ML20036A242

Forwards Radiological Survey Plan for General Atomics Sva Facility in San Diego,Ca

ML20036A242
Person / Time
Site:	07000734
Issue date:	04/22/1993
From:	Landis M OAK RIDGE ASSOCIATED UNIVERSITIES
To:	Cillis M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
NUDOCS 9305100320
Download: ML20036A242 (16)

Text

.

n nn 1

ORISE I

Oc;i ou mna.o ~smint,cm sew ~co mo. ooc nc,~

.yy D F,' -

. m~~3 eu Q: y so n es n.,~

/

M4. A f~m.

^

April 22,1993 -

Mr. Mike Cillis

[

I

~

U.S. Nuclear Regulatory Commission 1

Region V -

Nuclear Materials and Fuel Fabrication Branch 1450 Maria Lane Suite 210 Walnut Creek, CA 94596-5368 3

SUBJECT:

RADIOIDGICAL SURVEY PLAN FOR THE GENERAL ATOMICS SVA FACILITY, SAN DIEGO, CALIFORNIA t

Dear Mr. Cillis:

Enclosed is a copy of the survey plan for the radiological survey of the General Atomics SVA Facility in San Diego, California.

This survey plan was developed based on the information provided in-the SVA":

Decommissioning Project, Phase I (Pre-Dismantlement) Survey Report February 1993. ESSAP provided comments on the GA Survey Report; a response to these comments would have facilitated development of a more '

site-specific survey plan. A more general approach was used to' develop the enclosed survey plan.

r If you have any questions or comments regarding this information, please contact me at (615) 576-2908.

Sincerely, -

{Y Michele R. Landis i

Project Manager Environmental Survey and l

Site Assessment Program

.I MRL:tte -

-[

Enclosure cc:

T. Mo, NRC/NMSS, 6H3

- R. Wilson, NRC/NMSS,6H3 D. Tiktinsky, NRC/NMSS, 6E6 C. Emeigh, NRC/NMSS, 4E4

. J. Reese, NRC/ Region V J. Berger, ORISE PMDA, 6E6 :

' File /213 f

l

'9305100320':930422

~

f-.. \\

'PDR ADOCK 07000734 '

-C, PDR P. O. BOX 117, OAK RIDGE, TENNES$f E 37831-0117 0t.

l Managed and opetoted QOok Ridge Associated Universities for the U.S Department of Energy..

4 4

RADIOLOGICAL SURVEY PLAN DRAFT FOR TIIE GENERAL ATOMICS SVA FACILITY SAN DIEGO, CALIFORNIA INTRODUCTION AND SITE HISTORY 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 conducted included:

Development of fuel fabrication processes, 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 surfaces of the facility.

Large production processes were shutdown in April of 1985; small fuel fabrication operations and demonstrations continued until 1990. The SVA Decommissioning Plan was submitted to i

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.

Decommissioning activities are being conducted in two phases. Phase I was the decontamination -

and radiological survey of '.he facility. Phase II is facility dismantlement with ' areas _ not decontaminated to be disposed of as low-level radioactive waste.

Prepared by the Environmental Survey and Site Assessment Program of Oak Ridge Institute for Science and Education, Oak Ridge, TN, under interagency agreement (NRC Fin. No. A-9076) between the U.S. Nuclear Regulatory Commission and the U.S. Department of Energy.

SVA FacDity - AprU 15,1993 HAPSSAN'IANS\\SVA\\SVA.001

Phase I activities began around October 1990 and continued to February 1993 and included the following activities:

Approval of the Plan by the NRC.

Removal of all equipment and internal structures.

Packaging of radioactive waste.

Pre-survey of the facility after removal of flooring, equipment and internal structures (i.e., mezzanines, wallboard, tile).

Decontamination of accessible surfaces.

Conducting detailed surveys of the facility surfaces.

t 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.2 Phase II activities, to be completed upon authorization from the NRC and State of California allowing GA to commence controlled dismantlement of the north end of the building, will include the following activities:

Dismantlement of the building; " exceptions" will be disposed of in a controlled manner as contaminated low-level radioactive waste or decontaminated to meet release criteria, P

clean portions of the building will be disposed of at a nearby landfill.

