A SEC 10 11 12 223 A SEC 10 8 9 224 A SEC 9 11 13 225 A SEC 9 12 12 226 A SEC 15 12 13 227 A SEC 15 13 15 228 A SEC 15 13 13 229 A SEC 15 12 13 43 l

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TABLE 4 (continued)

DIRECT RADIATION LEVELS PHASE III

. CA TECHNOLOGIES S AN DIEGO, CALIFORNI A Gamma Exposure Rates Gamma Exposure Rates Sample ID Locationa at I m Above the Surf ace At the Surface

( :a/h) (tR/h) 230 A SEC 12 15 15 231 A SEC 12 15 15 232 A SEC 11 16 16 233 A SEC 11 12 12 234 A SEC 11 ,

16 16 235 A SEC 13 15 15 236 A SEC 13 14 15 237 A SEC 13 15 15 238 A SEC 13 16 15 239 A SEC 14 15 15 240 A SEC 14 13 15 241 A SEC 13 13 14 242 A SEC 19 14 15 243 A SEC 19 15 16 244 A SEC 17 12 14 245 A SEC 17 11 11 246 A b b b 247 A SEC 17 11 13 248 A SEC 17 11 12 249 A SEC 18 10 10 250 A SEC 20 13 13 251 A SEC 20 11 10 252 A SEC 16 11 11 44

TABLE 4 (continued)

DIRECT RADIATION LEVELS MEASURED ON PHASE III PROPERTIES Gamma Exposure Rates Gamma Exposure Rates Sample ID Location a at 1 o Above the Surface At the Surface

( $/h) ( 2/h) 253 A SEC 16 13 13 254 A SEC 16 13 15 255 A SEC 18 11 13 256 A SEC 18 13 15 257 A SEC 18 13 15 258 A SEC 18 13 15 259 A SEC 19 16 13 260 A SEC 19 13 11

- 261 A b b b 262 A SEC 19 23 20 263 A SEC 20 13 13 264 A SEC 19 18 16 265 A b b b 266 A SEC 16 13 13 267 A SEC 16 13 15 aRefer to Figures 10 to 29.

b Measurement not performed.

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TABLE 5 RADIONCUllDE (X)NCENTRATIONS IN S0lt PHASE lll GA TECHNOLOGIES SAN DIEGO, CALIFORNIA 6

1 Sample Radlonuclide Concentrations (pCl/g) ,

No. Location a Co-60 Cs-137 Ra-226 6-235 u-238 Th-228 Th- 232 182A SEC 4 <0.04 1.77 1 0.20D 0.70 1 0.11 <0.22 <0.50 <1.80 <0.27 18 5A SEC 4 0.17 1 0.80 0.10 1 0.07 0.90 t 0.21 <0.27 0.28 t 1.6 0.64 1 0.05 0.86 t 0.52 184A SEC 4 <0.05 0.1210.09 1.0 t 0.18 <0.21 0.45 t I.3 <0.28 1.26 ? 0.42 185A SEC 4 <0.06 <0.04 1.16 t 0.26 <0. 50 0.87 ! 0.90 <0.26 1.24 ? 0. 50 '

186A SEC 4 <0.05 0.16 1 0.09 0.83 1 0.28 0.08 1 0.10 1.5510.72 0.89 t 0.29 1.14 1 0.55 18 7A SEC 2 <0.04 0.08 1 0.08 0.73 1 0.12 <0.15 <0.45 <l.59 0.77 ? 0.27 IB8A SEC 2 <0.05 0.25 1 0.10 0.96 1 0.24 <0.19 <0.44 <0.18 1.02 t 0.50 189A SEC 2 <0.05 0.25 2 0.07 0.70 2 0.18 0.10 1 0.08 0.61 1 0,81 0.59 1 0.24 3.70 t 0.45 190A SEC 2 <0.05 0.26 1 0.10 0.95 1 0.28 <0.18 <0.54 <0.25 0.79 t 0.28 19 tA SEC 2 <0.05 0.17 1 0.08 <0.14 0.46 1 0.50 <0.4l <0.17 0.57 t 0. 58 192A SEC 1 <0.04 0.85 1 0.11 0.68 1 0.12 0.10 t 0.08 1.14 1 2.72 0.85 1 0.22 0.60 t 0.24

