ML20137F419

Amend 39 to License SNM-0696 for General Atomics,Revising Safety License Condition S-1 as Listed

ML20137F419
Person / Time
Site:	07000734
Issue date:	03/27/1997
From:	Weber M NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20137F413	List: ML20137F407 ML20137F419 ML20137F426
References
NUDOCS 9704010099
Download: ML20137F419 (9)

Text

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l NRC YORM 374 PACE 1 OF 9 PAGES I I

g po.eg) U.S. NUCLE AR REGULATORY COMMISSION

! MATERIALS LICENSE -

i g Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10, j 3 l Code of Federal Regulations Chapter 1, Parts 30,31,32,33,34,35,39,40 and 70, and in reliance on statements and representations heretofore p!

l made by the licensee, a license is hereby issued author. zing the licensee to receive, acquire, possess, and transfer byproduct, source, and special 5!

I nuclear material designated below; to use such rnaterial for the purpose (s) and at the place (s) designated below; to de!lver or transfer such material i to persons authorized to receive it in accordance with the regulations of the applicable Part(s). This license shall be deemed to contain the conditions

specified m Section 183 of the Atomic Energy Act of 1954, as amended, and is subject to all applicable rules, regulations and orders of the Nuclear i Regulatory Commission now or hereafter in effect and to any conditions speciGed below.

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, Licensee l l l

I 1. 3. Ucense number l General Atomics SNM-696, .

i Amendment 39 l 2. p 1 P.O. Box 85608 4. Expiration date December 31, 1989 :E i San Diego, California 92186-9784' lE i 5. Docket or Reference No 70-734 iE i jp I, 6. Byproduct, source, and/or 7. Chemical and/or physical 8. Maximum amount that licensee jE I special nuclear material form may possess at any one time jf under this license I ;E I A. Uranium A. Enriched up to 19.99% A. 200 kilograms U-235 E

,1 U-235 lj i 't i B. Uranium B. Enriched 20 to 100% U-235 B. Less than 5000 gm*  !, l I 'E I

i C. U-233 C. Any C. Less than 2000 gm U-233*

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i D. Plutonium D. Encapsulated and/or sealed sources D. Less than 2000 gm total Pu*

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i E. Plutonium E. Bred but unseparated E. Less than 1000 gm ,1 l total ?u* i l

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( F. Plutonium F. Plated calibration F. Less than 5 grams g

1 source total Pu* )l lI ,

i G. Plutonium G. Solutions, precipitates G. Less than 5 grams ,1 l i solids and total Pu* ;I l l lI l 1 1 l

• The sum total quantity of strategic special nuclear material possessed at any one g time must be less than 5,000 grams computed by the formula: )

i Grass = grams U-235 in uranium enriched to 20% or more plus 2.5 (grams U-233 + lI ,

i grams plutonium) i ll l I l 9. Authorized place of use: The licensee's San Diego, California site as specified in ll l

the aforesaid application and supplements. p l lI i il I  !!

i 9704010099 970327 i i PDR ADOCK 07000734 l l C PDR l l

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p 10. This license shall be deemed to contain two sections: Safety Conditions and '

' I Safeguards Conditions. These sections are part of the license, and the licensee I

$ is subject to compliance with all listed conditions in each section. I, I I 4 i I I I I J

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Date: By: . M . O g 5

N Division of Fuel Cycle Safety i

and Safeguards, NMSS Washington, DC 10555 i g

N (Provided w/ Amendment 31)

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Enclosures:

1. License Condition for Leak Testing i N

Sealed Plutonium Sources, dtd 4/93 i N g N 2. License Condition for Plutonium Alpha ii N Sources, dtd 4/93 N y N 3. Guidelines for Decontamination of I N Facilities..., dtd 4/93 i N i N I N '

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. MATERIALS LICENSE Docket or Reference Number g SUPPLEMENTARY SHEET 7:;-734 ll SAFETY CONDITIONS 3

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SAFETY CONDITIONS E Ei i S-1. Authorized use: For use in accordance with statements, representations, and i'

} conditions contained in Part II " License Specifications" dated July 24, 1981, and i 1 g supplenants dated March 16 and December 24, 1982; February 4, November 14, and November 15, 1983; April 10, April 12, June 28, September 4, and September 7, 1984; Il i'

i l December 5, 1985; May 23, September 25, and December 10, 1986; December 21, 1987; i l  ; March 4, March 9 (2), March 22, Aprji 267: August 22, September 8, and November 2, i