Removal of all underground drain lines.

Soil remediation (as needed).

Soil sampling, analysis and documentation.

Submittal of a Phase II (post-dismantlement) report to the NRC summarizing the activities completed in Phase II.

SVA Facilay - April 15, 1993 2,

H:\\ESSAl'. PLANS \\SVA\\SVA.001

NRC concurrence that the open land site meets the criteria.

Removal of the site from GA's NRC and State licenses.

GA has completed the Phase I activities. The U.S. Nuclear Regulatory Commission, Region V Office, has requested that the Environmental Survey and Site Assessment Program (ESSAP) of Oak Ridge Institute for Science and Education (ORISE) perform a radiological survey of portions of this facility.

SITE AND FACILITY DESCRIPTIONS The SVA facility is located in the north half of Building 37 (SVA facility) located in Sorrento Valley at 11222 Flintkote Avenue, San Diego, California.

Approximately 41,000 square feet housed fuel fabrication processing equipment, offices, change rooms, laboratories, storerooms, a machine shop and stockroom.

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 Building 37) in relation to other structures at the GA Sorrento Valley complex.

i 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 r

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

$VA Facility - April 13,1993 3

nussanrwswvAwvAun

~

1 Zone 9 North and South Ends of the North Tunnel 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 i

2 2

The 3700 m (41,000 ft ) facility being decommissioned consist 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 with 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 shield walls forming storage aisles.

t 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.

CAS (icae 3) - A concrete block structure with a cast-in-place roof located within the west HEPA room building (Zone 12).

North Annex (Zone 11)- A metal structure similar to those previously described, south wall of which is the north wall of the main building.

Security Annex (SAS) (Zone 13) - A reinforced concrete structure consisting of four rooms and two hallways. One of the hallways extends south along side the north annex.

svA raciay. Apra 15.1993 4

n uSSAPJuNSUVAUVA.001

I The floors consist of about eight (8) inches of reinforced concrete. Concrete walls are about 7-12 inches thick. Metal walls and roofing are of standard corrugated metal stock.

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 considered to be contaminated. Fixative has been applied to the inside ceiling and trusses to fix 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.

OBJECTIVE The objectives of the confirmatory process are to provide independent document reviews and radiological data, for use by the NRC in evaluating the adequacy of the licensee's radiological status report, relative to established guidelines.

In addition, ESSAP will perform measurements for total alpha and beta surface activity. This data will not be sufficient to meet the recommendations of NUREG/CR-5849 for final-status i

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.

RESPONSIBILITY r

Work described in this survey plan will be performed under the direction of Michele l2ndis Project Manager with ESSAP. The cognizant site supervisor has the authority to make appropriate changes to the survey procedures as deemed necessary. After consultation with the NRC site representative, the scope of the survey may be altered as the survey progresses.

Deviations to the survey plan or procedures will be documented in the site log book.

Y I

SVA Faciliy - Apru 15,1993 5

nxssAr ru.nswvawv4.un

4 PROCEDURES Survey activities will be conducted in accordance with the ORISE ESSAP Survey Procedures 4

and Quality Assurance Manuals. Specific procedures applicable to this survey are listed on Page 9 of this survey plan. Identification oflow and high potential areas, used in this survey plan, is the same as that designated by GA.

DOCUMENT REVIEW ESSAP has reviewed the licensee's radiological survey data. Procedures and methods utilized by the licensee were reviewed for adequacy and appropriateness. The data were reviewed for.

accuracy, completeness, and compliance with guidelines.

CONFIRMATORY SURVEY

^

Reference Grid The reference grid systems established by the licensee will be utilized where possible.

Measurement locations on ungridded surfaces will be referenced to prominent building features or the existing grid, t

Surface Scans Surface scans for alpha, beta, and gamma activity will be performed using large-area gas proportional and NaI scintillation detectors, coupled to countrate meters with audible indicators.

