ML20245L663
| ML20245L663 | |
| Person / Time | |
|---|---|
| Site: | 07000734 |
| Issue date: | 07/31/1989 |
| From: | Cotten P OAK RIDGE ASSOCIATED UNIVERSITIES |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| Shared Package | |
| ML20245L660 | List: |
| References | |
| CON-FIN-A-9076 ORAU-89-F-98, NUDOCS 8908220231 | |
| Download: ML20245L663 (88) | |
Text
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l ORAU 89/F-98 j I' ] O I
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FACILITIES IN R g ulatory BUILDINGS 2 AND 9 Commission's Rgion V Of5ce GENERAL ATOMICS g ' t,"i,n,
$ *d bY SAN DIEGO, CALIFORNIA Industrial and Medical Nuclear Safety P. R. COTTEN I
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I Environmental Survey and Site Assessment Program Energy / Environment Systems Division FINAL REPORT JULY 1989 I
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I' NOTICES The opinions expressed 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 responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or pro,es s disclosed, or represents that its use would not infringe privately owned rigSts. Reference herein to any speci!!c commercial product, process, or service by trade name, mark, manufseturer, or otherwise, does not necessarily constitute or imply its endorsement or recommendation, or favoring by rhe U.S.
Government or any agerwy thereof. The views and opinions of authors expressed herein do not necessarl'y state or reflect those of the U.3. Government or any agency thereof.
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ORAU 89/F-98 g.l j };i,.D Gh CONFIRMATORY SURVEY'
-OF FACILITIES IN'
~-
-BUILDINGS 2 AND 9 GENERAL ATOMICS SAN DIEGO,: CALIFORNIA.
Prepared by I~
P.R. COTTEN
)'
s:1' Environmental Survey and Site Assessment Program I.
-Energy / Environment Systems Division' Oak Ridge Associated Universities-Oak Ridge, TN ' 37831-0117' Project Staff J.D. Berger-F.A. Templon G.R. Foltz C.F. Weaver J.L. Payne Prepared for Division of Industrial and Medical Nuclear Safety-U.S. Nuclear Regulatory Commission Region V Office FINAL REPORT JULY 1989 This report is based on work performed under Interagency Agreement (NRC Fin.
)
No._
A-9076) between the U.S.
Nuclear Regulatory Commission and the U.S. Department of Energy.
Oak Ridge Associated Universities performs complementary work under contract number DE-AC05-760R00033 with the U.S. Department of Energy.
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TABLE OF CONTENTS Page IAst of Figures.
11 1
-List of Tables v
j Introduction and Site History. -....................
1 Site Description.
2 Procedures.
2 Results.
6 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
-I Appendix C: Guidelines for Decontamination of Facilities and 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 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 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 Roome Included in Group 3 Decommissioning.
16 FIGURE 7:
Section C of Building 2, Indicating Rooms Included in Group 3 Decommissioning.
17 FIGURE 8:
Decontamination Stages for the " Hot Suite" Area 18 Building 9.
FIGURE 9:
Layout if Room 234, Indicating Locations of Surface Contamination Measurements.
19 FIGURE 10: Layout of Room 302 with Adjoining Walkways, Indicating Locations of Sampling and Surface Contamination Measurements.
20 FIGURE 11: Layout of 309, Room 1, Indicating Locations of Sampling and Surface Contamination Measurements.
21 FIGURE 12: Layout of 309, Room 2, Indicating Locations of Sampling and Surface Contamination Measurements.
22 l
FIGURE 13: Layout of Room 315, Indicating Locations of Surface contamination Measurements.
23 FIGURE 14: Layout of Rooms 321 and 323, Indicating Locations of Surface Contamination Measurements.
24 FIGURE 15: Layout of Mezzanine 321/323, Indicating Locations of 25
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Surface Contamination Measurements.
FIGURE 16:
Layout of Room 327, Indicating Locations of Surface 26 Contamination Measurements.
FIGURE 17: Layout of Mezzanine 325/327, Indicating Locations of 27 I
Surface Contamination Measurements.
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LIST OF FIGURES (Continued)-
Page FIGURE 18:
Layout of Mezzanine 335/337, Indicating Locations of Surface' Contamination Measurements.
28 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 Contamination Measurements.
30 FIGURE ~21: Layout of Mezzanine 343/345 Indicating Locations of Surface Contamination Measurements.
31 FIGURE 22: ' Layout of Room 347, Indicating Locations of Surface Contamination Measurements.
32
' FIGURE 23:
Layout of Mezzanine 347/349 Indicating Locations of Surface Contamination Measurements.
