ML20196B004

Amend 9 to License SNM-696 for General Atomics,Authorizing Possession & Use of U,U-233 & Plutonium & Release of Approx 277 Acres of Land for Unrestricted Use

ML20196B004
Person / Time
Site:	07000734
Issue date:	06/22/1988
From:	Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20196B002	List: ML20196A995 ML20196B004 ML20196B033 ML20196B041
References
NUDOCS 8806300176
Download: ML20196B004 (5)

Text

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j 0 84 U.S. NUCLE AR RE1ULAToRY COMMIS$loN PAGE

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MATERIALS LICENSE f Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438 f

p Code of Federal Regulations, Chapter I, Parts 30,31,32,33,34,35,40 and 70, and in reliance on statements and representations y

4} heretofore made by the licensee, a license is hereby issued authorizing the licensee to receive, acquire, po source, and special nuclear

• material designated below; to use such material for the purpose (s) and at the place (s) designated below; to l L dcliver or transfer such material to persans authorized to receive it in accordance with the regulations of the applicable Part(s). This

,R k license shall be deemed to contain the conditions specified in Section 183 of the Atomic Energy Act of 1954, as amended, f subject to all applicable rules, regulations and orders of the Nuclear Regulatory Commission now or hereafter in eff conditions specified below.

Licensee J

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3. License number E

1 General Atomics SNM-696,

, >k Amendment No. 9 i

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JUN-H 1983 ii P. O. Box 85608 4' Expiration' ate i

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San Diego, California 92138 Decemher_1L_1989 d

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5. Docket or b

f Reference No.70-734

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7. Chenical and/or physical

8. Maximum amount that licensee jb il; 6. Byproduct, source, and/or l

special nuclear material form may possess at any one time lk under this license

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Uranium enriched in A.

As described in'that A.

985 kilograms of

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1; U-235 isotope

. portion of the licensee's U-235 F:

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in Item 9 of this license

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U-233 B.

Any B.

5 kilograms of f

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U '33 lp, f

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Plutonium C.

' Encapsulated and/or C.

3 Kilograms total Pu y

1 Sealed Sources fb s

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Plutonium D.

Bred but unseparated D.

1 kilogram total Pu f

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Plutonium E.' Platedcelibration E.

5 grams total Pu

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Plutonium F.

Solutions, precipitates F.

5 grams total Pu

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Amendment No. 9 MATERIALS LICENSE l

SUPPLEMENTARY SHEET JUN 2 21988 t

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Authorized use:

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1 For use in accordance with statements, representations, and conditions contained F

1 in Part II "License Specifications" dated July 24, 1981, and supplements dated L

I March 16, and December 24, 1982; February 4, November 14, and November 15, 1983; I

April 10, April 12, June 28, September 4, and September 7, 1984; December 5, 1985;

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y May 23, September 25, and December 10, 1986; December 21, 1987; March 4,

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March 9, (2), and March 22, 1988.

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10. Authorized Place of Use:

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6 The licensee's San Diego, California site at 10955 John Jay Hopkins Drive and h

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g 11220 Flintkote Avenue as specified in the aforesaid application and supplements.

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11. Records of all safety-related reports and analyses shall be retained as follows:

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Copies of criticality and radiation safety analyses shall be retained for at J

[t least 2 years or for 6 months after a project is terminated, whichever is j j longer.

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Copies of all other safety-related records'(e.g., plant alterations and p

1 additions, abnormal occurrences associated with radioactivity releases, d

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%l audits and inspections, instrument calibrations, ALARA findings, training 9

and retraining,~ personnel exposures, routine. radiation and environmental d

f surveys) shall be retained for at 1 east 2 years or longer lif required by q

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12. Notwithstanding the statements in Section 5.4.2 in the License Specification 4,!

1 Volume (Part II), if double batching is not credible, the maximum safe batch size Dj shall be no more than 75 percent of the minimum critical mass independent of the H

f degree of water moderation and reflection.

However, when the Th/U atomic ratio q

is > 3.6 and the H/U 1 20, the maximum safe batch size'may be increased to 790 g n

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contained U-235 independent of whether double batching is credible, j

4 13. The Director QACD, upon recommendation of the appropriate manager within p) i j

4 QACD, shall have authority to require immediate termination of activities d

l and/or corrective action in any situation which, in their judgment, could lij lead to the unnecessary exposure of personnel to ionizing radiation, g

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release of radioactive material, loss or damage of property, or 4

1 non-compliance with the license or a regulation.

llj il JJ 3 14. The Criticality and Radiation Safety Committee (CRSC), functioning as an ALARA M

3 Committee, shall meet at least annually to review (1) reports of audits and Q

l' inspections performed since the last ALARA review and (2) employee exposures and q

effluent release data to determine (a)~if there are any upward trends developing in

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personnel exposures for identifiable categories of workers, types of operations, or

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effluent releases, (b) if exposures and releases might be lowered in accordance with j

i the ALARA concept, and (c) if equipment for effluent and exposure control is being j

j properly used, maintained, and inspected.

