ML20154E591

Amend 8 to License SNM-696,authorizing Use of 985 Kg U Enriched in U-235 & 5 Kg U-233 for Use in Accordance W/ Statements & Conditions Contained in Part II - License Specs

ML20154E591
Person / Time
Site:	07000734
Issue date:	05/11/1988
From:	Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20154E584	List: ML20154E580 ML20154E591
References
NUDOCS 8805200258
Download: ML20154E591 (5)

Text

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4 64 U.S. NUCLEAR REGULATORY COMZlS$loN ## - OF .PACC5 l MATERIALS LICENSE j '

Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93 -438), and Title 10 i Code of Federal Regulations, Chapter I, Parts 30,31,32,33,34,3S,40 and 70, and in reliance on statements and representations '

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%l source, heretofore and specialmade by the nuclear material licensee, designated below; a to uselicense is hereby such material for the purpose issued (s) andauthorizing the licensee at the place (s)deugnated below;to 'tto r deliver or transfer such material to persons authorized to receise it in accordanee with the regulations of the appeable Part(s). This I i

license shall be deemed to contain the conditions specified in Section 183 of the Atomie Energy Act of 1954, as amended, and is ,I

{ subject to all applicable rules, regulations and orders of the Nuclear Regulatory Commission now or hereafter in effect and to any ;

( conditions speci6ed below. y Ucensee l l i 1

1. 3. Ueense number hem MG SNM-696, .

'l i.mendment No. 8 y

.. , I anbigo, 4. Espiration date December 31, 1989 fornia 92138

5. Docket or 'l Reference No.70-734 y

,4 6. Byproduct, source and/or 5

7. Chemical and/or physical S. Maximum amount that licensee I i special nuclear material form may possess at any one time ~I y under this license w ., ,

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p' A. Uranium enriched in A. As described in that A. 985 kilograms of 'p; U-235 isotope portion of the licensee's U-235 pi p!

14 application referred to it 14j in Item 9 of this license B B. U-233 B, Any B. 5 kilograms of l

. U-233 p.

h C. Plutonium C. Encapsulated and/or C. 3 kilograms total Pu  !

6 Sealed Sources I '

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( D. Plutonium D. Bred but unseparated D. 1 kilogram total Pu [

E. Plutonium E. Plated calibration E. 5 grams total Pu ,t

! source 3 I P t F. Plutonium F. Solutions, precipitates F. 5 grams total Pu B l and solids l-

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No more than 1,000 grams of U-235 will be in the form of UF6'

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q U.S. NUCLE AQ REGuL AVoQY CoMMISSloN

'i N AC Form 374 A PAGE 2 OF 5 PAGEs I

! O 84 LKenne numt:n I MATERIALS LICENSE [ ,d yp M on Y No. 8 y

SUPPLEMENTARY SHEET 70-734

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9. Authorized use: b

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! For use in accordacce with statements, representations, and conditions contained i in Part II "Licer se Specifications" dated July 24, 1981, and supplements dated ,

March 16, and Decenber 24, 1982; February 4, November 14, and November 15, 1983; April 10, April 12, June 28, September 4, and September 7, 1984; December 5, 1985; May 23, September 25, and December 10, 1986, December 21, 1987; March 9, (2), l and March 22, 1988.

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10. Authorized Place of Use:

lg- The licensee's San Diego, California site at 10955 John Jay Hopkins Drive and 11220 Flintkote Avenue as specified in the aforesaid application and supplements. l3 W

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

h1 a. Copies of criticality and radiation safety analyses shall be retained for at I I,

jl least 2 years or for 6 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 is additions, abnormal occurrences associated with radioactivity releases, 4

[d audits and inspections, instrument calibrations, ALARA findings, training and retraining, personnel exposures, routine radiation and environmental surveys) shall be retained for at least 2 years or longer if required by (q regulations. y 4't 12 M

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h . Notwithstanding the statements in Section 5.4.2 in the License SpecificationVolum shall be no more than 75 percent of the tr 'imum critical mass independent of the f y) l19 g

degree of water moderation and reflection. However, when the Th/U atomic ratio is > 3.6 and the H/U < 20, the maximum safe batch size may be increased to 790 g p

pt contained U-235 independent of whether double batching is credible.

