ML20036C161

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Forwards Final Rept Confirmatory Survey of Facilities in Bldgs 2 & 9,GA,San Diego,Ca
ML20036C161
Person / Time
Site: 07000734
Issue date: 08/09/1989
From: Cotten P
OAK RIDGE ASSOCIATED UNIVERSITIES
To: Fish R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
NUDOCS 9306140336
Download: ML20036C161 (1)
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Oak Ridge Enercy /

Associated Post Offce Box 117 cnvronment Universities Oak R>cge Tennessee 37831-0117 Systenis Division August 9, 1989 Mr. Ray Fish Region V Nuclear Regulatory Commission 1450 Maria Lane, Suite 210 Walnut Creek, CA 94596

Subject:

FINAL REPORT, CONFIRMATORY SURVEY OF FACILITIES IN BUILDINGS 2 AND 9, CENERAL ATOMICS

Dear Mr. Fish:

i Enclosed is the final report on the Confirmatory Survey of Facilities in i

Buildings 2 and 9, General Atomics, San Diego, California.

Please provide any comments your office may have at your earliest convenience.

I may be reached i

at FTS 626-3355 or contact Jim Berger at FTS 626-3305.

Sincerely, t); SQ Phyllis R. Cotten Health Physics Team Leader Environmental Survey and Site Assessment Program PRC:jls Enclosures cc:

L. Rouse, NRC/6H3

'G.

LaRoche.,:NRC/6H3-D. McCaughey, NRC/6H3 D..Tiktinsky, NRC/6A4 E. Davis, NRC/6A4 B. Pate, NRC Region 5 C. Hooker, NRC Region 5 I

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Industrial and Medical Nuclear Safety P. R. COTTEN I

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Environmental Survey and Site Assessment Program Energy / Environment Systems Division I.

FINAL REPORT JULY 1989

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I NOTICES The opinions erpressed herein do not necessarily reflect the opinions of the sponsoring institutions of Oak Ridge Associated Universities.

This report was prepared as an account of work sponsored by the United States Government. Neither the United States Government nor the U.S. Department of Energy, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibliity for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any speelfic commercial product. process, or service by trade name, mark, manufacturer, or otharwise, does not necessarily constitute or imply its endorsement or recommendation, or favoring by the U.S.

Government or any agency thereof.The views and opinions of authors expressed herein do not necessurity state or retteet those of the U.S. Government or any agency thereof.

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ORAU 89/F-98 I

CONFIRMATORY SURVEY OF FACILITIES IN I

BUILDINGS 2 AND 9 GENERAL ATOMICS SAN DIEGO, CALIFORNIA I

Prepared by P.R. COTTEN I

Environmental Survey and Site Assessment Program Energy / Environment Systems Division I

Oak Ridge Associated Universities Oak Ridge, TN 37831-0117 I

Project Staff g

J.D. Berger F.A. Templon 5

G.R. Foltz C.F. Weaver J.L.

Payne I

Prepared for Division of Industrial and Medical Nuclear Safety U.S. Nuclear Regulatory Commission Region V Office 1

I FINAL REPORT JULY 1989 I

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This report is based on work performed under Interagency Agreement (NRC Fin.

No.

A-9076) between the U.S.

Nuclear kegulatory Commission and the U.S. Department of Energy.

Oak Ridge Associated Universities performs complementary work under contract number DE-AC05-760R00033 with the I

U.S. Department of Energy.

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I I-TABLE OF CONTENTS I

Page 11 List of Figures.

List of Tables v

Introduction and Site History.

1 Site Description.

2 i

Procedures...............

2 Results.

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i Comparison of Survey Results with Guidelines 9

Summary.

10 References 66 Appendices Appendix A: Major Sampling And Analytical Equipment Appendix B: Measurement and Analytical Procedures l

Appendix C: Guidelines for Decontamination of Facilities and R

Equipment Prior to Release for Unrestricted Use or Termination of Licenses for By-product, Source, or Special Nuclear Material I

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LIST OF FIGURES I

Page FIGURE 1:

Map of the San Diego Area, Indicating the Location of General Atomics Facilities...............

11 FIGURE 2:

General Atomics Plant Layout................

12 FIGURE 3:

Layout of Building 2 (L Building Complex) 13 I

FIGURE 4:

First Floor of Building 9 Indicating the Former Location of the TRIGA Fuel Fabrication " Hot Suite" Area.

14 FIGURE 5:

Section A of Building 2, Indicating Rooms Included in Group 3 Decommissioning.

15 FIGURE 6:

Section B of Building 2, Indicating Rooms Included in Group 3 Decommissioning.

16 FIGURE 7:

Section C of Building 2, Indicating Rooms Included in-17 Group 3 Decommissioning.

1 FIGURE 8:

Decontamination Stages for the " Hot Suite" Area 18 Building 9.

I FIGURE 9:

Layout of Room 234, Indicating Locations of Surface 19 Contamination Measurements.

FIGURE 10: Layout of Room 302 with Adjoining Walkways, Indicating Locations of Sampling and Surface Contamination 1

Measurements.

....................... 20 I

7 FIGURE 11: Layout of 309, Room 1, Indicating Locations of Sampling i

21 and Surface Contamination Measurements.

FIGURE 12: Layout of 309, Room 2, Indicating Locations of Sampling' i

22 and Surface Contamination Measurements.

FIGURE 13: Layout of Room 315, Indicating Locations of Surface Contamination Measurements.................

23 f

FIGURE 14: Layout of Rooms 321 and 323, Indicating Locations of l

Surface Contamination Measurements.

24 i

I FIGURE 15: Layout of Mezzanine 321/323, Indicating Locations of 25 Surface Contamination Measurements.

FIGURE 16: Layout of Room 327. Indicating Locations of Surface I

26 Contamination Measurements.

FIGURE 17:

Layout of Mezzanine 325/327, Indicating Locations of 27 Surface Contamination Measurements.

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LIST OF FIGURES (Continued)

I Page FIGURE 18: Layout of Mezzanine 335/337, Indicating Locations of i

28 Surface Contamination Measurements.

FIGURE 19: Layout of Mezzanine 339/341 Indicating Locations of Surface Contamination Measurements.

29 FIGURE 20: Layout of Rooms 343/345, Indicating Locations of Surface 30 Contamination Measurements.

FIGURE 21: Layout of Mezzanine 343/345, Indicating Locations of 31 Surface Contamination Measurements.

FIGURE 22: Layout of Room 347, Indicating Locations of Surface 32 Contamination Measurements.

FIGURE 23: Layout of Mezzanine 347/349, Indicating Locations of 33 Surface contamination Measurements.

FIGURE 24:

Layout of Rooms 425, 427, and 429 Indicating Locations 34 of Surface Contamination Measurement.

I FIGURE 25: Layout of Mezzanine 425, 427, and 429, Indicating Locations of Surface Contamination Measurements.

35 i

FIGURE 26:

Layout of Rooms 431 and 433 Indicating Locations of Surface Contamination Measurements.

36 FIGURE 27:

Layout of Mezzanine 431/433, Indicating Locations of I

Surface Contamination Measurements.

37 FIGURE 28: Layout of Mezzanine 615/617, Indicating Locations of Surface Contamination Measurements.

38 FIGURE 29: Layout of Room 647, Indicating Locations of Surface 39 Contamination Measurements.

FIGURE 30: Layout of Mezzanine 645/647, Indicating Locations of Surface Contamination Measurements.

40 I

FIGURE 31:

Layout of Room 649, Indicating Locations of Surface 41 Contamination Measurements.

FIGURE 32: Layout of Room 651 Indicating Locations of Surface 42 Contamination Measurements.

FIGURE 33: Layout of Room 33, Indicating Locations of Surface 43 Contamination Measurements.

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LIST OF FIGURES (Continued)

I Page FIGURE 34: Layout of Room 34, Indicating Locations of Surface I

44 Contamination Measurements.

FIGURE 35: Layout of Room 38, Indicating Locations of Surface 45 Contamination Measurements.................

FIGURE 36: Layout of Room 39, Indicating Locations of Surface 46 Contamination Measurements.

FIGURE 37: Layout of Main Entrance Hallway, Indicating locations of Surface Contamination Measurements.

47 FIGURE 38: Layout of Rooms 47A and 46B (Old Change Room), Indicating Locations of Surface Contamination Measurements 48 FIGURE 39: Layout of Room 48, Indicating Locations of Surface Contamination Measurements.

