ML20196D476

Confirmatory Survey of Phase IV Decommissioning General Atomics,San Diego,Ca, Final Rept

ML20196D476
Person / Time
Site:	07000734
Issue date:	11/30/1988
From:	Cotten P OAK RIDGE ASSOCIATED UNIVERSITIES
To:
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ML20196D466	List: ML20196D461 ML20196D476
References
ORAU-88-J-79, NUDOCS 8812090104
Download: ML20196D476 (87)

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Prepared by

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oak Rid e ^$$ociated CONFIRMATORY SURVEY 9

Universities Prepared for OF 1

U.S. Nuclear i

Regulatory commission's PHASE IV DECOMMISSIONING Regi:n V Office Sponsored by GENERAL ATOMICS Division of Ud $u'c"iear Safety SAN DIEGO, CALIFORNIA d

Jica P. R. COTTEN

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i Radiological Site Assessment Nogram Manpower Education, Research, and Training Division FINAL REPORT November 1988 l

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NOT1CES The epanione esproceed hete4n de not necessetley reflect the opinione of the opensering inettutione el ook Ridge Assetteted Unkereities.

I This topett woe propeted as en aceovat of weth openooted by the United States Oevemment Neithee the United States Oevernment not the U.S. Depettment of Energy, not say of theit e@yees, mehee any weitenty, espress of impued, of snowmos any logel Rebelity et mpchelbuity for the secursey, completeness, et usefvinese of any leformation, appetelve, prodwe t, et preceos dieeeeeed, et topteeent s that it s use wecid net infringe pelvotefy owned tigh ts. Rekte nce heteen to any spoeifle eemmetelel product, process, of eefvice by trede name, metti, monstecturet, et otherwise, does 1

not neeeeeertly eenetitute et imply its endettement, tocommendeIten, et tevoting by the U.S. Government et en y agency i

l theteet. The views and openlene of authere espressed herein de not necessatify stole of teMeet these of the U.S.

Oevotament et any agency thereof.

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t;0NFIRMATORY SURVEY OF L-PHASE IV DECOMMISSIONING GENERAL ATOMICS SAN DIEGO, CALIFORNIA Prepared by.

P.R. COTTEN Radiological Site Assessment Program Manpower Education, R.isearch, and Training Division Oak Ridge Associa

.1 Universities Oak Ridge TN 37831 0117 Projer.t Staff J.D. Berger C.H. Searcy 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 November 1988 This report is based on work performed under Interagency Agreement DOE No 40 816-93 NRC Fin.

No.

A 9076 between the U.S.

Nuclear Regulatory Cessission and the U.S.

Department of Energy.

Oak Ridge Associated l

Vr;1versities performs complementary work under contract number DE AC05 760R00033 with the U.S. Depa*tment of Energy.

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TABLE OF CONTENTS P,, age List of Figures.

11 List of Tables.

iv Introduction and Site History...................

1 Site Description..

2 Procedures.

2 Results.

7 l

Comparison of Survey Results with Guidelines.

11 Summary..............................

12 References.

55 Appendices i:fpendix A: Confirmatory Survey Plan for Phase IV Deconmissioning CA Technologies Appendix B: Esjor Sampling and Analytical Equipnent Appendix C: Measurement and Analytical Procedures Appe,endix D: Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Licenses for Byproduct, Source, or Special Nuclear Material Appendix E: Decommissioning Guidelines f.)r the General Atomics Facility

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h LIST OF FIGURES Page FIGURE 1: Map of the San Diego Area, Indicating the Location of General Atomics Facilities.

13 FIGURE 2: General Atomics Plant Layout 14 FIGURE 3: Areas Included in Various Decommissioning Phases.

15 FIGURE 4:

Plan View of Area B1..................

16 FIGURE 5:

Plan View of Area B3 "Callan Ponds" 17 FIGURE 6:

Layout of Building 2 (L Building Complex) 18 FIGURE 7:

Section P f Building 2. Indicating Rooms Included in Phase IV commissioning.

19 FIGURE 8: Sectier

>f Building 2, Indicating Rooms Included in Phase acommissioning.

20 FIGURE 9:

Layout of Room 228, Indicating Locations of Surface Contamination Measurements 21

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FIGURE 10:

Layout of Room 230, Indicating Locations of Surface Contamination Measurement 7......

22 FIGURE i:

Layout of noom 232. Indicating Locations of Surface Contamination Measurements.

23 FIGURE 12:

Layout of Room 236, Indicating Locations of Surface Contaminution Measurements.

24 FIGURE 13:

Layout af Room 311, Indicating Locations of Surface contamination Measurements.

25 FIGURE 14:

Layout of Room 319 Indicatf nt Locationr of Surface Contanination Measurements 26 FIGURE 15:

Layout of Room 331/333, Indicating Locations of Surface Contamination Measuremants.

27 FICURE 16:

Layout of Room 331/333, Mezzanine, Indicating Locations of Surface Contamination Measurements.

28 FIGURE 17:

Layout of Room 419/421 Indicating Locations of Surface Contamination Measurements 29 11 f

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LIST OF FIGURES (Continued)

FIGURE 18: Layout of Room 419/421 Hezzanine, Indicating Locations

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of Surface Contamination Measurements.

30 FIGURE 19: Layout of Room 435/437 Indicating Locations of Surface Contamination Measurements.

31 FIGURE 20:

14yout of Room 435/437 Mezzanine, Indicating Locations of Surface Contamination Measurements 32 FIGURE 21: Callan Ponds. Area 83. Indicating the 10 m Grid System for Survey Reference.

33 FIGURE 22: Locations of Measurements and Sampling from the Ungridded Portion of Area 53...................

34 FIGURE 23: Area 51 Indicating Locations of Measurements and Sampling.

35 FIGURE 24: Subsurface Soil Sampling Locations, Callan Ponds, Area 53.........................

36 FIGURE 25: Locations of Background.".;asurements and Baseline Soil Samples from the Vicinity of General Atomics.

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LIST OF TABLES Page TABLE 1:

Background Radiation Levels.

38 TABLE 2:

Baseline Radionuclide Concentrations in Soil......

39 TABLE 3:

Summary of Surface Contamination Measurements, Building 2 L Building Complex.

40 TABLE 4:

Summary of Surface Contamination Measurements Following Additional Cleanup of the L Building Complex (Building 2) 42 TABLE 5:

Camma Exposure Rates Measured in Area B1........

43 TABLE 6:

Camma Exposure R.,es at 10 m Crid Intervals in Area B3.

44 TABLE 7:

Camma Exposure Rates in Ungridded Portions of Area B3 47 TABLE 8:

Radionuclide Concentrations in Soil From Area B1....

48 TABLE 9:

Radionuclide Concentrations in Surface Soil from Area B3 49

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TABLE 10:

Radionuclide Concentrations in Subsurface Soil From Area B3 51 TABLE 11:

S 90 and Isotopic Uranium Concantrations in Selected Soil Samples.

53 TABLE 12:

Summary of Surface Contamination Measurements in Area B3 Facilities.

54 1.

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CONFIRMATORY SURVEY OF PHASE IV DECOMMISSIONING GENERAL ATOMICS SAN DIEGO, CALIFORNIA INTRODUCTION AND SITE HISTORY In mid 1984, General Atomics (CA) of San Diego, California, initiated decomnissioning activities for the purpose of releasing portions of their facilities from Nuclear Regulatory Commission (NRC) licensing restrictions.

The decommissioning is being accomplished in separate phases.

Phase I cctivities included the Solar Evaporation Pond area, the areas immediately surrounoing the former Waste Processing Facility, the Incinerator Pr.d a previous burial site for contaminated asphalt, the hillside and canyon below the waste handling facilities, and undeveloped land surrounding the vaste processing facilities; Phase II areas were the former Waste Processing Facility cnd the Incinerator Pad; and Phase III consisted of approximately 87 hectares cf undeveloped land, surrounding the main General Atomics plant facilities, and the shipping and receiving area of Building 5.

These Phase I, II, and III areas were previously remediated and confirmatory surveys performed by ORAU.

Results of those surveys are presented in separate reports, 1*3 Two small land areas, B1 and B3, were excluded from the Phase 1;I decommissioning activities.

Area B1 consists of three canyons behind the Hot Cell and TRIGA facilities. Area B3 is the former sewage treatment facility knavn as "Callan Ponds".

These two areas and twelve labcratories in Building i of the L Building Complex have been designated as Phase IV decommissioning.

Potential radiological contaminants on these portions of the General Atomics site, have been identified as enriched uranium, thorium, and longer half life fission and activation products.

At the request of the Nuclear Regulatory Commission, Region V Office, the Radiological Site Assessment Program of Oak Ridge Associated Universities conducted a radiological survey to confirm the status of the Phase IV area, relative to the NRC guidelines for release to unrestricted usw.

This survey was performed June 20-29,1988, in accordance with a survey plan submitted to I

L the Region V Office of the NRC (Appendix A).

Procedures and results of this survey are presented in this report.

SITE DESCRIPTION f

The General Atomics facilition are located near the intersection of Interstate 5 and Genesee Road,

. tor-yoxientely 20 km north of San Diego, CA (Figures 1 and 2).

Phase ~

-7 at a a,i illustrated in Figure 3.

The 6.1 hectares of Area 51, m "n w f igs ' e 4, is undeveloped; the terrain consists primarily of extreu y hea n brush, steep hills, and canyons with limited accessibility.

Area 53, also known as

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is a former sewage treatment i

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facility occupying approximately 1.2 hectart.s (Figure 5).

Various structures in this area include the flocculating tanks, a trickle filter tank, two clarifying tanks, a primary (north) and secondary (south) digester, and the basement and concrete foundation of the pumphouse.

The majority of the buildings are circular tanks of varioes depths and heights.

The flocculating tanks and pumphouse basement are rectangular strvetures.

East of the digesters are three shallow evaporation ponds.

The L Building Complex, containing Building 2, is the focal point of the plant site.

Building 2 is divided into three laboratory sections (A, B, and C),

and is used to house office and laboratory facilities. Many of the labs are no longer operational, and GA has identified non radioactive material programs for this space.