$[ 195A SEC I <0.05 0.14 1 0.12 1.08 1 0.20 <0.21 <0.61 <0.25 <0.24 194A SEC l <0.05 <0.05 0.62 1 0.16 <4.19 <0.43 <0.16 0.50 ! O.50 195A SEC 1 <0.05 0.45 1 0.10 0.71 1 0.20 0.10 1 0.10 1.16 ! 2.66 C.58 t 0.11 0.72 10.55 196A SEC I 0.06 <0.07 <0.18 <0.25 <0.74 <0.50' <0.51 19 7A SEC 7 <0.04 <0.05 0.86 1 0.17 <0.88 <0.47 <0.21 0.87 1 0.48 198A SEC 3 <0.05 <0.05 0.65 1 0.24 0.15 2 0.07 0.60 t 0.74 1.66 1 0.85 0.60 ! 0.50 199A SEC 3 <0.04 <0.05 <0.14 <0.16 1.76 e 1.12 <0.10 <0.25 200A SEC 3 <0.05 0.07 1 0.04 0.76 1 0.12 <0.17 0.82 ? 0.52 <0.16 0.62 t 0.57 201A SEC 5 <0.05 <0.05 0.40 2 0.11 0.07 2 0.08 0.98 i 0.70 0.40 t 0.20 0. 54 ? 0.20 202A SEC 3 <0.05 0.05 t 0.15 0.76 1 0.17 <0.19 <0.52 <0.22 0.92 1 0.54 205A SEC 7 <0.05 <0.05 0.78 ? 0.17 <0.19 0.60 1 0.44 <0.17 1.15 ! 0. 56 204A SEC 7 <0.04 0.23 ! 0.85 0.60 t 0.17 0.08 t 0.08 0.88 1 0.84 0.71 ! 0.20 0.90 ! 0.51 205A SEC 7 <0.04 <0.04 0.78 1 0.15 <0.18 <0.50 <0.28 <0.24 206A SEC 7 <0.04 <0.05 0.61 t 0.15 <0.18 0.59 1 0.75 <0.16 0.49 ! 0.28 20 7A SEC 7 <0.04 0.58 1 0.11 0.70 t 0.17 <0.20 <0.57 <0.19 1.07 ! 0.?>

208A SEC 8 <0.05 1.01 1 0.16 0.80 t 0.20 <0.18 <0.54 <0.21 0.75 ! 0.40 209A SJC 8 <0.04 0.48 1 0.15 0.84 t 0.19 <0.20 0.77

  • 0.70 <0.17 1.15 t 0. 56

~_ -

~

i TABLE 5 (Continued)

HADIONrut.1DE ONCENTRATIONS IN SOtt PHASF 111 GA TEOP 40LOGIES SAN 01 EGO, CALIFORNIA 6

1 Sample Radionuclide Concentrations rJI/ql ,

No. Locationa Co-60 Cs-137 Ra-226 U-255 U-238 Th-228 Th- 252 210 A SEC 8 <0.04 0.58 1 0.05 0.85 ! 0.24 <0.20 <0.60 <0.19 0.89 t0.55 218 A SEC 8 <0.04 0.15 1 0.10 1.08 1 0.20 <0.20 <0.67 <0.25 <0. 50 212 A SEC 5 <0.06 0.44 1 0.16 1.48 1 0.50 <0.32 1.20 1 0.64 <0. 50 1.61 ! 0.54 215 A SEC 5 <0.06 0.2920.09 1.25 t 0.25 <0.51 <0.91 <0.27