49 FIGURE 40: Layout of Room 49A, Indicating Iocations of Soil and Surface Contaminant Measurements.

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FIGURE 41: Layout of Room 50, Indicating Locations of Soil and Surface Contamination Measurements.

51 FIGURE 42: Layout of Sidewalk Area Outside Room 48, Indicating Locations of Surface Contamination Measurements 52 FIGURE 43: Locations of Background Measurements and Baseline Soil Samples from the Vicinity of General Atomics.

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I LIST OF TABLES s

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Background Radiation Levels................

54 TABLE 2:

Baseline Radionuclide Concentrations in Soil.

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TABLE 3:

Su2mnary of Surface Contamination Measurements Bui1 ding 2, L Building Complex.

56 TABLE 4:

Sum: nary of Surface Contamination Measurements Building 9 E Building Complex.

62 TABLE 5:

Radionuclide Concentrations in Soil.

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CONFIRMATORY SURVEY OF FACILITIES IN I

BUILDINGS 2 AND 9 GENERAL ATOMICS SAN DIEGO, CALIFORNIA INTRODUCTION AND SITE HISTORY In mid 1984, General Atomics (GA) of San Diego, California, initiated decommissioning activities for the purpose of releasing portions of their facilities from Nuclear Regulatory Commission (NRC) licensing restrictions.

Because of the numerous building and land areas being decommissioned and the varied nature of former operations in these facilities, the decommissioning is I

i being conducted in phases.

Phase I activities included the Solar Evaporation Pond area, the areas immediately surrounding the former Waste Processing Facility, the Incinerator Pad, a previous burial site for contaminated asphalt, the hillside and canyon below the vaste handling facilities, and undeveloped land surrounding the vaste processing facilities; Phase II areas were the former Vaste Processing Facility and the Incinerator Pad; Phase III consisted of approximately 87 hectares of undeveloped land, surrounding the main General I

Atomics plant facilities, and the shipping and receiving area of Building 5; and Phase IV included three canyons behind the Hot Cell and TRIGA facilities, a I-treatment plant known as " Callan Ponds," and 12 laboratories in former sewage Building 2 of the L Building Complex. These Phase I, II, III, and IV areas were previously remediated and confirmatory surveys performed by ORAU. Results of those surveys are presented in separate reports.(1-4) The Building 2 laboratories and offices, included in Phase IV decommissioning were designated an " Group 1"

and " Group 2" facilities. An additional 19 laboratories, 12 of which include mezzanine areas, and 10 separate mezzanines only in Building 2 have been decontaminated as part of the " Group 3" activities.

These rooms and 2

mezzanines occupy approximately 904 m ; the primary radionuclides used in these areas were Cs-137, Co-60, Sr-90, thorium, and uranium (natural, depleted, and enriched).

2 area of Building 9, E Building Complex, has been An approximate 268 m Stage 1 of the current GA decommissioning activities. This dacontaminated as is part of the building area, known as the " Hot Suite," once associated with I

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the TRIGA fuel fabrication facility; now housed at a different location. The primary contaminant in this facility was uranium with U-235 enrichments, I

varying from 3 to 10%.

At the request of the NRC, Region V Office, the Environmental Survey and Site Assessment Program of Oak Ridge Associated Universities conducted a radiological survey to confirm the status of these portions of Buildings 2 and 9, relative to the NRC guidelines for release to unrestricted use.

This survey was performed March 14-23, 1989, in accordance with a survey plan submitted to the Region V Office of the NRC.

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

SITE DESCRIPTION The General Atomics facilities are located near the intersection of Interstate 5 and Genesee Road, approximately 20 km north of San Diego, CA (Figures 1 and 2).

Buildings 2 and 9 are illustrated in Figures 3 and 4.

I Building 2, a two-story, semicircle building, located in the center of the GA facility, consists of office and laboratory space divided into three sections (A, B, and C).

Some laboratories have mezzanine areas which were also utilized as both office or additional laboratory space.

The nineteen laboratories and 22 mezzanines, included in this survey are shown on Figures 5, 6, and 7.

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Building 9,

located to the west of Building 2, is also a large (5541 m )

two-story structure.

A large portion of the building har been leased out to I

several different companies; the former TRIGA Fuel Fabrication " Hot Suite" was located in an area of Building 9 which is now occupied by GA's telecommunications group.

The entire

" Hot Suite" area originally occupied 375 m2 of area and contained 9 rooms and 2 hallways (Figure 8); only the Stage 1 portion of the area is included in this survey.

Obiectives I

The objectives of the survey were to confirm that the radiological condition of those areas of Buildings 2 and 9, included in this phase of I

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decommissioning, is accurately presented in the General Atomics report and to provide information and data for evaluation of the site status, relative to NRC I

guidelines for release for unrestricted use.

Document Review I

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The licensee's survey reports for the unrestricted release of portions of Buildings 2 and 9 was reviewed by ORAU(5-7).

Data presented in these reports were compared to the established release guidelines.

Facility Survey I

The following " Group 3"

laboratories and office areas were surveyed in Section A of Building 2:

Rooms 647, 649, and 651 and the mezzanines of Rooms

-615/617 and 645/647.

In Section B, Room 234 was surveyed.

Rooms 302, 309, (Rooms 1 and 2), 315, 321, 323, 327, 343, 345, 347, 425, 427, 429, 431, and 433-and mezzanines of Rooms 321/323, 325/327, 335/337, 339/341, 343/345, 347/349, 425/427/429, 431/433, 615/617, and 645/647 were surveyed in Section C of Building 2.

In the " Hot Suite" of Building 9 Rooms 33, 34, 38, 39, the main entrance hallway, a portion of 46B, 47A, 48, 49A, 50, and the sidewalk area I

outside Room 48 were surveyed, Figures 9 through 42 show the layouts of these areas.

I Gridding I

An alphanumeric 2 m x 2 m reference grid system was established on the floor and lower walls (up to 2 m) for each room and mezzanine surveyed.

Measurements made on upper walls, ceiling, or equipment were referenced to the established grid or prominent building features.

I Surface Scans I

Alpha, beta-gamma, and gamma scans were performed on floors and lower

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walls, using an alpha / beta gas proportional large avea detector, beta-gamma GM detectors, and NaI(Tl) gamma scintillation detector, with audible indicating i

i scaler /ratemeters.

Scans of surface areas not accessible to the large area 4

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detector, i.e.,
ceilings, and overhead areas such as ledges, beams, piping, fixtures, counter tops, equipment, and ductwork were performed using portable I

ZnS alpha scintillation and GM detectors.

Locations of elevated radiation levels were noted for additional measurements.

Surface scans using a NaI(Tl) scintillation detector, were performed in areas where the floor had been removed and the underlying soil was exposed.

Additional measurements were made with a beta-gamma CM detector to define any areas where elevated locations were identified.

Exposure Rate Measurement I

Gamma exposure rates were determined throughout the facilities, based on gamma scan data and cross-calibration with a pressurized ionization chamber.

Measurement of Surface Contamination Levels In Building 2,

surface contamination measurements were performed on a total of 78 randomly selected grid blocks on the floor and lower walls.

In each grid surveyed, direct measurements of alpha and beta-gamma contamination I

levels were systematically performed at the center and four points midway between the center and block corners.

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

Single point measurements for total and removable alpha and beta-gamma contamination levels were performed on upper

walls, overhead surfaces (higher than 2 m) such as ledges, ceilings, beams,
pipes, ductwork, and miscellaneous equipment.

A total of 152 single I

measurements were collected.

Direct measurements and smears were also collected from floor drains at several locations. Measurement locations in Building 2 are indicated on Figures 9 through 32.

Five point measurements were performed in 16 grid blocks in Building 9 and single point measurements were performed at 29 locations. Measurements were also performed on 2 floor drains.

Figures 33 through 42 show the locations of the surface contamination measurements in this Building.

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Soil Sampling I

Soil samples were collected from excavated floor areas.

In Building 2 ten samples were collected from the excavated trenches in Rooms 302, 309 (1 and 2),

the adjoining hallway, and the outside area where the drainline had previously emptied into a waste tank (Figures 11 and 12). Samples (four) were also collected from open trenches in Rooms 49A and 50 (Figures 40 and 41).

Miscellaneous Samples A large area swipe was used to collect a sample of residue from a floor drain in room 425.