Twelve specific labs in section B and C have been identified for verifict. tion (Figures 6 thru 8).

PROCELURES Obiectives The objectives of the survey were to confirm that the radiological condition of the Phase IV areas is accurately presented in the General Atomics report and to provide information and data for evaluation of the site status, relative to NRC guidelines' for release for unrestricted use.

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L Document Review i

The licensee's survey report for the releasc of the Phase IV area for unrestricted use and other supporting documents were reviewed by ORAU 6 Data 4

presented in these reports were compared to the estabitshed release guidelines.

Survey Plan A plan was prepared, based on the review of CA documents and standard ORAU i

procedures for confirmatory radiological survey. The plan was submitted to the NRC, Region V,

for review and Gement. A copy of the survey plan has been included as Appendix A of this report.

Building 2 Survey Cridding An alphanumeric 2 m x 2 m reference grid system was established on the floor and lower walls (up to 2 m) of laboratories in Building 2.

These include Rooms 228, 230, 232, and 236 of Section B and 311, 319, 331/333, 419/421, and 435/437 of Section C (Figures 7 and 8).

Lab combinations of 331/333, 419/421, cnd 435/437 were gridded together as one room.

Figures 9 through 20 show the room layouts and reference grid systems. Measurements on the upper walls and ceiling were referenced to the floor grid system. The mezzanine areas of rooms 419/421, 331/333, and 435/437 vere not gridded. Measurement locations were

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referenced to prominent building features.

Surface Scans Alpha, bata-gamma, and gamma scans were performed on floors and lower walls, using alpha / beta gas proportional large area detectors and NaI(TI) gamma ceintillation detectors with audible indicating scaler /ratemeters.

Scans of surface areas not accessible to the large area detector, i.e.,

upper walls,

ceilings, and overhead areas such as ledges, beams, piping, fixtures, counter

tops, equipment, and ductvork were performed using portable ZnS alpha 3

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L scintillation and "Pancake" CM beta gamma detectars.

Locations of elevated radiation levels were noted for additional measurements.

Nessurement of Surface Contamination Levels A total of 60 grid blocks on the floor.snd lower walls in the gridded creas of Building 2 were randomly selected for surface contamination measurements.

Figures 9 through 17 indicate the grid blocks selected for five point measurements.

In each grid surveyed, direct measurements of alpha and beta gamma contamination levels were systematically performed at the center and four points midway between the center and block corners.

Smears for removable cipha and beta contamination were performed at that location in each grid block where the highest direct level w4s obtained.

Seventy four single point measurements for total and re.novable alpha and beta-gamma contamination levels were performed on upper walls, overhead surfaces (higher than 2 m) such as ledges, ceilings, beams, pipes, ductwork.

end miscellaneous oquipment. Measurement locations are indicated on Figures 9 through 20.

Exposure Rate Meesurements Camma expcsure rates were measured at 10 locations in Sections B and C of Building 2.

A pressurized ionization chamber (PIC) was used for these measurements.

Outdoor Survey C:idding s Because of inaccessibility, a roterence grid system was not established in Area Bl.

Radiation levels and sampling locations were referenced to prominent f

land features; the survey was concentrated in the canyons and drainage areas.

In Area B3, a 10 m reference grid system was established over the region of the evaporation ponds (Figure 21).

Prominent surface features and landmarks 4

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vere used to reference the location of measurements in the vicinity of the process buildings and the surrounding area.

Surface Scans Walkover gamna surface scans vero conducted at 1 to 2 m intervals in 9

accessible locations of areaa B1 and B3, Portable NaI(T1) gamma scintillation detectors with audible indicating ratemeters, were used to perform these scans.

Exposure Rate Measurements Exposure rate measurements were made at the surface and at 1 m above the surface at gridline intersections and at locations, randomly selected for h

sample collection (Figures 21 through 23).

Portable gamma scintillation detectors, calibrated onsite against a pressurized ionization chamber, were used for these measurements.

Sampling surface (0 15 cm) soil samples of approximately 1 kg each were collected 3

at 10 m grid intervals, at property boundaries, and in the ungridded portians of Area B1 and Area B3.

Ten soil samples were collected from Area B1 and 79 samples from Area B3 (Figures 21 through 23).

Three boreholes were drilled in evaporation pond 1 and one borehole each in evaporation ponds 2 and 3.

locations of these boreholes are shown on Figure 24.

Caesa radiation scans were performed in boreholes to identify elevated radiation levels, which might indicate subsurface residues.

A radiation profile was determined by measuring gamma radiation levels at 15 cm intervals between the surface and bottom of the hole.

Soil samples were collected at 15 cm intervals.

The sampling depth of each hole was approximat.ely 1 m or to "refusal".

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Area 53 Facility Survey Measurement Location References A reference grid system was not established inside the seven (7) process

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facility structures in Area 53.

Measurement locations were referenced to prominent structure features.

Surface Scans Alpha, beta gamma, and gamma scans were performed on the floor and lowet valls, using an alpha / beta gas proportional large area detector and NcI(TI) samma scintillation detectors.

Limited scans of surfaces, not accessib'.e by f

the large area detector, were performed using portable Zns alpha scintillation Cnd "Pancake" GM beta gamma detectors.

Measurement of Surface Contamination Levels Forty one single point measurements for total alpha and beta gamma contamination were performed on the floor and lower walls in the process

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facility structures.

Smears for removable alpha and beta contamination were performed at each location.

Background and Baseline Measurements Background measurements and soil samples were collected to determine area background and to provide baseline radionuclide concentrations for comparison purposes.

Locations of the background measurements and baseline samples are shown in Figure 25.

Samplo Analyses and Interpretation of Results Samples were returned to laboratories in Oak Ridge, Tennessee, for analyses.

All.. pies were analyzed by gamma spectrometry.

The major radionuelides of interest were Cs 137, Co 60, U-235, U 238, and Th 232;

however, spectra were reviewed for the presence of other significant 6

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photopeaks.

Selected individual samples and composite samples were also cnalyzed for Sr 90 and isotopic uranium. Additional information concerning cnalytical equipment and procedures is presented in Appendices B and C.

Survey results were compared to NRC guidelines for decommissioning of the General Atomics Waste Processing Facility (Appendices D and E).

RESULTS Document Review of the survey report submitted by CA to the NRC, indicates ORAU's review

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that the procedures and instrumentation used were consistent with industry cceepted prsctices.

CA findings identified elevated areas within the property boundaries in the Hot Cell Area.

Sa ples collected by CA from the drainage j

creas below the Hot Cell facility contained radionuclide levels within established guidelines.6 CA decontaminated 12 laboratories and 3 mezzanine rooms in Building 2.

Data presented by CA indicate that these areas are within the established NRC guidelines.

Background Levels and Baseline Concentrations Background exposure rates and baseline radionuclide concentrations in soil from the vicinity of the General Atomics site are presented in Table 1 and Table 2.

Exposure rates ranged from 7 to 13 pR/h, at one meter from the surface.

Cobalt 60 concentrations were less than 0.1 pCi/g, Cs 137 ranged from

<0.1 to 0.2 pCi/g, U 235 ranged from <0.2 to 0.7 pCi/g, U 238 ranged from 1.1 to 1.6 pCi/g, and total thorium concentrations ranged from 1.3 to 3.2 pCi/g.

These levels are typical of radionuclide concentrations normally occurring in the, environment.

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Buildinz 2 Survey Surface Scans Surface scans identified small isolated areas of elevated alpha. and beta radiation levels in three laboratory areas. These areas were identified for CA personnel, and additional remedial action was performed.

In Lab 331/333 a contaminated laboratory hood and plenus was removed from the room to reduce contamination levels. Resurveys of these areas indicated that the cleanup was g

I effective in reducing the contamination levels below the NRC guideline levels.

Surface Cont a ination Measurement

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Table 3 summarizes the rasults of surface contamination measurements in Building 2.

For the most part, alpha and beta gamma levels were well below the release criteria and, in many instances, less than the detection sensitivities of the instrumentation.

The highest grid block average for alpha was 2

2 970 drs/100 cm ar.d 16000 dps/100 cm for beta gamma. The maximum removable alpha and beta contamination levels ranged from <3 to 14 dpa/100 cm2 and <6 to 2

12 dpa/100 cm, respectively.

Following additional removal of contamination the levels for alpha and beta gamma measurements were reduced to 2

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<21 dps/t00 en and 740 dps/100 cm, respectively. Removable con';; amination levels were <3 dpa/100 cm2 2 for beta (Table 4).

for alpha and <6 dp /100 cm For single point measurements the highest alpha measurement of 2

970 dps/100 cm was measured on a counter top on the mezzanine of Room 331/333, 2

and the hichest beta gamma measurement exceeded 110000 dpa/100 cm. identified as a small area on the surface of a laboratory hood in Room 311. After the removs1 of the paint from this area, contamination levels were reduced to 2

90 dpa/100 cm for alpha and 1200 dp /100 cm2 for beta gamma (Table 4).

The levels of removable contamination for alpha and beta contamination ranged from

<3 to 16 dpa/100 cm2 2

and <6 to 41 dpm/100 cm,

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Exposure Rate Measurement Exposure rate measurements, performed in laboratories designated for

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conff raation, hallways, and non. occupied office space in Building 2, ranged from 11 to 15 pR/h.

Outdoor Area Survey Surface Scans Camma scans of Area B1 identified some locations of slightly elevated (several times background) samma radiation levels, near the operating facilities; no elevated g a a levels were noted in Area B3.

Exposure Rate Measurements Table 5,

6, and 7 present the results of exposure rate measurements in Area 51 and B3.

Exposure rate levels in Area B1 ranged from 15 to 25 pR/h at l

1m above the surface and from 15 to 25 pR/h at surface contact. The highest level was observed at a location near the Hot Cell facility. The elevated I

readings observed in area B1 are attributed to the operating TRICA and Hot Cell facilities.

Levels in Area B3 ranged from 11 to 17 gR/h at 1 m above the surface and from 11 to 20 pR/h at surface contact.