  • 5'
  • 1.45 214 A SEC 5 <0.05 0.0210.11 1.56 1 0.28 <0.24 2.02 1 1.18 <0. 50 1.80 t0.40 215 A SEC 6 <0.04 0.04 1 0.07 0.57 1 0.16 0.25 1 0.25 0.59 1 0.40 <l.68 0. 51 !0.24 216 A SEC 6 <0.06 0.11 f 0.06 1.50 f 0.25 <0.27 <0.85 <0.05 1.21 1 0.48 217 A SEC 6 <0.05 <0.04 0.51 1 0.16 <0.14 <0.55 <0.20 0.46 ! 0. 55 218 A SEC 6 <0.05 <0.04 1.56 1 0.25 <0.28 0.84 1 1.25 <0.29 f.69 ! 0.42 219 A SEC 6 <0.05 <0.04 1.0 1 0.22 <0.26 <0.75 <0.25 0.89 !0.55
c. 220 A SEC 9 <0.04 <0.04 1.05 1 0.22 <0.22 <0.69 <0.27 1.25 ! 0.44 221 A SEC 10 <0.04 0.05 1 0.09 1.15 t 0.26 <0.25 <0.59 <0.25 1.27 ! 0.57 222 A SEC 10 <0.05 0.15 1 0.09 1.11 1 0.25 <0.26 f.40 1 1.45 <0.25 1.68 ! 0.57 225 A SEC 10 <0.04 0.10 1 0.09 0.65 1 0.20 <0.17 <0.55 <0.19 0.72 10.52 224 A SEC 10 <0.04 <0.04 1.28 f 0.22 <0.25 1.07 i O.59 <0.25 8.75 t 0.48 225 A SEC 9 <0.05 0.1810.11 0.92 10.25 <0.26 <0.85 <0.28 1.12 10.14 226 A SEC 15 <0.07 <0.05 1.16 1 0.29 <0.25 <0.88 <0.52 <0.40 227 A SEC 15 <0.06 0.08 1 0.10 1.55 t 0.28 0.51 1 0.44 <0.70 <0.50 1.71 ! 0.56 228 A SEC 15 <0.05 <0.06 1.5820.24 <0.52 <0.95 <0.55 2.00 ! 0.52 229 A SEC 15 <0.06 0.05 f 0.10 1.10 1 0.26 <0.25 <0.79 <0.27 1.06 ! O.50 250 A SEC 12 <0.05 0.06 t 0.11 1.16 t 0.24 <0.26 0.68 1 1.62 <0.25 1.5010.42 231 A SEC 12 <0.06 0.49 1 0.14 1.52 1 0.25 40.26 <0.85 <0.52 1.92 10.57 252 A SEC 11 <0.04 <0.04 1.59 1 0.27 <0.29 0.65 1 0.87 <0.26 1.50 t 0. 50 255 A SEC 11 <0.07 I.01 1 0.16 0.64 ! 0.20 <0.28 <0.64 <0.22 0.64 20.40 254 A SEC 11 <0.06 0.0520.09 1.10 t 0.17 <0.29 <0.86 <0. 50 1.46 t 0.45 255 A SEC 15 <0.04 0.06 1 0.08 1.04 1 0.26 <0.25 0.86 2 1.26 <0.29 2.02 ' O.49 2 56 A SEC 15 <0.05 0.08 ! 0.06 1.25 t 0.22 <0.28 0.89 ! 0.69 <0.27 1.50 ? 0.47 257 A SEC 15 <0.07 0.21 ! 0.07 1.55 t 0.25 <0.29 <0.82 <0.55 3.73 ' 0.rW

TABLE 5 (Continued)

RADIONCULIDE (DNCENTRA110NS IN SolL PHASE III GA TECHNOLOGIES SAN DIEGO, CALIFORNIA Sample Radlonuclide Concentrations (pCl/g) ',

No. Location a Co-60 Cs-157 Ra-226 U-235 6-2 58 Th-228 Th- 252 2 58 A SEC 15 <0.06 3.11 1 0.09 0.99 i 0.19 <0.27 <0.77 <0.25 1.48 ?0.59 259 A SEC 14 <0.04 <0.04 1.5610.16 <0.19 <0.54 <0.22 1.17 ! O. 58 240 A SEC 14 <0.06 <0.06 1.54 1 0.54 <0.51 <0.94 <0.51 1.60 t 0.44 24l A SEC 15 <0.07 0.0210.10 1.55 i 0.28 <0.27 <0.90 <0. 54 1.94 t0.55 242 A SEC 19 <0.06 0.56 i 0.11 1.16 t 0.24 <0. 50 <0.84 <0.29 1.28 t 0.49 24 5 A SEC 19 <0.06 1.15 1 0.20 1.52 10.55 <0.28 <0.15 <0.55 1.45 ! 0.49 244 A SEC 17 <0.05 0.16 1 0.10 0.98 1 0.17 <0.27 <0.85 <0.28 1.10 t0.46 245 A SEC 17 <0.06 <0.05 0.75 t 0.22 <0.22 1.90 i 1.58 <0.52 1.44 ?0.58 247 A SEC 17 <0.07 0.02 1 0.10 1.15 1 0.26 <0.26 <C.80 <0.28 2.15 1 0.56 248 A SEC 17 <0.06 0.05 1 0.09 0.91 i 0.24 <0.21 <0.66 <0.27 1.19 1 0.40 249 A SEC 18 <0.05 0.21 2 0.10 0.o5 1 0.15 <0.22 <0.65 <0.20 1.09 ? 0. 59