33 FIGURE 24: Layout of Rooms 425, 427, and 429, Indicating Locations of Surface Contamination ~ Measurement.
34 FIGURE 25:
Layout of Mezzanine 425, 427, and 429, Indicating Locations of Surface Contamination. Measurements 35 FIGURE 26: Layout of Rooms 431 and 433, Indicating Locations of Surface Contamination Measurements.
36 L FIGURE 27: ' Layout of Mezzanine 431/433, Indicating Locations of 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 Contamination Measurements.
39 FIGURE 30: Layout of Mezzanine 645/647, Indicating Locations of 40 Surface Contamination Measurements.
FIGURE 31:
Layout of Room 649, Indicating Locations of Surface Contamination Measurements..
41 FIGURE 32: Layout of Room 651, Indicating Locations of Surface Contamination Measurements.
42 FIGURE 33:
Layout of Room 33, Indicating Locations of Surface Contmaination Measurements.
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l LIST OF FIGURES (Continued) t
'5 Pag.,
FIGURE 34:
Layout of Room 34, Indicating Locations of Surface 8
Contamination Measurements.
44 I
FIGURE 35: Layout of Room 38, Indicating Locations of Surface Contamination Measurements.
45 FIGURE 36:
Layout of Room 39, Indicating Locations of Sarface 46 Contamination Measurements.
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FIGURE 37: Layout of Main Entrance Hallway Indicating Locations of Surface Contamination Measurements.
47 FIGURE 38: Layout of Rooms 47A and 4CB (Old Change Room), Indicating 48 Locations of Surface Contamination Measurements.
FIGURE 39: Layout of Room 48 Indicating Locations of Surface Contamination Measurements.
49 FIGURE 40: Layout of Room 49A, Indicating Locations of Soil and Surface Contaminant Measurements.
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FIGURE 41: Layout of Room 50, Indicating Locations of Soil and 51 Surface Contamination Measurements.
FIGURE 42: Layout of Sidewalk Area Outside Room 48, Indicating i
52 Locations of Surface Contamination Measurements.
FIGURE 43: Locations of Background Measurements and Baseline Soil I
Samples from the Vicinity of General Atomics.
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I LIST OF TABLES Page
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54 TABLE 1:
Background Radiation Levels TABLE 2:
Baseline Radionuclides Concentrations in Soil.
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Summary of Surface Contamination Measurements Building 2, TABLE 3:
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L Building Complex.
TABLE 4:
Summary of Surface Contamination Measurements Building 9, I
62 E Building Complex.
TABLE 5:
Radionuclido Concentrations in Soil....
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h CONFIRMATORY SURVEY OF FACILITIES IN Ig BUILDINGS 2 AND 9 l3 GENERAL ATOMICS SAN DIEGO, CALIFORNIA l-INTRODUCTION AI?D 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.
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Because of the numerous building and land areas being decommissioned and the varied nature of O rmer operations in these facilities, the decommissioning is 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 waste handling fac,ilities, and undeveloped land surrounding the waste processing facilities; Phase II areas were the former Waste Processing Facility and the Incinerator Pad; Phase III consisted of approximately 87 hectares of undeveloped land, surrounding the rain 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
former sewage treatment plant known as " Callan Ponds," and 12 laboratories in Building 2 of the L Building Corrplex. 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 as " Group 1"
and " Group 2" facilities. An additional 19 laboratories, 12 of which include mezzanine areas, and 10 separate mezzanines only in Building 2
)
I 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 Cs-137, Co-60, Sr-90, thorium, and uranium (natural, depleted, and areas were enriched).
I 2 area of Building 9, E Building Complex, has been An approximate 268 m Stage 1 of the current GA decommissioning activities. This decontaminated as is part of the building area, known as the " Hot Suite," once associated with l
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I the TRICA fuel fabrication facility; new housed at a different location. The primary contaminant in this facility was uranium with U-235 enrichments, 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 unrestriend use.
This survey was performed March 14-23, 1989, in accordance with a survey plan submitted to I
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 Sen Diego, CA (Figures 1 and 2).
Buildings 2 and 9 are illustrated in Fi urus 3 and 4.
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l l 5 Building 2, a two-story, semicircle building, located in the center of the CA 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 2.2 mezzanir.es, 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 has been leased out to I
several different companies; the former TRIGA Fuel Fabrication ' Hot Suite" was located in an area of Building 9 vhich is now occupied by CA's telecommunications Sroup.