Radionuelide Concentrations in Soil Samples Table 8 presents the concentrations of gamma emitting radionuclides, measured in surface soil collected from Area Bl.

Cobalt.60, concentrations were

<0.1 pCi/g, Cs.137, concentrations ranged from <0.1 to 2.2 pCi/5; U.235, ranged from

<0.2 to <0.3 pCi/g; U 238, ranged from <0.9 to 1.7 pCi/g; Th.228, 0.1 to 0.6 pCi/g; and Th.232, <0.4 to 1.9 pCi/g. These concentra*. ions are within the ranges of baseline samples.

Table 9 presents the radionuclide concentration in soil samples collected from the surface of Area 53.

Concentration ranges were:

Co.60, <0.1 to 0.2 pCi/g; Cs.137, <0.1 to 2.0 pCi/g; U 235, <0.2 to 0.7 pCi/g; U 238, <0,5 to 9

13.0 pCi/g; Th 228, 0.2 to 0.8 pCi/g, and Th 232,

<0.3 to 2.7 pC1/g.

Approximately 5% of the samples contained U 235 and U 238 concentrations above

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the range in baseline samples.

Concentrations in subsurface soil samples were within the ranges of baseline samples.

The results are tabulated in Table 10.

Concentrations of Co 60 ranged from

<0.1 pCi/g; Cs 137,

<0.1 to 0.2 pCi/g; Ra 226,

<0.2 to 1.5 pCi/g; U 235, <0.3 to 0.2 pCi/g; U 238, <0.1 to 4.1 pCi/g; Th 228, 0.3 to 0.7 pCi/g; and th 232,

<0.3 to 2.1 pC1/g.

On the basis of these results, there does not appear to be migration of radionuclides into subsurface soils.

I Soil samples were randomly selected from Area B1 and Area B3 to determine the concentrations of Sr 90 and isotopic uranium: Table 11 presents the results of these analyses.

Strontium 90 concentrations were below the detection l

sensitivity of the procedure.

Isotopic uranium analyses indicate U 235 contributions ranging from natural to slightly enriched.

The activity ratio of U 234 to U 235, based on the higher concentration samples presented in Table 11, is approximately 27:1.

l Area B3 Facility Surveys l

Surface Scans Surface scans of the process buildings did not identify any locations of olevated alpha, beta gamma, or gassa radiation levels.

Measurament of Surface Contamination Levels Table 12 summarizes the results of surface contamination measurements in tha, process facility buildings in Area B3.

The maximu:s alpha and beta gamma 2

total contamination levels ranged from <21 to 210 dpm/100 cm and 2

<410 to 2730 dpa/100 cm, respectively. Removable contamination ranged from <3 to 5 dps/100 cm2 and <6 to 7 dpm/100 cm2 for alpha and beta, respectively.

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COMPARISON OF SURVEY RESULTS WITH GUIDELINES The guidelines for decommissioning the General Atomics facilities are presented in Appendices D and E.

Surface contamination limits for building surfaces are based on primary contaminants of uranium, Cs.137, and Co.60, identified on this site, and are:

Alpha 2

2 5000 dpa/100 cm, averaged over 1 m 2

2 15000 dps/100 cm, maximum in 100 cm 2

1000 dps/100 cm, removable Beta.Camma 2

2 5000 dpa/100 cm, averaged over 1 m 2

2 15000 dpa/100 cm, maximum in 100 cm 2

1000 dps/100 cm, removable Initial surveys of the 12 laboratories indicated that the surface contamination levels were below guideline levels, with the exception of 'one small area in Room 236, the laboratory hood in Room 311, and several locations in Room 331/333.

Additional remedial action by CA personnel reduced the radioactivity levels in these locations to below guideline levels.

Exposure rate guidelines at 1 m above the surface are limited to 10 pR/h, cbove background, ever an area of 30 ft (9.1 m) x 30 ft (9.1 m) or greater; the guideline level for smaller areas is 20 R/h above background.

At General

Atomics, the total exposure rate guidelines are thus 19.7 pR/h and 29.7 pR/h, based on an average background level of 9.7 pR/h. With exception of small creas near the Hot cell and TRICA facilities in Area 51, the measured exposure levels were below 19.7 pR/h.

The measured levels above 19.7 pR/h were limited to small areas and were less than the 29,7 pR/h applicable guideline.

Concentrations of radionuclides in soil were all below the guideline levels established for this decommissioning project.

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SUMMARY

At the request of the NRC Region V Office, Oak Ridge Associated s

Universities performed a confirmatory survey of Phase IV decommissioning activities at Ceneral Atomics in San Diego, California, during June 7 28, 1988.

The survey included alpha, beta gamma, and gamma scans; exposure rate I

measurements; measurements of total and removable surface contaminatior' and 1

measurements of radionuclide concentrations in soil.

The survey identified several small areas of residual contamination in laboratory rooms which were remediated and resurveyed by ORAU. Other measurements and samples were within the established guidelines.

Based on these results, it is ORAU's opinion that i

the decontamination efforts by the licensee have been effective in meeting the radiological conditions, established for release of this site for unrestricted

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vc'tss FlGURE 9: Laycut cf Room 225, inciccting Lc:ctions cf Surfcce Cont:mination

',t e c s u r e m e n t s 21

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n.oco WALL MEASUREMENT LOCATIONS

]CRoBLock A

[s$f$c*p*oidf)

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a b

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METERS FIGURE 12: Layout of Room 236, Indicating Locations of Surf ace Contamination Measurements 24

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untas FIGURE 14: Layout of Room 319. Indicating Locations of Surf ace Contamination Measurements 26

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FIGURE 15: Layout of Room 331/333, Indicating Locations of Surface Contamination Measurements 27 l

s GAT 31 L

r k

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n_

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WALL MEASUREMENT LOCATIONS (SINGLE POINT)

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2 METERS FIGURE 17: Layout of Room 419/421, Indicating Locations of Surface Contamination Measurements 29

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FIGURE 18: Layout of Room 419/421 Mezzanine, Indicating Locations of Surface Contamination Measurements 30

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METERS FIGURE 19: Layout of Room 435/437, Indicating Locations of Surface Contamination Measurements 31

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WALL MEASUREMENT LOCATIONS FLOOR / LOWER WALL (SINGLE POINT)

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i FIGURE 20:

Layout of Room 435/437 Mezzanine, Indicating Locations of Surface Contamination Measurements 32

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FIGURE 21: Collan Ponds, Area 83, Indicating the 10 r 1 Grid System For Survey Reference 33

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FIGURE 23: Area 81 Indicating Locations of Measurements and Sampling 35

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0 5

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GENERAL ATOMICS

'3 p' FACILITIES i

6 GENESEE AVE.

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FIGURE 25: Locations of Background Measurements and Baseline Soil Samples from the Vicinity of

{

General Atomics 37 I

L TABLE 1

/

1 BACKGROUND RADIATION LEVELS PHASE IV DECOMMISSIONING GENERAL ATOMICS SAN DIEGO, CALIFORNIA" Cama Exposure Rates Gamma Exposure Rates b

Location at 1 m Above the Surface at the Surface (uR/h)

(pR/h) 1 7

8 2

8 8

3 7

7 4

10 10 5

13 15 6

13 1.5 RANGE 7 to 13 7 to,15 AVERAGE 9.7 10.5 cFollow-up Confirmatory Survey of Fhase I Decommissioning Former Waste Processing Fccility CA Technologies, San Diego, CA, March, 1988.

bR:fer to Figure 25.

(

{

(

l 38 I

m m

m m

v r-m.

m.

m v

TABLE 2 BASELINE RADIONIEL:DE CONCENTPATIONS IN S0ll PHASE IV OECGellS$10NING E NERAL ATONICS SAN OBE00, CAllFORNIA*

Radlonuclide Concentration (pCl/O Location Co-60 Cs-137 U-235 U-238 Th-228 Th-232 K-40 1

<0.1

<0.1 0.6 1 0.l*

<0.2 1.6 i 1.2 1.310.5 14.0 1 1.7 2

<0.1 0.2 1 0.1 0.510.2

<0.2 1.6 1 1.5 2.0 1 0.9 25.0 1 3.3 3

<0.1

<0.1 0.7 1 0.2 0.4 1 0.2 1.110.5 2.210.6 10.4 i 1.7 4

<0.1

<0.1 1.2 1 0.3

<0.3

<1.1 3.1 1 0.8 29.0 1 3.4 5

<0.1

<0.1 0.2 1 0.2 0.7 1 0.6 1.310.6 3.210.8 24.3 1 2.7 6

<0.1

<0.1 0.7 1 0.2

<0.2 3.010.9 1.9 1 0.8 30.2 1 2.9 RANGE

<0.1 to <0.1

<0.1 to <0.2 0.5 to 1.2

<0.2 to <0.7 1.1 to 1.6 1.3 to 3.2 0.6 to 30.2 AVERAE

<0.1

<0.1 0.8

<0.5 1.3 2.3 22.2 aFoltou-ep Confirmatory Survey of Phase I Cecomunissioning Former hste Processing Facility GA Technologies, San Diego, CA, Iterch, 1988 bRefer to Figure 25.

cthcertaintles represent the 95$ confidence levels, based only on counting statistics; additional laboratory uncertaintles of 16 to 105 have not been propageted lato these data.

l l

l l

l l

l l

l

m m _.

m m

TABLE 3 r

Stpe4ARY OF SURFACE CONTAMINATION M AStREM NTS BUILDING 2 L BUILDING CO WLEX FHASE IV DECOWilSS10NING GENERAL ATONICS SAN DIEGO, CALIFORNIA Highest Grid TOTAL CONTAMINATION REMOVABLE CONTAMINATION Areas 2

(d es/100 cus )

Exceeding

1. of Grid BlorAs or Block Average Idpm/100 on 3 i

Ross or Aree*

Location Locations Esasured Alpha Beta Alpha Range Bota-Gessee Range Alpha Range Beta Range Criterta Laboatory Section B 228 Floor / Lower unil 5