[l 250 A SEC 20 <0.08 0.11 ! 0.12 1.15 10.25 <0.27 <0.97 <0. 54 1.52 !0.54 251 A SEC 20 <0.05 <0.05 0.57 1 0.17 <0.20 <0.60 <0.21 ' O.52 t 0.27 252 A SEC 16 <0.05 0.62 1 0.16 0.89 1 0.25 <0.27 <0.86 <0.35 1.21 !0.48 253 A SEC 16 <0.04 0.48 1 0.12 1.20 1 0.25 <0.24 1.54 1 0.60 <0.25 1.40 t 0.55 254 A SEC 16 <0.07 0.29 1 0.21 1.51 ? 0.25 <0.31 <0.96 <0.51 1.27 ! 0.49 255 A SEC 18 <0.07 <0.06 1.56 1 0.26 <0.27 <0.85 <0. 58 1.91 ! 0.56 256 A SEC 18 <0.04 0.02 2 0.11 1.42 1 0.55 <0.29 0.78 1 0.67 <0.50 1.95 t0.47 257 A SEC 18 <0.06 <0.04 1.40 ! 0.55 <0.51 <0.92 <0.55 1.45 t0.51 258 A SEC 18 <0.06 <0.10 1,69 1 0.35 <0. 50 <0.89 <0.57 <0.4I 259 A SEC 19 1.15 1 0.21 0.91 1 0.16 0.47 i 0.18 <0.22 0.4 5 t 1. 58 <0.17 <0.21 260 A SEC 19 <0.04 0.04 1 0.08 0.29 i 0.16 <0.19 <0.55 <0.19 0.47 1 0.55 262 A SEC 19 <0.05 0.08 1 0.12 1.59 t 0.27 <0.25 <0.85 <0.50 1.57 ?0.42 265 A SEC 20 <0.07 0.07 i 0.15 0.88 i 0.25 <0.25 <0.64 <0.25 1.12 ! 0.45 264 A SEC 19 <0.05 0.11 i 0.10 1.46 1 0.26 <0. 50 1.76 1 1.27 <0.27 1.11 ! 0.45 265 A SEC 19 <0.06 0.35 1 0.17 0.86 1 0.25 <0.25 <0.71 <0.27 I.45 ? 0 . 58 266 A SEC 16 <0.05 0.15 ! 0.09 l.16 ! 0.29 <0.26 1.55 ! 0.92 <0.25 1.0 ?0.40 8

Refer to figures 10 through 29 b

uncertainties represent the 951 confidence levels, based only on counting statistics; additional la t>>ra t or y uncertaint.es of ! 6 to 105 have not tenen propagated into these data.

w. . - . - - - -

TABLE 6 RADIONUCLICE CONCENNATICNS IN CoueOSITE Soll PHASE fil GA TECHNOLOGIES SAN OlEGO, CALIFORNIA Radlonuclide Concentrations (eCl/g)

Sample lype 8 Sr-90 V-234 U-235 U-238 Compostto A 0.48 ! 0.18 D 1.50 t 0.20 0.08 2 0.05 1.03 ! 0.'I7 ComposIto B 0.09 1 0.09 1.34 !0.24 0.16 ! 0.10 1.33 ! 0.24 Composite C 0.28 1 0.10 1.33 ! 0.30 0.18 ! 0.12 0.88 ! 0.24 ComposIto 0 0.22 2 0.10 1.31 2 0.25 0.10 t 0.07 1.26 1 0.22 a$aaple Identification numbers:

Composite A: (182A, 183A, 184A, 185A, 186A )

Composite 8: (222A, 223A, 224A)

Composite C: (242A, 243A, 259A, 260A)

Coeposite 0: (250A, 251A,'263A)

D Uncertaintles represent the 955 confidence levels, based only on counting statisticsl additional laboratory uncertainties of f 6 to 101 have not been propcgated into these data.