One paint sample was collected from a ledge in the mezzanine area of room 321 (Figure 14 and 24).

Background and Baseline Measurements I

Background measurements and soil samples were collected to determine area background and to provide baseline radionuclide concentrations for comparison I

purposes.

Locations of the background measurements and baseline samples are shown in Figure 43.

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

All soil samples were analyzed by gamma spectrometry.

The major radionuclides of interest were Co-60, Cs-137, U-235, U-238, and Th-23?;

however, spectra were reviewed for the presence of other identifiable or I

significant photopeaks.

Smears were counted for alpha and beta levels, using a low background gas proportional counter. Additional information concerning analytical equipment and procedures is presented in Appendices A and B.

Survey results were compared to NRC guidelines for decommissioning of the General Atomics Facility (Appendix C).

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RESULTS Document Review ORAU's review of the survey reports, submitted by GA to the NRC, indicates that the procedures and instrumentation used were consistent with current industry accepted practices. A review of the documentation indicated that GA successful in identifying problem areas and decontaminatiing these areas to was the guidelines established.

Additional material was reviewed for 2 areas, where the survey was completed after the initial report was prepared.

Several inconsistencies between the field survey data and the final documentation were noted; however, these inconsistencies were minor and did not involve situations of guidelines being exceeded.

One area surveyed by ORAU had not yet been surveyed thoroughly by GA.

Background Levels and Baseline Concentrations I

Background exposure rates and baseline radionuclide concentrations in soil from the vicinity of the General Atomics site are presented in Table 1 and I

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 exposure rates and radionuclide concentrations, normally occurring in the environment.

I Building 2 I

Surface Scans Surface scans identified several locations of residual beta-gamma contamination exceeding guidelines in four laboratory areas.

These were in Rooms 1 and 2 of 309 (floor and lower wall), Room 315 (below tile floor and wall),

and Room 321 (window ledge).

Sampling paint from the mezzanine window ledge in 321, removed the contamination at this location. The other areas were brought to the attention of the licensee; additional cleanup was performed, resulting in reduction of the direct radiation to below guideline levels.

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Exposure Rates I

Exposure rates throughout all surveyed areas were in the range of natural background levels, i.e. less than 13 pR/h, at 1 m above the surface.

Surface Contamination Levels Table 3 summarizes the results of surface contamination measurements in Building 2.

These data represent the measurements performed after any I

additional cleanup of areas identified by the ORAU surface scans.

In many instances, the levels were below the detection sensitivities of the procedure.

For five-point grid block measurements the individual total alpha and 2

beta-gamma levels ranged from

<24 to 100 dpm/100 cm from <320 to 2

5700 dpm/100 cm,

respectively; the highest grid block averages were 2

2 43 dpm/100 cm for alpha and 2700 dpm/100 cm for beta-gamma.

Removable alpha 2

contamination levels ranged from

<3 to 21 dpm/100 cm and removable beta 2

contamination ranged from

<6 to 9 dpm/100 cm.

Single-point measurements of total contamination ranged from <27 to 1500 dpm/100 cm2, alpha, and from <320 I

2 to 9000 dpm/100 cm, beta-gamma. The highest alpha and beta-gamma measurements were on a step, leading to the mezzanine area of Rooms'431/433. Removable 2 and alpha contamination at these locations ranged from <3 to 9 dpm/100 cm removable beta contamination ranged from <6 to 64 dpm/100 cm2, I

Radionuclide Concentrations in Soil Samples I

Concentrations of radionuclides in soil samples collected from excavated trench areas in Building 2 are presented in Table 5.

Samples were collected I-from Room 302, the hallway, the outside sidewalk, and from Rooms 1 and 2 of 309.

Co-60 concentrations ranged from <0.1 to 19.0 pCi/g. The removal of additional soil reduced Co-60 concentrations to 3 pCi/g.

Cs-137 concentrations ranged from

<0.1 to 7.0 pCi/g; U-235 levels ranged from <0.2 to <0.5 pCi/g; U-238 levels ranged from <0.6 to 2.0 pCi/g; and Th-232 concentrations ranged from <0.4 to 2.0 pCi/g.

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Miscellaneous Sa=ples I

No detectable activity was present on the large area swipe taken from the drain in Room 425.

The paint sample from the window ledge on the mezzanine of Room 321 was known to contain activity, based on the direct measurements, before and after the sample was collected. This sample was not analyzed, because it would not be representative of the final radiological conditions.

Followup measurements at this sampling location indicated total and removable contamination levels were below detection limits.

I Building 9 Surface Scans Surface scans identified one location of elevated direct radiation; this was a small area above a doorway in Room 48.

This location was brought to the attention of the licensee, and further cleanup reduced direct measurements to acceptable levels.

I Exposure Rates I

At 1m above the surface exposure rates throughout the facility were in the range of natural background levels of approximately 10 to 13 pR/h.

Surface Contamination Levels Results of surface contamination measurements in Building 9 are summarized in Table 4.

For five-point grid block surveys total individual contamination 2

measurements ranged from <24 to 1300 dpm/100 cm for alpha and from <360 to 2

for beta-gamma.

Highest grid block averages were 6400 dpm/100 cm 470 dpm/100 cm,

alpha, and 1900 dpm/100 cm2, beta-gamma; these maximum levels 2

occurred on the floor of Room 49A.

Removable contamination from grid block surveys was, for the most part, less than the detector sensitivity, with alpha 2

measurements ranging from

<3 to 19 dpm/11 cm and beta measurements ranging 2

from

<6 to 14 dpm/100 cm.

For single-point measurements the levels for total 2

contamination for alpha and beta-gamma ranged from <24 to 240 dpm/100 cm, and 8

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2

<320 to 9300 dpm/100 cm,

respectively.

The highest levels were from the location above the doorway in Room 48, which was identified by scans and I

further remediated by the licensee. Removable contamination levels were low; 2

alpha ranged form

<3 to 36 dpm/100 cm and beta ranged from

<6 to 2

35 dpm/100 cm,

Radionuclide Concentrations in Soil Samples Table 5 lists the concentratiens of radionuclides present in soil samples I

l from Rooms 49A and 50.

Cobalt-60, and Cs-137 concentrations were <0.1 pCi/g-l U-235 levels ranged from <0.2 to <0.3 pCi/g; U-238 concentrations ranged from l

<0.6 to 3.0 pCi/g; and Th-232 concentrations were from 1.0 to 2.0 pCi/g.

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COMPARISON OF SURVEY RESULTS WITH GUIDELINES 1

The guidelines for decommissioning the General Atomics facility are presented in Appendix C.

Surface contamination limits for building surfaces are based on primary contaminants of uranium, Cs-137, and Co-60, identified on I

this site, and are:

Alpha 2

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

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

i 1000 dpm/100 cm, removable Beta-Camma 2

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

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

1000 dpm/100 cm, removable The survey performed by ORAU detected several isolated locations of residual contamination on surface areas. Additional clean-up was performed by the licensee, resulting in reduction or removal of the contaminant.

In 2

Buildin5s 2 and 9 all grid blocks satisfied the 5000 dpm/100 cm average level.

2 There were several individual measurements between 5000 and 15000 dpm/100 cm ;

however, each of these measurements represented small, isolated spots of contamination and averaging with contiguous surfaces resulted in satisfying the 2

5000 dpm/100 cm average guideline.

No measurements were in excess of the I

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2 15000 dpm/100 cm guideline level.

Removable contamination levels were also 2

well within the guideline value of 100 dpm/100 cm,

Exposure rates throughout the buildings were in the range of background levels and therefore well within the guideline of 10 pR/h above background.

Concentrations of radionuclides in soil samples from excavated floor areas j

were all well within the guideline values established specifically for the GA site decommissioning.

SUMMARY

At the request of the NRC Region V Office, during March 1989, Oak Ridge Associated Universities performed a confirmatory survey of portions of Buildings 2 and 9,

being decommissioned by General Atomics in San Diego, California.

The survey included alpha, beta-gamma, and gamma scans and measurements of total and removable surface contamination, exposure rates, and I

radionuclide concentrations in soil.

The initial scans identified several small areas of residual contamination; these were immediately cleaned by the I

licensee and resurveyed by ORAU.

Final measurements indicated that all radiological conditions satisfied the established decom.nissioning guidelines.

Based on the findings of this survey, it is ORAU's opinion that the office and laboratory areas of Building 2 and Building 9, included in this decommissioning effort, now meet the guidelines for release from radiological restrictions.