27

<470

<25-30 (470- 510

<3 (6

Upper unit /Cwiling" 2

WA WA 45

<470

<3

<6 g 230 Floor / Lower hil 5

32 570

<25-40

<450-570

<3

<6 Upper We1I/C.Il 4ng 3

W.i WA 30-110

<470

'3

<6 1

232 Floor / tower West 5

53 730

<21-45

<420-730

<3

<6 Upper unil/Colling*

3 WA WA

<25-40

<470

<3

<6 D

236 Floor / Lower ustl 5

28 16000

<21-31 (420- 62000

<3-14

<6-12 Upper We1I/CeIIIaq' 3

WA WA

<21-74

<420

<3

<6-41 l

Labeatory Sectton C 311 Floor / Lower Wall 10 64 900

<21-64 (450- 1200

<3 (6-8 FIoor*

2 WA WA

<21-50

<450

<3

<6 Upper metf/ Celling" 6

WA N/A

<25-36

<500

<3

<6-7 Equipment (Hood)C 2

WA WA 230 1100008 1

b 319 FIoor/ Lower heil 4

37 820

<21-53

<490-870

<3 (6-9 Upper mil /Colling" 3

WA N/A

<25-27

<500

<3 (6-7 Floor

• 1 WA WA 21

<490

<3

<6

m

~

v s

TABLE 3 (Contlawed)

Supe 4AR) 0F SIRFACE (X)MTAttlNATION ICSIREteENTS BUILDING 2, I. BUILDIteG C0rLEX PHASE IV DEC00041SS10NING

/

GENERAL AT0041CS SAN DIEGO, CAtlFORNIA Highest Grid TOTAL CONTAMileATION RE980VA8LE CONTAMINATION Areas

1. of Grid Blocks or Block Average (dpa/100 cm )

(dpn/100 cm2)

Exceeding Rcom or free Location Locations Measured Alpha Bote Alphe Range Sets <mmme Range Alphe Range Beta Range Criterla 331/333*

Floor / Lower Iseg gb 9

970 730

<28-2800

<450-920

<3-5

<6 1

Upper testa /Colling S

N/A WA

<21-140

<450

<3

<6-12 0

C 331/333 Floor / Lower nemli 7

N/A N/A

<21-40

<450-570

<3

<6 c

Mezzanine Upper teoll/Colling*

2 N/A N/A

<21-120 (450

<3-16

<6 d

Counter tops' 7

WA WA 80- 970

<450-24000

<3

<6 4

41?/421' Floor / Lower Weig 8

36

<470

<21-45 (470

<3

<6 i

b Upper teoll/ Celling

• 3 WA N/A

<21-53

<470

<3

<6 e

Counter Tops

• 1 N/A WA 160

<470

<3

<6 41?/421 Lo.or imell' 5

WA WA

<21 (470

<3 (6

b Morrentne 435/437*

Floor / Lower teoll 9

44

<600

<21-62

<500

<3

<6-7 b

Upper teoll/Colling#

4 WA N/A

<21

<500

<3

<6-8 435/437 F1oor/ Lower temII 7

WA WA

<21

<500

<3

<6 l

c Mezzentne' l

l apeter to Figures 9 through 20 bFlye point o.asurement.

cSind e point measurement.

d8efore edditional cleanup.

• Rooms gridded together.

IMO samples were collected from the floor - area was carpeted.

CSurplus eqelpment storece area.

k

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3 l

d l

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8 o

t e

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1 t

W m

L r

e a

/

a d

c r

p r

t n

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a a

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s o

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l o

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5 1

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s i

s 2

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n e

1 n

n a

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u R

e t

t t

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r c

c N

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e e

e o

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3 3

f l

r 3

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1 1

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L TABLE 5 GAMMA EXPOSURE RATES MEASURED IN AREA B1 PHASE IV DECOMMISSIONING GENERAL ATOMICS SAN DIEGO, CALIFORNIA Gamma Exposure Rate Gamma Exposure Rate At 1 m Above the Surface At the Surface Location" (yR/h)

(uR/h) 1 TRIGA Canyon 20 20 2 TRIGA Canyon 18 18 3 Hot Cell Canyon 25 25 4 Hot Cell Canyon 20 20 5 Hot Cell Canyon 20 20 6 East of Culvert 18 18 7 End of Access Road 15 15 8_ TFF Canyon 22 20 9 TFF Canyon 17 17 l

4R0for to Figure 22.

r

\\

L TABI.E 6 CASMA EXPOSITRE RATES AT 10 m GRID INTERVA1.S IN AREA B3 PHAS1'. IV DECOMMISSIONING GENERAL ATOMICS SAN DIEGO, CALIFORNIA r

Gamma Exposure Rat,e Gamma Exposure Rate

'(

at 1 a above the surface at the surface 1,ocatio n" (DR/h)

(pR/h)

(

SN, OE 12 12 SN, 10E 13 13 5N, 20E 13 13 SN, 30E 13 13 SN, 40E 12 13 5N, 50E 12 11 5N, 60E 12 12 5N, 70E 12 13 5N, 80E 13 13 5N, 90E 11 11 5N,100E 13 13 SN,110E 13 13 5N,120E b

5N,125E 13 14 15N, OE 13 13 15N, 10E 13 13

[

15N, 20E 15 15 15N, 30E 15 15 15N, 40E 15 17 15N, 50E 15 15

(

15N, 60E 15 15 15N, 70E 15 15 15N, 80E 13 13

(

15N, 90E 13 13 15N,100E 13 13 15N,110E 15 15

[

15N,120E 15 15

\\

15N,130E 25N, OE 12 12 25N, 10E 13 13 25N, 20E 13 12 25N, 30E 13 13 25N, 40E 13 15 25N, 50E 13 15 25N, 60E 15 15 25N, 70E 15 15 25N, 80E 13 13 25N, 90E 13 13 25N 100E 13 15 44 v-

TABLE 6 (Continued)

GA.efA EXPOSURE RATES AT 10 m GRID INTERVALS IN AREA B3 PHASE IV DECOMMISSIONING GENERAL ATOMICS SAN DIEGO, CALIFORNIA Gamma Exposure Rate Gamma Exposure Rate at 1 m above the surface at the surface 8

Location (pR/h)

(pR/n) 25N,110E 15 15 25N,120E 15 15 t

25N,130E 13 13

35N, OE 13 13 35N, 10E 13 13 35N, 20E 13 13 35N, SOE 12 13-35N, 40E 13 15 35N, 50E 13 17 35N, 60E 13 13 35N, 70E 15 13 35N, 80E 15 15 35N, 90E 11 11 35N,100E 15 15 35N,110E 15 15 35N,120E 17 17 35N,130E 13 13 45N, OE 11 11 45N, 10E 11 13

[

45N, 30E

(

45N, 40E 45N, 50E 45N, 60E

[

45N, 70E 45N, 80E 45N, 90E 13 13 45N,100E 12 12 43N,110E 15 15 45N,120E 16 17 45N,130E 15 15 45N,145E 13 13 SS, 0E SS, 10E SS, 20E 11 11 SS, 30E 12 12 55, 40E 11 11 l

SS, 50E SS, 60E 11 11 l

1 45 f

~ e f

s L

TABLE 6 (Continued) f GAMMA EXPOSURE RATES AT 10 m GRID INTERVAIS IN AREA B3 PHASE IV DECOMMISSIONING GENERAL ATOMICS SAN DIEGO, CALIFORNIA Gamma Exposure Rate Gamma Exposure Rate at 1 a above the surface at the surface Location (uR/h)

(WR/h) 55, 70E 55, 80E 58, 90E f

55,100E 17 17 aR:fer to Figure 21.

bDash indicates seasurement not performed, due to inaccessibility of location.

l f

46 l

L L

TABLE 7 l

i GAMMA EXPOSURE RATES IN UNGRIDDED PORTIONS OF AREA B3 PHASE IV DECOMMISSIONING GENERAL ATOMICS SAN DIEGO, CALIFORNIA Gamma Exposure Rate Gamma Exposure Rate At 1 a Above the Surface At che Surface a

Locations (uR/h)

(pR/h) 1 11 12 2

11 11 3

12 12 4

12 13 5

12 12 6

13 13 7

12 12 8

11 11 9

10 20 10 12 12 11 17 18 aR3fer to Figure 22.

[

47 l

~

m

.m v.

m...

r c---

TABLE 8 r

RADIONUCLIDE CONCENTRATIONS IN Soll FROM AREA 81 RMSE IV OECGeelS$10NING E ERAL ATOMICS SAN DIEGO, CALIFORNIA Radlonoclide Concentration (pCI/gl Location

• Co-60 Cs-137 U-235 U-238 Th-228 Th-232 b

I TRICA Canyon imder Linac 05603

<0.1

<0.1

<0.2 0.810.5 0.5 1 0.1 1.6 1 0.3 2 40m Domo from DS605

<0.1 0.2 1 0.1

<0.3

<l.0 0.6 1 0.1 1.9 1 0.4 3 Hot Cell under Linac

<0.1 0.1 1 0.1

<0.3 1.4 1 0.8 0.4 1 0.1

<0.4 4 Hot Cell Canyon

<0.1 0.4 1 0.1

<0.3 1.7 1 0.5 0.5 i 1.1 1.5 1 0.2 5 Hot Cet1 Canyon, Botton

<0.1 2.2 1 0.1

<0.3 0.7 1 0.7 0.6 1 0.1 1.5 1 0.4 6 East End of Culvert & Main Canyon

<0.1

<0.3

<0.2 1.2 1 0.2 0.1 1 0.1 0.4 1 0.1 7 East End of Access R>al

<0.1 0.8 1 0.1

<0.2 1.0 1 0.6 0.4 1 0.1 0.9 1 0.2 8 TFF Canyon

<0.1 0.1

<0.3

<0.9 0.6 1 0.1 1.6 1 0.3 9 TFF Canyon

<0.1

<0.1

<0.2 1.0 1 0.3 J.4 1 0.1 1.0 1 0.2 ORefer to Figure 23.

buncertaintiss represent the 955 confidence levels, based only on counting statistics; additional laboratory uncertalntles of i 6 to 10% have not been propagated into these Jata.

