ML20217P909

Amend 41 to SNM-0696 for General Atomics

ML20217P909
Person / Time
Site:	07000734
Issue date:	03/02/1998
From:	Weber M NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20217P908	List: ML20217P904 ML20217P909 ML20217P916
References
NUDOCS 9803110207
Download: ML20217P909 (7)

Text

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1 't i MATERIALS LICENSE lg l I

. J954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10, h  !

l l Pursuant to the Ato,mic Energy As  !

l 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 I made by the licensee, a license is hereby issued authorizing the licensee to receive, acquire, possess, and transfer byproduct. source, and specia! _

l nuclear material designated below; to use such material for the purpose (s) and at the place (s) designated below; to deliver or transfer such mater to persons authorized to receive it in accordance with the regulations of the applicable Pan (s). This license shall be deemed to contain the conditions i

specified in Section IFi of the Atomic Energy Act of 1954, as amended, and is subject to all applicable rules, reFulations and orders of t'Te Nuclear j l l Regulatory Commission now or hereafter in effect and to any conditions specified below, j I

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Ucensee l l E l

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General Atomics P.O. Box 85608

3. Ucense number SNM-696 Amendment 41 fT I  !!-

San Diego, Califomia 92186-9784  ; ~

l , I ' Expiration date '

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, 5. Docket or s70-734 g.

j l Reference No I.

I 6. Byproduct, source, and/or ' 7, Chemical and/or physical ' 8. Maximum amount that licensee F I special nuclear material form may possess at any one time I-I under this license k i Enriched up to 19.99% A. 200 kilograms U-235 g A. Uranium A. (I-l i U-235 I;I I I:

I B. Uranium B. Enriched 20 to 100% U-235 B. Less than 5000 gm* f l [

! C. U-233 C. Any C. Less than 2000 gm l . U-233*

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

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l f:T y E. Plutonium E. Bred but unseparated E. Less than 1000 gm h.:',

l total Pu* .t :

1 Il I F. Plutonium F. Plated calibration F. Less than 5 grams N I total Pu*

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I i G. Plutonium G. Solutions, precipitates G. Less than 5 grams tr I

I solids and total Pu* h d

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I L The sum total quantity of s'.rategic special nuclear material possessed at any one time must be less [

l i than 5,000 grams computed by the formula:

' I Grams = grams U-235 in uranium onriched to 20% or more plus 2.5 (grams U 233 + grams [

I plutonium) b I -j i J l -.

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1 l l 9. Authorized place of use: The licensee's San Diego, Califomia site as specified in the aforesaid g l l application and supplements. g i I N l 10. This license shall be deemed to contain two sections: S&fety Conditions and Safeguards Conditions. g l These sections are part of the license, and the licensee is subject to compliance with all listed g

! I conditions in each section. g I g i l l N I N l tg8 REG j l

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1 Date:

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\; e By ' Michael F. Wetie,. f'r. Chief * (9 l

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Division of Fuel Cycle Safety i/(I I

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and Safeguards, NMSS q j s Washington, DC,20555 g j

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Enclosures:

1. License Condition for Leak Testing g i j Sealed Plutonium Sources, did 4/93 g l 1 N I

y 2. License Condition for Plutonium Alpha g l

j Sources, dtd 4/93 g i i N i 3. Guidelines for Decontamination of g i Facilities..., did 4/93 g I N N N i N 4 W 4 8 4 8 4 4 4 N e a a n

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l SUPPLEMENTARY SHEET 70-734 g I -

r 1 SAFETY CONDITIONS g I r l E I E I

SAFETY CONDITIONS E I L I

S-1. Authorized use: For use in accordance with statements, representations, and conditions contained in E I

Part ll " License Specifications" dated July 24,1981, and supplements dated March 16 and E I

December 24,1982; February 4, November 14, and November 15,1963; April 10, April 12, June 28, I I