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Section C of Building 2, Indicating I

Rooms included in Group 3 Decommissioning 17 1

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i FIGURE 8: Decontamination Stages for the " Hot Suite" Area

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FIGURE 9: Lcycut of Room 234, Indicating Lccations of Surface Contamination Measurements 19

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.f" FIGURE 10: Layout of Room 302 with Adjoining Walkways, indicating Locations of Sampling and Surface Contamination Measurements 20

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i METERS FIGURE 11: Layout of 309, Room 1, Indicating Locations of Sampling and Surface Contamination Measurements 21 p

t GAT 37 f~

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.i METERS FIGURE 13: Layout of Room 315, Indicating Locations of Surface Contamination Measurements 23

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FIGURE 14: Layout of Rooms 321 and 323, Indicating Locations of Surface Contamination Measurements 24

l CAT 40 i

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FIGURE 15: Layout of Mezzanine 321/323, Indicating Locations of Surface Contamination Measurements 25

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FIGURE 16: Lcyout of Room 327, Indicating Locations of Surf ace Contamination Measurements 26

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FIGURE 17: Layout of Mezzanine 325/327, inclicating Locations of Surface Contamination Measurements 27

_ _, _ _ -, _ _ _ - - _ _ _ _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ' - ' - - ' ~ ~ ~ ~ ' ' ~ ~ ~ ~ ~ ~ ~ ~ ~ ' ~ ~ ~ ~ ~ ~ ~ ~ ~ '

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FIGURE 18: Layout of Mezzanine 335/337, Indicating Locations of Surface Contamination Measurements 28

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FIGURE 20: Layout of Rooms 343/345, Indicating Locations of Surface Contamination Measurements 8

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Surf ace Contamination Measurements 31

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.l Surface Contamination Measurements n

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GAT 49 I I W. I / //$ // I 3.5 Yb WA N' I ^ = // _ki / o ^ B C o g 7 g %W V/V v/7 A W/A ?/fi*s W$ l I 1 I MEASUREMENT LOCATICNS ] GRID BLOCK ( 5 14 E t T) I _ _ PLATFORM (35 CM HfGH) N g w\\ 1 I ? METERS I I FIGURE 25: Layout of Mezzanine 425, 427, and 429, Indicating Locations .h of Surface Contamination Mecsurements n g

EE E E E E E E E E E E N E E E E E E; l GAT 50 j \\ / \\ / \\ / \\ / \\ / 'i '_// / \\ / ,/ \\ ~ ~ / g j \\ta \\ / / FT k M \\ / /; \\ / MEASUREMENT LOCATIONS /j/[j'; \\ / cRID BLOCK ![ [![/sb' A USYGUE PT) CABINET ,7 / // //O E HOOD g A B C D E ( Nb' \\, 431 433 i j A METERS FIGURE 26: Layout of Rooms 431 and 433, Indicating Locations of Surf ace Contamination Measurements

CAT 51 I I STAIRS CAN NET l 5 / W.. 4 w,0 f2'd W \\ A a zd 'I l ,j// ,o A B C D E //hb l '/p/ wiNoows 8 I MEASUREMENT LOCATIONS GRfD BLOCK I

  • s'k'N g

U i i L UETERS I 5 FIGURE 27: Layout of Mezzanine 431/433, Indicating Locations of j Surf ace Contaminction Measurements n y

GAT 52 i STAIRS E y ' 77, fh I / l Es G 9 A B C D E i / \\ && *s >g A I MEASUREMENT LOCATIONS / GRID BLOCK I g UPPER WALL / CEILING (S!NGLE POINT) 4-E / / I: I / 9 i i METERS I I FIGURE 28: Layout of Mezzanine 615/617, Indicating Locations of g Surf ace Contamination Measurements n y

9 l cats 3 A I /! V. I 7.5 ff: [f' ! //, k a e o l A B C I MEASUREMENT LOCATIONS i I. GRID BLOCK g UPPER WALL /CE! LING (SINGLE POINT) I N h

  • !N h

9 f METERS 'I FIGURE 29: Layout of Roorn 647, Indicating Locations of g Surf ace Contamination Measurements 3, g

GAT 54 I 77 l ' //' / ~l% / i / \\ N [ j 4 5'*S /l,'/l,' /l 2 d pu / O A B C D E // / Wif4 DOWS I MEASUREMENT LOCATIONS GRID BLOCK I-1 UPPER WALL /CE!UtJG = (SINGLE POINT) N i A I k l ? t METERS I I FIGURE 30: Layout of Mezzanine 645/647, Indicating Locations of Surf ace Contamination Measurements g I

GAT 55 I cf I I ~ I I 73 6 / / / - [- g 4 Ihbi

E A

B C I MEASUREMENT LOCATIONS / GRID BLOCK g UPPER WALL / CEILING (SINGLE POINT) WINDOWS

===rd N I A idk T l ? I METERS I FIGURE 31: Layout of Room 649, Indicating Locations of l Surface Contamination Measurements e g

CAT 56

I a

i I A C F I 7.5 I Ih E zh I w O/ // g 2 A ' o A B C I MEASUREMENT LOCATIONS @ cmo etocx A [s$r$5[E pS((j Eiunc winocws N I l I ? 1 METERS I FIGURE 32: Layout of Room 651, Indicating Locations of l Surf ace Contamination Measurements g u

GAT 57 I WINDOWS ._f d y_ H 'l-bg.,k l/ I 5.5 4 I ~ 2) + I Ii - - _. _ _. of l I Q i I MEASUREMENT LOCATIONS / GRID BLOCK N

  • }N j

h 9 i i l. METERS I I FIGURE 33: Layout of Room 33, Indicating Locations of g Surface Contamination Measurements .e g e

GAT 58 I WitjDOW l 9 ./ 1m I VE4 o 5.5 V..ll \\ 4 I o = REMO ED / 0 A B C C+1.25 I MEASUREMENT LOCATIONS GRID BLOCK N I 1 e A ? i i METERS I FIGURE 34: Layout of Roorn 34, Indicating Locations of l Surf ace Contamination Measurements 44 . I

P GAT 59 I I 7 6 I 2 I 0 ) i A B B+1 I MEASUREMENT LOCATIONS GRID block A UPPER WALL /CEIUNG ^ (SINGLE point) I N 1 ~? A ? 1 / METERS j I l FIGURE 35: Layout of Room 38, Indicating Locations o' l Surface Contamination Measurements I

GAT 60 'I WINDOWS 4 I 3.5 2 o i i A B C D I I I MEASUREMENT LOCATIONS / GRID BLOCK N 1 I d A ? i METERS I I FIGURE 36: Layout of Room 39, Indicating Locations of l Surf ace Contamination Measurements I

. GAT 61 f I .I

*r-Wit 4DOW L

L 1,,, I 7 I 6 - -/ - I 34 33 t 4 ~ 2 DRAIN 38 I O A B C D E F G 41 31 I MEASUREMENT LOCATIONS ] cRio et.ock I I l + I A 9 f MmERS FIGURE 37: Layout of Main Entrance Hollway,. Indicating Locations of l Surface Contamination Measurements I

i i GAT 62 l I bh 4 f l 6 I 47A 4 i /, / ,g HALLWAYI / I, // 3- [f N LLWAY l o-A' B C C + 1.5 i DRAIN k [ !/// /4 t ? a' i MEASUREMENT LOCAT:GNS l t j y GRID BLOCK i { __ __ TEMPcRARY j WALLS ,I 1 N i e ~ ,I h 9 f METERS i FIGURE 38: Layout of Rooms 47A and 468 (Old Change Room), Indicating Locations of Surface Contornination l Measurements j 48 I.,

CAT 63 l j I i 7.5 3ATTERY / // CHARGE / ,// ROCM '9"I l .1

4 1

2 'l I D A B C D I NEW PLYWOOD / COVERED BAY DOOR i," MEASUREMEtJT i_OCATIOt4S A A B ceiD etoCs A UPPER WALL /CE! LING (SINGLE POINT) g A i l 45 0 I e METERS I FIGURE 39: Layout of Room 48, Indicating Locations of Surface Contamination Measurements 49

