ML20058E837

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Final Rept, Radiological Survey of General Atomics Sva Facility San Diego,Ca
ML20058E837
Person / Time
Site: 07000734
Issue date: 10/31/1993
From: Beck W, Landis M, Payne A
OAK RIDGE ASSOCIATED UNIVERSITIES
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
Shared Package
ML20058E832 List:
References
CON-FIN-A-9076 NUDOCS 9312070188
Download: ML20058E837 (44)
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10 - 73 Y RADIOLOGICAL SURVEY OFTHE GENERAL ATOMICS SVA FACILITY SAN DIEGO, CALIFORNIA [ DOCKET 70-734] j M. R. LANDIS AND M. A. HENKE Prepared for the U.S. Nuclear Regulatory Commission Region V Office i .-^ $h k syy, / j '. A- ~n,. .omp .g f :Nw g i 93120~/018B 931109 PDR ADOCK 07000734 ] C PDR r-(If. n

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OAK TUDOB INGTITUTE FOR SCIENCE AND EDtJCATION. i Environmental Survey and Site Assessment Program ' Energy / Environment Systems Division ' ~

P i l i b 5 d f 1 r i 1 I i i The Oak Ridge Institute for Science and Education (ORISE) was established by the U.S. Department of Energy to undertake national and international programs in science and engineering education, training and management systems, energy and environment systems, and medical sciences. ORISE and its programs are operated by Oak Ridge Associated -{ Universities (ORAU) through a management and operating contract with the U.S. Depanment of Energy. Established _ ~ in 1946. ORAU is a consortium of 65 colleges and universities. I NOTICES 1 The opinions expressed herein do not necessarily reflect the opinions of the sponsoring institutions of Oak Ridge i i Associated Universities. i This report was prepared as an account of work sponsored by the United States Government. Neither the United States -'t Government nor the U.S. Department of Energy, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, - apparatus, product, or process disclosed, or represents that its use would not infringe on privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, mark, manufacturer, or j otherwise, does not necessarily constitute or imply its endorsement or recommendation, or favor by the U.S. Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of 6 the U.S. Government or any agency thereof. .i .y ~i

4 ORISE 93/J-141 RADIOLOGICAL SURVEY OF THE GENERAL ATOhUCS SVA FACILITY SAN DIEGO, CALIFORNIA Prepared by r M. R. Landis and M. A. Henke Environmental Survey and Site Assessment Program Energy / Environment System Division Oak Ridge Institute for Science and Education Oak Ridge, Tennessee 37831-0117 Prepared for U.S. Nuclear Regulatory Commission Region V Office t Sponsored by the Office of Nuclear Materials Safety and Safeguards OCTOBER 1993 i FINAL REPORT This report is based on work performeo under an Interagency Agreement (NRC Fin. No. i A-9076) between the U.S. Nuclear Regulatory Commission and the U.S. Department of Energy. Oak Ridge Institute for Science and Education performs complementary work under contract number DE-AC4)5-760R00033 with the U.S. Department of Energy. ] Gewrat Asames SVA Facuay Oricea 71.1993 f 1 J

( 4 F RADIOIDGICAL SURVEY OF TIIE GENERAL ATOMICS SVA FACILITY SAN DIEGO, CALIFORNIA / I Prepared by: / p ha Date: lo/M/qr Michble landis, Projedt Mana'ger ~ /~ Environmental Survey and Site Assessment Program i /f3 Reviewed by: h Date: /8 Wilhim L. Beck,'X6 ting l2boratory Manager / Environmental Survey and Site Assessment Program Reviewed by: mm Date: / Obi f 93 Ann T. Payne, Quality Assurdnce Officer Environmental Survey and Site Assessment Program i Reviewed by: .e C Date: /0/Sydf3 fjb. Berger, Proggm Director / / Environmental Survey and Site Assessment Program I h I ? ? Ooneral Akanu o SVA Tecuny Ock*er 21,1993 n ,--,m- ,sv-n w

4 4 1 ACKNOWLEDGEMENTS j The authors would like to acknowledge the significant contributions of the following staff members: I t FIELD STAFF l E. H. Bjelland T. L. Bright j G. R. Foltz E.

d. Montalvo LABORATORY STAFF 3

R. D. Condra J. S. Cox R. L. Epperson M. J. Laudeman i S. T. Shipley i I CLERICAL STAFF l l D. A. Cox T. T. Claiborne R. D. Ellis M. S. Perry K. E. Waters ILLUSTRATOR i E. A. Powell 7 T. D. Herrera l i . I { Omeral Akumco SVA fuihty Ockter 21,1993 ?

V 4 a 1 8 TABLE OF CONTENTS PAGE Li st o f Fig u res............................................... i1 List of Tables.............................................. iii Abbreviations and Acronyms..................................... iv Introduction and Site History.................................... 1 Site Description............................................. 3 Obj ecti ves................................................. 5 Document Review............................................ 5 Procedures ............................................... 6 i Findings and Results.......................................... 7 Comparison of Results with Guidelines............................... 8 S u m mary................................................. 9 t References ..............................................24 i i Appendices: i t i L Appendix A: Major Instrumentation Appendix B: Survey and Analytical Procedures Appendix C: Guidelines for Decontamination of Facilities and Equipment to Release for Unrestricted use or Termination of License for Byproduct, Source, or Special Nuclear Material i f i, t L i e t Oemeral Marmica SVA Faciley Octater 21.1993 i I

