ML20202B401

Amend 52 to License SNM-696 for General Atomics,Releasing Certain Portions of Bldg 39 (Svb) to Unrestricted Use

ML20202B401
Person / Time
Site:	07000734
Issue date:	01/26/1999
From:	Emeigh C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20202B381	List: ML20202B378 ML20202B401 ML20202B409
References
NUDOCS 9901290070
Download: ML20202B401 (8)

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U.S. NtJCLEAR RECT'LATORY COMMISSION MATERIALS LICENSE Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Tit!c 10, Code of Federal Regulations, Chapter I, Parts 30, 31,32,33,34,35,36,39,40, and 70, and in reliance on statements and representations heretofore made by the liccasce, a license is hereby issued authorizing the licensee to receive, acquire, possess, and transfer byproduct, source, and special nuclear material designated below; to use such material for the purpe,se(s) and at the place (s) designated below; to deliver or transfer such material 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 in Section 183 of the Atomic Energy Act of 1954, as amended, and is subject to t.Il applicable rules, regulations, and orders of the Nuclear Regulatory Commission now or here Aer in effect and to any conditions specified txlow.

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Licensee

l. General Atomics 3. License Number SNM-696, Amendment 52

2. P.O. Box 85608 4. Expiration Date December 31,1989 Srn Diego, California 92186-9784 5. Docket No.70-734

, n pt R F e Reference No.

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6. Byproduct Source, and/or N7;# Chemical and/or Physical A 8. Maximum amount that Licensee Special Nuclear Material A/

Form Q May Possess at Any One Time

_ Under This License I N

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.J - {'J. I A. Uranium AN(

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i tJ-2 35 ? f p { a$ 2 Enriched O u to 9.99% A.O200 kilo g ,

.. p$q szx L s p, p B. Uranium g) C B. nn d 20;t'o 100,%: B.Less than 5000 gm*

DU-23 l 7 g ,$"

n% %  %

$ liduif[# h Less than 2000 gm C. U-233 $ Cl 'kdL AnydWj[

WW , U-233*

D. Plutonium D. : Encapsulated end/or D. Less than 2000 gm sealsdiouibes' total Pu*

E. Plutonium E. Bred but unseparated E. Less than 1000 gm total Pu*

F. Plutonium F. Plated calibration F. Less than 5 grams source total Pu*

G. Plutonium G. Solutions, precipitates G. Less than 5 grams solids and total Pu*

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

Grams = grams U-235 in uranium enriched to 20% or more plus 2.5 (grams U-233 + grams plutonium) 9901290070 990126 Il l PDR ADOCK 07000734 hj C PDR j l~

NRC FORM 374A U.S. NUCL F.A2 EEGULATORY COMMISSION PAGE 2 of 8 PAGES License Number SNM-696 Docket or Reference Number MATERIALS LICENSE SUPPLEMENTARY SHEET 70-734 Amendment No. 52

. 9. Authorized place of use: The licensee's San Diego, California site as specified in the aforesaid application and supplements.

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

These sections are part of the license, and the licensee is subject to compliance with alllisted conditions in each section.

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y/p ' t [% n,0.ve:3 g O FOR THE NUCLEAR REGULATORY COMMISSION

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Dite: /[26/99 '

By: Charles W. Emeiah. Actina ief .:,

Division of Fuel Cycle Safety 3 and Safeguards, NMSS Washington, DC 20555 (Provided w/ Amendment 31)

Enclosures:

1. License Condition for Leak Testing Sealed Plutonium Sources, dtd 4/93

2. License Condition for Plutonium Alpha Sources, did 4/93

3. Guidelines for Decontamination of Facilities..., dtd 4/93

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NRC FORM 370A U.S. NUCLEAR REGULATORY COMMISSION PAGE 3 of 8 PAGES Ucense Number SNM-696 Docket or Reference Number h1ATERIALS LICENSE SUPPLEMENTARY SHEET 70-734 Amendment No. 52 SAFETY CONDITIONS S-1. Authorized use: For use in accordance with statements, representations, and conditions contained in Part 11 " License Specifications" dated July 24,1981, and supplements dated March 16 and December 24,1982; February 4, November 14, and Novembe! i5,1983; 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 4, March 9 (2), March 22, April 26, August 22, September 8, and November 2,1988; May 25 and November 17,1989; June 27,1990; April 30 and September 27,1991; March 5, March 18, June 24, and September 10,1992; January 20,1995; the "SVA Decommissioning Plan" dated April 1,1990 (submitted by letter dated March 30,1990); August 22,1990 (submitted by letter dated August 24,1990); June 15 1992pJuly 12 and August 23,1994; Group 6 Laboratories unrestricted use request dated AugEstb32,999k IWarch 1,1995; Group 7 Laboratories unrestricted use request dated December 5, ,1Gi95l Group 8B Labora' tories unrestricted use request dated August 23, 1996; October 15,1996; Mril 30,1997; Group 9 Labora'thes unrestricted use request dated July 17, 1997: Building 30 Laboratories unrestricted use release dated July 25,1997; and January 29,1998; Site Decommissioning Rfin dated October 11 and Deceintie65,1996; April 18,1997; January 15, 1998; Hot Cell Decomm7ssionirighar dated April 22/1998, Group 10 Labs dated August 14, Building 27 Roof release dated Adgup]t 25f apd Bylding 30 - @ase li dated Septem W ': g [.A,3% y " qff December 22,1998, (SVB).,1 W.?:

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S-2. Records of all safety-related' reports and ns'yses shallbe retained as follows:

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Copies of criticality and radiation s'afety' analyses sha%e retained for at least 2 years or for '

6 months after a proje'ctis terminated,ihiche'ver i6jonger.

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b. Copies of all other safety-relifedfecords;(e.E, plant alterations and additions, abnormal occurrences associated with radioactivity releases, audits and inspections, instrument calibrations, ALARA findinos, training and retraining, personnel exposures, routine radiation and environmental surveys) shall be retained for at least 2 years or longer if required by regulations.

S-3. Notwithstanding the statements in Section 5.4.2 in the License Specification Volume (Part II), if double batching is not credible, the maximum safe batch size shall be no more than 75 percent of the minimum critical mass independent of the degree of water moderation and reflection. However, when the Th/U atomic ratio is > 3.6 and the H/U s 20, the maximum safe batch size may be increased to 790 g contained U-235 independent of whether double batching is credible.

S-4. 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 lead to the unnecessary exposure of personnel to ionizing radiation, release of radioactive material, loss or damage of property, or non-compliance with the license or a regulation.

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NRC FORM 374A U.S. NUCLEAR REGt'LATORY COMMISSION PAGE 4 i,f r, PAGES License Number SNM-696

~ MATERIALS LICENSE Docket or Reference Number SUPPLEMENTARY SHEET 70-734 Amendment No. 52 S-5. 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 performed since the last ALARA review and (2) employee exposures and effluent release data to determine (a) if there are any upward trends developing in personnel exposures for identifiable categories of workers, types of operations, or effluent releases, (b) if exposures and releases might be lowered in accordance with the ALARA concept, and (c) if equipment for effluent and exposure control is being properly used, maintained, and inspected.

The CRSC evaluation, recommendations, and corrective actions shall be documented and the report shall be sent to the appropriate operations managers and the Vice President, Finance and Administration.

,VfR REGg S-6. Radiological Work Permits (RWPS) shall be issued'forJall unplanned or non-routine work with licensed material not covered by ayA. The RWP shall be signed by Health Physics management or a senior staff member before related work can commence. A seniopstaff member shall be a Health Physics Technician having a miriffnum of,5 years' experience.in fadiation safety. An evaluation of the safety effectiveness of the perihit shall be rnade upon cornpfetion of the work.