GAT 64 E I i 4 TRE.NCH 6.5 y 6 I i 7/ /&h~ \\ 4 WINDOW t I -) g t A B C D l TEt# ARY _ L_____] MEASUREMENT LOCATIONS [ I GRID BLOCK g UPPER WALL / CEILING (5:NGLE PO;NT) SOIL SAMPUNG E O LOCATIONS g SCABBLED CONCRETE N -) g 0 I { h 9 4 i METERS FIGURE 40: Layout of Room 49A, Indicating Locations-of l Soil and Surf ace Contamination Measurements so g

GAT 65 il g_____ ll l l- T M^"' 1 I TRENCH 2.5 .f_! I 2 A s' s- .I o A B C D I d I i MEASUREMENT LOCATIONS GRID BLOCK A UPPER WALL /CElUNG A (SINGLE PCiNT) Soil SAMPUNG O LOCATIONS x t> 1 l A ? f i METERS I FIGURE 41: Layout of Room 50, Indicating Locations of g Soil and Surface Contamination Measurements 51

cates POCF EAVE I / u / / I ' " o' / /'// L I I BAY DOOR c4e ROOF EAVE / 1 i e 1 I l 8 MEASUREVE'd LOCATIONS N r "W A ? i UETE RS .E .I ,8 FlGURE 42: Layout of Sidewalk Area Outside Room 48, Indicating I Locations of Surf ace Contaminat, ion Measurements 52 I

u CAT 4a I 1 DEL H MAR PAClFIC l COAST HWY. l [3 GENERAL ATOMICS [ 7' FACILITIES (is e p 'S GENESEE AVE. / M!RAMAR ( x 5 ke L /@ UNIVERSITY E D 7,2/ / [g l LA JOLLA l N 4 1S R4C/F/C PACiRC OCEAN BEACH SION l mD W 7 SAN 7 Dl EGO euy I MEASUREMENT AND N ' SAMPLING LOCATIONS MILES d 3 0 1 2 3 4 5 O 2 4 6 8 KILOMETERS N FIGURE 43: Locations of Background Measurements and g Baseline Soil Samples from the Vicinity of General Atomics l 53

w' TABLE 1 g L BACKGROUND PADIATION LEVELS GENERAL ATOMICS -i I SAN DIEGO, CALIFORNIAa Gamma Exposure Rates Gamma Exposure Rates g. Locationb at 1 m Above the Surface 'a t the Surface (pR/h) (pR/h) I 7 8 2 8 8 I 3 7 7 4 10 10 5 13 15 6 13 15 RANGE 7 to 13 7 to 15 AVEFAGE 9.7 10.5 aData obtained during confirmatory survey of phase I decommissioning activities (I*) b efer to Figure 43. R L 54

TAPLE 2 BASELINE RADIONUCLIDE CONCENTRATIONS {N Soll GENERAL ATOMICS SAN DIEGO CAliFORNIAa l Radionuclide Concentration (pCl/g) Locationb Co-60 Cs-137 U-235 U-238 Th-228 Th-232 K-40 1 <0.1 <0.1 0.6 i 0.1c <0.2 1.6 1 1.2 1.3 1 0.5 14.0 1 1.7 2 <0.1 0.2 1 0.1 0.5 1 0.2 <0.2 1.6 1 1.5 2.010.9 25.0 1 3.3 3 <0.1 (0.1 0.7 1 0.2 0.410.2 1.110.5 2.210.6 10.4 1 1.7 4 <0.1 <0.1 1.2 1 0.3 <0.3 <1.1 3.1 0.8 29.0 1 3.4 5 <0.1 <0.1 0.2 1 0.2 0.7 i 0.6 1.310.6 3.210.8 24.3 1 2.7 i 6 <0.1 (0.1 0.7 1 0.2 <0.2 1.0 1 0.9 1.9 1 0.8 30.2 1 2.9 l 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 u AVERAGE <0.1 <0.1 0.8 <0,5 1.3 2.3 22.2 II*I eData obtained during conf irmatory survey of phase I decommissionina act ivit ies bRefer to Floure 43. cUncertaintles represent the 95% confidence levels, based only on countinq statistics; additional laboratory uncertainties of i 6 to 10% have not been propagated into these data.

TABLE 3 SlM4ARY OF SURFACE WNTAM4 NATION MEASLREMENTS BUILDING 2, L BUILDiHG COMPLEX GENERAL ATOMICS SAN DIEGO, CALIFORNIA

  1. of Geld Blocks Highest Grid TOTAL CONTAMINATION REMOVABLE CONTAMINATION 2

Roo ora location or Locations Block Avernae (dpm/100 cm2) (dpm/100 cm 3 Area Measured (dpm/100 cm2) Alpha Ranae Deta-Gamma Range Alpha Range Beta-Gamma Range Alpha Beta 234 Floor 2b <27 420 <27 - 38 <320 - 640 <3 <6 - 8 Lower Wall 2b <27 <320 <27 - 38 <320 - 590 <3 - 3 <6 - 7 U. Wall / Celling 4C N/A N/A <27 - 85 <320 - 480 <3 - 3 (6 - 64 b <27 1100 <27 - 38 690 - 1400 <3 (6 $ 302 Floor I I Lower Wall U. WalI/ Celling D 309 Room 1 Floor 3 <27 2700 <27 1200 - 5200 <3 <6 D Lower Wall 2 47 1500 <27 - 122 910 - 1800 <3 <6 U. Wall / Celling 4C N/A 'N/A <27 - 47 1000 - 2000 <3 - 3 <6 - 10 309 Room 2 Floor' Lower WalI 6b <27 1500 <24 - 85 970 - 4100 <3 <6 - 8 U. Wall /Colling IC' N/A N/A <27 1700 <3 <6 315 Floor '3b <27 390 <24 - 28 <320'- 1100 <3 (6 - 9 Lower Wall 3 <27 <320 <24 - 56 <320 - 510 <3 <6 - 7 b U. Wall /Cellino 4C N/A N/A <27 - 85 <320 - %0 <3 (6 - 10

_._------.-___a_i_,-

r TABLE 3 (Continued) S(NMARY OF SURFACE (X)NTAMINATION MEASUREMENTS BUILDING 2. L BUILDING COMPLEX GENERAL ATO41CS - SAN DIEGO, CAllFORNI A

  1. of Grid Blocks Highest Grid TOTAL CONTAMINATION REMOVABLE CONTAMINATION t

2 -Room or Location or Locations Block Average (dpm/l00 cm ) (dom /100 cm ) a Area Measured (dpm/100 cm2) Alpha Range Beta-Gamma Range Alpha Range Beta-Gamma. Range Alpha Beta f Floor 4b 36 1200 <27 - 66 <560 - 1700 <3 (6 - 7 321/323 Lower Wil 4b 32 930 <27 - 66 <320 - 1100 <5 <6 U. Mstl/ Celling 4c N/A N/A <27 - 38 350 - 1400 <3 (6-6 Miscellaneous 1 (Draln)c N/A N/A 1100 <3 <6 0 321/323I Floor 4b N/A N/A (27 <320 - %0 <3 <6 Mezzanine Lower Wall 4D N/A N/A (27 - 28 <320 - 800 <3 - 3 (6 - 7 U. Wall / Celling IC N/A N/A 28 560 <3 8 Miscellaneous 1 (Hoodic N/A N/A <27 720 <3 <6 327 Floor 2 33 530 <27 - 66 (320 - 850 <3 - 9 <6 b Lower Wall 2D. <27 380 <27 - 56 <320 - 830 <3 <6 U. Wall / Celling 4C N/A N/A <27 - 28 . <320 - 400 ' <3 (6 325/327' Floor' 4C N/A N/A (27 <320 <3 - 9 <6 Mez zanine tower Wall 4c N/A N/A <27 - 38 <320 <3 (6 U, Wall / Celling -1C N/A N/A 56-370 <3 - 3 <6 - 12 Miscellaneous I (Duct)c N/A N/A <27 <320 <3 12 _.I_._.___-____._._ __m____ _.._._____..___m .________._____.__..__m_._____

TABLF 3 (Continued) Stt' MARY OF 6unf 6CE WNT AMINATION MEASUREMENTS BUILDING 2, L BUILDING COW LEX GENERAL ATCHICS SAN DIEGO, Calif 0RNIA ( l