1 LIST OF FIGURES PAGE FIGURE 1: Plot Plan of General Atomics Facilities, San Diego, California 11 FIGURE 2: Plot Plan of Sorrento Valley Facility, San Diego, California........ 12 FIGURE 3: SVA Facility Zone Designations......................... 13 FIGURE 4: Zone 6 - Location of Elevated Direct Radiation 14 l FIGURE 5: Zone 7 - Iecation of Elevated Direct Radiation 15 FIGURE 6: Zone 8 - locations of Elevated Direct Radiation............... 16 c FIGURE 7: Zone 11 - Imcations of Elevated Direct Radiation............... 17 i i s ? f i t General Akunra SVA Facinny Ocuder 21,1993 11 k n-. -,,c- ,-m -v---

r r s I LIST OF TABLES PAGE TABLE 1: Area and Surface Classifications......................... 18 TABLE 2: Summary of Surface Activity Measurements.................. 21 TABLE 3: Summary of Surface Activity Measurements in Areas of Elevated Direct Radiation............................22 i } f l a r.i Aw. sva ruany awr 21. im iii

t ABBREVIATIONS and ACRONDIS i ASME American Society of Mechanical Engineers CAS Central Alarm System 2 cm square centimeter epm counts per minute DOE Department of Energy 2 dpm/100 cm disintegrations per minute /100 square centimeters EML Environmental Measurements Laboratory EPA Environmental Protection Agency ESSAP Environmental Survey and Site Assessment Program ft foot GA General Atomics GM Geiger-Mueller HEPA High Efficiency Particulate Air kg kilogram m' square meter MDA Minimum Detectable Activity Nal sodium iodide NIST National Institute of Standards and Technology NRC Nuclear Regulatory Commission ORISE Oak Ridge Institute for Science and Education pCi/g picocurie per gram SAS Secondary Alarm System SNM Special Nuclear Material SVA Sorrento Valley "A" ZnS zine sulfide e L 2 i Ormeral Anarnes SVA l'acilny Ockmes 21,1993 iv

4 i RADIOLOGICAL SURVEY OF TIIE GENERAL ATOMICS SVA FAsCILITY j SAN DIEGO, CALIFORNIA INTRODUCTION AND SITE IIISTORY I General Atomics (GA) operated the Sorrento Valley "A" (SVA) fuel fabrication facility under U.S. Nuclear Regulatory Commission (NRC) License SNM-696 and State of California Source and Byproduct license 0145-80 beginning in 1959. Activities canducted included: Development of fuel fabrication processes, i Fabrication of new fuel for several reactors and other fuel utilization programs, Design of coated particle fuel, and Design, construction and qualification of manufacturing equipment. Radioactive materials used in these manufacturing operations included highly enriched uranium and thorium. Operations resulted in the contamination of process equipment and some internal suifres of the facility. Large production processes were discontinued in April of 1985; small fuel fabrication operations continued until 1990. The SVA Decommissioning Plan was submitted to the NRC in April 1990 and revised August 1990. Final NRC approval was given in October 1990. Additionally, changes to the release criteria specified in the plan were requested per GA letter dated April 14, 1992 and approved by NRC letter dated May 1, 1992.52 5 Decommissioning activities are being conducted in two phases. Phase I was the decontamination and radiological survey of the facility; Phase II is facility dismantlement, with areas not e decontaminated to be disposed of as low-level radioactive waste. Phase I began about October 1990 and continued to February 1993; the following activities were included: Ormetal Akunsre SVA Facitay October 21.1993 i t r

i Approval of the Plan by the NRC. Removal of all equipment and internal structures. Packaging of radioactive waste. Decontamination of axessible surfaces. l Conducting detailed surveys of the facility surfaces. Decontamination of " hot spots" identified during the survey. Re-survey of the " hot spots" and identification of all exceptions (locations which could not be decontaminated and/or surveyed and will be disposed of as radiological waste or decontaminated to meet the release guidelines during the dismantlement of the building). Application of fixative to selected surfaces to contain/ control surface contamination during dismantlement. Shipment of radioactive waste to DOE disposal sites. Submittal of Phase I report to NRC. Phase II activities, to be completed upon authorization from the NRC and State of California, will include the following: [ Dismantlement of the building; items identified as exceptions will be disposed of in a controlled manner as contaminated low-level radioactive waste or decontaminated to meet i release criteria. Clean portions of the building will be disposed of at a nearby landfill. Removal of all underground drain lines. Soil remediation (as needed). Post-remedial action soil sampling, analysis and documentation. [ Submittal of a Phase II (post-dismantlement) report to the NRC summarizing the activities comple.ted in Phare II. NRC concurrence that the open land site meets the criteria. h Gruwra! Aksones SVA Facilfr) Ocuber 21.1993 2

I In February 1993, GA submitted the Phase I repon to the NRC.' The final survey consisted of f surface scans for alpha and beta activity, smears for removable activity and exposure rate measurements. At the request of the NRC Region V Office, the Environmental Survey and Site Assessment Program (ESSAP) of the Oak Ridge Institute for Science and Education (ORISE) conducted confirmatory activities and additional radiological measurements at the General Atomics SVA l Facility. This report describes the procedures and results of those activities. SITE DESCRIITION The SVA facility is located in the north half of Building 37 (SVA facility) in Sorrento Valley at 11222 Flintkote Avenue, San Diego, California. Figure 1 illustrates the location of the GA Sorrento Valley Complex in relation to other GA facilities. Figure 2 illustrates the location of Building 37 (and the north end of Ruilding 37)in relation to other structures at the GA Sorrento Valley complex. j Approximately 3700 m (41,0001t) housed fuel fabrication processing equipment, offices, I 2 2 change rooms, laboratories, storerooms, a machine shop and stockroom. For project control and [ tracking, the facility was divided into 14 zones which are described below and shown in Figure 3. Zone 1 North Tunnel Annex Zone 2 China Wall Zone 3 CAS (Central Alarm Station) Zone 4 West Vault i Zone 5 Hot Machine Shop (North End) and Stockroom (South End) Zone 6 Vault Office and Assay Room Zone 7 Soot Filter Pads Located Outside North of Building 37 Zone 8 Production Floor (Section 1-4) l Zone 9 North and South Ends of the North Tunnel Omvat Akuruca SVA Fatihty Octdior 21,1993 3 m r %..g...,w.- 9 --yy r-v-- y 9g-