The entire " Hot Suite" area originally occupied 375 m2 of area and contained 9 rooms and 2 hallways (Tigure B); only the l
Stage i portion of the area is included in this survey.
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Objectives l gW 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
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as decommissioning, is accurately presented in the General Atomics report and to prov!de information and data for evaluation of the site status, relative to NRC guidelines for release for unrestricted use.
Document Review The licensee's survey reports for the unrestricted release of portions of Buildings 2 and 9 was reviewed by ORAU(5-7), r,ata presented in these reports were corppared to the established release guidelines.
I facility Survey 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 B
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 outside Room 48 were surveyed, Figures 9 through 42 show the layouts of these areas.
Gridding I
x 2 m reference grid system was established on the An alphanumeric 2 m floor and lower walls (up to 2 m) for each room and mezzanine surveyed.
I Measurements made on upper walls, ceiling, or equipment were referenced to the established grid or prominent building features.
Surface Scans I
were performed on floors and lower Alpha, beta-gamma, and gassa scans walls, using an alpha / beta gas proportional large area detector, beta-gamma GM detectors, and NaI(TI) gamma scintillate 9n detectors with audible indicating scaler /ratemeters.
Scans of surface areas not accessible to the large area I
s i,
' detector, i.e.,
- ceilings, and overhead areas such as ledges, beams, piping, fixtures,. counter tops, equipment, and ductwork were performed using portable ZnS alpha scintillation and GM detectors. Locations of elevated radiation levels were noted for additional measurements.
Surface scans using a NaI(TI) scintillation detector, were performed in creas where' the floor had been removed and the underlying soil was exposed.
Additional measurements were made with a beta-gamma GM detector to define any creas where elevated locations were identified.
Exposure Rate Measurement 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 ef 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 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 Fi ures 9 through 32.
5 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 rurface contamination measurements in this Building.
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W Soil Sampling 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
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collected from open trenches in Roems 49A and 50 (Figures 40'and 41).
Miscellaneous Samples
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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 16 and 24).
I Background and Baseline Measurements Background measurements and soil samples were collected to determine area back round and to provide baseline radionuclides concentrations for comparison 5
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purposes.
Locations of the background measurements and baseline samples are shown in Figure 43.
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-232;
- 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 backgraund gas proportional counter. Additional information concerning analytical equipment and procedures is presented in Appendices A and B.
Survey l
results 'were compared to NRC guidelines for decommissioning of the General Atomics Facility (Appendix C).
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I 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 decontaminating 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 I
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 radionuclides 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 lavels are typical of exposure rates and radionuclides 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 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 I
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 2
removable beta contamination ranged from <6 to 64 dpm/100 cm,
I Radionuclides 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 Samples No detectable activity was present on the large area swipe taken from the s
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 radiologic'al conditions.
Followup measurements at this sampling location indicated total and removable contamination levels were below detection limits.
I Building 9 Surface Scans I
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 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 I
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 2
2 470 dpm/100 cm,
alpha, and 1900 dpm/100 cm, beta-gamma; these maximum levels occurred on the floor of Room 49A.
Removable contamination from Brid 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 I
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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<320 to 9300 dpm/100 cm, respectively.
The-highert levels were from the 11rcation above';the' doorway in Room 48,.which was ide.stified by scans and; further' remediated by the licensee. Removable contamination levels'were low; 2
elpha ranged form
<3 to 36 dpm/100 cm ' and beta ranged from' <6 to 2
'35 dpm/100 cm,
Radionuclides Concentrations'in Soil Samples Table 5 lists the concentrations of radionuclides present in soil samples
'from Rooms 49A and 50.
Cobalt-60, and Cs-137 concentrations were <0.1 pCi/g;
.U-235 levels ranged from <0.2 to <0.3 pCi/g; U-238 concentrations ranged from
<0.6 to 3.0 pCi/g; and Th-232' concentrations were from 1.0 to 2.0 pc'i/g.
COMPARISON OF SURVEY RESULTS WITH GUIDELINES The-guidelines for decommissioning' the Ceneral Atomics-facility'are.
presented in Appendix C.
Surface contamination limits for building surfaces cre. based on primary contaminants of uranium, Cs-137, and Co-60, identified.on this site, and are:
Alpha 2
2 5000 dpm/100 cm, averaged over 1 m 2
2
,15000 dpa/100 cm, maximum in 100 cm 2
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 dpa/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
Buildings 2 and 9 all grid biccks satisfied the 5000 dpm/100 cm average level.