, g 1988; May 25 and November 17,g1989; Dune 27,7 1990;jApril 30 and September 27, 1991; i

, p March 5, March 18, June 24, land September 10,1992';/ January 20, 1995; and in the i ',

"SVA Decommissioning Plan" dated April 1, 1990 (submitted by letter dated March 30, Ei

1990); August 22, 1990 / submitted by letter dated August 23 1990); June 15, 1992; Il

July 12andAugust23M994; Group 6Laboratoriesunrestrfckeduserequestdated ii y August 12, 1994; March 1, 1995; Group 7 Laboratories unrestricted use request dated iE'i i g. December 5, 1995; Group 88 Laboratories unrestricted use request dated August 23, i 1996; and October 15, 1996. *

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, S-2. Records of all safety-related reports and~analys.es'shall be rita.'ined as follows: I1 c ,

a. Copies of criticality and-radiation-safety analyses shall be' retained for at l i

, least 2 ye.wf or for 6 months af ter a project (is t.erminated7whichever is y

longer. ,) 7m p{ f ge-  ?

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! b. Copiesofall(othersafety-relatedrecords_(e.g.,' planta]terationsand '

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additions, abnormal occurrences associated with radioactivity releases, audits i

and inspections Linstrument. calibrations, ALARA findings;-training and 1 l l retraining, personnel exposures, routine rtdiation and environmental surveys) i

shall be retained.for at least 2! years or longer if; required by regulations. g

. E S-3. Notwithstanding the statements in Section 5.4.2 in ths License Specification Volume j N (Part II), if double batching,is not credible, the maximum safe batch size shall be !_

g 5 no more than 75 percent of the minimum critical mass independent of the degree of N gi water moderation and reflection. However, when the Th/U atomic ratio is 1 3.6 and I the H/U s 20, the maximum safe batch size may be increased to 790 g contained U-235 g

I independent of whether double batching is credible.

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N N S-4. The Director QACD, upon recommendation of the appropriate manager within QACD, i g

N shall have authority to require immediate termination of activities and/or g N corrective action in any situation which, in their judgment, could lead to the ,

5 unnecessary exposure of personnel to ionizing radiation, release of radioactivs ,

I. material, loss or damage of property, or non-compliance with the license or a ,

N regulation.

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l Licent.e Number g'

,p SNM-696 Amendment 39 g l .

, MATERIALS LICENSE Docket or Reference Number l l SUPPLEMENTARY SHEET 70-734 ,

I i y SAFETY CONDITIONS E S-5. The Criticality and Radiation Safety Committee (CRSC), functioning as an ALARA  !

I Committee, shall meet at least annually to review (1) reports of audits and i I inspections performed since the last ALARA review and (2) employee exposures and i I effluent release data to determine (a) if there are any upward trends developing in i I personnel exposures for identifiable categories of workers, types of operations, or i I effluent releases, (b) if expot.ures and releases might be lowered in accordance tl 1 with the ALARA concept, and (c) if equipment for effluent and exposure control is Il I being properly used, maintained, and inspected. I 3

i i The CRSC evaluation, recommendations, and corrective actions shall be documented i

~1 and the report shall be sent to the appropriate operations managers and the Vice i

.I i 1 President, Finance and .Administ G d ion" RF 0/ i1 1 S-6. Radiological Work Permitsr(RWP$) Yshall be ra issued fo/', ll unplanned or non-ro ll l work with licensed materfal' not covered by a WA. Th~e-RWPs s hall be signed by Health g' q Physics management oria senior staff member before relateihvork can commence. A p l senior staff member shall be a Health Physics Technician hiying a minimum of 5 g

( years' experience in radiation safety. An evaluation of the safety effectiveness g g of the permit shall'he made~upon completion of the work. (, p 4 J . .; g 1 S-7. Radiation safety training, appropriate to the employee.'s needs,sshall be given to l 1 all new employees. ,

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q S-8. Radiation safety training and indoctrination shall be conducted:by the Health ;l y Physics Manager;or by a similarly, qualified individual. The Health Physics Manager ,

v y maydelegatetraininginjthatportionlofjthecoursetoanindiyidualwhois ,

y uniquely og4H fied to present it. 'it )!

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y S-9. Continuous air sampling shall be' conducted in:any area where licensed material can , ;

g become airborne. s.

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l S-10. The location of air samplers shall be checked annually and whenever any process or i I

y equipment changes are made to verify the representativeness of work area air l sampling. In addition, the location of air samplers shall be checked at the I y I; j commencement of operations in any area that has been shutdown for more than 6  !

months to verify the representativeness of air sampling.