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Zone 10 East Mezzanine Zone 11 North Annex Zone 12 West HEPA Room Zone 13 SAS (Secondary Alarm Station) Zone 14 Outside Walls of Building BUILDING CONSTRUCTION The report facility consists of the following: Main Building (Zones 1, 2, 6, 8, 9 and 10) - Concrete tilt-up panel construction. The panels are attached to a structural steel framework and rest against the edge and footings of the concrete floor and has a composition roof. A storage tunnel is located under the east edge of the main floor. West Vault (Zone 4)- A heavily reinforced concrete storage structure with numerous l 1 shield walls forming storage aisles. Hot Machine Shop and West HEPA Room Buildings (Zones 5 and 12, respectively) - Consist of metal siding and roofs attached to structural steel framework with concrete floors. These structures abut the main building, west vault and north annex. 1 CAS (Zone 3) - A concrete block structure with a cast-in-place roof located within the West HEPA Room Building (Zone 12). Soot Filter Pads (Zone 7). Concrete pads located outside and north of Building 37. i 1 North Annex (Zone 11)- A metal structure similar to those previously described, south 1 wall of which is the north wall of the main building. %ma Av.t. svA ruany Ockie M. W 4 {

=. -- \\ Secondary Alarm System (SAS) (Zone 13) - A reinforced concrete structure consisting _ i of four rooms and two ha!! ways. One of the hallways extends south along the north annex. The floors consist of abcut 20 cm of reinforced concrete. Concrete walls are about 18-30 cm thick. Metal walls and roofing are of standard corrugated metal stock. ( f Composite roofs are metal decking with insulation and tac coverings. The roof of the SVA main building consists of ribbed steel decking topped with a layer of rigid insulation, multiple layers or roofing and a bituminous top dressing. The sheets of metal span supporting roof trusses and purlins to which they are welded. The roofis contaminated. Fixative has been applied to the t inside ceiling and trusses to bind the contamination in place and facilitate the safe removal of these portions of the building during dismantlement. The roof will be disposed of as radioactive waste; or, if feasible, portions may be decontaminated. P OBJECTIVES The objectives of the ESSAP activities were to provide independent document reviews and radiological data, for use by the NRC in evaluating the adequacy of the licensee's radiological i status report, relative to established guidelines. This report describes the proceduxs and results of the survey. j t DOCUMENT REVIEW ESSAP reviewed the licensee's documentation associated with the decommissioning survey.*" ' Analytical procedures and methods utilized by the licensee and its contractor were reviewed for s adequacy and appropriateness. The final-status survey results and supporting data were reviewed l for accuracy, completeness, and compliance with guidelines. G i (kam! Aunks $VA TEMay Ockner 21,1993 5 ) i

PROCEDURES I l During the period of April 23-30, 1993, ESSAP performed confirmatory and radiological surveys of the General Atomics SVA Facility. Confirmatory survey activities included surface scans for alpha and beta activity and smears for removable activity. In addition, ESSAP performed measurements for total alpha and beta surface activity; these data are not sufficient to meet the recommendations of NUREG/CR-5849 for final-status surveys, but may be used by the NRC to supplement the licensee's data and assist the NRC in evaluating the radiological status of the facility. The survey was in accordance with a plan submitted to and approved by [ J NRC Region V.5 The licensee's classification of areas as having low or high potential for contamination was used to develop the ESSAP survey plan. Area and surface classifications are given in Table 1. t SURVEY PROCEDURES Reference Grid d The reference grid systems established by the licensee were utilized. Individual grid blocks (1 m X 1 m) were identified by their southeast coordinates. Measurement locations on [ ungridded surfaces were referenced to prominent building features or the existing grid. I e Surface Scans Surface scans for alpha, beta, and gamma activity were performed using large-area gas proportional and Nal scintillation detectors, coupled to ratemeter-scalers with audible indicators. In areas classified as low potential zones,50 to 100% of the floor surfaces were scanned for alpha, beta, and gamma activity. In high potential zones 50 to 100% of the floor surfaces were scanned for alpha, beta, and gamma activity and 25% of the wall and ceiling surfaces were i scanned for alpha and beta activity. I.ocations of elevated direct radiation, identified by surface scans, were marked for further investigation. I I Oemeral Aksnas $YA l'acinny Oct*cr21,1993 6

Surface Activity Measurements Measurements to determine total alpha and total beta surface activity were performed on randomly selected grid blocks. In the gridded areas the measurements were made at the approximate center of the selected grids. The number of direct measurements taken was based 2 2 on a measurement frequency of 1 per 25 m for high-potential floors,1 per 100 m for 2 high-potential walls and ceilings, and I per 200 m for all low-potential surfaces. Total alpha and total beta measurements were taken at 30 locations on the combined low-potential surfaces and at 225 locations on the combined high-potential surfaces. These measurements were taken using ZnS scintillation and thin-window GM detectors, coupled to ratemeter-scalers. A smear sample for determining removable activity was obtained at each direct measurement location. Direct measurements were also performed at locations of elevated direct radiation identified by i the surface scans. SAMPLE ANALYSIS AND DATA INTERPRETATION Samples and survey data were returned to the ESSAP laboratory in Oak Ridge, Tennessee, for analyses and interpretation. Smears were analyzed using a low-background alpha / beta counter to determine gross alpha and gross beta activity. Direct measurements and smears were reported 2 in units of dpm/100 cm Additional information concerning major instrumentation, sampling equipment, and analytical procedures is provided in Appendices A and B. Results were compared to the NRC guidelines which are provided in Appendix C. i FINDINGS AND RESULTS i DOCUMENT REVIEW The decommissioning plan and Phase I reports were reviewed and comments provided.W Concerns raised included the procedure for measurements of total surface activity and the interpretation and application of the thorium surface activity guidelines. The licensee's responses to these comments were also reviewed and comments provided.7-'" i o=,.i a-. sva rm cw*.o 2i. im 7 l t