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There were several individual measurements between 5000 and 15000 dpm/100 cm ;
however, each of these measurements represented small, isolated spots of
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contamination and averaging with contiguous surfaces resulted in satisfying the 2
5000 dpm/100 cm average guideline.
No measurements were in excess of the l'
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t 15000 dpm/100 cm guideline level.
Removable contamination levels were. also 2
well within the guideline value of 100 dpm/100 cm,
'I 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 were all well within the guideline values established specifically for the GA site decommissioning.
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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
radionuclides concentrations in soil.
The initial scans identified several small areas of residual contamination; these were immediately cleaned by the licensee and resurveyed by ORAU.
Final measurements indicated that all radiological conditions satisfied the established decommissioning 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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FIGURE 1: Map of the Son Diego Area, Indicating the Location of General Atomics Facilities 11 I
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FIGURE 3: Layout of Building 2 (L Building Complex)
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I FIGURE 5: Section A of Building 2, Indicating Rooms included l.
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FIGURE 9: Layout of Room 234, Indicating Locations I
of Surf ace Contamination Measurements 19
' GAT 35 I
e WINDOW OUTSIDE 6
N CONCRETE WALKWAY A
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s ROOM 3b2 A
B C
4.
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ROOM 309 I
i MEASUREMENT LOCATIONS GRID BLOCK g SOIL SAMPLING LOCATIONS I
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FIGURE 10: Layout of Room 302 with Adjoining Wolkways, Indicating Locations of Sampling and Surface Contamination I
Measurements 20 o
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FIGURE 11: Layout of 309, Room 1, Indicating Locotions of g
Sampling and Surface Contamination Measurements
l
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FIGURE 12: Layout of 309, Room 2, Indicating Locations of Sampling and Surf ace Contamination Measurements 22 g
i
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FIGURE 13: Layout of Room 315, Indicating Locations of t
Surface Contamination Measurements g
n y
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FIGURE 14: Loyout of Rooms 321 and 323, Indico^.ing Locations of Surface Contamination Measurements n
g
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I FIGURE 15: Layout of Mezzanine 321/323, Indicating Locations of j
j Surface Contamination Measurements j
25 8
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A A
4
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4 A
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FIGURE 16: Layout of Room 327, Indicating Locations of I
Surface Contamination Measurements 26
GAT 42
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DUCT MEASUREMENT LOCATIONS GRID BLOCK UPPER WALL /COLING (SINGLE POINT)
- g l
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I FIGURE 17: Layout of Mezzanine 325/327, Indicating Locations of Surface Contamination Measurements 27
. GAT 70 I
g i
Wit DOWS 3
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0 2
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I FIGURE 18: Layout of Mezzanine 335/33'7, Indicating Locations of Surf ace Contamination Measurements g
2e
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I FIGURE 19: Layout of Mezzonine 339/341, Indicating Locations of Surf ace Contamination Measurements g
29 5
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METERS FIGURE 20: Layout of Rooms 343/345, Indicoting Locations of Surface Contamination Measurements t
5
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I FIGURE 21: Layout of Mezzanine 343/345, Indicating Locations of g
Surf ace Contamination Measurements 31
GAT 46
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FIGURE 22: Layout of Room 347, Indicating Locations of Surface Contamination Measur ements 32
____f______________
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FIGURE 23: Layout of Mezzanine 347/349, Indicating Locations of Surf ace Contornination Measurements 33
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B FIGURE 25: Layout of Mezzanine 425, 427, and 429, Indicating Locations of Surface Contamination Measurements 25
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1 GAT 52 '-
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!o FIGURE 28: Layout of Mezzanine 615/617, Indicating Locations of Surface Contamination Measurements 38
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39 I
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FIGURE 31: Layout of Room 649, Indicating Locations of Surface Contamination Measurements g
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FIGURE 32: Layout of Room 651, Indicating Locations of Surface Contamination Measurements 42 I
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FIGURE 37: Layout of Main Entrance Hollway, Indicating Locations of Surface Contamination Measurements g
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4 FIGURE 38: Layout of Rooms 47A and 46B (Old Change Room),
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KILOMETERS Ji FIGURE 43: Locations of Background Measurements and I
Baseline Soil Samples from the Vicinity of General Atomics 53
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TABLE 1 BACKGROUND RADIATION LEVELS I E GENERAL ATOMICS g
SAN DIEGO, CALIFORNIAN I
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(pR/h)
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i
i REFERENCES i
I
.1.