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U.S. NUCLEAR RE!ULAToRY CoMMisSloN N;C hem 374A PAGE 3

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Amendment No. 9 MATERIALS LICENSE d="""'"*'

j E'JPPLEMENTARY SHEET JUN 2 21988 i

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70-734 g

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l The CRSC evaluation, recommendations, and' corrective actions shall be J

documented and the report shall be sent to the appropriate operations h

I managers ano the Vice President, Finance and Administration, i

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15. Radiological Work Permits (RWPS) shall be issued for all unplanned or N

f non-routine work with licensed material not covered by a WA. "The RWP shall i

be signed by Health Physics management or a senior staff member before related j

)f work can commence.

A senior staff member shall be a Health Physics Technician having a minimum of 5 years' experience in radiation safety.

An esoluation of l

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

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f! 16. Radiation safety training, appropriate to the employee's needs, shall be given to all new employees.

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17. Radiation safety training and indoctrination shall be conducted by the Health 4

1, Physics Manager or by a similarly qualified individual.

The Health Physics lp li Manager may delegate training in that portion of the course-to an individual who M

[p is uniquely qualified to present it.

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18. Continuous air sampling shall be conducted in any area where licensed material j

can become airborne.

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19. The location of air samplers shall be checked annually and whenever any process or equipment changes are made to verify the representativeness of work area air l

%j sampling.

In addition, the location of air samplers shall be checked at the j

commencement of operations in any area that has been shutdown for more than j

6 months to verify the representativeness of air sampling.

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1 20. 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 l

%j dual HEPA filtering of the effluent air.

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21. Notwithstanding the statements made in Section 4.'1.5 of the revised application 1

dated November 1983, the licensee shall conduct leak testing of sealed plutonium 1

1 sources and alpha sources in accordance with Annex A, "License Condition for Leak 1

4 Testing Sealed Plutonium Sources," dated November 1979, and Annex B, "License l

l Condition for Plutonium Alpha Sources," respectively.

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22. The licensee shall prepare and submit to the Chief, Fuel Cycle Safety Branch, l

g Division of Industrial and Medical Nuclear Safety, NHSS, U. S. Nuclear Regulatory l

A Commission, Washington, DC 20555, a report whenever there is any new residential l

1 development within one mile around the site that constitutes a significant change 3

in parameters that may be affected by the release of radioactive materials into i

l the environment.

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l C Fum 374A U.S. NUCLE AR RESULAToRY COMMISSloN 4

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MATERIALS LICENSE Amendment No. 9 na dma numbu l

SUPPLEMENTARY SHEET JUN 2 21988 h

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23. The licensee shall implement, maintain and execute the response measures of his l

I Radiological Contingency Plan submitted to the Commission on May 25, 1984, and h

I supplemented on August 22, 1984.

The licensee shall also maintain implementing ji f

l procedures for his Radiological Contingency Plan as necessary to implement the i

Plan.

The Plan shall be fully implemented by February 12, 1985.

This If y

g Radiological Contingency Plan and associated implementing procedures supersede f

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the emergency planning requirements of 10 CFR 70.22(i) as they refer to onsite y

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planning and notification procedures.

The licensee shall make no change in his Y

E Radiological Contingency Plan that would decrease the response effectiveness of N

fl the Plan without prior Commission approval as evidenced by a license amendment.

P The licensee may make changes to his Radiological-Contingency Plan without prior j

4l Commission approval if the changes do not decrease the response effectiveness of g

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the Plan.

The licensee shall maintair. records of changes that are made to the l

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Plan without prior approval for a period of 2 years from the date of the change I

and shall furnish the Chief, Fuel Cycle Safety Branch, Division of Industrial 9

((%l and Medical Nuclear Safety, NMSS, U. S. Nuclear Regulatory Commission, B

Washington, DC 20555, and the appropriate NRC Regional Office specified in Appendix 0 of 10 CFR Part 20, a report containing a description of each change l l ql within 6 months after the change is made.

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'1 li 24. At the end of plant life, the licensee shall decontaminate the site and facilities, l

It authorized as a place of use for special nuclear material, in accordance with the

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f general decommissioning plan submitted by your letter dated July 25, 1986, and its i

e supplement dated October.15,.1986, so that these facilities and grounds can be t

q released for unrestricted use.