S Surface Scans Surface scans for alpha, beta, and gamma activity identified seven areas of elevated direct radiation. These areas are listed in Table 2. Surface Activity Ixvels Results of total and removable activity levels, from randomly selected locations are summarized 2 in Table 3. Total activity levels ranged from <69 to 180 dpm/100 cm, for alpha, and <740 2 to 1500 dpm/100 cm, for beta. Removable activity levels were less than the minimum 2 detectable activity of the procedure, for alpha, which is < 12 dpm/100 cm, and ranged from 2 < 17 to 25 dpm/100 cm, for beta. Results of total and removable surface activity levels at locations identified by surface scans are 2 summarized in Table 2. Total alpha activity levels ranged from < 73 to 5100 dpm/100 cm and 2 total beta activity levels ranged from 1700 to 17,000 dpm/100 cm, COMPARISON OF RESULTS WITII GUIDELINES Guidelines for acceptable surface contamination levels, used by the NRC to determine whether a facility may be released for unrestricted use, are summarized in Appendix C. The contaminants at the SVA facility were uranium and thorium. For alpha activity the guidelines established are: i Total Activity 2 2 1,000 dpm/100 cm, averaged over 1 m 2 2 3,000 dpm/100 cm, maximum in 100 cm Osmers! Akwks SVA Facday Ockda 21.1903 8

Removable Activity 2 200 dpm/100 cm / For beta activity the guidelines established are: Total Activity 2 2 5,000 dpm/100 cm, averaged over 1 m 2 2 15,000 dpm/100 cm, maximum in 100 cm Removable Activity 2 1,000 dpm/100 cm All the measurements performed at randomly selected locations were within the guidelines. Measurements performed at areas of elevated direct radiation identif'ed by surface scans are in Table 2. In Zone 7, alpha activity on a concrete pad exceeded the maximum allowed in a 100 2 cm area. In Zone 11, beta activity behind an I-beam exceeded the maximum allowed in a 100 2 cm area. Both of these areas were remediated and resulting surface activity levels were within the guidelines. At a foundation /walljunction in Zone 7, alpha and beta activity levels were between the average and maximum guideline values. Due to the access limitations at this location which prevented additional measurements, this area was added to the list of exceptions. 2 Alpha and beta activity exceeded the maximums allowed in a 100 cm area on an interior roof in Zone 6. This area was also added to the list of exceptions. Three areas with slightly elevated gamma levels, approximately twice background, were identified in Zone 8. These three areas were added to the list of exceptions.

SUMMARY

In April 1993, ESSAP performed a radiological survey of the General Atomics SVA Facility in San Diego, California. Activities performed included document review, surface scans and surface activity measurements. Ocamal Anomace SVA Facilny Octrea 21. Im 9

4 Document reviews raised several concerns regarding guidelines and survey methodology; these concerns were resolved between the NRC and licensee. With exception of the identification of several small areas of residual activity, the results of the ESSAP radiological sun'ey supported the conclusions of the licensees survey, relative to satisfying the guidelines established for this project. l l l l a.ml Atmu SVA IEMay atte 21, Im 10

SVA1 SVA sa N I (FUEL MANUFACTURING) N { g. G\\ 2 ,s SORRENTO / II VALLEY /[' slTE u / ici MAIN SITE 5 JOHN J. HOPKINS DRrd Qy '4;p N h x x x rENCE h NOT TO SCALE FIGURE 1: Plot Plon of Genero! Atomics Focilities, Son Diego, Cclifornia e chad Akmuce SVA f acany Ockda 21, M3 I1

SVA2 I PARKNG sToRAct SFED L*2 a, e5[i 59 sinfa F DD q:s e uwlEupucj-D f i g g v ,c. E E $..'$ 7 tox $5t? i ). stonAct 3: a e \\ Nww y l mDc. @B'Q- ]- 42 1 N Q Y N w? FACILJTY STORAGE AREA N n Y x X FENCE A 0 100 t o 30 WETERS FIGURE 2: Plot Plan of Sorrento Volley Focility, Son Diego, Californio Ommi Akunes $VA Icany Ockdn 21. Im 12

WA3 4 4 EDCB l ZOtt 7 FUME SCRUBBER SAS l SOOT flLTER PAD / ZONE 13 WvU yta pe / 49 10 ol O l., 48 47 SROPNML K J HGF t l HOT MACHNE 46 SHOP STOCKROOW NORTH NNEX 45 zout 3 7ayt 33 44 43 9 [-- 42 41 i E -+ 40 wtsi YAutT 5 ~ 39 VAULI OTTCE w 20NE 4 ASSAY RM. PRODUCTION FLOOR g i TUNNELS ARE zout c IONE 8 N 38 n l sEcTION 4 LOCATED ON l !i' 37 6 [ LOWER LEVEL ! I = 36 l wes7 i, 33 NEPA PRODUCTON FLOOR (AST ROOM ZONE 6 WEZZANNE N-34 ZONE 12 SECTON 3 ZONE 10 e 33 2ND LEVEL = 32 31 PRODUCTON FLOOR ~ ZONE B j g 5 2 j SECTON 2 29 g g PRODUCTON FLOOR h 27 ZONE e 2 a r$ MON 1 0 y 26 l3 i $ 25 chm wAu fowE 2 z \\ - ~,1 N h h li NOT TO SCALE f!GURE 3: SVA Focility Zone Designations o.wa Aw. SVA 1wuay OcW 21,1m 13