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REFERENCES

1. Be rge r, J.D. , "Confiroatory Survey of Phase I Decommissioning Former b'aste Processing Facility, CA Technologies, San Diego, California," Oak Ridge Associated Universities, July 1986.
2. "Proposed Confirmatory Survey Plan for 215 Acres at the CA Technologies Site, CA Tecnhologies, San Diego, California," Oak Ridge Assoc'sted Universities, September 8, 1987
3. Letter from K. E. Asmussen (CA Technologies, Inc.) to R. D. Thomas (U.S.

'!uclear Regulatory Commission, Region V),

Reference:

"Licens e SN't-696, Docket 70-734", Augitst 12, 1987.

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  • APPENDIX A MAJOR SAMPLING AND ANALYTICAL EQUIPMENT l

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APPENDIX A MAJOR SAMPLING AND ANALYTICAL EQU1PMTNT The display or description' of a specific product is not to be construed as an' endorsemgdt of' that product or its manufacturer by the . authors or their employer.

A. Direct Radiation Measurements Eberline "RASCAL" Portable Ratemeter-Scaler

-Model PRS-1 (Eberline, Sante Fe, NM)

Eberline PRM-6 Portable Ratemeter (Eberline, Sante Fe, NM)

Ludlum Floor Monitor Model 239-1

. (Ludlum, Sweetwater, TX)

Eberline Alpha Scintillation Probe Model AC-3-7 i (Eberline, Sante Fe, NM)

Eberline GM Pancake Probe Model HP-260 (Eberline, Sante Fe, NM) f Victoreen Beta-Gamma "Pancake" Detector Model 489-110 1 (Victoreen, Cleveland, OH) i Victoreen NaI Scintillation Detector Model 489-55 (Victoreen, Cleveland, OH)

Reuter-Stokes Pressurized Ionization Chamber

" Model RSS-Ill 4

(Reuter-Stokes, Cleveland, OH)

B. Laboratory Analyses Automatic low-background Alpha-Beta Counter Model LB5110-2080 (Tennelec, Inc., Oak Ridge, TN)

High-Purity Germanium Detector Model GMX-23195-S, 23% efficiency

( EC&G ORTEC, Oak Ridge, TN)

A-1 ,

s 6

Used in conjunction with:

Lead Shield, G (Gamma Products Inc. , Palos Hills , IL)

~ High Purity'$ermanium Coaxial Well Detector Model GWL-110210-PWS-S, 23% Ef f iciency (EC&G ORpEC, Oak Ridge, TN)

Used in - conjunction with:

Lead Shield Model C-16 (Applied Physical Technology, Atlanta, GA) 1 High Purity Germanium Detector Model IGC25, 25% Ef ficiency (Petnceton Gamma-Tech, Princeton, NJ)

Used in conjunction with:

Lead Shield (Nuclear Data, Schaumburg, IL)

Multichannel Analyzer ND-66/ND-680 Sys tem (Nuclear Data Inc., Schaumburg, IL)

Alpha Spectrometry System Tennelec Electronics (Tennelec, Oak Ridge, TN)  ;

Surf ace Barrier Detectors '

(EG&G ORTEC, Oak Ridge, TN)

Multichannel Analyzer Model ND-66 (Nuclear Data, Schaumburg, IL) l i

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.- APPENDIX B 1 MEASUREMENT AND ANALYTICAL PROCEDURES 5.

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APPENDIX B Me as u reme n t and Analytical Procedures Su rf a ce Sca ns- ,

Surf ace' scans in the -f acility were perf ormed by passing the _ probes slowly over the surf ace. The distance between the probes and the surf ace was maintained at a minimum - nominally about I cm. Identification of elevated levels was based on increases in the audible signal f rom the recording or indicating- ins trument.

Alpha and beta-gamma scans of large surf ace areas on the floor of i the f acility ,

we re accomplis hed by use of a gas proportional floor monitor, with a 600 cm' sens itive area. -The instrument was slowly moved in a systematic pattern to cover 100% of the accessible area. Combinations of detectors and ins trument for the scans were:

- Beta-Gamma - Pancake G-M probe with PRM-6 ratemeter.