Locations of elevated direct radiation detected by scans will be marked for further investigation.

In low potential areas,100% of the floor surfaces will be scanned for alpha, beta, and ' gamma activity. In high potential areas, 50 to 100% of the floor surfaces will be scanned for alpha, beta and gamma activity and 25% of the wall and ceiling surfaces will be scanned for alpha and beta activity.

SVA Facility, April 15.19M h

HMSSAPRANSWMSVA.WI

RADIOLOGICAL SURVEY Surface Activity Measurements Measurements of total and removable alpha and beta activity will be performed at randomly selected locations. These measurements will be performed using thin-window GM and ZnS scintillation detectors, coupled to countrate meters.

In low potential areas, approximately 30 measurements will be performed. In high potential areas approximately 200 measurements will be performed on floor surfaces and 30 on wall and ceiling surfaces.

Direct measurements and smears will also be obtained from locations of elevated activity identified by surface scans. Areas of residual activity, in excess of the guidelines, will be brought to the immediate attention of the licensee and the NRC. If additional remediation is performed during the ESSAP survey, follow-up measurements will be performed.

SAMPLE ANALYSIS AND DATA INTERPRETATION Samples and data will be returned to ORISE's ESSAP laboratory in Oak Ridge, TN for analysis and interpretation. Smears will be analyzed for gross alpha and gross beta activity using a low -

background gas proportional counter, and the results will be converted to units of disintegrations 2

2 per minute per 100 cm (dpm/100 cm). Direct measurements for surface activity will be 2

converted to units of dpm/100 cm. The data generated will be compared with the licensee's documentation and NRC guidelines established for release to unrestricted use..2 Results will be presented in a report and provided to the NRC for review and comment.

I l

SVA Facility. April 15.1993 7

H2SS@MS4VAWVA.W1 J

GUIDELINES S

The surface contamination guidelines for beta-gamma emitters are:

Total Activity 2

2 5,000 dpm #-7/100 cm, averaged over a 1 m area 2

2 15,000 dpm S-7/100 cm, maximum in a 100 cm area Removable Activity 2

1000 dpm S-y/100 cm The surface contamination guidelines for uranium are:

Total Activity 2

2 5,000 dpm a/100 cm, total, averaged over a 1 m area 2

2 15,000 dpm a/100 cm, total, maximum in a 100 cm area Removable Activity 2

1000 dpm a/100 cm TENTATIVE SCHEDULE Measurement and Sampling April 26-30,1993 Sample Analysis May 3-14,1993 Draft Report June 1993 i

j SVA Facility Apra 15,1993 8

H:\\ESSAPPLANS\\SVA\\SVA.001 I

9 4

LIST OF CURRENT PROCEDURES Applicable procedures from ORISE ESSAP Smvey Procedures Manual (Revision 7; May 31, 1992) include:

Section 5.0 Instrument Calibration and Operational Check-Out 5.1 General Information 5.2 Electronic Calibration of Ratemeters 5.3 Gamma Scintillation Detector Check-Out and Cross Calibration 5.4 Alpha Scintillation Detector Calibration and Check-Out 5.5 GM Detector Calibration and Check-Out 5.6 Proportional Detector Calibration and Check-Out 5.9 Floor Monitor Check-Out 5.13 Field Measuring Tape Calibration Section 7.0 Scanning and Measurement Techniques 7.1 Surface Scanning 7.3 Alpha Radiation Measurement 7.4 Beta Radiation Measurement Section 8.0 Sampling Procedure 8.8 Miscellaneous Sampling 8.9 Sample Identification and Labeling Section 9.0 Integrated Survey Procedures 9.2 General Survey Approaches and Strategies Section 10.0 Health and Safety Control of Cross Contamination 7

Section 11.0 Quality Assurance and Quality Control k

SVA Facility. Apra 15. 1993 9

n:u:SSAriPIANSWVA4VA.001

REFERENCES 1.

"SVA Decommissioning Plan," General Atomics, April 1990, revised August 1990.

2.