The corporate' commitment that funds will be made i

I qi available for decommissioning the facility, provided by letter dated September 10,

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1986, is hereby incorporated as a condition of the license.

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% 25. Notwithstanding the statements made in Section 4.3.5 of the revised application dated November 1983, the release of the facilities and equipment for um astricted I

use from the plant site or to unrestricted areas onsite shall be in accordance with the enclosed Annex C, "Guidelines for Decontamination of Facilities and i

I' Equipment Prior to Release for Unrestricted Use or Termination of Licenses for By product, Source or Special Nuclear Material", dated July 1982.

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26. The licensee is hereby exempted from the provisions of 10 CFR 70.24 during the modification of the SV-A criticality alarm system insofar as this section applies to materials held in the SV-A building under this license subject to the following:

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1 a.

The criticality alarm system shall be in service in all areas where the

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quantity of special nuclear material (SNM) does not meet the exemption criteria

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in Section 4.2.1.4 of the specification volume with the exception of the SNM storage vaults in the SV-A building.

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There shall be no movement of any special nuclear material (SNM) into, out of, or within the SV-A building SNM storage vaults while the criticality alarm I,systemisnotinservice.

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73ct op paces ucen2 numbe' SNM-696 N

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27. Notwithstanding the statement in Section 4.2.1.4, Part II of the license, the

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l trip levels will be readjusted after each monthly test of the criticality alarm p

I system if the alarm peint fails to activate within approximately 5 seconds, more r

l than once out of four trials.

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28. Notwithstanding the statements in Section 4.2.1.4, Part II of"the license, no g!

material handling shall be allowed in any area in which the required criticality

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alarm system is inoperative.

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29. The licensee maj reduce the radiation safety, nuclear criticality safety, and p

d erivironmental surveillance requirements within the HTGR fuel fabrication and B.

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storage areas in the SV-A Building,- TRIGA fuel manufacturing building, and in i

I f(l the GA Hot Cell possessing fissile and/or other radioactive material, during a period of reduced activities as specified in the application dated April 23, 1985, l

l subject to the following modifications:

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The survey frequencies and contamination control measures specified in the t

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d; license shall be used whenever work is performed on or with equipment which

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[i handles radioactive material, j

b.

Any work performed on equipment which handled radioactive materials shall be g

authorized by and performed under a radiation work permit.

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I All openings of ventilation ducts and enclosures which are not completely 3l c.

3 sealed shall be maintained with a minimum airflow of 25 LFM.

The licensee j

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shall determine.non at least a semiannual basis, that this minimum airflow j

g, is maintained.~.

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d.

If air sample results indicate an increase in airborne contamination to 1

10 percent or more of the appropriate MPC, survey frequencies shall be increased to the levels specified for Type II laboratories.

j TheManager,NuclearSafety,orhisdesigneeshallperformacriticality e.

inspection, at least annually, of all areas specified.

l FOR THE NUCLEAR REGULATORY COMMISSION 4

l JUN 2 21988 i

oF g By:

Leland C. Rouse i

Date:

M Division of Industrial and 7

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Medical Nuclear Safety (I

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Washington, DC 20555 l

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NUCLEAR REGULATORY COMMISSION j

WASHINGTON, D. C. 20555

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JUN 2 21988 IMUF:EYS DOCKET N0:

70-734 LICENSEE:

General Atomics (GA)

FACILITY:

San Diego, California

SUBJECT:

CATEGORICAL EXCLUSION FOR AMENDMENT REQUEST DATED MARCH 4, 1988 By application dated March 4,1988, GA requested an amendment to Special Nuclear Materials License No. SNM-696 to authorize the release of approximately 277 acres of land for unrestricted use.

The licensee has cleaned off the land to acceptable levels which are below the NRC target criteria. The staff has conducted an evaluation of GA's decontamination efforts and concludes that the following conditions have been met:

1.

There is no significant change in the type or significant increase in the amount of any effluents that may be released offsite, 2.

There is no significant increase in individual or cumulative occupational radiation exposure, 3.

There is no significant construction impact, and 4.

There is no significant increase in the potential for or consequences from radiological accidents.

Therefore,inaccordancewith10CFR51.22(c)(11),neitheranEnvironmental Assessment nor an Environmental Impact Statement is warranted for this proposed action.

FOR THE NUCLEAR REGULATORY COMMISSION SM (L s g Leland C. Rouse, Chief Fuel Cycle Safety Branch Division of Industrial and Medical Nuclear Safety, NMSS 1