S/A4 41 T ] car, I i 4g 4. ._.. c). .J 39 _.2.. 1 ll r, P N M N h

  • $'N

@IELEVATED DIRECT RADIATION NOT TO SCALE FEET O 6 g uETras nGURE 4: Zone 6 - Locotion of Elevated Direct Radiation Georrat Ausnn $V*. f unny (ksder 73, SW) }4

svAs mura-snoo -l.... --r.... 1 ... +... _. t.. HP/CFWJG..C... e f _ pgy. MR ' -.mtu em _.2._.. s 49 o!o (, not acmet SHOP 43 FUWE SORUDEER l 4 7.......'. SOCT FPJEp> PAD.. _.................... _ _.................. _ _ _.F e e . _....... _ N M L K J H G l S R O P a 2 14 h h // h ELEVATED D: RECT RADIATION NOT TO SCALE h 0.IU 12 6 4 ucites FIGURE 5: Zone 7 - Location of Elevated Direct Radiction Ormeral Akutwa SVA I eenlay Chidurt21, 1993 15

SVA6 l gj .......O: l l 1 s a s e n i 4Q ..Q... j-. 4 1 8 39..._.4..._ _.j... .. a c3._... _.. 7 4 4 4 t 1 4- ..d.u $- -u m ....E-.... 0 37 c:3 - !j f l . Q) ,re=r - ~ Q' i 1 I 5 4 3 I f ~- - ~ - > - + - - m-- -i 36 a, 35

  • - - E L-o I-b I

k- ! -- bCI-8 i 4 t r - "-- - - --i l 34 - r - --.. -- -+ -~-- .3 a,: 1 4 33 - + - ~ - -' - --- - --- i + - r- ~ -',n"--~- ~ g I i I L 4 32 J 5 i ]j 4.... .. p.. ._4. t 1 8 f 1 1 1 5 1 f O I I ( ~. - - - - i 30 , - -- ~ , - - - - - ~ '-- - ~, - - - + ~-- 1 1 a 1 i 29 4_.. 3 ', [i::D 28 - + ~ + - * - * - * - '~ $ - ~ ~ - ~ ' ' ' ~ ~ ' - "N 27 J- ~ 0 - -a, --- - l - - 26 - L",----+----",-----e,---- J 2 1 f p$ ..2...._._.. P N M L K J H C F E D C 0 A N J-,

    • y

.. ELEVATED D: RECT RAD 1ATION NOT TO SCALE h 0 12 6 METERS FIGURE 6: Zone 8 - Locations of Elevated Direct Radiation General Akumca SVA Iacahty (k*9ter 21,1993 }h

. y l SVA7 l ~_ t 1 i l t 47 ~... .... _.. ~ -. _ ~ .i i, N t i r i i 1' a E 4,- *-, -+ 46 i-J- + - 4" " E, "- +"U l e ( t I 1 t ..i...f._......5.. .{..,.

4...

.,...J.. . ~ .,a ..A

4..

.~?.. . o.J...i 4$ i 1, i t 1, 1 1 3, t -t - -i - - --M-- 1 - * -"- - '- ~ - ' - "L-4 - " 4-" " - i 44 i i 6 l I t ? i i i ...j.... 4....j.._ l 4 3 i..... i.. ..J. . {.....;. ..J... -.. i.._.. 4_ _...{......i- ...[....;_. { i i 5 i i i i i i i i t i 47

l.... t

.. l. e ..{. ...i.....,4... ..4. .p,..........<.i.. 4 i 4 r i .i 4 t i i i e e i j i i 4j j.. ...4... j'.... <............. ..... ~. - .-4.- S R O P N M L K J H G F E D C B i i l .i l 1 1 I i i 1 N h y ELEVATED DIRECT RADIATION NOT TO SCALE h 0 12 METERS l l FIGURE 7: Zone 11 - Locations of Elevated Direct Radiction i 1 o-.14=-. sva rmany m**= 21. im 17 1 i

  • W t

f ~ TABLE 1 AREA AND SURFACE CLASSIFICATIONS i GENERAL ATOMICS SVA FACILITY SAN DIEGO, CALIFORNIA m 5 f Zone Arra Surface Comments Clas. ification .~. j 1 North Tunnel Annex Floor Low Walls Low Ceiling low 2 China Wall Floor low Ceiling-Production Floor an Exception Wall low Ceiling-Mezzanine Low 3 Central Alarm Station Floor low (CAS) Walls Iew = Ceiling lew Outside Walls Iow Roof High 4 West Vault Floor High Walls High Ceiling High 5 Hot Machine Shop / Floor . Low Corrugated Metal Walls and Ceiling are Stock Room Walls Imw Exceptions 6 Assay Room Floor High Walls IAw Ceiling low Roof Low Outside Walls low 7 Heater, Soot Filter and Floor Iow Fume Scrubber Pads 2 -e ,----g- -,-~-s-w ~ ~ ~ -~ ~ + m u e am ..e, v--n-, m. e

{ TABLE 1 (Continued) f AREA AND SURFACE CLASSIFICATIONS GENERAL ATOMICS SVA FACILITY s SAN DIEGO, CALIFORNIA k ly Zone Area Surface Comments Clas i tion s 8 Production Floor Floor High East Wall and Ceiling are Exceptions Section 1 West Wall Imw East Mezzanine Ceiling Low South Vault Walls High 8 Production Floor Floor High East Wall and Ceiling are Exceptions Section 2 West Wall Iow g East Mezzanine Ceiling Low 8 Production Floor Floor High East Wall and Ceiling are Exceptions Section 3 West Wall low East Mezzanine Ceiling Low 8 Production Floor Floor High Ceiling an Exception Section 4 Walls Low East Mezzanine Ceiling - Imw 9 North Tunnel-North Floor High End Walls High Ceiling High 9 North Tunnel -South Floor High End West Wall High East Wall Low Ceiling Low 10 East Mezzanine Floor High East Wall and West Ceiling are Walls Low Exceptions l Ceiling Low