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LE O l S-7. Radiation safety training, appropriate to the~ employee's needs,e shall be given to all new employees. ,

S-8.

'D Lh. MG G[W ^ l Radiation safety training.and indoctrination sball be con.ducteN by the. Health Physics Manager or by a l similarly qualified individual. The HealttEPfyNes Manager rifay delegate training in that portion of the I

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course to an individual who,is u'niquely ' qualified toy' resenfit: i

'Q C Q l S-9. Continuous air sampling shall be conducted in any area where licensed material can become airborne.

k p. & Q 4 S-10. 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 sampling. In addition, the location of air samplers shall be checked at the commencement of operations in any area that has been shutdown for more than 6 months to verify the representativeness of air sampling.

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.

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

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

l l Plutonium alpha sources shall be subject to the actions specified in the attached " License Condition for Plutonium Alpha Sources," dated April 1993.

- S-13. The licensee shall prepare and submit to the Chief, Licensing Branch, Division of Fuel Cycle Safety and Safeguards, NMSS, U.S. Nuclear Regulatory Commission, Washington, DC 20555, a report whenever there is any new residential development within 1 mile around the site that constitutes a significant change in parameters that may be affected by the release of radioactive materials into the environment.

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NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION PAGE 5 or C PAGES License Number SNM-696 Docket or Reference Number

' MATERIALS LICENSE ,

SUPPLEMENTARY SHEET 70-734 Amendment No. 52 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 S-23 was incorporated into License Condition S-9 by adding the date of May 25,1989; License Condition S-9 later became S-1.

S-15. At the end of plant life, the licensee shall decontaminate the site and facilities, 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 supplement dated October 15,1986, so that these facilities and grounds ca" . teleased for unrestricted use. The corporate commitment that funds will be made available for decommissioning the facility, provided by letter dated September 10,1986, is hereby incorporated as a condition gen of the license.R E G g S-16. Release of equipment, facilitie's; or packages to the'unre,stricted area or to uncontrolled areas onsite shall be in accordance withithe attached " Guidelines for Decontamination of Facilities and Equipment Prior to Release for UnrestYicted Use or Termination of Li6enses for Byproduct, Source, or Special Nuclear Material," dated' April 1993. 4 k .Q1 ? . im 4 O S-17. Deleted by Amendmen(37, Septernber 1996. The SVA facility has been decommissioned and released for general use.

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S-18. Notwithstanding the statement in Section 4. U4, Part.ll of thNiicense, the trip levels will be readjusted after each monthly test'6Lthe crificaldylld Eyitenifif the fiarm point fails to activate within approximately 5 secondicmore'than orice'6ut off6Lir trialsi g y u g

S-19. Notwithstanding the statemen't's in Section 4.2.1.4, Pirl11 of the license, no material handling shall be allowed in any area in which the rhuired criticalitEalarm system is inoperative.

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

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

S-22. Deleted by Amendment 37, September 1996. The SVA facility has been decommissioned and released for general use.

S-23. The licensee shall maintain and execute the response measures described in the Emergency Plan dated October 10,1997, supplemented by letter dated November 6,1997; and Revision Date 10/98; or as further revised by the licensee consistent with the provisions of 10 CFR 70.32(1).

S-24 The licensee shall develop individual survey plans for each facility or group of laboratories and provide NRC a 30-day notification, prior to GA initiating a final survey, to allow the NRC to schedule in-process inspections / surveys if required.

NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION PAGE 6 or 8 PAGES License Number SNM-696 MATERIALS LICENSE IMn or Reference Number SUPPLEMENTARY SHEET 70-734 Amendment No. 52 S-25 The licensee must submit for review and approval to NRC residual contamination and characterization data and planned decommissioning procedures for areas where:

1. Decommissioning procedures will be required that have not been used by the licensee in previous decommissioning activities or have not been identified in the Site Decommissioning Plan dated October 11,1996, as amended December 5,1996; April 18,1997; and January 15, 1998;

2. Workers would be entering areas where surface contamination and radiation levels are significantly higher than routinely encountered during previous decommissioning operations; c- pc

3. Procedures could result in sighificantly,., greater airborne concentrations of radioactive materials than have been presEnt in previous decominis'sioning operations; or

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4. Procedures could' result in significantly greater releases of radioactive material to the environment thg3 those a,ssociated with p , lods e decommissioning operations.

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NRC FORM 374A U.S. NUCLEAR RECULATORY COMMISSION PAGE 7 of 8 PAGES License Number SNM-696

' Docket or Reference Number MATERIALS LICENSE SUPPLEMENTARY SHEET 70-734 Amendment No. 52 SAFEGUARDS CONDITIONS SECTION 1.0 - FACILITY ORGANIZATION

Currently there is no license condition in this section. The necessary information has been incorporated into l cn gpproved Fundamental Nuclear Material Control Plan, dated February 1998.

SECTION 2.0 - FACILITY OPERATION L

SG-2.1 Deleted by Amendment 37, S p erpbg99,6 Not applicable under a possession only license.

SG-2.2 Deleted by Amendment @, September 1996. Not applicable under a possession only license.

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. Deleted by Amendment 37,, September 1996. No.t appli, cable under a possession only license.

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Not applicable under a possession only license.

SG-2.4 rnber 199 Deleted by Amen <r _dment E

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SECTION 3.0 - MEASUREMENTS b i . Vig/g_ f , , g )

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l SG-3.1 Deleted by Amendment 37/ Se mb [1996. Not'appibble under a possession only license.

SG-3.2 Q ' J h 5.ukJ5 QQU & f Q Deleted by Amendmer)t 37, Septe'mber 1996f Not apphcable under a possession only license.

l Q y, q.~ g SG-3.3 Deleted by Amendment 37, Se, ptember 1996. Not applicable under a possession only license.

l N k k -fc ~Y l SECTION 4.0 - MEASUREMENT CONTROL

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

I SG-4.2 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

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

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

l SG-4.5 Deleted by Amendment 37. September 199'6. 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.

SG-4.7 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

SG-4.8 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

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NRC FORM 374A U.S. NUCLEAR REGOLATORY COMMISSION PAGE 8 of 8 PAGES License Number SNM-696

' MATERIALS LICENSE Docket or Reference Number SUPPLEMENTARY SIIEET 70-734 Amendment No. 52 SECTION 5.0 - INVENTORY

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

' SG-5.2 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

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

SECTION 6.0 - RECORDS AND REPORTS SG-6.1 Deleted by Amendment 37, Septgber i996. Not applicable under a possession only license.

Q.h ' ' j U(Jz SECTION 7.0 - INTERNAL CONTROL 4j SG-7.1 N O Deleted by Amendment.37, September 1996. Not applicable under a possession only license.

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SG-8.1 Deleted by Amer)dment37,- ternber1996,* Not applicable under a possession only license.

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R SECTION 9.0 - PHYSICAL PROTECTION REQUIREMENTS'FORVORMULA QUANTITIES OF STRATEGIC SPECIAL NUCLEAR MATERIAlygMWe~gy $

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SG-9.1 i The licensee shall fol!I v the measu'res' described,ittthe physical protection plan entitled, " Fixed Site and Transportation Plan fpr the Protection cf Special Nuclear Material of Moderate and Low Strategic Significance," dated May 1989/sutNnitted by letter dated May 8,1989; and as it may be further revised in accordance with the' pro' visions of 10 CFR 70.32(e).

SECTION -10.0 - TEMPORARY OR ONE TIME CONDITIONS SG-10.1 Deleted by Amendment 31, dated July 1995.

SG-10.2 Deleted by Amendment 31, dated July 1995.

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

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