  1. of Grid Blocks Highest Grid TOTAL CONTAMINATION REMOVABLE CONTAMINATION 2

Room ora location or Locations __ Block Average (dpm/100 cm ) (dpm/100 cm 1 Are Measured (dpm/100 cm2) Alpha Range Beta-Gamma Range Alpha Range Beta-Gamma Range Alpha Beta s 335/337 Floor 3c N/A N/A <27 ,38 <320 <3 <6 f Mezzanine Lower Wall. 2C N/A N/A <27 - 38 <320 <3 <6 U. Wall / Celling 1C N/A N/A <27 <320 <3 <6 $ 339/341' Floor de N/A N/A <27 - 28 <320.- 560 <3 - 3 <6 Mezzanine Lower Wall 4C N/A N/A <27 - 28 <320 - 480 <3 (6 U. Wall / Celling 2c N/A N/A <27 - 28 <320 <3 <6 - 6 343/345 Floor ab 30 560 <27 - 56 <320 - 770 <3 <6 - 9 Lower Wall 3b <27 760 <27 - 38 <320 - 1100 <3 - 3 (6 'U. Wall / Celling SC N/A N/A <27 - 66 <320 - 450 <3 - 3 (6 - 12 Miscellaneous 1 (Duct)c N/A N/A 28 <320 <3 (6 343/345f Floor 4C N/A N/A <27 - 38 (320 <3 - 3 <6 - 9 Mezzanine Lower Wall 4c N/A N/A <27 - 38 <320 - 430 <3 (6 U. Wal l/ Cell ing 2c N/A N/A (27 <320 <3 <6 347 Floor 2 <27 460 <27 - 47 <320-- 750 <3 (6 - 7 b Lower Wall 2 32 650 (27 - 47 <320 - 1000 <3 - 3 <6 - 10 D U. Wall / Celling 4C N/A N/A <27 28 <320 - 770 <3 <6 - 31

O E N N N E N E. N E N N N N E N M M TABLE 3 (Continued) SlfMARY OF StHFACE CONTAMINATION MEASUREMENTS 13UllDING 2. L BUILDING COMPLEX GENERAL ATOMICS SAN DIEGO, CAllFORNIA

  1. of Celd Blocks Highest Grid TOTAL CONTAMINATION REMOVARLE CONTAMINATION Room or Location or Locations Block Average (dpm/100 cm2)

(dpm/100 cm ) a Area Measured (dpm/100 cm2) Alpha Range Beta-Gamma Range Alpha Range Beta-Gamma Range Alpha Ekta f Floor 4C N/A N/A <27 - 75 <320 <3 - 3 <6 347/349 Mezzanine Lower Wall 4c N/A N/A <27 - 47 <320 - 770 <3 - 3 <6 - 6 U. Wal l/ Cell ing 2 N/A N/A <27 <320 <3 (6 C V

  • 425/427/429' Floor 66 43 600

<27 - 100 <320 - 850 <3 - 21 (6 - 10 tower Wall 7b 36 490 <27 - 85 <320 - 750 <3 <6 - 8 U. Wall / Celling 4c N/A N/A <27 - 38 <320 - 530 <3 <6 - 8 Mi scel laneou s 1 (Duct)c N/A N/A 47 <320 <3 <6 f Floor 3c N/A N/A <25 <430 <3 <6 425/427/429 C N/A N/A <25 - 27 (430 <3 <6 Mezzantne Lower Wall S U. Wall / Celling Hiscellaneous 1 (Sink)c N/A N/A <25 <430 <3 <6 b <27 <320 (27 - 28 <320 - 560 _<3 <6 431 Floor 2 Lower Wall 2D <27 <320 (27 - 38 <320 - 320 5 <6 U. Wall / Celling 4C N/A N/A <27 - 47 <320 <3 - 5 <6 Miscellaneous 1 (S ink )c N/A N/A 330 510 <3 (6

O M M N E E E. O E E M N U U M T ABLE 3 (Con t i nu ed ) SLNMARY OF SURF ACE CONT AMINAT ION f( ASTH EMENTS BullD{NG 2, L BUILDING COMPLEX GENERAL ATOMICS SAN DIEGO, CAliFORNI A

  1. of Geld Blocks Highest Grid TOTAL CONTAHINAtlON REMOVABLE CONTAMINATION Room oro location or locations Block Average (dom /100 cm2)

(dpm/100 cm ) Area Heasured (dpm/100 cm2) Alpha Range Deta-Gamma Range Alpha Range Deta-Gamma Range Alpha Beta D 433 Floor 2 <27 490 <27 - 38 <320 - 640 <3 (6 b Lower Wati 2 <27 700 (27 - 56 <320 - 910 <3 <6 U. Wa l I /Ce! I f nq 3c N/A N/A <27 <320 - 670 <3 (6 M i sc el l aneou s 1 04 cod) N/A N/A <27 <320 <3 6 m O 431/433 Floor 50 N/A N/A <25 - 1500 <430 - 9000 <3 - 3 (6 - 26 f Mezzantne Lower Wall 3c N/A N/A <25 - 45 (430 <3 (6 U. Waff/ Celling f Floor 4C N/A N/A <27 - 47 <320 <3 - 5 <6 615/617 Mezzanine Lower Wa i I 3c N/A N/A <27 - 28 <320 <3 <6 U. Wa t I/ Cell Ing 4c N/A N/A (27 - 47 <320 - 450 <3 (6-7 647 Floor 2 (27 730 <27 - 38 <320 - 880 <3 (6 - 8 b Lower Wall 2b <27 540 <27 - 66 <320 - 800 <3 <6 - 6 U. Wall / Celling de N/A N/A <27 - 190 <320 - 450 <3 - 9 <6 - 19 645/647f Floor ac N/A N/A (27 <320 - 370 <3 <.6 - 8 Pezzantne Lower Wall 3c N/A N/A <27 - 85 <320 <3 <6 - 6 U. Wall / Celling 3C N/A N/A 56 - 75 <320 <3 - 5 (6 - 8

~. - l T ABLE 3 (Cont inued) l l Slp ARY OF StHFACE CONTAMiNAT4ON MEAStEEMENTS BUILDING 2, L DUILDING COMPLEX CENERAL ATOMICS SAN DIEGO, CALIFORNIA l

  1. of Grid Blocks Highest Grid TOTAL CONTAMINATION REMOVABLE CONTAMINATION Room ora Location or Locations Block Average (dpm/100 cm2)

(dpm/100 cm2) Area Measured (dpm/100 cm2) Alpha Range Beta-Gamma Range Alpha Range Beta-Gamma Range Alpha Beta b 64 9 Floor 2 <27 740 <27 - 85 <320 - %0 <3 (6 b Lower wall 2 <27 370 (27 - 75 <320 - 560 <3 <6 U. Wall / Celling 3C N/A N/A (27 - 56 <320 <3 - 5 <6 - 8 i Miscellaneous 1 (Hood)C N/A N/A <27 <320 <3 (6 m W b 651 FI N 2 <27 590 <27 - 56 <320 - 670 <3 - 3 <6 b Lower Wall 2 28 770 <27 - 38 (320 - 850 <3 <6 U. Wall / Celling 4C N/A N/A (27 - 66 <320 - %0 <3 - 3 <6 8Refer to Figures 9 to 32 b Five point measurnment. C$ ingle point measurement, d N/A; Not Appl icable. [ e-; Heasur ments not performed. IRooms were gridded together.