SepMmber 4, and September 7,1984; December 5,1985; May 23, September 25, and December 10, E I

1986; December 21,1987; March 4, March 9 (2), March 22, April 26, August 22, September 8, and E I

November 2,1988; May 25 and November 17,1989; June 27,1990; April 30 and September 27,1991; I I

March 5, March 18, June 24, and Saptember.10,,1992; January 20,1995; and in the "SVA I I

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I Decommissioning Plan" dated April 1,1990 (submitted by letter dated March 30,1990), August 22, I

1990 (submitted by letter dated August 24,1990); June 15,1992; July 12 and August 23,1994; E I

Group 6 Laboratories unrestricted use request dated August 12,1994; March 1,1995; Group 7 I

I Laboratories unrestricted use request dated December 5,1995; Group 88 Laboratories unrestricted I I

use request dated August 23,1996; October 15,1996, and April 30, and Group 9 Laboratories 1 I "

unrestricted use request dated July 17,1997. 1 I I I

S-2. Records of all safety-related reports and analyses shall be retained as follows! E l I I a. Copies of criticality and radiation safety analyses shall be retained for at least 2 years or for 6 I I months after a project is terminated, whichever is longer. E I E I b. Copies of all other safety-related records (e.g., plant alterations and additions, abnormal 5

! occurrences associated with radioactivity releases, audits and inspections, instrument calibrations, 5 I

ALARA findings, training and retraining, personnel exposures, routine rsdiation and environmental 5 I

surveys) shall be retained for at least 2 years or longer if required by regulations. E I 1.V 3

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t l 'S-3. Notwithstanding the statements in Section 5.4.2 in the Ucense Specification Volume (Part il), if double 1 I batching is not credible,' the maximum safe batch size shall be no more than 75 percent of the t I minimum critical mass independent of the degree of water moderation and reflection. However, when E I the Th/U atomic ratio is t 3.6 and the H/U $ 20, the maximum safe batch size may be increased to 790 t l g contained U-235 independent of whether double batching is credible. t l ,: - 1 I S-4. The Director QACD, upon recommendation of the appropnate mana9er within QACD, shall have I l authority to require immediate termination of activities and/or corrective action in any situation which, in I l their judgment, could lead to the unnecessary exposure of personnel to ionizing radiation, release of f I radioactive material, loss or damage of property, or non-compliance with the license or a regulation. I l I i S-5. The Criticality and Radiation Safety Committee (CRSC), functioning as an ALARA Committee, shall I l meet at least annually to review (1) reports of audits and inspections pefformed since the last ALARA k I review and (2) employee exposures and effluent release data to determine (a) if there are any upward r l trends developing in personnel exposures for identifiable categories of workers, types of operations, or L l effluent releases, (b) if exposures and releases might be lowered in accordance with the ALAR % I I ceiwi, and (c) if equipment for effluent and exposure control is being properiy used, maintained, and E I inspected. L 1 E I The CRSC evaluation, recommendations, and conective actions shall be documented and the report i I shall be sent to the appropnate operations managers and the Vice President, Finance and i I Administration. I I I 1 i M MMMMMMMMMMMMMMMMMMMMMMM . 1 . . . . . . . . 1 . . 1 . s 1 x Prmied on recycled pape.

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3 MATERIALS LICENSE thket or Reference Numter I 70-734 !g y ,

SUPPLEMENTARY SHEET g  !

N E y SAFETY CONDITIONS g W G N a N W 5 I li u I E S-6. Radiological Work Permits (RWPS) shall be issued for all unplanned or non-routine work with licensed U

material not covered by a WA. The RWP shall be signed by Health Physics management or a senior I

y staff member before related work can commence. A senior staff member shall be a Health Physics

, Technician having a minimum of 5 years' experience in radiation safety. An evaluation of the safety y

effectiveness of the permit shall be made upon completion of the work.

-S-7. Radiation safety training, appropnate to the employee's needs, shall be given to all new employees.