Beta-Gamma - Pancake G-M probe with PRS-1 scaler /ratemeter.

Gamma - NaI scintillation detector (3.2 cm x 3.8 cm crystal) with PRM-6 ratemeter.

Alpha - ZnS probe with PRS-1 scaler /ratemeter.

Alpha / Beta - Gas proportional floor monitor with Ludium Model 222-s cale r/ rat eme te r .

Alpha and Beta-gamma Surf ace Contamination Measurements Meas urements of total alpha radiation level were pe rf ormed using Eberline Model PRS-1 portable s cale r/ratemete rs with Model AC-3-7 alpha scintillation probes. Measurements of total beta-gamma radiation levels were perf ormed using Eberline Model PRS-1 portable s caler/ratemeters with Model HP-260 thin-window

. "pancake" G-M probes . Count rates (cpm) were converted to disintegration rates (dpm/100 ca#) by dividing the net rate by the 4 4 ef ficiency and correcting f or the active area of the detector. Ef f ective window areas were 59 cm' f or the ZnS detectors and 15 cm' f or the G-M detectors . The background count rate for ZnS alpha probes averaged approximately 2 cpm; the average background count rate was approximately 40 cpm f or the G-H detectors.

B-1 w- , - - - ~

Removible Contamination Meaourerents Smear easurements were perf ormed on nunbered filter paper disks, 47 en in dianeter. Smears were placed in labeled envelopes with the location and other pertinent information recorded. The smears were counted on a iov background proportional,tounter at the Oak Ridge laboratory.

Exeosure Rate Measurements

'feasurements of gamma exposure rates were performed using an Eberline PRM-6 portable ra t eme t e r with a Victoreen Model 489-55 gamma scintillation probe containing a 3.2 cm x 3.8 cm NaI(TI) scintillation crystal. Count rates were converted to exposure rates ( L2/h) by onsite cross-calibration with a Reuter Stokes model RSS-111 pressurized ionization chamber.

Soil Sample Analvsis _

Camsa Spectroscopy soil samples were dried, mixed, and a portion sealed in 0.5-liter Marinelli beaker. The quantity placed in the beaker was chosen to reproduce the calibrated counting geometry and ranged from 600 to 800 g of soil. Net soil weights were determined and the samples counted using intrinsic germanium and Ce(Li) detectors coupled to a Nuclear Data Model ND-680 pulse height analyzer system. Background and Compton stripping, peak search, peak identification, and concentration calculations were performed using the computer capabilities inherent in the analyzer system. Energy peaks used for determination of radionuclides of concern were:

Co 1.173 MeV Cs-137 - 0.662 MeV Ra-226 - 0.609 MeV from Bi-214 (secular equilibrium assumed)

U-235 - 0.144 MeV U-238 - 0.094 MeV f rom Th-234 (secular equilibrium assumed)

Th-228 - 0.583 MeV from T1-209 (secular equilibrium assumed)

Th-232 - 0.911 MeV from Ac-228 (secular equilibrium assumed)

Spectra were also reviewed for the presence of other radionuclides.

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i Strontium-90 Analysis Aliquots of, soil were dissolved by pyrosulfate fusion and the strontium-precipitated a's a sulfate. Successive treatments with EDTA preferentially removed lead and excess calcium and returned the strontium to solution. Ferric and other . insoluble hydroxides was _ precipitated at a pH of 12 to 14. S t ront ium was reprecipitated as a sulfate. Barium was re oved as a chromate using DTPA.

The final precipitate of strontium carbonate ' was counted using a low-background Tennelee alpha-beta proportional counter.

fd Alpha Spectrometry for Isotopic Uranium Aliquots of soil were dissolved by pyrosulf ite fusion and precipitated ' with -

barium sulfate. The barium sulfate precipitates were redissolved and uranium separated b,c liquid - liquid extraction. Uranium sas then precipitated with a cerium fluoride carrier and counted using surface barrier detectors (ORTEC),

alpha spect rome te rs (Tennelec), and an ND-66 Multichannel Analyzer (Nuclear Data).