T ABLE 4 SLNMARY OF SURFACE CONT AMINATION MEA $tREMENTS BUILDING 9, E BulLDING COMPLEX GENERAL ATONICS SAN DIEGO, CAliFORNI A

  1. of Grid Blocks Highest Geld TOTAL CONTAMlNATION REMOVABLE CONTAMINATION Room ora Location or Locations Block Avereae (dpm/100 cm2)

(dpm/l0O cm ) Area Measured (dpm/100 cm2) Alpha Ranoe Beta-Gamma Ranae Alpha Ranoe Beta-Gamma Range Alpha Beta 33 FIoor lb N/Ac N/A <24 430 <3 <6 b N/A N/A <24 <430 <3 <6 Lower Wa1l I U. WelI/CeliIng d D N/A N/A <24 <430 <3 <6 $ 34 F1oor 2 Lower Wall Ib N/A N/A <24 <430 3 <6 U. Wall / Celling 38 Floor 2* 45 1600 <27 - 670 <360 - 6400 <3 - 3 <6 Lower Wall le <27 <360 <27 - 28 <360 <3 (6 U. Well/ Celling 39 Floor 28 81 1200 <24 - 360 550 - 1700 <3 <6 Lower Wall U. Wall / Celling 2D N/A N/A 36 <360 - 380 <3 <6

TABLE 4 (Cont inued ) StNMARY OF SURFACE WNTAMINATION MEASUREMENTS BUILDING 9, E BUILDsNG COPPLEX GENERAL ATCHICS SAN DIEGO, CALIFORNI A

  1. of Grid Blocks Highest Grid TOTAL CONTAMINATION REMOVABLE CONTAMINATION Room or location or Locations Block Average (dpm/100 cm )

(dpm/100 cm ) Area Measured (dpm/100 cm2) Alpha Range Beta-Gamma Range Alpha Range Beta-Gamma Range Alpha Beta Main F1oor 2 N/A N/A <24 <430 <3 <6 b Entry Lower Wall Hall U. Wall / Celling Miscellaneous 1(Draln)b N/A N/A <430 <3 <6 ta Hallway floor tb N/A N/A <24 600 <3 (6 b N/A N/A 38 <430 <3 (6 (portion Lower Wa l l I of Old U. Wa l l/Cel l ing Change Room) 47A/478 Floor 4 N/A N/A 47 - 190 <320 - 990 <3 - 3 (6 D Lower Wall 2 N/A N/A (27 - 28 (320 <3 10 b U. Wall / Celling Mi scel laneous 1 (Draln)b N/A N/A 930 <3 <6 48 Floor 2 38 1700 <27 - 75 590 - 3500 3-5 <6 8 Lower Wall 2e (27 <320 <27 - 47 <320 - 370 <3 <6 U. Wall / Celling Ab N/A N/A (27 - 240 <320 - 9300 <3 - 36 (6 - 35 l ---.m.

e W W W W W W W mW W M M M M M TABLE 4 (Cont inued ) SINMARY OF SURFACE CONTAMINATION MEASUREMENTS BUILDING 9, E BUILDING COMPLEX GENERAL ATOMICS SAN DIEGO, CALIFORNI A

  1. of Grid Blocks Highest Grid TOTAL CONTAMINATl0N REMOVABLE CONTAMINATION Room or Location or Locations Block Average (dpm/100 cm 1 (dpm/100 cm )

Area Measured (dpm/100 cm2) Alpha Range Deta-Gamma Range Alpha Range Beta-Gamma Range Alpha Beta 49A Floor 2 470 1900 56 - 910 1000 - 3600 <3 - 5 (6 8 Lower Wall 2 34 <320 <27 - 56 <320 <3 - 19 (6 - 14 8 U. Wall / Celling 2 N/A N/A 28 - 47 <320 <3 <6 D m 8 290 840 <27 - 1300 530 - 1300 <3 <6

  • SO Floor 1

Lcwer Wall le 32 <320 <27 - 66 <320 <3 <6 U. Wall / Celling 2b N/A N/A <27 - 38 <320 <3 <6 Outside Floor 2b N/A 73 - 97 1100 - 3400 <3 <6 Sidewalk Lower Wall U. Wall / Celling 8Ref er to Figures 33 to 42 bSingle point measurements. CN/A; Not Applicable. d-; Measurement not performed. 8Five point measurements. IRooms were gridded together. e .m.

TABLE 5 R AD10NUCLiDE CONCENTRATlONS iN SO4L BUILDINGS 2 AND 9 GENERAL ATOMICS SAN DIEGO, CAllFORNIA Radlonuclide Concentration (pCl /ql Du ll ding / Room location Co-60 Cs-137 U-235 U-238 Th-228 Th-232 a Buildino 2 b <0.3 <0.7 <0.1 2.010.3 302 B, 1.5 <0.1 0.1 1 0.l Trench in Hall 0.3 1 0.1 <0.1 <0.2 <0.8 <0.1 2.0 1 0.3 B, 7, Bottom of Trench Outside <0.1 3.0 1 0.1 <0.3 <0.6 <0.1 2.0 1 0.2 309, Room 1 A+1, 1.8 0.8 i 0.1 1.0 1 0.1 <0.2 <0.7 <0.1 1.0 1 0.3 309, Room 2 A,6 Bottom of Trench 0.110.1 1.0 0.1 <0.3 <0.7 <0.1 2.0 1 0.5 tn 309 A+1.5, 5.8 0.1 i 0.1 7.0 1 0.2 <0.3 <0.8 <0.1 1.0 1 0.3 cn 309c B+1,1 19.0 1 0.4 <0.1 <0.3 <1.0 <0.1 2.0 1 0.5 309d B+1,1: Small Hole 3.0 1 0.2 1.0 0.1 <0.4 2.0 1 0.9 <0.1 2.0 1 0.3 309 B+1,1: Bla Hole 0.3 1 0.1 (0.1 <0.3 1.0 1 1.0 <0.1 2.0 1 0.4 d 309 A+1,3.2 0.1 1 0.1 <0.1 <0.5 <0.7 <0.1 <0.4 Building 9 49A B+.5, 1.75, Bl do. 9 Trench <0.1 <0.1 <0.3 0.7 10.2 <0.1 1.010.4 50 B+.5, 0, Bido. 9 Trench <0.1 <0.1 <0.2 <0.6 <0.1 2.0 1 0.2 50 B+.5, 2.5, Bldg. 9 Trench <0.1 <0.1 <0.2 2.0 t 0.3 <0.1 2.0 1 0.2 50 0,0 (0.1 <0.1 <0.2 3.0 1 0.7 <0.1 2.0 1 0.3 aRef er to Floures 10-12, 40 and 41 buncertainties represent the 951 confidence levels, based only on countino statistics; edditional laboratory uncertaintles of i 6 to 10f have not been groDaoated into these data, cRefore additional remediation. dafter additional remediation.

.] I l 5 REFERENCES 1. " Confirmatory Survey of Phase I Decommissioning, Former Waste Processing

Facility, GA Technologies, San Diego, California," Oak Ridge Associated Universities, July 1986.

2. " Confirmatory Survey of Phase II Decommissioning, Former Waste Processing Facility, CA Technologies, San Diego, California," Oak Ridge Associated Universities, March 1987. 3. " Confirmatory Survey of Phase III Decommissioning, CA Technologies, San Diego, California," Oak Rdige Associated Universities, February 1988. 4 " Confirmatory Survey of Phase IV Decommissioning, General Atomics, San Diego, California," Oak Ridge Ass ciated Universities, November 1988. 5. General Atomics. Decontamination of Selected General Atomics Science Laboratories For Release To Unrestricted Use, San Diego, California, December 21, 1988. 8 6. General Atomics. Decontamination of the " Hot suite" Area of The TRIGA Fuel Fabrication Facility Formerly Located in Building 9 For Release to Unrestricted Use, Stage 1, San Diego, California, January 27, 1989. 7. General Atomics. Summary of the Decontamination of Labs 307/309 For Release to Unrestricted Use. San Diego, California, February 29, 1989. I I I I I i I l 66 5

8 j i g i i 1 I I i APPENDIX A MAJOR SAMPLING AND ANALYTICAL EQUIPMENT 5 l8 (B 8 L lI I

L APPENDIX A f-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 i Eberline " RASCAL" i Portable Ratemeter-Scaler Model PRS-1 j (Eberline, Santa Fe, NM) 8 Eberline PRM-6 f Portable Ratemeter (Eberline, Santa Fe, NM) l Ludlum Floor Monitor Model 239-1 1 (Ludlum, Sweetwater, TX) Eberline Alpha Scintillation Probe Model AC-3-7 (Eberline, Santa Fe, NM) i Eberline GM Pancake Probe Model HP-260 } (Eberline, Santa Fe, NM) B Victoreen Beta-Gamma " Pancake" Detector Model 489-110 (Victoreen, Cleveland, OH) Victoreen NaI Scintillation Detector l Model 489-55 (Victoreen, Cleveland, OH) B. Laboratory Analyses Automatic low-background Alpha-Beta Counter l Model LB5110-20B0 (Tennelec. Inc., Oak Ridge, TN) ~ l High-Purity Germanium Detector Model GMX-23195-S, 23% efficiency (EG&G ORTEC, Oak Ridge, TN) Used in conjunction with: lead Shield, G-16 (Gamma Products, Inc., Palos Hills, IL) A-1 I

lI lI ~ High Purity Germanium Coaxial Well Detector l Model GWL-1102010-PWS-S, 23% efficiency (EC&G ORTEC, Oak Ridge, TN) Used in conjunction with: ? Lead Shield Model G-16 (Applied Physical Technology Atlanta, GA) i High Purity Germanium Detector Model IGC25, 25% efficiency (Princeton Gamma-Tech, Princeton, NJ) [ Used in conjunction with: Lead Shield (Nuclear Data, Schaumburg, IL) I Multichannel Analyzer ND-66/ND-680 System (Nuclear Data Inc., Schaumburg, IL) (I I lI lI I lI .I il l A-2 \\