N

~

L 0

k TABLE 9 RA010NLCLIDE CONCENTRATIONS IN St.RFACE Soll FRO 4 ARFA B3 PHASE IV OECOMMIS$10NING GENERAL ATOMICS SAN OlEGO, CALIFORNIA Radionuefide Concentretlon (cCl/c) e Location Co-60 Cs-137 U-235 U-238 Th-228 Th-232 SN, 0

<0.1 0.1 1 0.1 0.1 1 0.2 0.7 1 0.4 0.3 1 0.1 0.4 2 0.2 D

91, 10E

<0.1 0.2 t. 0.1

<0.2 0.5 1 0.2 0.4 2 0.1 1.1 1 0.2 SN, 20E

<0.1 0.2 1 0.1

<0.2 1.2 2 0.7 0.6 1 0.1 1.4 1 0.2 SN, 20E

<0.1

<0.1

<0.2 1.2 1 0.3 0.5 1 0.1 1.3 1 0.2 SN. 40E (0.1 0.1 1 0.1

<0.2 0.8 1 0.9 0.4 1 0.1

<0.3 SN, SOE

<0.1

<0.1

<0.2 0.3 2 0.5 0.3 1 0.1 0.7 2 0.2 SN, 60E

<0.1 0.1 1 0.1

<0.2 1.3 1 0.5 0.3 1 0.1 1.0 1 0.3 SN, 70E

<0.1 0.3 1 0.1 0.3 2 0.2 0.6 1 0.4 0.4 1 0.1 1.1 1 0.2 SN, 60E

<0.1 0.1 1 0.1

<0.2 1.6 2 0.3 0.4 1 0.1 1.3 1 0.2 SN,100E

<0.1

<0.3

<0.2 1.3 2 0.5 0.4 2 0.1 0.9 1 0.2 SN,110E

<0.1 0.2 1 0.1

<0.2 0.6 2 0.9 0.5 i 0.1 1.2 1 0.2 SN, 12SE

<0.1 0.3 2 0.1

<0.2 1.1. t 0.3 0.3 1 0.1 0.7 1 0.2 ISN, OE (0.1 0.1 1 0.1

<0.2 1.2 1 0.5 0.4 2 0.1 1.2 2 0.2 I SN, 10E

<0.1 0.1 1 0.1

<0.2 1.2 2 0.6 0.5 i 0.1

<0.3 ISN, 20E

<0.1 0.2 1 0.1

<0.3 2.1 1 1.2 0.8 2 0.1 1.5 1 0.2 ISN, 30E

<0.1 0.1 1 0.1

<0.2 2.3 1 0.5 0.7 1 0.1 1.5 1 0.3 ISN, 40E

<0.1 0.3 1 0.1 (0.3 S.8 1 0.5 0.6 2 0.1 2.3 1 0.4 ISN, SOE

<0.1 0.2 2 0.1

<0.3 1.4 2 1.2 0.7 + 0.1 2.0 2 0.2 j

1SN, 60E

<0.1 0.1 1 0.1

<0.3 0.6 1 0.7 0.8 1 0.1 2.7 1 0.3 l

1SN, 70E

<0.1 0.1 1 0.1

<0.3 3.8 1 0.9 0.5 2 0.1 1.5 2 0.3 1SN, 80E

<1 0.1 1 0.1 0.3 2 0.2 1.2 1 0.8 0.3 1 0.1 0.9 1 0.2 ISN, 90E

<0.1

<J.1

<0.2 0.8 1 0.3 0.4 2 0.1 1.5 2 0.2 ISN 100E

<0.1 0.1 1 0.1 0.7 1 0.2 1.4 1 0.5 0.4 i 0.1 1.1 1 0.2 1SN,110E

<0.1 0.2 2 0.1 (0,0 0.5 1 0.4 0.$ 1 0.1 1.2 2 0.2 1SN,120E

<0.1 0.4 2 0.1

<J.2 2.2 1 0.4 0.5 2 0.1 1.1 1 0.2 f

2SN, OE

<0.1 0.1 1 0.1

<0.2 1.2 1 0.5 0.3 1 0.1 0.6 1 0.3 2SN, 1M

<0.1 0.1 2 0.1

<0.2 0.7 1 0.3 0.3 1 0.1 1.5 1 0.2 2SN. 20E cc.1 0.2 2 0.1

<0.2 2.3 1 0.3 0.4 2 0.1 1.0 2 0.2 2SN, 2M

<0.i 0.5 1 0.1

<0.3 0.7 1 0.4 0.4 2 0.1 1.3 1 0.2 25W, 40E

<0.1

<0.1

<0.2 2.7 1 0.3 0.3 1 0.1 1.0 1 0.2 2SN, SOE

<0.1 0.3 1 0.1

<0.2 1.6 1 0.4 0.4 2 0.1 1.0 1 0.2 2sN, 60E (0.1

<0.1

<0.3 1.1 1 0.5 0.7 1 0.1 2.0 2 0.2 f

2SN, 7M

< 0,1 0.1 1 0.1 (0.3 1.7 +. 0.3 0.5 1 0.1 1.3 1 0.2 25N, 80E'

<0.1 0.1 1 0.1

<0.3 1.7 2 0.6 6 4 1 0.1

<0.3 2SN, 90E

<0 !

<0.1

<0.2 1.0 2 0.7 0.320.1

<0.3 2SN.100E

<0.1 0.2 1 0.1

<0.3 0.5 1 0.4 0.2 2 0.1 1.4 1 0.2 2SN,110E

<0.1 (0.1 (0.3 0.6 1 0.4 0.7 + 0.1 1.6 1 0.3 2 M,120E

<0.1 0.2 1 0.1

<0.3 1.5 2 0.8 0.7 1 0.1 1.7 1 0.2 3SN, OE

<0.1

<0.1

<0.2 3.2 2 1.1 0.3 2 0.1 1.0 1 0.2 3SN, 10E (0.*

0.1 1 0.1

<0.2 1.3 2 0.3 0.2 1 0.1 0.9 1 0.2 3SN, 20E

<0.1 0.1 1 0.1 so.3 1.3 2 0.6 0.4 1 0.1 1.2 1 0.2 3SN, 30E

<0.1 0.7 1 0.1 0.6 1 0.3 8.7 t 1.0 0.5 2 0.1 1.2 1 0.2 3SN, 4M

<0.1 0.4 2 0.1

<0.2 0.6 1 0.7 0.3 2 0.1 0.5 1 0.3 49 k

TABLE 9 (continued)

RADIOMILIDE CONCENTRATIONS IN SLRFACE Soll 6

FRG4 AREA B3 PHASE lY DECOMMIS$10NING GENERAL ATCaelCS SAN 01E00, CALIFORNIA Redlonuclide Concentration foC1/g) location Cc-60 Co-137 U-235 U-238 Th-228 Th-232 35N, SOE

<0.1

<0.1

<0.2

<0.6 0.3 1 0.1 0.9 1 0.2 35N, 60E

<0.1

<0.1 0.8 1 0.2 3.4 1 1.0 0.5 1 0.1 1.3 1 0.2 35N, 70E

<0.1 0.1 1 0.1

<0.3 1.910.5 0.610.1 1.610.2-35N, 80E

<0.1 0.1 1 0.1

<0.3 0.7 1 1.1 0.4 1 0.1

<0.3 35N,100E 0.2 1 0.1 0.5 1 0.1

<0.3 4.510.9 0.510.1 1.6 2 0.2 35N,110f

<0.1 0.1 2 0.1

<0.3 0.8 1 0.7 0.7 1 0.1 1.7 1 0.3 35N,120E

<0.1

<0.1

<0.4 1.9 2 0.8 0.6201 1.8 1 0.3 35N,130E

<0.1

<0.1

<0.3 1.7 1 0.6 0.3 1 0.1 1.0 1 0.2 45N, 0

<0.1 0.1 1 0.1

<0. 2

<0.7 0.3 1 0.1 1.0 1 0.2 45N, 10E

<0.1

<0.1

<0.3 0.6 2 0.6 0.3 1 0.1 0.8 t'0.1 45N,100E

<0.1 0.3 1 0.1

<0.2 1.510.7 0.3 1 0.1 0.8 1 0.2 45N,110E

<0.1 0.4 1 0.1

<0.3 3.0 2 0.8 0.5 1 0.1 1.2 1 0.3 45N,120E

<0.1 2.0 1 0.1 0.7 2 0.4 13.0 1 2.2 0.4 1 0.1 1.2 2 0.3 45N,145E

<0.1 0.1 1 0.1

<0.7 1.1 1 0.5 0.3 1 0.1

<0.3 SS, 40E

<0.1

<0.1

<0.2

<0.5 0.3 2 0.1 0.7 1 0.2 55,100E

<0.1

<0.1

<0.2 0.4 1 0.5 0.3 2 0.1 1.0 1 0.1 1

<0.1 0.2 2 0.1

<0.2 0.6 i C.6 0.2 + 0.1 0.6 1 0.2

(

2

<0.1 0.7 1 0.1

<0.2

<0.7 0.3 2 0.1 0.7 2 0.2 3

<0.1 0.1 1 0.1

<0.2 1.1 1 0.6 0.2 1 0.1 0.7 1 0.2 4

<0.1 0.2 2 0.1

<0.3 1.7 2 0.8 0.4 1 0.1 0.9 1 0.2 5

<0.1 0.1 2 0.1

<0. 2 0.4 2 0.6 0.3 2 0.1 0.6 1 0.3 6

0.1 1 0.1 0.5 1 0.1

<0.2 0.3 2 4.8 0.4 1 0.1

<0.3 7

<0.1

<0.1

<0.2 0.9 2 0.5 0.3 2 0.1 0.5 1 0.3 8

<0.1 0.7 1 0.1

<0.2

<0.7 0.2 2 0.1 0.6 1 0.1 f

9

<0.1

<0.1 0.7 2 0.2 2.3 2 0.6 0.3 2 0.1 0.8 1 0.2 10

<0.1

<0.1

<0.2 0.5 1 0.3 0.3 2 0.1 0.7 2 0.2 11

<0.1

<0.1

<0.2 0.710.3 0.220.1 0.6 2 0.1 sRefer to Figures 21 and 22.

buncertelnti,es represent the 995 confidence levels, based only on counting statistics; additional laboratory unc rtelntles of 16 to 105 have not been propagated into these date.

l 50 l

1 n

33 3 3 223 2 2233 23 22 23 0 00 0 0 0 0 0 0 0 00 00 00 2

111 1 1111 1111 11 11 hT 5542 81 3 3 2051 1 8 87 1 1 1 1 1 1 1 1 1 1 1 2 1 1 1 1 e

1 1 1 1 1 21 1 1 1 1 1 1 1 1 1 82 000 0 000 0 0 000 00 00 2

)

1111 1111 1111 11 11 g

h

/

T 654 5 5655 3 4 66 47 75 l

C 0 P00 00 0 0 00 00 00 0d p

(

no i

tar 1 8 5

81 7

06 07 77 tn 8

1 0 0

01 0

1 0 1 0 00 c

2 11

8. 1 11 0. 1 7 11 4 11 11 e

3 n

0 1

0< 1 9. 0<

50 1 1 t

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00 1

02 1

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e d

N i

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cs F

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2 3

S G

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3 3 3 3 3 3 332 23.i 3 1 3 33 S

4 I

0 N

2 0c 0 u0 0 0 0 0

0 S R 0 0 0 0<

N 1

2. <

< < 2 <

(

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BS G F.