Uncertainties and Detection Limits The uncertainties associated with the analytical data presented in the tables of this report, represent the 95% confidence levels for that data. These uncertainties were calculated based on both the gross sample count levels and the associated background count levels. When the net sample count was less than the 95% statistical deviation of the background count, the sample concentration was reported as less than the detection capability of the measurement procedure.

Because of variations in background levels and Compton contributions from other radionuclides in samples, the detection limits dif f er f rom sample to sample and instrument to ins t rument . Additional uncertainties of 26 to 10%, associated with sampling and laboratory procedures, have not been propagated into the data presented in this report.

Calibration and Quality Assurance Laboratory and field survey procedures are documented in the following

anuals , developed specifically for the Oak Ridge Associated Universities' B-3

Radiological Site As s ess ;_,n t Program: "Survey Procedures Manual,' Revisi m 3 j May 1987; "Laboratory Procedures Manual", Re vis ion 3, May 1987 and "Quality

- Assurance Manual", Revision 1, June 1987.

With the. exception of the meas u reme nts conducted with portable gamma j scintillation survey meters, ins t rume nts were calibrated with NBS-traceable s tanda rds . The calibration procedures for the portable gamma instruments are perf ormed by comparison with an NBS calibrated pressurized ionization chamber.

Quality control procedures on all ins truments included daily background au d che ck-s our ce meas urements to conf irm equipment operation within acceptable s tatis tical f luctuations . The ORAU laboratory participates in the EPA and EML Quality Assurance Programs .

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APPENDIX C GUIDELINES FOR DECONTAMINATION OF FACILITIES AND EQUIPMENT PRIOR TO RELEASE FOR UNRESTRICTED USE OR TERMINATION OF LICENSES FOR BYPRODUCT, SOURCE OR SPECIAL NUCLEAR MATERIAL l

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CUIDELINES FOR DECONTAMINATION OF FACILITIES AND EQUIPMENT

. PRIOR TO RELEASE FOR UNRESTRICTED USE

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OR TERMINATION OF LICENSES FOR. BYPRODUCT, SOURCE OR SPECIAL NUCLEAR MATERIAL U.S. Nuclear Regulatory Cocenission 4

Division of Fuel Cycle & Material Safety l Washington, D.C. 20555 1

July 1982 l

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The instructions in this guice, in conjunction with Table 1 specify the radionuclides and radiation exposure rate limits which should be used in decontamination and survey of surfaces or premises and equipment peior to abandonment or release for unrestricted use. The limits in Table 1 do not apply to premises, equipment, or scrap containing induced radioactivity for which the radiological considerations pertinent to their use may be different. .The release of such f acilities or items f rom regulatory cont rol is conside~ red on case-by-case basis.

1. The licensee shall make a reasonable effort to eliminate residual contamination.
2. Radioactivity on equipment or surfaces shall not be covered by paint ,

plating, or other covering material unless contamination levels, as determined by a survey and documented, are below the limits specified in Table 1 prior to the application of the covering. A reasonable effort must be made to minimize the contamination prior to use of any covering.

3. The radioactivity on the inrerior surf aces of pipes, drain lines, or ductwork shall be determined by making measurements at all traps, and other appropriate access points, provided that contamination at these locations is likely to be representative of contamination on the interior of the pipes, drain lines, or ductwork. Surfaces or premises, equipment, or scrap which are likely to ba contaminated but are of such size, construction, or location as to make the surface inaccessible for purposes of measurement shall be presumed to be contaminated in excess of the limits.
4. Upon request, the Commission may authorize a licensee to relinquish possession or control of premises, equipment, or scrap having surfaces contaminated with materials in excess of cne limits specified. This may include, but would not be limited to, special circumstances such as razing of buildings, transfer of premises to another organization continuing work with radioactive materials, or conversion of facilities to a long-t e rm storage or standby status. Such requests must:
a. Provide detailed, specific information describing the premises, i

equipment or scrap, radioactive contaminants, and the nature, extent, and degree of residual surf ace contamination.

" b. Provide a detailed health and safety analysis which reflects that the residual amounts of materials on surface areas, together with other considerations such as prospective use of the premises, equipment or scrap, are unlikely to result in an unreasonable risk to the health and safety of the public.