13. The Director QACD, upon recommendation of the appropriate manager within QACD, shall have authority to require immediate termination of activities

< and/or corrective action in any situation which, in their judgment, could bl 4

lead to the unnecessary exposure of personnel to ionizing radiation, p y release of radioactive material, loss or damage of property, or ;M non-compliance with the license or a regulation. il

14. The Criticality and Radiation Safety Committee (CRSC), functioning as an ALARA Committee, shall meet at least annually to review (1) reports of audits and inspections perforthed since the last ALARA review and (2) employee exposures and effluent release data to determine (a) if there are any upward trends developing in 4

% personnel exposures for identifiable categories of workers, types of operations, or 14 effluent releases, (b) if exposures and releases might be lowered in accordance with l 14 tha ALARA concept, and (c) if equipment for effluent and exposure control is being f properly used, maintained, and inspected.

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! NRC Fom 374A U.S. Nucl.E AR QEGuLAToRY COMMISSION l PAGE 3 or 5 anoes I Lwense nurnber .I I SNM-696,_ Amendment. No. 8 MATERIALS LICENSE " "" ' l SUPPLEMENTARY SHEET l 70-734 3 l

5 l t The CRSC evaluation, recommendations, and corrective actions shall be l

! documented and the report shall be sent to the appropriate operations .3 l managers and the Vice President, Finance and Administration. lI F

l 15. Radiological Work Permits (RWPS) shall be issued for all unplanned or non-routine I work with licensed material not covered by a WA. The RWP shall be signed by Health l

Physics management or a senior staff member before related work can commence. A y senior staff member shall be a Health Physics Technician having a minimum of pl 5 years' experience in radiation safety. An evaluation of the safety effectiveness 't of the permit shall be made upon completion of the work. I

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

17. Radiation safety training and indoctrination shall be conducted by the Health Physics l Manager or by a similarly qualified individual. The Health Physics Manager may I kl delegate training in that portion of the course to an individual who is uniquely #

qualified to present it, f,

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

become airborne. W li' Di i

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 N sampling. In addition, the location of air samplers shall be checked at the fy commencement of operations in any area that has been shutdown for more than l4 6 months to verify the representativeness of air sampling, y i I4 Yl k 20. The laboratories in which plutonium in a dispersible form may be used shall have F l P exhaust ventilation systems separate from other building exhausts and shall provide > '

dual HEPA filtering of the effluent air. I f.4 g 21. Notwithstanding the statements made in Section 4.1.5 of the revised application dated p 4 November 1983, the licensee shall conduct leak testing of sealed plutonium sources >

k and alpha sources in accordance with Annex A. "License Condition for Leak Testing >

l f4 Sealed Plutonium Sources," dated November 1979, and Annex B, "License Confition for Plutonium Alpha Sources," respectively.

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

Division of Industrial and Medical Nuclear Safety, NMSS, U. S. Nuclear Regulatory 0 ,

Commission, Washington, DC 20555, a report whenever there is any new residential D ;

development within one mile around the site that constitutes a significant change D. I in parameters that may be affected by the release of radioactive materials into fl the environment. p D  ;

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NRC Foem 374 A U.S. NUCLE AR REGULATOnY COMMISSION { pggg 4 OF b PAGES I

!* License number l S 8 MATERIALS LICENSE g ]-69 , g pgdg g No.

SUPPLEMENTARY SHEET D

!70-734 p i p

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

Radiological Contingency Plan submitted to the Commission on May 25, 1984, and ;p, supplemented on August 22, 1984. The licensee shall also maintain implementing procedures for his Radiological Contingency Plan as necessary to implement the

Plan. The Plan shall be fully implemented by February 12, 1985. This Radiological Contingency Plan and associated implementing procedures supersede the emergency planning requirements of 10 CFR 70.22(i) as they refer to onsite planning and notification procedures. The licensee shall make no change in his Radiological Contingency Plan that would decrease the response effectiveness of the Plan without prior Commission approval as evidenced by a license amendment. The licensee may .