" Confirmatory Survey of Phase I Decommissioning, Former Vaste Processing i
Facility, CA Technologies, San Diego, California," Oak Ridge Associated Universities, July 1986.
s l
2.
" Confirmatory Survey of Phase II Decommissioning, Former Waste Processing Facility, GA Technologies, San Diego, California," Oak Ridge Associated Universities, March 1987.
j I
3.
" Confirmatory Survey of Phase III Decommissioning, GA Technologies, San
/
Diego, California," Oak Rdige Associated Universities, February 1988.
4.
" Confirmatory Survey of Phase IV Decommissioning, General Atomics, San Diego, California," Oak Ridge Associated Universities, November 1988.
5.
General Atomics.
Decontamination of Selected General Atomics Science Laboratories For Release To Unrestricted Use, San Diego, California, December 21, 1988.
6.
General Atomics.
Decontamination of the " Hot suite" Area of The TRICA Fuel Fabrication Facility Formerly Located in building 9 For Release to Unrestricted Use, Stage 1, San Diego, California, January 27, 1989.
7.
General Atomics.
Summarv of the Decontamination of Labs 307/309 For Release to Unrestricted Use.
San Diego, California, February 29, 1989.
L
)
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l 66
_.___.__________._______a
1 I
I
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I I
5
--x A g
MAJOR SAMPLING AND ANALYTICAL EQUIPMENT i
i I
l 5
4 I
I l
E 8
I I
3:
APPENDIX A MAJOR SAMPLING AND ANALYTICAL EQUIPMENT The. display or description of a specific product is not to be construed as an endorsement of that product or its manufacturer by the authors or their employer.
I A.
Direct Radiation Measurements Eberline " RASCAL" I.
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)
Eberline Alpha Scintillation Probe I'
Model AC-3-7 (Eberline, Santa Fe, NM)
Eberline GM Pancake Probe Model HP-260 (Eberline, Santa Fe, NM) 5 Victoreen Beta-Gamma " Pancake" Detector Model 489-110 (Victoreen, Cleveland, OH)
Victoreen NaI Scintillation Detector Model 489-55 (Victoreen, Cleveland, OH)
I B.
Laboratory Analyses 1 B' l-Autcmatic low-background Alpha-Beta Counter l
Model LB5110-2080 (Tennelec, Inc., Oak Ridge, TN) i H'gh-Purity Germanium Detector l.
Model GMX-23195-S, 23% efficiency (EG&G ORTEC, Oak Ridge, TN)
Used in conjunction with:
I Lead Shield, G-16 (Gamma Products, Inc., Palos Hills, IL)
A-1
\\
B High Purity Germanium Coaxial Well Detector Model GWL-1102010-PWS-S, 23% efficiency (EG&G ORTEC, Oak Ridge, TN)
Used in conjunction with:
Lead Shield Model G-16 (Applied Physical Technology, Atlanta, GA)
High Purity Germanium Detector 3
Model IGC25, 25% efficiency r g (Princeton Gamma-Tech, Princeton, NJ)
Used in conjunction with:
Lead Shield (Nuclear Data, Schaumburg, IL')
.ig:
. Multichannel Analyzer W
ND-66/ND-680 System (Nuclear Data Inc., Schaumburg, IL)
B I
j8 I
I I
l 8
I A-2
--w-,-.,7-.. _,.
9 APPENDIX B MEASUREMENT AND ANALYTICAL PROCEDURES i
)
)
L i
1 I
APPENDIX B Measurement and Analytical Procedures Surface Scans I
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 p
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 the-floor of the facility were accomplished by use of a gas proportional floor 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:
Beta-Gamma - Pancake G-M Probe with PRM-6 ratemeter.
Beta-Gamma - Pancake G-M Probe with PRS-1 scaler /ratemeter.
G====
- 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 Beta-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 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
(dpa/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.
B-1
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.
Exposure Rate Measurements 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-111 pressurized ionization chamber.
Soil Fample 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 analyzer system.
Background and Compton stripping, peak search, peak identification, and concentration calculations were performed using the computer capabilities inherent in the analyzer system.