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N A O L O E mT A oA C E

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T T G RO N R V E E E F I N

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1 1

1 1

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0 0

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1 1 1 1 1 1 1 1 1 1 1 1

)

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0 0 00 0 0

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2. <

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1 < 1 <

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6 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 C

40 0 0 000 0 0 0 00 00 00 o

< < (

( < (

ac cmcmm mcmmc mm mm m

m mcms m

~

c h

t 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 p

1 4 7 0 1 4 7 0 1 4 7 0 1 4 1 4 e

1 1

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00 0 0 000 0 O 0 0 0 00 00 3 6 9 3 6 9 3 6 9 3

3 E E E E E E E

.E E

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~5 5 S 9 8 0, 0 o

I a4 4 4 1 1 1 1 0 0 0 C 66 t 6 1,

1 1, 1, 1 1 1, T, t

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N N N N N 1 N N N wS N N N N e

c S S 0 0 @0 5 S 5 S 9 9 8 8 o

L t I I I 4 4 4 4 1 1 1 1 m

s~

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a 0 0 l

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d 8

0 a

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2 1 8 t

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r.

0 t

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CA d

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R R

a t

t S

G s

B N

A d

S I

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g

)

U 3 3 r.

M N

N 3

e OS 1 2

i n

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G 0 0 t

u N

C I

F U

nu B S M l

i O l o

t S

l T A c

n N A 4 o

0 E KA C R 0 n

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T A C L,

n I

A E A O 7

0 R 4 O R G 3

y 1

T O E E 1

1 1 l

n N R V N I

s 0 0 o

D E

E F I E

C L

C B

N E

N d

A O

S A

e T

C A

S s

H a

E P

b C

a

,t I

L s ad C

l U

e OI d

v e N

1 1 e s 0 0 e

l D

r h

A e t R

c n o e

'n d

i I

f n d o e c t a

5 g 5 a 9 p mm o

c c e r h

h p t

5 5 t

p 7 0 n

t.

e e

1 D

r e 00 e b 6 9 s

. e t 4 r o 2 p ne er e

/

r v

u s a g e h i

l s

n E E F t f o

0 0 n i 66 oil i

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s I

L TA8LE 11

$r-90 AND ISOTOPlc LRANilN CONCENTRATIONS IN SELECTEU Soll $AMPLES PHASE IV OECO#4t$$10NING

[

GENERAL ATOMICS

(

$AN OlEJO, CALIFORNIA Redlonuclide Concentration (pCl/c) location

• Depth

$r-90 U-234 U-235 U-238 Area 81'

(

C TRIGA Cenyon Surface

<0.1 1.2 1 0.2

<0.1 1.2 1 0.2 Hot Cell Canyon Surface

<0.1 1310.2

<0.1 1.3 2 0.2 Hot Cell Canyon Sur' ace

<0.2 1.3 1 0.2 0.1 2 0.1 1.4 2 0.2 f

TFF Canyon (#8)

Surface

<0.1 0.4 1 0.1 0.1 2 0.1 0.3 1 0.1 East End of Culvert (#6)

Surface

<0.1 0.7 1 0.1

<0.1 0.7 2 0.1 East End of Access Roed (#7)

Surface

<0.1 0.9 2 0.1

<0.1 0.8 :: 0.1 Atta BS

[

SN, 20E surface

<0.1 1.1 1 0.2

<0.1 0.6 1 0.2 l

SN, 60E Surface

<0.1 1.5 1 0.1

<0.1 1.0 1 0.1 SN, 100E Surface

<0.1 0.8 1 0.2

<0.1 0.7 2 *J.2 W. 110E Surface

<0.1 1.0 1 0.2

<0.1 0.910.2 f

15N, 30E Surface

<0.1 2.5 1 0.3 0.1 1 0.1 1.7 1 0.3 IW, 60E Surface

<0.1 1.6 1 0.3 0.1 2 0.1 1.1 1 0.3 15N, 1204 Surface

<0.1 2.5 2 0.3

<0.1 1.8 1 0.2 2)N, OE Surfece

<0.1-0.8 1 0.2

<0.1 0.9 1 0.2 25N, 100E Surface

<0.1 2.9 1 0.4 0.1 2 0.1 2.2 1 n.4 35N, 50E Surface

<0.1 1.4 1 0.3 (0.1 0.9 ?. 4 3 4 5N, OE

$urface

<0.1 1.3 2 0.3 0.1 1 0.1 0.8 2 0.2 f

North of Primary Olgester (74) Surface

<0.2 5.1 1 0.4 0.2 1 0.1 2.9 1 0.3 At Souts Fence At Boundary (78) Surf ace

<0.1 1.4 1 0.3 0.1 1 0.1 1.4 2 0.3 18N, 60E 0- 15 cm

<0.1 1.5 1 0.2 0.1 1 0.1 0.9 1 0.1 f

18N, 60E 30- 45 cm

<0.1 1.9 1 0.2 0.110.1 1.3 1 0.1 IGN, 60E 60- 75 cm (0.1 1.9 1 0.4 0.1 2 0.1 1.6 1 0.4 18N, 60E 90-105 cm

<0.1 1.6 1 0.2 0.1 2 0.1 1.4 1 0.2 22.0 1 0.8 1.8 1 0.3 8.8 1 0.5 3'N, 30E turface 4.4 2 0.4 0.1 1 0.1 2.010.3 35N, 60E Surface 33.0 1 0.9 1.6 1 0.3 19.4 1 0.7

~

ASN, 120E Surface 9.0 1 0.6 0.5 1 0.2 4.2 2 0.4 Setween the Pusehouse Surface and Flocculation Tank (#9) eRefer to Figure 23.

{

bRefer 4 Figures 21, 22, and 24 cijncertalettes represent the 955 confidence levels, based only en counting statistics; additional laboratory uncertaintles of 2 6 to 105 have not prope2ated into these atta.

53

s l

c h

TA8LE 12

$UMMARY OF StR*CE CONTAMINATION MEASUREMENTS IN AREA 83 FACILITIES PHASE IV DECCMMIS$10NINO

(

OENERAL ATOMICS

$AN DIEGO, CALIFORNIA TOTAL CONTAMINATION REMOVA8LE CONTAMINATION 2

Number of (dpe/100 cm2)

(dpm/100 cm 3 Location

• Measurements Alpha Range Sete Comms Range alpha Range Beta Rengs Floculating Tanks Floors 6

<21-210 1100-1800

<3 46 Lose r We ll 6

<12-170 1100-2700

<3

<6 -7 Tricklo Filter Tank Floor 3

<21-64 1500-1800

<3

<6 Loser Well I

<21 1300

<3 7

West Clarifying Tank 3

<30- 85 670-1500

<3

<6 Floor f

Lower Well 2

<30 1I00

<3

<6 EOt Clarifying Tank Floor 2

32-42 1200-1700

<3

<6 Lower WeiI 2

53-120 1500-2700

<3

<6

[

Pwiphouse Rosement l

Floor 2

<30- 32 1400

<3

<6 Lower Well 2

<30

<410-900

<3

<6 f

Secondary (South) Olgester Floor 3

<30 450- 930

<3

<6 Loser Wei1s 2

<30 1100-1200

<3 (6

Priman (North) Olgester Floor 2

<30 630- 700

<3

<6 Lower Wells 2

32-140

<410

<3

<6 Fumphoute Foundation (Concrete Slab) 3

<30 800-1000

<3-5

<6-7 eRef:r to Figure S.

54 1

I t

REFERENCES 1.

"Confirmatory Survey of Phase I Decommissioning, Former Waste Processing

(

Facility, CA Technologies, San Diego, California," Oak Ridge Associated

(

Universities, July 1986.

2.

"Confirmatory Survey of Phase II Decom:nission'.ng, Former Vaste Processing

(

Facility, CA Technologien San Diego, California," Oak Ridge Associated Universities, March 1987.

[

3.

"Confirmatory Survey of Phase III Decommissioning, CA Technologies, San t

Diegs, California," Oak Ridge Associated Universities, February 1988.

4.

Letter from K.E. Asmussen (CA Technologies, Inc.) to R.D. Thomas (U.S.

Nuclear Regulatory Conssission, Region V),

Reference:

"License SNM.e>6 Docket 70 734", May 10, 1988.

{

5.

Letter from L. Quintana (CA Technologies, Inc.) to J.D. Berger (Oak Ridge Associated Universities), May 26, 1988.

6.

Letter from K.E. Asmussen (CA Technologies, Inc.) to R.D. Thomas (U.S.