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y l l S-11. The laboratories in which plutonium in a dispersible form may be used shall have exhaust ventilation systems separate from other building exhausts and shall provide Il I;

dual HEPA filtering of the effluent air.

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3 S-12. Sealed Plutonium sources shall be subject to the leak testing and actions specified I in the attached " License Condition for Leak Testing Scaled Plutonium Sources," I N dated April 1993. I 1 W il

$ Plutonium alpha sources shall be subject to the actions specified in the attached Il El " License Condition for Plutonium Alpha Sources," dated April 1993. I Il i II i

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SNM-696 Amendment 39 , ,

f , MATERIALS LICENSE Docgegorgference 4 Number l l SUPPLEMENTARY SHEET l SAFETY CONDITIONS lj N  !'

N i 4 S-13. The licensee shall prepare and submit to the Chief, Licensing Branch, Division of Ii I Fuel Cycle Safety and Safeguards, leiSS, U.S. Nuclear Regulatory Commission, il N Washington, DC 20555, a report whenever there is any new residential development ii I within 1 mile around the site that constitutes a significant change in parameters i I that may be affected by the release of radioactive materials into the environment. I I I I S-14 Deleted by Amendment 14 dated August 3, 1990 (originally numbered S-23 in 1990 - i I 1992 and renumbered to S-14 in Amendment 23 dated October 7, 1993). The information i I in License Condition S-23 was incorporated into License Condition S-9 by adding the i i date of May 25, 1989* License o tgn g9[ r became S-1.

S-15. At the end of plant .ife,-tbe licensee shall decontaIninate the site and facilities, g y authorized as a place of t in accordance with the i q generaldecommissionin~gfus'eforspecialnuclearmater}al plan submitted by your letter date July 25, 1986, and its l l supplement dated October 15, 1986, sothatthesefacilitici(s,andgroundscanbe g

( released for unrestr,1cted use. The corporate commitment thatTfunds will be made p ,

i availablefordecoimeissioningthefacility,providedbylette}redatedSeptember10, yl

( 1985, is hereby incorporated as a condition of theilicense. Ei Q M i ,'s s

l e p l q S-16. Release of equipment, facilities, or packagess to!the unrestricted area or to i1 l uncontrolled area's onsite shall be in accordance;with the attach ~ed " Guidelines for g <

1 Decontamination;of Facilities and Equipment Prio'rlto' Release foe Unrestricted Use g.

j or Termination of Licenses for Byproduct, Source, or Special Nuclear Material," iI dated April 1993P J

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y S-17. Deleted by Amenda'lt 37,~ September 1996'.! (ThetSVA facility has'been decommissioned e g q and released for general use. ,

f g g l S-18. levels Notwithstanding the# statement in'Section 4.2.1.4,lPart II$f the license, the trip will be readjustcd after each monthly test'of the' criticality alarm system l y ,

3 if the alarm point fails to activate within approximately 5 seconds, more than once ,

y out of four trials. '

l S-19. material 4

Notwithstanding the statements in Section 4.2.1.4, Part II of the license, no handling shall be allowed in any area in which the required criticality l',;

y alarm system is inoperative. ,

3 I S-20. Deleted by Amendment 37, September 1996. The SVA facility has been decommissioned ,I and released for general use. ,

! S-21. Deleted by Amendment 31 dated September 1995. Fuel elements were shipped back to II l

I the licensee on October 3, 1988.

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The SVA facility has been decommissioned 8}lS-22.DeletedbyAmendment37, and released for general use. September 1996. l i

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g PAGES l g LKense Number g

. p SNM-696 Amendment 39 i g MATERIALS LICENSE r.xwici or nefecce Number g g SUPPLEMENTARY SHEET 70-734 g

' I i y SAFETY CONDITIONS ,

! N  !