5. Prior to release of premises for unrestricted use, the licensee shall make a comprehensive radiation survey which establishes that contamination is within the limits specified in Table 1. A copy of C-1

the <urvey report shall be filed with the Division of Fuel Cycle and Material Safety, USNRC, '4a sh ing t on , D.C. 20555, and also the Administrator of the NRC Regional Office having jurisdiction. The report sho,uld be filed at least 30 days prior to the planned date of abandonment. They survey report shall:

a. ,Identif y the premises.
b. Show that reasonable effort has been sade to eliminate residual contamination.
c. Describe the scope of the survey aad general procedures followed.
d. State the findings of the survey in units specified in the instruction.

Following review of the report, the KRC will consider visiting the facilities to confirm the survey.

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4, TARIE I ACCEPTABIE SURFACE CONTAMINATION LEVEL.S Nuclidesa Averageb,c,f Maximumb,d,f Removableh,c,f U-nat, U-235 U-238, and 5,000 dpa a/100 cm 2 15,000 dem a/100 cm 2 1,000dpmh100cm 2 associated decay products ,

2 2 2 Transuranics, Ra-226, Ra-228, 100 dpm/100 cm 300 dpm/100 cm 20 dpe/iOO cm Th-230, %-228, Pa-231, Ac-227, 1-125, 1-129 2 2 Th-nat, Th-232, Sr-90, Ra-223 1000 dpm/100 cm 2 3000 den / LOO cm 200 dpm/100 cm Ra-224, U-232, I-126, 1-131, 1-133 2 2 Beta gamena emitters (nuclides 5000 dpm Sy/100 cm 15,000 dpa 81/100 cm 1000 dpm 61/100 cm#

with decay modes other than

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alpha emission or spontaneous fission) except Sr-90 and others noted above.

a Where surface contamination by both alpha- and beta-gamma-emitting nuclides exists, the limits established for alpha- and beta-gamma-emitting nuclides should apply independently.

b As used in this table, dpm (disintegrations per minute) means the rate of emission by radioact Ive material as determined by correcting the counts per minute observed by an appropriate detector for background, ef ficiency, and geometric factors associated with the instrumentation.

c Measurements of average contaminant should not be averaged over more than I square sneter. For objects of less surface area, the average should be derived for each such object.

2 d % e maximum contamination level applies to an area of ngt smore than 100 cm ,

e ne amount of removabic radioactive material per 100 cm of surface area should.be determined by wiping that area with dry filter or soft absorbent paper, applying m>derate pressure, and assessing the amount of radioactive material on the wipe with an appropriate instrument of known efficicucy. When removable contamination on objects of less surface area is determined, the pertinent levels should be reduced proportionally and the entire surface should be wiped.

I %e average and maximum radiation levels associated with surface contamination resulting fross beta gamm.s emitters should not exceed 0.2 mrad /h at I cm and 1.0 mrad /h at I cm, respectively, measured through not more than 7 milligrams 3,er square centimeter of total absorber.

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DECOMMIS?IONING CUIDELINES FOR THE GA TECHNOLOGIES FACILITY

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APPENDIX D ,

r Decommissioning Guidelines for the

, GA Technologies Facility Targe,t criteria for unrestricted release of the GA Technologies' Uaste Processing. Facility and surrounding areas are presented in the licensee's final I

report and are as follows:

External Radiation The gamma exposure rate at 1 m above the ground surf ace shall not exceed 10 LR/h above background for an a rea of greater than 30 ft (9.1 m) x 30 ft (9.1 m) and shall not exceed 20 $/h above background for any discrete area (i.e. less than 30 ft (9.1 m) x 30 ft 9.1 m)).

Inhalation and Ingestion Concentrations of radionuclides in soil shall be such that inhalation and ingestion are not expected to result in annual dose equivalents exceeding 20 mrem to the lung or 60 mrem to the bone.

Limiting soil concentrations were derived to satisfy these external and internal target criteria. The concentration limits are presented in the following Table.

Radionuclide Concentration Limit Above Background (pCi/g)

Depleted Uranium 35 Enriched Uranium 30 Thorium (Natural) 10 Co-60 3 1

Cs-137 15 St-90 1.8 x 10 3 l

Uhere more than one radionuclide is present, the sum of the ratios of the individual radionuclide concentrations to their respective concentration limits shall not exceed 1.

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