TABLE I (Continued) g AREA AND SURFACE CLASSIFICATIONS a, - GENERAL ATOMICS SVA FACILITY ~ { SAN DIEGO, CALIFORNIA i 5 f I SVA y Zone Area Surface Comments Classification i i1-North Annex Floor High Wall-Imw Ceiling law 12 West HEPA Room Floor High West Wall and Ceiling are Exceptions Walls Low i 13 SAS Hallway and Four Floor Imw oo Rooms Walls low Ceiling low 14 Outside Walls of Walls Low Building t h j J i: k "... _. -... ~.. - _ _... _..,.,. _,.... _... ~ ~.,. _. - - _.. _ -.-.. _.. 2,..~_.-.. ....~. ---....a

{ ~ TABLE 2 i(

SUMMARY

OF SURFACE ACTIVITY MEASUREh!ENTS IN AREAS OF ELEVATED DIRECT RADIATION j GENERAL ATOMICS SVA FACILITY p SAN DIEGO, CALIFORNM 5 f Pre-Remediation Post-Remediation E Total Activit Total Activit Removable Activity (dpm/100 cmh (dpm/100 cm (dpm/100 cm ) Zone

ation, 3

2 Alpha Beta Alpha Beta Alpha Beta 6 Interior Roof 1 3500 17000 N/A N/A N/A N/A Above Zone 6 7 Outdoor Pad 2 2 5100 13000 < 78 < 660 < 12 < 17 M 8 Flood

  • 3

< 73 2900 N/A N/A N/A N/A b 8 Floor

  • 4

< 73 1700 N/A N/A N/A N/A b 8 Floor

  • 5 85 2400 N/A N/A N/A N/A 11 Behind I-Beam 6

1700 15000 < 73 820 < 12 < 17 11 Foundation

  • 7 2300 12000 N/A N/A N/A N/A

" Refer to Figures 4-7. b.Area added to exceptions list.

  • Area had elevated gamma direct radiation.

-~

[ TABLE 3 E, f

SUMMARY

OF SURFACE ACTIVITY MEASUREMENTS IN AREAS OF ELEVATED DIRECT RADIATION -j GENERAL ATOMICS SVA FACILITY p SAN DIEGO, CALIFORNIA f Range of Range of Total Activit Removable u Build.mg 37 North (dpm/100 cmh Activity ( pm/100 j em N Zone Surface Classification AI ha Beta Alpha Beta P g n eng

  1. 1 North Tunnel Floor Low I

80 940 < 12 < 17 Annex Lower Walls Low I < 73 810 < 12 < 17 y

  1. 2 China Wall Floor Low I

< 73 < 740 < 12 < 17 Lower Walls Low I < 73 < 740 < 12 < 17

  1. 3 Central Floor Low I

< 73 < 740 < 12 < 17 Alarm Station

  1. 4 West Vault Floor High 18

< 69-100 < 750-990 < 12 < 17 Lower Walls High I8 < 69-85 < 750 < 12 < 17 Upper Walls / Ceiling High 6 < 69 < 750 < 12 < 17

  1. 5 Hot Machine Floor High 14

< 73-180 < 740-1500 < 12 < 17 Shop Lower Walls Low 2 < 73 < 740 < 12 < 17

  1. 6 Assay Room Floor High 4

< 73-140 960-1200 < 12 < 17 Lower Walls low I < 73 790 < 12 < 17

  1. 7 Outdoor Floor High 2

< 73-90 < 740 < 12 < 17 Concrete Pad

  1. 8 Production Floor High 77

< 73-150 < 740-1500 < 12 < 17-25 Floor Lower Walls Low 2 < 73 < 740 < 12 < 17

[ TABLE 3 (Continued) [

SUMMARY

OF SURFACE ACTIVITY MEASUREMENTS IN AREAS OF ELEVATED DIRECT RADIATION { GENERAL ATOMICS SVA FACILITY L SAN DIEGO, CALIFORNIA a Range of Range of Build.mg 37 North Total Activity Removable g (dpm/100 cm ) Activity ( pm/100 cm Na Zone Surface Classification AI ha Beta Alpha Beta P M m ents

  1. 9 North Tunnel Floor High 5

< 73-140 920-1100 < 12 < 17 Walls High 4 < 73 960-1100 < 12 20 g Upper Walls / Ceiling High 2 < 73 < 740-1100 < 12 < 17 Upper Walls / Ceiling Low I < 73 1200 < 12 < 17

  1. 10 East Floor High 24

< 73-100 < 740-1000 < 12 < 17-19 Mezzanine Lower Walls Low 2 < 73 < 740 < 12 < 17

  1. 11 North Annex Floor High 38

< 69-100 < 750-1200 < 12 < 17 Lower Walls Low 6 < 69 < 750-880 < 12 < 17 Upper Walls / Ceiling Low 3 < 69-90 < 750-800 < 12 < 17

  1. 12 West HEPA Floor High 13

< 73-120 < 740-100 < 12 < 17 Room Lower Walls Low 2 < 73 < 740 < 12 < 17

  1. 13 SAS and Floor Low 4

< 73-80 < 740 < 12 < 17 Hallway Lower Wa!!s Low 2 < 73 < 740 < 12 < 17

REFERENCES o t 1. letter from K. E. Asmussen (GA) to J. W. N. Hickey (U.S. NRC, Headquarters), " Decontamination Guidelines for GA's SVA Decommissioning Project," April 14, 1992. 2. Ietter from J. W. N. Hickey (U.S. NRC Headquarters) to K. E. Asmusen (GA), May 1, t 1992. 3. "SVA Decommissioning Project Phase I (Pre-Dismantlement) Survey Report," General Atomics, February 1993. 4. "SVA Decommissioning Plan," General Atomics, April 1990, revised August 1990. 5. Radiological Survey Plan for the General Atomics SVA Facility, San Diego, California," ORISFJESSAP, April 22,1993. 6. Ixtter from M. R. I2ndis (ESSAP) to M. Cillis (U.S. NRC, Region V)," Comments on Documentation for the SVA Decommissioning Project at GA Technologies," December 31, 1992. f 7. Letter from K. E. Asmussen (GA) to M. Cillis (U.S. NRC, Region V), " Responses to j ORISE Comments on GA's SVA Decommissioning Plan," February 10,1993. 8. 12tter from M. R. Landis (ESSAP to M. Cillis -(U.S. NRC, Region V), "SVA Decommissionmg Project, Phase I (Pre-Dismantlement) Survey Report, General Atomics, February 1993," March 24,1993. j 9. Fax from K. E. Asmussen (CA) to M. R. Landis (ESSAP), "SVA Decommissioning Project i Phase I Survey Report and March 29,1993 Conference Call," March 26,1993.