Energy peaks used for I.
determination of radionuclides of concern were:
Co-60 1.173 MeV Cs-137 0.662 MeV U-235 0.144 MeV U-23S 0.094 MeV from Th-234 (secular equilibrium assumed)
Th-232 0.911 MeV from Ac-228 (secular equilibrium assumed)
Spectra were also reviewed for the presence of other radionuclides.
I B-2
[
Uncertainties and Detection Limits
(-
)
The uncertainties associated with the analytical data presented in the tables of this report, represent the 95% confidence levels for that data.
These uncertainties were calculated based on both the gross sample count levels and the associated background count levels. When the net sample count was less than the 95% statistical deviation of the background count, the sample concentration was reported as less than the detection limits of the procedure.
Because of variations in background levels, sample weights or volumes, and Compton contributions from other radionuclides in samples, the detection limits differ from sample to sample and instrument to instrument.
Additional uncertainties of 1 6 to 10%, associated with sampling and laboratory procedures, have not been propagated into the data presented in this report.
Calibration and. Quality Assurance 1
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 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.
1 Quality control procedures on all instruments included daily background and check-source measurements to confirm equipment operation within acceptable statistical fluctuations.
The ORAU laboratory participates in the EPA and EML Quality Assurance Programs.
B-3
i.
)
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I I
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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 NUCLEAk MATERIAL I
I I
I I
g
- g I
I
APPENDIX C GUIDELINES FOR DECONTAMINATION OF-FACILITIES AND EQUIPMENT PRIOR TO RELEASE FOR UNRESTRICTED USE OR TERMINATION OF LICENSES FOR BYPRODUCT, SOURCE, OR SPECIAL NUCLEAR MATERIAL U.S.. Nuclear Regulatory Commission Divison of Fuel Cycle & Material Safety Washington, D.C.
20555 l
July 1982 L
L 1
1
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 surf aces or premises and equipment prior to. abandonment or release for unrestricted use.
The limits in Table 1 do I
not apply to premises,. equipment, or scrap containing induced radioactivity for which the radiological considera'tions pertinent to their use may be different. The release of such facilities or items from regulatory control 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, plating, or o t.her 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 ef fort must be made to minimize the contamination prior to use of any covering.
3.
The radioactivity on the interior surfaces 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 interior of the pipes, drain lines, or ductwork.
Surfaces or I.
premises, equipment, or scrap which are likely to be contaminated but are of such size, construction, or location as to make the surface inaccessible for purposes of r:easurement shall be presumed to be contaminated in excess of the limits.
4.
Upon request, the Commission may authorize a licensee to relinquish I
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 circumstances such razing of buildings, transfer of premises to another organization as I
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 safety analysis which reflects that l
the residual amounts of materials on surface areas, together with other considerations such as pro spective use of the pr emis es,
equipment or scrap, are unlikely to result in an unreasonable risk to the health and safety of the public.
5.
Prior to release of premises for unrestricted use, the licensee shall make a
comprehensive radiation survey which establishes that contamination is within the limits specified in Table 1.
A copy of ln I
I the survey report shall be filed with the Division of Fuel Cycle and I
Material Saf ety,
- USNRC, Washington, D.C.
- 20555, and also the Administrator of the NRC Regional Office having jurisdiction.
The report should be filed at least'30 days prior to the-planned date of abandonment. The survey report shall:
Identify the premises.
a.
b.
Show that reasonable ef fort has been made to eliminate residual contamination, Describe the scope of the survey and' general procedures followed.
c.
d.
State the findings of the survey in units specified in the
~
instruction.
Following review of the report, ' the NRC will consider visiting the facilities to confirm the survey.
I I
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9 4.
' ADDITIONAL
- DECOMMISSIONING GUIDELINES FOR THE.
GENERAL ATOMICS FACILITY Target ' criteria for unrestricted release of the Gen'eral Atomics Waste coprocessing Facility and surrounding, areas are presented in tlie licensee's final report and are as followst 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)].
Inhalation and Ingestion
-Concentrations of radionuclides in soil shall be such that inhalation and-ingestion-are not expected to result in annual dose equivalents exceeding.
20 arem 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
-following Table.
Radionuclides Concentration Limit Above Background (pCi/g)
'. Depleted Uranium 35 Enriched Uranium 30 Thorium.(Nacural) 10 Co-60.
8 Cs&137 15 Sr-90 1.8 X 103 C-4
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- Where 'more.than!one radionuclides is present, the.' sum of:the ratios of the'!
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. individual; radionuclides - - concentrations;;to;.their? respective. concentrations-
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