.. = - _.. [t f !!I l +lI !I '!!I 4-1 i ~

g i

APPENDIX B MEASUREMENT AND ANALYIICAL PROCEDURES I I 1 i I 1 I P 5 I j I-I I Y

I i APPENDIX B I 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 normally about 1 cm. Identification of elevated maintained at a minimum 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 -I floor of the facility were accomplished by use of a gas proportional floor the monitor, with a 600 cm2 sensitive area. The instrument was slowly moved in a systematic pattern to cover 100% of the accessible area. Combinations of detectors and instrument for the scans were: I 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. I Alpha - ZnS Probe with PRS-1 scaler /ratemeter. Alpha-Beta - Gas proportional floor monitor with Ludlum Model 2220 scaler /ratemeter. Alpha and Peta-Gamma 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 5-Eberline Model PRS-1 portable scaler /ratemeters with Model HP-260 thin-window " pancake" G-M probes. Count rates (cpm) were converted to disintegration rates 2 (dpm/100 cm ) by dividing the net rate by the 4r efficiency and correcting of 2 for the the active area of the detector. Effective window areas were 59 cm ZnS detectors and 15 cm2 for 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 for the G-M detectors.

E I Removable Contamination Measurements Smear measurements were performed on numbered filter paper disks, 47 mm in diameter. Smears were placed in labeled envelopes with the locations and other pertinent information recorded. Smears were counted on a low-background gas-proportional counter. I Exposure Rate Measurements i I Measurements of gamma exposure rates were performed using Eberline PRM-6 Victoreen Model 489-55 gamma scintillation probe portable ratemeters with a containing 3.2 cm x 3.8 cm NI(Tl) scintillation crystal. Count rates were converted to exposure rates (pR/h) by cross-calibrating with a Reuter Stokes 'model RSS-lll pressurized ionization chamber. Soil Sample Analysis Soil samples were dried, mixed, and a portion sealed in 0.5-liter g W 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 analyzer sys tein. 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: I Co-60 1.173 MeV Cs-137 0.662 MeV U-235 0.144 MeV ll ~ U-238 0.094 MeV from Th-234 (secular equilibrium assumed) Th-232 0.911 MeV from Ac-228 (secular equilibrium assumed) t Spectra were also reviewed for the presence of other radionuclides. 8 I B-2 I

8 y 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 l 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 limits of the procedure. ~ Because of variations in background levels, sample weights or volumes, and l Compton contributions from other radionuclides in samples, the detection limits I differ from sample to sample and instrument to instrument. Additional uncertainties of + 6 to 10%, associated with sampling and laboratory procedures, have not been propagated into the data presented in this report. l l Calibration and Quality Assurance l 1 I Laboratory and field survey procedures are documented in manuals developed specifically for the Oak Ridge Associated Universities' Environmental Survey and Site Assessment Program. I With the exception of the measurements conducted with portable gamma f 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. B l 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 l Quality Assurance Programs. B B-3

I

I f
I 1

il i I - I APPENDIX C I GUIDELINES FOR DECONTAMINATION OF FACILITIES AND EQUIPMENT PRIOR TO RELEASE FOR UNRESTRICTED USE OR I TERMINATION OF LICENSES FOR BY-PRODUCT, SOURCE OR SPECIAL NUCLEAR MATERIAL I I I . I g I I I I

I I APPENDIX C GUIDELINES FOR DECONTAMINATION OF FACILITIES AND EQUIPMENT I PRIOR TO RELEASE FOR UNRESTRICTED USE OR TERMINATION OF LICENSES FOR BYPRODUCT, SOURCE, OR SPECIAL NUCLEAR MATERIll. l i I I I I I U.S. Nuclear Regulatory Co==ission Divison of Fuel Cycle & Material Safety I Washington, D.C. 20555 I I I July 1982 I I I I

I The instructions in this guide, 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 eq uip=en t prior -l to abandonment or release for unrestricted use. The limits in Table 1 do not apply to premises, equipment, or scrap containing induced radioactivity w for which the radiological considerations pertinent to their use may be different. The release of such facilities or items from regulatory control I is considered on a 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, I 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 I covering. 3. The radioactivity on the interior suzfaces of pipes, drain lines, or I. 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 I interior of the pipes, drain lines, or ductwork. Surfaces or premises, equipment, or scrap which are likely to be conta=inated but are of such size, construction, or location as to make the surface I - for purposes of measurement shall be presumed to be inaccessible contaminated in excess of the limits. 4. Upon request, the Cc= mission 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 would not be limited to, special cir Aistances such . I as razing of buildings, transf er of premises to anot2er organization continuing work with radioactive materials, or conversion of facilities to a long-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 saf ety analysis which reflects that the residual amounts of materials on surface areas, together with I 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 f or 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 I C-1

I the survey report shall be filed with the Division of Fuel Cycle and }3 Material Saf ety,

USNRC, Washington, D.C.
20555, and also the Administrator of the NRC Regional Office hav ing jurisdiction.

The report should be filed at least 30 days prior to the planned date of

I abandonment. The survey report shall

Identify the premises. a. 's b. Show that reasonable effort has been made to eliminate residual 1 contamination. Describe the scope of the survey and general procedures followed. c. I d. State the findings of the surv ey in units specified in the instruction. i Following review of the report, the NRC will consider visiting the facilities to confirm the survey. I I I I I I i I I I I I C-2 .I

m m m M M M M M M M M M mm m m m m TABLE 1 ACCEPTABLE SURFACE CONTAMINATION LEVELS Nuclidesa Averageb,c.f flaximumb,d,f Removableb,c,f U-nat, U-23 5, U-23 8, and 5,000 dpm a/100 cm2 15,000 dpm a /100 cm2 1,000 dpm a/100 cm2 associated decay products Transuranics, Ra-226, Ra-22 8, 100 dpm/100 cm2 300 dpm/100 cm2 20 dpm/100 cm2 Th-230, Th-22 8, Pa-231 Ac-227, I-125, I-129 2 2 200 dpm/100 cm Th-nat, Th-232, Sr-90, Ra-223 1000 dpm/100 cm2 3000 dpm/100 cm Ra-224, U-23 2, I-126, I-131, 1-133 2 n Beta gamma emitters (nuclides 5000 dpm Sy/100 cm2 15,000 dpm Sy/100 cm2 1000 dpm By/100 cm /, with decay modes other than alpha emission or spontaneous fission) except Sr-90 and others noted above. a Where surf ace 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 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 Hensurements 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 the maximum contamination level applies to an area of not more than 100 cm2, 2 of surface area should be determined by e The amount of removable radioactive material per 100 cm I 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 ef ficiency. When removable contamination on objects of less surf ace area is determined, the pertinent levels should Ife l reduced proportionally and the entire surfcce should be wiped. f l The average and maximum radiation levels associated with surface contamination resulting from beta-gamma cmitters should not exceed 0.2 mrad /h at I cm and 1.0 mrad /h at I cm, respectively, measured through l not more than 7 milligrams per square centimeter of total absorber. .~

p I I ADDITIONAL DECOMMISSIONINC GUIDELINES FOR THE GENERAL ATOMICS FACILITY I Target criteria for unrestricted release of the General Atomics Waste Processing Facility and surrounding areas are presented in the licensee's final report and are as follows: I External Radiation The gamma exposure rate at 1 m above the ground surface shall not exceed 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)). I Inhalation and Ingestion I 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 are derived to satisfy these external and internal target criteria. The concentration limits are presented in the p following Table. Radionuclide Concentration Limit Above Background (pCi/g) I Depleted Uranium 35 Enriched Uranium 30 Thorium (Natural) 10 Co-60 8 Cs-137 15 Sr-90 1.8 X 103 I C-4

lI ? Where more than one radionuclide is present, the sum of the ratios of the individual radionuclide concentrations to their respective concentrations i limits shall not exceed 1. j I I I I k I I I I I I I 1 I I l I C-5 ..}}

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