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S-8. Radiation safety training and indoctrination shall be conducted by the Health Phwsics Manager or by a l similatty qualified individual. The Health Physics Manager may delegate training in that portion of the y y

y course to an individual who is uniquely qualified to present it. g I I S-9. Continuous air sampling shall be conducted in any area where licensed material can become airbome.

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S-10. The location of air samplers shall be checked annually and whenever any process or equipment y

changes are made to verify the representativeness of work area air sampling. In addition, the location g I y

of air samplers shall be checked at the commencement of operations in any area that has been g y

shutdown for more than 6 months to verify the representativeness of air sampling. y S-11. The laboratories in which plutonium in a dispersible form may be used shall have exhaust ventilation l systems separate from other building exhausts and shall provide dual HEPA filtering of the effluent air.

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S-12. Sealed Plutonium sources shall be subject to the leak testing and achons specified in the attached y " License Condition for Leak Testing Sealed Pletonium Sources," dated April 1993. g Plutonium alpha sources shall be subject to the actions specified in the attached " License Condition for l Plutonium Alpha Sources," dated April 1992.

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S-13. The licensee shall prepare and submit to the Chief, Licensing Branch, Division of Fuel Cycle Safety anc y

Safeguards, NMSS, U.S. Nuclear Regulatory Commission, Washington, DC 20555, a report whenever g there is any new residential development within 1 mile around the site that constitutes a significant g y change in parameters that may be affected by the release of radioactive materials into the environmentg I

S-14 Deleted by Amendment 14 dated August 3,1990 (originally numbered S-23 in 1990 - 1992 and y renumbered to S-14 in Amendment 23 dated October 7,1993). The information in License Condition y y S-23 was incorporated into License Condition S-9 by adding the date of May 25,1989; License g

, Condition S-9 later became S-1. y B N y S-15. At the end of plant life, the licensee shall decontaminate the site and facilities, authorized as a place of g ,

y use for special nuclear material, in accordance with the general decommissioning plan submitted by g  !

y yourletter dated July 25,1986, and its supplement dated October 15,1986, so that these facilities and g  !

y grounds can be released for unrestricted use. The corporate commitment that funds will be mede g i y available for decommissioning the facility, provided by letter dated September 10,1986, is hereby g y irici,rps,id as a condition of the license. g 3 N s n a

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g License Numter I l g SNM-696 Amendment 41 l l

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g MATERIALS LICENSE lhket or Reference Number ~! l g ,

SUPPLEMENTARY SHEET 70-734 l l

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SAFETY CONDITIONS I

, l 8 I S-16. Release of equipment, facilities, or pacirages to the unrestricted area or to uncontrolled areas onsite l shall be in accordance with the attached " Guidelines for Decontamination of Facilities and Equipment gl g

Prior to Release for Unrestricted Use or Termination of Licenses for Byproduct, Source, or Snecial gl g

Nuclear Material," dated April 1993. g l

S-17. Deleted by Amendment 37, September 1996. The SVA facility has been decommissioned and l released for general use.

, g S-18. Notwithstanding the statement in Section 4.2.1.4, Part ll of the license, the trip levels will be readjusted l after each n;cnthly test of the criticality alarm system if the alarm point fails to activate within

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, approximately 5 seconds, more than once out of four trials g S-19. Notwithstanding the statements in Section 4.2.1.4, Part 11 of the license, no material handling shall be l allowed in any area in which the required criticality alarm system is inoperative,

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' S-20. Deleted by Amendment 37, September 1996. The SVA facility has been decommissioned and y

g released for general use. g ,

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

, on October 3,1988. g B 5" g

S-22. Deleted by Amendment 37, September 1996. The SVA facility has been decommissioned and g g

released for general use. g N El g S-23. The licensee shall maintain and execute the response measures described in the Emergency Plan g g dated August 1995 (letter dated August 30,1995), and as revised by letter dated June 6,1996, with g, g pages dated May 1996; or as further revised by the licensee consistent with the provisions of 10 CFR g g 70.32(i). g B E i, E