(

Nuclear Regulatory Commission, Region V),

Reference:

"License $NM 696 Docket 70-734", June 2, 1988, l

l l

l l

l l

55

1 r

l s

[

l l

l I

APPENDIX A

[

CONFIRMATORY SURVEY PIAN FOR PHASE IV l

DECOMMISSIONING, CA TECHNOLOGIES l

l

~

e

APPENDIX A CONFIRMATORY SURVEY PIAN i

FOR

{

PHASE IV DECOMMISSIONING CA TECHNothGIES SAN DIEGO, CALIFORNIA 1.

Site History and Description In mid 1984, CA Technologies, Inc.

(CA) of San Diego, California, initiated decommissioning activities for the purpose of releasin, portions of their facilities from Nuclear Regulatory Commission (NRC) f licensing restrictions.

The deco'smissioning is being accomplished in separate phases.

Verification of Phases I,

II, and III have been

{

completed.

Phase IV properties include the abandoned sewage treatment facility known as

'Callon Ponds',

(Area B3),

13 laboratories in Building 2, and Area 51, the caryon area to the west and below the TRIGA and tot cell facilities.

The Callon Ponds consist of approximately 1.2 hectares enclosed by a security fence.

Several remaining structures, used during operation, are the pumphouse, a trickle filter tank, a primary (north) and secondary (south) digester, flocculating tanks, two

(

.arifying tanks large evaporation pond, and two smaller evaporation ponds.

Buildint 2 is divided into three laboratory sections. The

{

13 rooms are locateo in the upper und lover levels of laboratory sections 2 (53 m ) of area in these 2

B and C.

There is approximately 5700 ft 13 rooms.

Area B1 is composed of approxirsately 6.1 hectares of steep canyons.

There are no facilities or equipment located in this area.

Potential radiological contaminants in the areas included in this survey have been ident.ified as enriched uranium, thorium, and longer half life fiss. ion and activation products.

Phase IV activities have been completed and reports vez. 1::ued by CA

{

Technologies on May 10, 1988 and June 2,1988, indicating that post f

Prepared by the Manpower Education, Research, and Training Division of Oak Ridge Associated Universities, Oak Ridge, Tennessee, under interagency agreement DOE No.

40 816 83.

NRC Fin. No. A 9076, between the U.S. Nuclear Regulatory Commission and the U.S. Department of Energy.

June 7, 1988 A-1

f L

(

du entamination radiological conditions satisfy the NRC guidelines for decommissioning.

Region V of the NRC has requested that the Oak Ridge Associated Universities (ORAU) Radiological Site Assessment Program perform a confirmatory radiological survey of Phase IV locations.

II.

Purpose f

The purpose of the confirmatory survey is to verify that remedial actions and associated documentation provide an accurate and complete description

(

of the condition of the property and thereby, confirm that remedial actions have been effective in satisfying the NRC guidelines for release for unrestricted use.

III. Responsibility Work described in this survey plan 4 11 be performed under the f

supervision of Mr.

J.D. Berger, Manager and Mr. C.L. Murphy, Assistant Manager with Radiological Site Assessment Program of Oak Ridge Associated

(

Universities, and in accordance with standard procedures set forth in "Survey Procedures Manual", "Laboratory Procedures Manual", and Quality Assurance Manual", developed specifically for that program.

IV.

Procedures f

A.

ORAU will review background documentation, radiological characterization data, and post remedial action data.

Information

(

vill be evaluated to assure that areas identified as exceeding site guide'.ine s have undergone remedial action and that residual l

contamination satisfies the established guidelines, i

s A-2

(

B.

A survey team froa ORAU will visit the CA site and perform visual inspections, independent measurements of alpha, beta gamma, and gamma radiation, and soil sampling.

Reference grid systems, established by

(

CA Technologies will be utilized, where possible.

{

C.

Independent measurements and sampling will be performed on portions of the area to be verified.

Typically, the independent survey will cover only a portion of the total remediated area, depending upon such factors as use

history, radiological

history, and decontamination procedures.

For larger areas independent surveys will typically covar from 10 to 50% of the remediated area; up to 100% of individual small remediated areas may be surveyed as part of f

the confirmatory process.

During field activities, the scope of the survey may be increased or decreased, based on findings as the work l

progresses.

1.

A walkover gamna surface scan will be performed over related remediated areas of the site, where access can be obtained, using portable gamma scintillation detectors and ratemeters with audible indicators. Traverses will be at 12 m intervals in the gridded areas and locations where elevated direct radiation f

levels are noted.

Scans may be expanded to the remainder of the remediated

area, if results of initial scans identify

{

discrepancies or deficiencies in the decontamination action.

Locations of elevated contact measurements will be documented for further a',

tion.

2.

Camma exposure race measurements will be made at the surface and 1 m above the surface at single locations near small remediated arcas and at 10 m intervals throughout remediated areas selected f

for independent survey, Measurements will also be made at locations of elevated direct radiation, identified by walkover

(

scans.

3.

Soil samples will be collected at locations of direct acasurement as indiccted in IV.C.2.

above. The samples will be collected A-3 l

r from the surface (0 15 cm) of the remediated area, except where b

direct measurements suggest possible residual, subsorface contamination.

In these cases, portaolo augering equipment will

(

be used to collect subsurface soil samples.

Subsurface samples to 12 m deep will be obtaine'd from 10-15 randomly selected

(

locations within the gridded area and in locations identified by surface scans as potential areas of residual contamination. The exact number,

location, and depth will be determined as the survey progresses.

4.

Where contamination may exist on facility or equipment surfaces, the surfaces will be scanned for elevated gamma radiation levels f

and for alpha and beta gamma contamination. Up to 100% of the areas selected for survey may be covered by the scans, depending upon the use and radiological history.

5.

Alpha and beta gamma contamination measurements will be performed on facility and equipment surfaces.

For remediated areas smaller 2

than 10 m, single point measurements of total contamination will be performed; the number of such measurements will be based on the actual area of each remediated location.

Sample locations will be referenced to prominent building features.

For areas 2

larger than 10m,

a 2 m x 2 m grid will be established on the

floor, and in selected grid blocks direct measurements of alpha and beta gamma contamination will be systematically performed at the center and at four points, midway between the center and the block corners.

Upper walls and ceiling measurement locations will be referenced to the floor grid or to pertinent building features.

6.

Smears for removable contamination will be performed oa remediated structures and equipment, at the location of highest direct measurement in each grid block surveyed, and at all locations of single-point measurements.

A-4

[

w l

7.

Direct measurements and smears will be obtained on piping, cracks, beams, ledges, ducts, and other surfaces where material might settle or accumulate.

The survey will also include the inside surfaces of any drains. The number of locations measured will be determined as the survey progresses.

Needs for additional measurements and sampling beyond the scope described in this plan will be determined based on specific site conditions and results.

{

8.

Samples of building material; residue from cracks,

ledges, piping, ducts, drains, and subfloor soil vill be collected. The number and location will be determined based on the availability of sample media and direct measurements, f

9.

Residual contamination, identified by di :t measurements, will be brought to the immediate attention of the licensee.

If additional cleanup is performed during the survey, ORAU will conduct follow up sampling and measurements of the cleaned areas.

V.

Data and Sample Analysis Samples and direce measurement data vill be returned to the Oak Ridge, TN laboratory for analysis and interpretation.

Data developed by the independent verification surveys will be compared with the established guidelines (Attachment A) to assure that decontamination has been effective in meeting these guidelines.

Soil, residue, tile, and other solid materials will be analyzed by solid state ganusa spectrometry.

Radionuclides of primary interest are U 238, U 235, Th 232. Th 228, Co 60, and Cs 137: however, spectra vill be reviewed for other identifiable photopeaks.

Selected and/or computed samples will be analyzed for Sr 90.

.A gross alpha beta counter will used to determine gross activity on smi.ars.

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Tentative Schedule L

Site Survey June 20 July 1,1988 Sample Analysis July 5 - August 1,1988 Draft Report September 1988 l

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ATTACHMENT A Decoimaissioning Guidelines for the CA Technologies Vaste Processing Facility Target criteria for unrestricted release of the GA Technologies' Vaste Processing Facility and surrounding areas are presented in the licensee's final report and are as follows:

External Radiation

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The gamma exposttre rate at 1 a above the ground surface shall not exceed 10 pR/n above background for an area of greater than 30 ft x 30 ft and shall not exceed 20 pR/h above background for any discrete area (i.e.

less than 30 ft x 30 ft).

Inhalation and Intention Concentrations of radionuclides in soll shall be such that inhalation and ingestion are not expected to result in annual dose equivalents exceeding 20 mram to the lung or 50 area to the bone.

1 Limiting soil concentrations were derived to satisfy these external and internal target criteria.

The concentration limits are presented in the following table.

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Radionuclide Concentration Limic Above Backaround (DCi/a):

Depleted Uranium 35 Enriched Uranium 30 Thorium (Natural) 10 Co.60 8

Cs.137 15 Sr.90 1.4 x 103 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.

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APPENDIX B

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MMOR SAMPLING AND ANALYIICAL EQUIPMENT

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APPENDIX B MMOR SAMPLING AND ANALYTICAL EQUIPMENT The display or description of a specific product is not to be construed as cn endorsement of that product or its manufacturer by the authors or their caployer.

A.

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

Eberline PRM 6 Portable Ratemeter (Eberline, Santa Fe, NM)

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

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

Eberline GM Pa.scake Probe Mod 1 HP 260 (Eberline, Santa Fe, NM)

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

Victormen Na1 Scintillation Detector Model 489 55 (Victoreen, Cleveland, OH)

B.

Laboratory Analyses Automatic low background Alpha Beta Counter Model L35110 2080 s,

(Tennelec, Inc., Oak Ridge, TN)

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High Purity Germanium Detector Model GMX 23195 S, 234 efficiency (EC&G ORTEC, Oak Rid 8 IN) 6 B-1

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j Used in conjunction with:

Imad Shield, C-16 (Canna Products. Inc., Palos Hills, IL)

High Purity Germanium Coaxial Well Detector Model GWL 1102010 PWS S. 234 efficiency (EG6G ORTEC, Oak Ridge TN)

Used in conjunction with:

IAad Shield Model G 16 (Applied Physical Technology Atlanta, GA)

High Purity Germanium Detector Model IGC25, 254 efficiency (Princeton Gamma Tech, Princeton, NJ..