"SVA Decommissioning Project Phase I (Pre-Dismantlement) Survey Report," General Atomics, February 1993.

3.

" 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 l

i l

$VA Facilny.' AprH 15. 1993 10 MESSAhMMSWVAUVA.W1

]

. +

4 t<

i APPENDIX A GENERAL ATOMICS SVA FACILITY l

COST ESTIMATE

• SAN DIEGO, CALIFORNIA l

1 Survey Preparation - $14K Survey preparation includes the following activities: - Document reviews, survey plans, j

the cost and time estimates, and trip planning and preparation (equipment calibration and -

packing).

j i

On-Site Activities and Travel - $84K i

On-site activities will include 30 man-days at the site performing the following: surface scans, surface activity measurements, sampling of soil and concrete, and exposure rate 3

measurements. The on-site expenses also include travel to and from the site (airlines, i

government and rental vehicles), hotel expenses, per diem, unpacking equipment, and logging in samples.

t f

1 1

Samole Analysis - $2K l

Includes analyses 'of smears for gross alpha and beta activity.

Reoort Preparation - $22K -

1 The report preparation will include. the 'following ' activities: : tabulation of data, j

illustration, writing the draft and final reports, word processing and reproduction.

[

i i

l

)

SVA FaciWy - Apn115,1993-A-1 H:UESAMPWS4VA4VAM1 A

--1--

i l

Total Cost Estimate - $122K t

• Estimates is best guess, based on information obtainedfrom licensee documents and prior site experience. Reduction or increase in the areas to be sunYyed andfrequency ofsampling/measurementfor any reason may change the scope ofthe sung and increase or decrease the cost estimate. The NRC site representative will be non)ed if major changes to the scope of the sun'ey need to be made.

l

[

i I

I I

a SVA Facilny Aprilif,1993 A-2 n:stssArel.ANSiSVA\\5VA,001'

.5VA1 sy-A i

(rUEL MANUFACTURIN N

i 1

9 r:

n SORRENTO 11 VALLEY SRE

>I g

~.

{

101 i

MAIN SITE 5

b f

.1 f 'kg 4

i N

.h.

+

x x

X FENCE h

NOT TO SCALE -

^

FIGURE 1: Plot' Plan of General Atomics Facilities,. San Diego, Californiai

~

s' 4

e N

Y a PARKNG STORa0E SED N ~ LN 4.y liL

$f_".'

s.v. r I

BU)G. 19 CUARD STADON Y.

D f":

I GAS lA, 5

i'.

(

umuru: Tug

>r"'

O k

k g g

-r B-s t._

Y k

k i'

HW I

g 2

2 N>

I B

B noaa E3 >

l 42

_ !q l

BLDG, N

L BLDG. 37 gm a

UPPER FLOOR STORADE AREA N

l l

~

X X

X FENCE N

0' 100 0

0 METERS L

FIGURE 2: Plot Plan of Sorrento. Volley Facility, Son Diego, California i

w e

SVA3 4

EDC8 l

SAS ZONE 13 WV UT 49 ZONE 7 48 47 5ROPNM LK J HGF l

l HOT MACHNE 46 SHOP STOCKROOW NORTH ANNEX 45 ZONE 5 ZONE 11 TUNtEl.S ARE 44 LOCATED ON 43 NR }M 42 E --

b 41 i E

40 WEST 3

VAULT OFDCE w

39

, VAULT ASSAY RW.

PRODUCTON FLOOR g

i

'ONE 4 ZONE 6 ZONE 8 N

38 I

SECTON 4 37 dg g

=

36 west 35 MA PRCOUCTON N EAST ROOM ZONE 8 MEZZANINE 34 ZONE 12 SECTON 3 ZONE to 33 2ND LEVE.L Wg 32 31 PRODUCTON FLOOR j

a l

ZONE 8 g $

SECTON 2 W

29 d q 28 PRODUCTON FLOOR b d 27

_ ZONE 8 0 g 26 ZONE

^

I h s

25 cw watt foNE 2

__. I N

h h

h NOT TO SCALE-FIGURE 3: Facility Zone Designations