make changes to his Radiological Contingency Plan without prior Commission approval I:

(, if the changes do not decrease the response effectiveness of the Plan. The licensee '(p g shall maintain records of changes that are made to the Plan without prior approval for a period of 2 years from the date of the change and shall 'p, furnish the Chief, Fuel Cycle Safety Branch, Division of Industrial and Medical Nuclear Safety, NMSS, U. S. Nuclear Regulatory Commission, Washington, k DC 20555, and the appropriate NRC Regional Office specified in Appendix 0 (g of 10 CFR Part 20, a report containing a description of each change within 6 months after the change is made.

h 24. At the end of plant life, the licensee shall decontaminate the site and facilities,

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

$ general decommissioning plan submitted by your letter dated July 25, 1986, and its .

14 supplement dated October 15, 1986, so that these facilities and grounds can be d released for unrestricted use. The corporate commitment that funds will be made

$ available for decommissioning the facility, provided by letter dated September 10, 3 1986, is hereby incorporated as a condition of the license. d@

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$ 25. Notwithstanding the statements made in Section 4.3.5 of the revised application dated  ;

F November 1983, the release of the facilities and equipment for unrestricted use from  ;

d the plant site or to unrestricted areas onsite shall be in accordance with the l

iq enclosed Annex C, "Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Licenses for By-product, Source or #y

% Special Nuclear Material", dated July 1982.

26. The licensee is hereby exempted from the provisions of 10 CFR 70.24 during the N 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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a. The criticality alarm system shall be in service in all areas where the quantity I

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! of special nuclear material (SNM) does not meet the exemption criteria in Section l

!i 4.2.1.4 of the specification volume with the exception of the SNM storage vaults l> in the SV-A building.

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b. There shall be no movement of any special nuclear material (SNM) into, out of, or ,

h within the SV-A building SNM storage vaults while the criticality alarm system is l ti not in service. 1 4

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NT.C Form 3h U.s. NUCLE An REGULATOnY COMMISSION j ,,qg g g, $ pggg3 License number MATERIALS LICENSE SNM-696, Amendment No. 8 l! SUPPLEMENTARY SHEET p 70-734 y j' N 1

3 1 4 1 D y! 27. Notwithstanding the statement in Section 4.2.1.4, Part II of the license, the trip p il levels will be readjusted af ter each monthly test of the criticality alarm system if ,k I the 11 arm point fails to activate within approximately 5 seconds, more than once out i f of four trials. I 1 >

28. Notwithstanding the statements in Section 4.2.1.4, Part II of the license, no l l

material handling shall be allowed in any area in which the required criticality fl j alarm system is inoperative.

g f D' I 29. The licensee may reduce the radiation safety, nuclear criticality safety, and 1

I l environmental surveillance requirements within the HTGR fuel fabrication and storage l l areas in the SV-A Building, TRIGA fuel manufacturing building, and in the GA Hot :l l j Cell possessing fissile and/or other radioactive material, during a period of 3p 1 reduced activities as specified in the application dated April 23, 1985, subject to ,li i the following modifications: >

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4 The survey frequencies and contamination control measures specified in the license l shall be used whenever work is performed on or with equipment which handles

{; radioactive material.

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i b. Any work performed on equipment which handled radioactive materials shall be $ i i authorized by and performed under a radiation work permit, 1

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All openings of ventilation ducts and enclosures which are not completely sealed l shall be maintained with a minimum airflow of 25 LFM. The licensee shall [p i determine, on at least a semiannual basis, that this minimum airflow is pj q maintained, d

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If air sample results indicate an increase in airborne contamination to 10 Is percent or more of the appropriate MPC, survey frisquencies shall be increased to j the levels specified for Type II laboratories. h gj q

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q The Manager, Nuclear Safety, or his designee shall perform a criticality Ej q inspection, at least annually, of all areas specified. Ej 1

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k p FOR THE NUCLEAR REGULATORY COMMISSION l 5 .,s Original Signen p...

I 3 Date: 54Y11 % Q( <,/ ', llM By: Leland C. Rouse B,.

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1 i Division of Industrial and D-1 Medical Nuclear Safety I

{ Washington, DC 20555 l

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