Used in conjunction with:

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Lead Shield l

(Nuclear Data, Schaumburg, IL)

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

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

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

Multichannel Analyzer Model ND 66 (Nuclear Data Schaumbur5. IL)

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APPENDIX C MEASUREMENT AND ANALYIICAL PROCEDURES I

O APPENDIX C Measurement and Analytical Procedures Surface Scans Surface scans in the facility were performed by passing the probes slowly over the surface.

The distance between the probes and the surface was maintained at a minimum nominally about 1 cm.

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 creas on the floor of the facility were accomplished by use of a gas proportional floor monitor, with a 600 em2 sensitive area. The instrument was slowly moved in a systematic pattern to cover 100n of the accessible area.

Combinations of detectors and instrument for the scans were:

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

Beta Camma 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 Cas proportional floor monitor with 1.udium Model 2220 scaler /ratemeter.

Alpha and Beta Ramna Surface Contamination 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 windov

• pancake" G M probes. Count rates (eps) were converted to disintegration rates 2

(dps/100 cm ) by dividing the net rate by the 4e efficiency and correcting of the active area of the detector.

Effective window areas were 59 cm2 for the Zns detectors and 15 cm2 for the G M detectors.

The background count rate for ZnS alpha probes averaged approximately 2 epm; the average background count rate was approximately 40 cpm for the C M detectors.

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Removable Contamination Measurements Smear measurements were performed on numbered filter paper disks, 47 mis in diameter.

Smears were placed in labeled envelopes with the locations and other pertinent information recorded. A ZnS alpha scintillation counting system was

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used to evaluate individual smears at the site; smears were recounted on a low background proportional countr.r at the Oak Ridge laboratory.

Exposure Rata Measurements Measurements of gamma exposure rates were performed using Eberline PRM 6 portable racemeters with a Victorsen Model 489 55 gamma scintillation probe containing 3.2 cm x 3.8 cm NaI(TI) scintillation crystal.

Count rates were convertad to exposure rates (pR/h) by cross calibrating with a Reuter Stokes model RSS.111 pressurized ionization chamber.

Soil Sample Analysis 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 typically ranged from 600 to 800 g of soil. Net soil weights were determined and the samples counted using intrinsic germanium detectors coupled to a Nuclear Data Model ND 680 pulse height enalyzer 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 radionuelides of concern were:

Co 60 1.173 MeV Cs 137 0.662 MeV U 235 0.144 MeV U-238 0.094 MeV from Th 234 (secular equilibrium assumed) n 228 0.583 MeV form T1 208 (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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Strontium-90 Analysis Aliquots of soil were dissolved by pyrosulfate fusion and the strontium precipitated as a sulfate.

Successive trea',nenta with EDTA preferentially removed lead and excess calcium and returned the strontium to solution.

Ferric cnd other insoluble hydroxides was precipitacad at a pH of 12 to 14.

Strontium was reprecipitated as a sulfate.

Barium was removed as a chromate using DTPA.

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

Alpha Spectrometry of Isotopic Uranium Aliquots of soil were acidified and evaporated to dryness. The residues were then dissolved by pyrosulfate fusion and precipitated with barium sulfate.

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The barium sulfate precipitates were reclassified 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 954 confidence levels for that data.

These uncertainties were calculated based on both the gross sample count levels cnd the associated background count levels. When the not sample count was less than the 954 statistical deviation of the background count, the sample concentration was reported as less than the detection limits of the procedure.

Bocause of variations in back round levels, sample weights or volumes, and 5

Ccapton contributions from other radionuclides in samples, the detection limits differ from sample to sample and instrument to instrument.

Additional uncertainties of + 6 to 104, associated with sampling and laboratory procedures, have not been propagated into the data presented in this report.

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Calibration and Quality Assurance Laboratory and field survey procedures are documented in manuals developed specifically for the Oak Ridge Associated Universities' Radiological Site Assessment Program.

Vith the exception of the measurements conducted with portable gsmaa 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 un 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

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DOE /EML Qus11ty Assurance Programs.

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APPENDIX D f

CUIDELINES 70R DECONTANINATION OF FACILITIES AND 1

EQUIPMENT PRIOR TO RELEASE FOR UNESTRICTED USE OR TDMINATION OF LICENSES FOR EY.FRODUCT, SOURCE OR SPECIAL NUCLEAR NATERIAL t

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APPENDIX D GUIDELINES TOR DECONTAMINATION OF TACILITIES AND EQUIPMENT PRIOR TO RELEASE FOR UNRESTRICTED USE OR TERMINATION OT LICENSES TOR BYPRODUCT, SO:,'RCE, j

l OR SPECIAL NUCLEAR MATERIAL l

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l U.S. Nuclear Regulatory Com:nission Divison of Tuel Cycle 6 Material Safety Washington, D.C.

20555 l

fuly 1982

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The instructions in this guide, in ca.mm. u with Table 1, specify n

...c s which should be used the radionuclides and radiatios exposui in decontamination and survey of surfa is gro.ses and equipment prior to abandonment or release for unrestrii -

..e The limits in Table 1 do not apply to premises, equipment, or scr.>

..sining induced radioactivity

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for which the radiological considerations pertinent to their use may be t.

differept. The release of such facilities or items from regulatory control is considered on a case-by-case basis.

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The licensee shall make a reasonable effort to eliminate residual contamination.

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Radioactivity on equipment or surfaces shall not be covered by paint, plating, or other covering material unlesn 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 reasonab? $

ef fort 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 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 ductvork.

Eurfaces or premises, equipment, or scrap which are likely to be contaminated but J

are of such size, conetructian, or location as to make the surface I

inaccessible for purposes of neasurement 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 surf aces contaminated with materials in excess of the limits specified, this may include, but vould 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 ang-term storage or standby status.

Such requests must:

a.

Provide detailed, specific information describing the premises, equipment or scrap, radioactive contaminants, and the nature, extent. and degree of residual surface contamination, b.

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

5.

Prior to release of premises for unrestricted use, the licenses shall make a

compr ehensiv e radiation survey which establishes that contamination is within the limits specified in Table 1.

A copy of D-1

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the survey 1. port shall be filed with the Division of Tuel Cycle and Material Safety.

USNRC, Washington, D.C.

20555, and also the Administrator of the NRC Regional Of fice having jurisdiction.

The report should be filed at least 30 days prior to the planned date of abandonment. The survey report shall:

f Identify the premises, a.

b.

Show that reasonable ef fort has been made to elininate residual contamination.

l Describe the scope of the survey and general procedures followed.

c.

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State the findings of the surv ey in units specified in the instruction.

l Tollowing review of the report, the NRC will consider visiting the facilities to confirm the sv ty.

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TABLE 1 ACCEPTABLE SURFACE CONTAMINATION LEV 12.S Nuclidesa Averageb,c f Maximumb,d,f Removable e.f b

U-nat, U-23 5 U-23 8, and 5,000 dpa a /100 cm2 15,000 dpm a/100 cm2 1,000 dpa a/100 cm2 associated decay products 2

2 Transuranics, Ra-226, Ra-228, 100 dpe/100 cm2 300 dps/100 cm 20 dps/100 cm Th-230, Th-228, Pa-231, Ac-227, 1-125, I-129 2

2 200 dpe/100 cm Th-nat, Th-232 Sr-90, Ra-223 1000 dpe/100 c 2 3000 dps/100 cm P2-224, U-232, I-126, I-131, 1-133 2

1000 dpm By/100 cm2 Beta gamma emi,ters (nuclides 5000 dpa Sy/100 cm2 15,000 dpa Sy/100 cm

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with decay modes other than alpha omission or scontanecus 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 s'aould apply independeastly.

b As used in this table, dpm (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, efficicacy, and geometric factors associated with the instrumentation.

Measurements of average contaminant should not be averaged over more than 1 square meter. For objects C

of less surface area, the average should be derived for each such object.

d the maximum contamination level applies to an are.a of not more than 100 cm2,

• The amount of removable radioactive material per 100 cm2 f surface area should be determined by wiping that area with dry filter or sof t absorbent paper, applying moderate prs 6sure, and assessing the amount of radioactive material on the wipe with an appropriate instrument of known ef ficiency. When scinovable contamination on objects of less surface area is determined, the pertinent levels should be reduced proportionally and the entire surface should be wiped.

l f The sverage and maximum radiation levels associated with surf ace contamination resulting from beta-gamma j

emitters should n9t exceed 0.2 mrad /h at I cm and 1.0 mrad /h at 1 cm, respectively, measured through l

not more than 7 milligrams per,quare centimeter of total absorber.

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I APPENDIX E DECOMMISSIONING CUIDELINES FOR THE l

GENERAL ATOMICS FACILITY l

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APPENDIX E DECOMMISSIONING GUIDELINES FOR THE f

GEKERAL ATOMICS FACILITY Target titoria for unrestricted release of the General Atcaics Vaste Processing Facility and surrounding areas are presented in the licensee's final report and are as follows:1 External Radiation The gsana exposure rate at 1 m above the ground surface shall not exceed

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10 pR/h above background for an area of greater than 30 ft (9.1 m) x 30 ft (9.1 m) and shall not exceed 20 pR/h above background for any discrete area (i.e. less than 30 ft (9.1 m) x 30 ft 9.1 m)).

Inhalation and Inx.stion Concentrations of radionuclides in soil shall be such that inhalation and f

ingestion are not expected to result in annual dose equivalents exceedt.;

20 arem to the lung or 60 area to the bone.

f Limiting soil oncentrations were deriv e to satisfy these external and internal target criteria.

The concentration limits are presented in the following Table.

Radionuclide Concentration Limit Above Background (pC1/t) f Depleted Uranium 35 Enriched Uranium 30

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Thorium (Natural) 10 Co 60 8

Cs 137 15 Sr 90 1.8 x ~03 E-1

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Where more than one.eidionuclide is prese.t, the sum of the ratios of the individual radionuclide cc. ocentratic. s to their respective concentrations limits shall not exceed 1.

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