10. Fax from K. E. Asmussen (GA) to M. R. Landis (ESSAP)," SVA Decommissioning Project _

Phase 1 Survey Reports and April 6,1993 Conference Call," April 5,1993.

11. " 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, August 1987.

i t i f Orswrn! AMs SVA Facany (k*kt 21,1993 24

i b 1 b h i t t t 9 I r APPENDIX A MAJOR INSTRUMENTATION i 6 5 i f 1 ) ? i i ? n i 4 i i i i l General Akunnos SVA l'acilay (ktober 21,199)

APPENDIX A MAJOR INSTRUMENTATION The display of a specific product is not to be construed as an endorsement of the product or its manufacturer by the authors or their employers. 4 DIRECT RADIATION MEASUREMENT Instruments Ludlum Ratemeter Model PRM-12 (Ludlum Measurements, Inc., Sweetwater, TX) Eberline " Rascal" Ratemeter-Scaler Model PRS-1 (Eberline, Santa Fe, NM) Ludlum Floor Monitor Model 239-1 (Ludlum Measurements, Inc., Sweetwater, TX) Ludlum Ratemeter-Scaler Model 2221 (Ludlum Measurements, Inc., Sweetwater, TX) Detectors Eberline GM Detector Model HP-260 2 i Effective Area, 3.5 cm (Eberline, Santa Fe, NM) Eberline ZnS Scintillation Detector Model AC-3-7 2 Effective Area,59 cm (Eberline, Santa Fe, NM) Ludlum Gas Proportional Detector Model 43-37 2 Effective Area,550 cm (Ludlum Measurements, Inc., Sweetwater, TX) Eberline NaI Scintillation Detector Model SPA-3 5.1 cm x 5.1 cm Crystal (Eberline, Santa Fe, N.M.) i Ocarsal Akwis SVA FacMay Ockder 21,1995 A-1

i LABORATORY ANALYTICAL INSTRUMENTATION low Background Gas Propo. tonal Counter Model LB-5110 (Tennelec, Oak Ridge, TN) i i r Oratsal Atumsa SVA Facusty Octabcv 21,1993 A-2

i i f i i i APPENDIX B SURVEY AND ANALYTICAL PROCEDURES t + i t ? l Onneral Akunnes EVA Fachy Orkeer 21.1993 I t

APPENDIX B SURVEY AND ANALYTICAL PROCEDURES SURVEY PROCEDURES 1 Surface Scans Surface scans were performed by passing the probes slowly over the surface; the distance i between the probe and the surface was maintaintd at a minimum - nominally about I cm. A large surface area, gas proportional floor monitor was used to scan the floors of the surveyed 2 2 areas. Other surfaces were scanned using small area (15.5 cm or 59 cm ) hand-held detectors. Identification of elevated levels was based on increases in the audible signal from the recording and/or indicating instrument. Combinadons of detectors and instruments used for the scans were: Alpha gas proportional detector with ratemeter-scaler ZnS scintillation detector with ratemeter-scaler i Beta gas proportional detector with ratemeter-scaler pancake GM detector with ratemeter-scaler Gamma NaI scintillation detector with ratemeter Surface Activitv Measurements Measurements of total alpha and total beta activi':y levels were performed using ZnS scintillation, and GM detectors coupled to portable ratemeter-scalers. Count rates (cpm), which were integrated over 1 minute in a static position, were converted to activity levels (dpm/100 cm ) by 2 dividing the net rate by the 4r efficiency and correcting for the active area of the detector. The alpha activity background count rates for the ZnS scintillation detectors averaged approximately 1 cpm for each detector. Alpha efficiency factors ranged from 0.16 to 0.18 for the ZnS i Otmeral Asornscs SVA Facilsty Ockdcr 21,1993 B-1

[ r scintillation detectors. The beta activity background count rates for the GM detectors averaged 46 cpm. Beta efficiency factors ranged from 0.29 to 0.32 for the GM detectors. The effective 2 2 window for the ZnS scintillation and GM detectors were 59 cm, and 15.5 cm, respectively. Removable Activity Measurements Removable activity levels were determined using numbered filter paper disks, 47 mm in 2 diameter. Moderate pressure was applied to the smear, and approximately 100 cm of the surface was wiped. Smears were placed in labeled envelopes with the location and other pertinent information recorded. ANALYTICAL PROCEDURES Removable Activity Smears were counted on a low background gas proportional system to determine gross alpha and gross beta activity. DETECTION LIMITS Detection limits, referred to as minimum detectable activity (MDA), were calculated using the following formula: MDA(dpm/100 cm ) = 2.71 + (4.66V'B ) 2 TxExG B = background (total counts) T = count time (min) to be used for field measurements E = operating efficiency [ counts i disinteptions i G = geometry,, detector area em i 100 i When the activity was determined to be less than the MDA of the measurement procedure, the result was reported as less than MDA. Because of variations in background levels, measurement efficiencies, and contributions from other radionuclides in samples, the detection limits differ from sample to sample and instrument to instrument. Gewal Ana SVA FaQW 71. wo B-2

