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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Pursuant to the Ato,mic Energy As

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

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Regulatory Commission now or hereafter in effect and to any conditions specified below, j

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Ucensee l

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3. Ucense number General Atomics SNM-696 I

P.O. Box 85608 Amendment 41 T

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San Diego, Califomia 92186-9784 I ' Expiration date

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5. Docket or 70-734 g.

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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

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Uranium A.

Enriched up to 19.99%

A.

200 kilograms U-235 (I-i I;

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U-235 I

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Uranium B.

Enriched 20 to 100% U-235 B.

Less than 5000 gm*

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C.

U-233 C.

Any C.

Less than 2000 gm l

U-233*

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D.

Plutonium D.

Encapsulated and/or D.

Less than 2000 gm l5:

I sealed sources total Pu*

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Plutonium E.

Bred but unseparated E.

Less than 1000 gm h.:',

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Plutonium F.

Plated calibration F.

Less than 5 grams N

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source total Pu*

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Plutonium G.

Solutions, precipitates G.

Less than 5 grams tr I

solids and total Pu*

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

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i than 5,000 grams computed by the formula:

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Grams =

grams U-235 in uranium onriched to 20% or more plus 2.5 (grams U 233 + grams

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l SUPPLEMENTARY SHEET 70-734

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Authorized place of use: The licensee's San Diego, Califomia site as specified in the aforesaid g

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application and supplements.

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This license shall be deemed to contain two sections: S&fety Conditions and Safeguards Conditions.

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These sections are part of the license, and the licensee is subject to compliance with all listed g

I conditions in each section.

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

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Enclosures:

1. License Condition for Leak Testing g

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2. License Condition for Plutonium Alpha g

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3. Guidelines for Decontamination of g

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PAGES _g l

License Number g

I SNM-696 Amendment 41 E

l MATERIALS LICENSE Docket or Reference Number

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l SUPPLEMENTARY SHEET 70-734 g

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1 SAFETY CONDITIONS g

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I SAFETY CONDITIONS E

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

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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

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S-2.

Records of all safety-related reports and analyses shall be retained as follows!

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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.

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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.

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'S-3.

Notwithstanding the statements in Section 5.4.2 in the Ucense Specification Volume (Part il), if double 1

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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.

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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.

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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 %

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ceiwi, and (c) if equipment for effluent and exposure control is being properiy used, maintained, and E

I inspected.

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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.

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SNM-696 Amendment 41 g

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SUPPLEMENTARY SHEET 70-734

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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

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

Technician having a minimum of 5 years' experience in radiation safety. An evaluation of the safety effectiveness of the permit shall be made upon completion of the work.

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-S-7.

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

l S-8.

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

y course to an individual who is uniquely qualified to present it.

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S-9.

Continuous air sampling shall be conducted in any area where licensed material can become airbome.

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

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

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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.

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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 dual HEPA filtering of the effluent air. g y

S-12. Sealed Plutonium sources shall be subject to the leak testing and achons specified in the attached g

" License Condition for Leak Testing Sealed Pletonium Sources," dated April 1993.

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l Plutonium alpha sources shall be subject to the actions specified in the attached " License Condition for Plutonium Alpha Sources," dated April 1992.

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I S-13. The licensee shall prepare and submit to the Chief, Licensing Branch, Division of Fuel Cycle Safety anc Safeguards, NMSS, U.S. Nuclear Regulatory Commission, Washington, DC 20555, a report whenever g y

there is any new residential development within 1 mile around the site that constitutes a significant g

change in parameters that may be affected by the release of radioactive materials into the environmentg y

I S-14 Deleted by Amendment 14 dated August 3,1990 (originally numbered S-23 in 1990 - 1992 and 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

y Condition S-9 later became S-1.

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

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

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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.

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PAGES !

u.S. NUCLEAR RE!uLAToRY Commission License Numter I l g

SNM-696 Amendment 41 l l g

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MATERIALS LICENSE lhket or Reference Number

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g SUPPLEMENTARY SHEET 70-734 l

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SAFETY CONDITIONS I l 8

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S-16. Release of equipment, facilities, or pacirages to the unrestricted area or to uncontrolled areas onsite 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 Nuclear Material," dated April 1993.

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

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

approximately 5 seconds, more than once out of four trials g

l S-19. Notwithstanding the statements in Section 4.2.1.4, Part 11 of the license, no material handling shall be allowed in any area in which the required criticality alarm system is inoperative, g

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

released for general use.

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l S-21. Deleted by Amendment 31 dated September 1995. Fuel elements were shipped back to the licensee on October 3,1988.

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

g released for general use.

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The licensee shall maintain and execute the response measures described in the Emergency Plan S-23.

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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

70.32(i).

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License Number d

SNM-696 Amendment 41 Il MATERI ALS LICENSE rAdet or Reference Number N

SUPPLEMENTARY SHEET 70-734

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SAFEGUARDS CONDITIONS g

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t SAFEGUARDS CONDITIONS j

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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.

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d SECTION 2.0 - FACILITY OPERATION g

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

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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.

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

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SECTION 3.0 - MEASUREMENTS g

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

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SG-3.2 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

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SG-3.3 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

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y SECTION 4.0 - MEASUREMENT CONTROL g

E SG-4.1 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

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s SG-4.2 Deleted by Amendment 07, September 1996. Not applicable under a possession only license.

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SG-4.3 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

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

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

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

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

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

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c SECTION 5.0 - INVENTORY g

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SG-5.1 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

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

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

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PAGES lg ucense Number lg SNM-696 Amendment 41 g

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MATERIALS LICENSE LkxLet or Reference Number gi y

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 SG-7.1 Delsted by Amendment 37, September 1996. Not applicable under a possession only licer:se.

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

SPECIAL NUCLEAR MATERIAL y

g SG-9.1 The licensee shall follow the measures described in the physical protection plan entitled, " Fixed 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).

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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.

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SG-10.3 Deleted by Amendment 31, dated July 1995.

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