N , I I S-23. The licensee shall maintain and execute the response measures described in the i i I Emergency Plan dated August 1995 (letter dated August 30,1995), and as revised by E i i letter dated June 6,1996, with pages dated May 19%; or as further revised by the E

1- licensee consistent with the provisions of 10 CFR 70.32(i). i

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l. i I SAFEGUARDS CONDITIONS i

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! I i l l SECTION I.0 -- FACILITY ORGANIZATION l

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I Currently there are no license conditions in this section. The necessary information has i I been incorporated into an approved plan. I c I . g

. I SECTION 2.0 -- FACILITY OPERATION g SG-2.1 DeletedbyAmendment37,g[emb%e 19b applicable under a possession l only license. &

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l SG-2.2 DeletedbyAmendmenDvt 37, September 19%. Not applicable under a possession (4s g E

p only license. gh Q E

) SG-2.3 DeletedbyAnddment37,; September 1996. Not applicabl under a possession  !

only license.y ,

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! SG-2.4 Deleted by Amendment 37, September 1996. Not a g i only license?, ,

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- n a possession g, i SECTION 3.0 -- MEASUREMENTS t_ 4 ,t' t ., -

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SG-3.1 Deleted by Amendment 37,'Septembe 1996.Not a pplicable under a possession ,

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4 j only license: "

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! SG-3.2 DeletedbyAmeMment37,Septembe'Y996. r NotApplicab1MSnderapossession l

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SG-3.3 Deleted by Amendment ~37, September 1996. Not applicable under a possession I 4

only license. I

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l SECTION 4.0 -- MEASUREMENT CONTROL ,

I i 1 E I SG-4.1 Deleted by Amendment 37, September 1996. Not applicable under a possession E l

I only license. E E

i SS-4.2 Deleted by Amendment 37, September 1996. Not applicable under a possession I 4

1 only license. E a R E 3 Deleted by Amendment 37, September 1996. Not applicable under a possession #

SG-4.3

', only license. E j l i 3 SG-4.4 Deleted by Amendment 37, September 1996. Not applicable under a possession E

_3 only license. E E

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, g License Number g; l l SNM-696 Amendment 39 g i

1 MATERIALS LICENSE Docket or Reference Number l '

J B SUPPLEMENTARY SHEET 70-734 i I i 1 1 SAFEGUARDS CONDITIONS i I '

4 I, s' l 1 l!

I I SG-4.5 Deleted by Amendment 37, September 1996. Not applicable under a possession i:

i I orly license. I '

! I i l I SG-4.6 Deleted by Amendment 37, September 19%. Not applicable under a possession i I only license. I

!' I i I SG-4.7 Deleted by Amendment 37, September 1996. Not applicable under a possession ii

I only license. I 3 I i

+ 1 SG-4.8 t applicable under a possession i I Deleted by Amendment 37, SeplA y Ig6 only license. g SECTION 5.0 -- INVENTORY V i g

I SG-5.1 Deleted by Amendment 37, September 1996. Notapplicalf[Eunderapossession s

! I only license. , '; pj g

I ,9 . v j ' / g 4 l SG-5.2 Deleted by Amendment 37,$ September 1996. Not applicable ^under a possession g j l only license. , 4Oi .

f g g i I a < i fa(;j .. g i l' SG-5.3 Deleted by Amendment 37, September 1996. Not: applicable un., der a possession g i

only license.-

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] p SECTION 6.0 -- RECORDS'AND REPORTS

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p' SG-6.1 Deleted by Amendment 37P' September ;1996.MNot applicable.linder a possession ,

g only license. O "^ WQf g 4

y SECTION 7.0 -- INTERNAL CONTROL

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g SG-7.1 Deleted by Amendment 37, September 1996. Not applicable under a possession ,

y only license. ,

' I SECTION 8.0 -- MANAGEMENT s I

SG-8.1 Deleted by Amendment 37, September 1996. Not applicable under a possession ,

g only license. ,

I I SECTION 9.0 -- PHYSICAL PROTECTION REQUIREMENTS FOR FORMULA 00ANTITIES OF STRATEGIC k SPECIAL NUCLEAR MATERIAL EI M i I

SG-9.1 The licensee shall follow the measures described in the physical protection E plan entitled, " Fixed Site and Transportation Plan for the Protection of I E,

Spect-1 Nuclear Material of Moderate and Low Strategic Significance," dated May

! 198'), submitted by letter dated May 8, 1989; and as it may be further revised E in accordance with the provisions of 10 CFR 70.32(e). E. '

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l SUPPLEMENTARY SHEET 70-734 ,

M i 1

y SAFEGUARDS CONDITIONS l I 4 6

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I 1 Il SECTION -10.0 -- TEMPORARY OR ONE TIME CONDITIONS (

I i i 3 1 SG-10.1 Deleted by Amendment 31, dated July 1995. i' i I I l-k SG-10.2 Deleted by Amendment 31, dated July 1995. I; W I i ,. SG-10.3 Deleted by Amendment 31, dated July 1995. t l' l l l l

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