+ I I i CALIBRATION AND QUALITY ASSURANCE l Analydcal and field survey activities were conducted in accordance with procedures from the following ESSAP documents: Survey Procedures Manual, Revision 7 (May 1992) Laboratory Procedures Manual, Revision 7 (April 1992) Quality Assurance Manual, Revision 5 (May 1992) 7 The procedures contained in these manuals were developed to meet the requirements of DOE Order 5700.6C and ASME NQA-1 for Quality Assurance and contain measures to assess processes during their performance. Calibration of all field and laboratory instrumentation was based on standards / sources, traceable to NIST, when such standards / sources were available. In cases where they were not available, standards of an industry-recognized organization were used. Quality control procedures include: Daily instrument background and check-source measurements to confirm that equipment operation is within acceptable statistical fluctuations, Participation in EPA and EML laboratory Quality Assurance Programs, Training and certification of all individuals performing procedures, Periodic internal and external audits. i b Gemmi Asarmos SVA Facinny CAkery 21,1993 8-3

5 1 APPENDIX C I GUIDELINES FOR DECONTAMINATION OF FACILITIES AhT EQUIPMENT PRIOR TO RELEASE FOR UNRESTRICTED USE OR TERMINATION OF LICENSES FOR BYPRODUCT, SOURCE OR SPECIAL NUCLEAR MATERIAL i ) h I l' l l I l i l i i General Akunsa SVA Faciley Oender 21,199)

i 4 GUIDELINES FOR DECONTAMINATION OF FACILITIES AND EQUIPMENT PRIOR TO RELEASE FOR UNRESTRICTED USE OR TERMINATION OF LICENSES FOR BYPRODUCT, SOURCE, i OR SPECIAL NUCLEAR MATERIAL r i 4 5 F i 9 U.S. Nuclear Regulatory Commission Division of Fuel Cycle & Material Safety Washington, D.C. 20555 I August 1987 l i I I l I l ? i L n f Ormern! Akunes SVA l'a:ilny OtwAwe 21,1993 C-] s

The instructions in this guide, in conjunction with Table 1, specify the radionuclides and t radiation exposure rate limits which should be used in decontamination and survey of surfaces or premises and equipment prior to abandonment or release for unrestricted use. The limits in Table 1 do not apply to premises, equipment, or scrap containing induced radioactivity for which the radiological considerations pertinent to their use may be different. The release of such facilities or items from regulatory control is considered on a case-by-case basis. 1. The licensee shall make a reasonable effort to eliminate residual contamination. t 2. Radioactivity on equipment or surfaces shall not be covered by paint, plating, or other covering meterial unless contamination levels, as determined by a survey and documented, are below the limits specified in Table I prior to the application of the covering. A reasonable effort must be made to minimize the contamination prior to use of any covering. 3. The radioactivity on the interior surfaces of pipes, drain lines, or ductwork shall be determined by msking measurements at all traps, and other appropriate access points, provided that cont.tmination at these locations is likely to be representative of contamination on the interior of tie pipes, drain lines, or ductwork. Surfaces or premises, equipment, or scrap which are likely to be contaminated, but are such size, construction, or location as to make the surface inaccessible for purposes of measurement, shall be presumed to be contaminated in excess of the limits. 4. Upon request, the Commission may authorize a licensee to relinquish possession or control of premises, equipment, or scrap having surfaces contaminated with materials in excess of the limits specified. This may include, but would not be limited to special circumstances such as razing of buildings, transfer from premises to another 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 safety analysis which reflects that the residual amounts of materials on surface areas, together with other considerations such as prospective use of the premises, equipment, or scrap, are unlikely to result in an unreasonable risk to the health and safety of the public. 5. Prior to relcase 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 the survey report shall be filed with the Division of Fuel Cycle, Medical, Academic, and Commercial Use Safety, U.S. Nuclear Regulatory Commission, 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: i wm

w. svuan am n. ms C-2

+ n w

a. Identify the premises. b. Show that reasonable effort has been made to eliminate residual contamination. c. Describe the scope of the survey and general procedures followed. 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. Dennat Aksnra SVA 1:acihty Octater 21,1993 C-3

TABLE 1 ACCEPTABLE SURFACE CONTAMINATION LEVELS f Nuclides' Average *^' Maximum *d# Removabic ^' 6 U-nat, U-235, U-238, and j associated decay products 5,000 dpm a/100 cm 15,000 dpm a/100 cm 1,000 dpm a/100 cm 2 2 2 I Transuranics, Ra-226, Ra-228, 9 Th-230, Th-228, Pa-231, f Ac-227, I-125,1-129 100 dpm/100 cm 300 dpm/100 cm 20 dpm/100 cm 2 2 2 j Th-nat, Th-232, Sr-90, Ra-223, Ra-224, U-232, I-126, I-131, I-133 1,000 dpm/100 cm 3,000 dpm/100 cm 200 dpm/100 cm 2 2 2 Beta-gamma emitters (nuclides with decay modes other than alpha emission or spontaneous fission) except Sr-90 and others noted above. 5,000 dpm #7/100 cm2 15,000 dpm Sy/100 cm2 1,000 dpm By/100 cm2 0 'Whem surface contamination by both alpha-and beta-gamma-emitting nuclides exists, the limits established for alpha-and beta-A gamma-emitting nuclides should apply independently.

  • 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.

' Measurements of average contaminant should not be averaged over more than i square meter. For objects ofless surface area, the average should be derived for each such object.

  • The maximum contamination level applies to an area of not more than 100 cm.

2 'The amount of removable radioactive material per 100 cm of surface area should be determined by wiping that area with dry filter 2 or soft absorbent paper, applying moderate pressure, and assessing the amount of radioactive material on the wipe with an appropriate instrument of known efficiency. When removable contamination on objects of less surface area is determined, the pertinent levels should be reduced proportionally and the entire surface should be wiped. The ave rage and maximum radiation levels associated with surface contamination resulting from beta-gamma emitters should not exceed 0.2 mrad /h at I cm and 1.0 mrad /h at I cm, mspectively, measured through not more than 7 milligrams per square centimeter of total absorber. .}}

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