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SUPPLEMENTARY SHEET 70-734 !l s SAFEGUARDS CONDITIONS Ql g

s t SAFEGUARDS CONDITIONS j e

k b SECTION 1.0 - FACILITY ORGANIZATION Currently there are no license conditions in this section. The necessary information has been incorporated int q cn approved plan. y 4

d SECTION 2.0 - FACILITY OPERATION a l g

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4 SG-2.1 Deleted by Amendment 37, September 1996. Not applicable under a possession only license. g 9 - .

g cl SG-2.2 Deleted by Amendment 37, September 19%. Not applicable under a possession only license, g E

SG-2.3 Deleted by Amendment 37, September 1996. Not applicable under a possession only license. g E

SG-2.4 Deleted by Amendment 37, September 19%. Not applicable under a possession only license. g E

g SECTION 3.0 - MEASUREMENTS g j

- s b SG-3.1 Deleted by Amendment 37, September 1996. Not applicable under a possession only license, j E

? SG-3.2 Deleted by Amendment 37, September 1996. Not applicable under a possession only license. g P g i SG-3.3 Deleted by Amendment 37, September 1996. Not applicable under a possession only license. y E

y SECTION 4.0 - MEASUREMENT CONTROL g E

SG-4.1 Deleted by Amendment 37, September 1996. Not applicable under a possession only license. g A s c

SG-4.2 Deleted by Amendment 07, September 1996. Not applicable under a possession only license. j k y SG-4.3 Deleted by Amendment 37, September 1996. Not applicable under a possession only license. g E

t SG-4.4 Deleted by Amendment 37, September 1996. Not applicable under a possession only license, g E

c SG-4.5 Deleted by Amendment 37, September 1996. Not applicable under a possession only license. g C

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SG-4.6 Deleted by Amendment 37, September 1996. Not applicable under a possession only license. j E

t SG-4.7 Deleted by Amendment 37, Septen;ber 1996. Not applicable under a possession only license. g E

c GG-4.8 Deleted by Amendment 37, September 1996. Not applicsbie under a possession only license. g 1!

c SECTION 5.0 - INVENTORY g C '

lll 5 SG-5.1 Deleted by Amendment 37, September 1996. Not applicable under a possession only license. gl c gl C

SG-5.2 Deleted by Amendment 37, Septensber 1996. Not applicable under a possession only licose, gl SG-5.3 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

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SUPPLEMENTARY SHEET 70-734 Ig l SAFEGUARDS CONDITIONS W E SECTION 6.0 - RECORDS AND REPORTS SG-6.1 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

SECTION 7.0 - INTERNAL CONTROL Delsted by Amendment 37, September 1996. Not applicable under a possession only licer:se.

SG-7.1 l

SECTION 8.0 - MANAGEMENT SG-8.1 Deleted by Amendment 37, September 1996.; Not applicable under a possession only license.

SECTION 9.0 - PHYSICAL PROTECTION REQUIREMENTS FOR FORMULA QUANTITIES OF STRATEGIC j y SPECIAL NUCLEAR MATERIAL g SG-9.1 The licensee shall follow the measures described in the physical protection plan entitled, " Fixed y Site and Transportation Plan for the Protection of Special Nuclear Material of Moderate and Low g y Strategic Significance," dated May 1989, submitted by letter dated May 8,1989; and as it may be y y further revised in accordance with the provisions of 10 CFR 70.32(e). g SECTION -10.0 - TEMPORARY OR ONE TIME CONDITIONS SG-10.1 Deleted by Amendment 31, dated July 1995. g SG-10.2 Deleted by Amendment 31, dated July 1995.

W E g SG-10.3 Deleted by Amendment 31, dated July 1995. g N N N E n E 1 ln E e E g E N E R E N E N E R E N E N E N E

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