ML20217R019
| ML20217R019 | |
| Person / Time | |
|---|---|
| Site: | 07000734 |
| Issue date: | 04/29/1998 |
| From: | Weber M NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20217R009 | List: |
| References | |
| NUDOCS 9805130088 | |
| Download: ML20217R019 (7) | |
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U.s. NUCLEAR REGULATORY Commission MATERIALS LICENSE Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10, Code of Federal Regulations, Chapter 1, Parts 30,31,32,33,34,35,36,39,40, and 70, and in reliance on statements and representations heretofore made by the licensee, 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 purpose (s) and at the place (s) designated below; to deliver or transfer such material to persons authorized to receive it in accordanca 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 tc all applicable rules, regulations, and orders of the Nuclear Regulatory Commission now or hereafter in effect and to any conditions specified below.
Licensee
- 1. General Atomics 3. Ucense Number SNM-696, Amendment 44
- 2. P.O. Box 85608 4. Expiration Date December 31,1989~
San Diego, California 92186-9784 _ _
- 5. Docket No.70-734 6 e Reference No.
- 6. Byproduct Source, and/or J . Chemical and/or Physical 8. Maximum amount that Licer' me Special Nuclear Material Form w
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May Possess at Any Goe Time A. Uranium s 4 ,
A. Enriched up to119.99% A.0200 kilograms U-235 q U-235Z \ jf i. O w .A s g,,y g B. Uranium W B. Ehriched 20 to 100%' , B.Less than 5000 gm*
yl:X e _N U-2'35 4 E v + % .:p 2 y y C. U-233 4
'q, C.' Any..
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(0 Less than 2000 gm U-233*
D. Plutonium D. Encapsulated $nd/or D. Less than 2000 gm sealbd sourdes total Pu*
E. Plutonium E. Bred but unseparated E. Less than 1000 gm total Pu*
F. Plutonium F, I lated calibration F. Less than 5 grams source total Pu*
G. Plutonium G. Solutions, precipitates G. Less '.han 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 plutoniun.)
9805130088 980429 PDR ADOCK 07000734 C PDR
NRC FORM 374A U.S. NUCLEAR REGULATORY Commission PAGE 2 of 7 PAGEs License Number SNM-696 MATERIALS LICENSE oocket or Reference Number SUPPLEMENTARY SHEET 70-734 Amendment No. 44
- 9. Authorized place of use: The licensee's San Diego, Cal:iornia 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 all listed conditions in each section.
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Y FORgHE NUCLEAR REGULATORY COMMISSION Date: !j/39!98 /
By: Michael F. Weber h/'
gy-Division of Fuel Cycle Sqlety 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, dtd 4/93 1
- 3. Guidelines for Decontamination of Fscilities..., dtd 4/93
NRC FORM 374A u.S. NUCLEAR REGULATORY COMMISSloN PAGE 3 of 7 PAGEs License Number i SNM-696 I MATERIALS LICENSli Docket or Reference Number SUPPLEMENTARY SHEET- 70-734 Amendment No. 44 SAFETY CONDITIONS S-1. Authorized use: For use in accordance with statements, representations, and conditions contained in Part il " License Specifications" dated July 24,1981, and supplements dated March 16 and December 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 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; and in 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 15,1992; July 12 and August 23,1994; Group 6 Laboratories unrestricted use'feq,u'est: dated, August 12,1994; March 1,1995; Group 7 Laboratories unrestricted use, request dated December,5,199,5; Group 8B Laboratories unrestricted use request dated August 23,1996; October 15,1996la'nd April 30, and Group 9 Laboratories unrestricted use request dated July 17,1997, and Building 30 Laboratories unrestricted use release dated July 25,1997, and January ,29,1998.
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S-2. Records of all safety-r$ lated rep $rfs and analyses'shall be retdined as follows:
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- a. Copies of criticalitf and radiation safe analyses.shall belretained for at least 2 years or for 6 months after a pr'oject is }erminais* " lchev5r is'iongera n
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- b. Copies of all other safety-relatedTeco h>(^(_g56e.g plant afterations and additions occurrences associat6d_ with rSdioactivyy' releases, ALARA findings, trainir%and retraining, personnel'gtfdits exposures, routine radiationand inspections, ins and environmenta!
surveys) shall be retained'for.at least 2 years or ionger if required by regulations, j WAgg5 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 2 3.6 and the H/U < 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.
NRC FORM 374A u.s. NUCLEAR REGULATORY Commission PAGE 4 of 7 PAGEs License Number SNM-696 MATERIALS LICENSE Docket or Reference Number 4 SUPPLEMENTARY SHEET 70-734 Amendment No. 44 i
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 controlis 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.
%.B R E G S-6. Radiological Work Permits (RWRShhall be issue /dfor;all unplanned or non-routine work with lic material not covered by a WfThe RWP shall be signed by Health Physics management or a senior staff member before related work can commence. A serfdrJtaff member shall be a Health Physics Technician having a minitylum of 5 years' experience in radiation safety. An evaluation of the safety effectiveness of the per'mit shall be made upon comhletion 6f~the work.
N ih) A'h O S-7. Radiation safety trainin6, appropri te to the_em(p yee's needkshall be given to Radiation safetyQtrainingctrinai 5
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S-8. siihil be conducted by the Health Physics Manager or by a similarly qualified individual. The_Healtl% sics Mandger rnsy delegate training in that portion of the course to an individual who is uniquelp qua ified to present it.'
4 q p S-9. Continuous air sampling silaII,be conducted'in any ar flere licensed material can become airbome.
S-10. The location of air samplers shall $ oheckedlan$ ally 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.
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 i
significant change in parameters that may be affected by the release of radioactive materials into the environment.
. NRC FORM 374A U.S. NUCLEAR REGULATORY CoMMisSloN PAGE of 5 7 PAGES Ucense Number SNM-696 MATERIALS LICENSE Docket or Reference Number SUPPLEMENTARY SHEET 70-734 Amendment No. 44 l l
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 ir.corporated 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 can be released 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 of the license. '
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S-16. Release of equipment, facilities,'or packages to the 6arestricted area or to uncontrolled areas onsite shall be in accordance with the attached " Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Licenses for Byproduct, Source, or Special Nuclear Material," dated April 1993. / P,
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m 2x, jQ[ l S-17. Deleted by Amendment 37, September 1996 {he SVA faci}lity ha)
S-18.
released for general use.
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Notwithstanding the st'$temdritjn Sebi5I after each monthly test:oftpysten3 the criticalityp[4[,
if a!6rm point fails ;toNart the activateN of th'Ilicense within approximately 5 seconds.)more tfian bncepufof fodr trials 9)
Notwithstanding theQ h ,, f W S *,9. statements in Section 4.2.1.4, Part@Q of the license, no material handling shall be allowed in any area in which the required criticality,alaNn system is inoperative.
6 4gpy 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, or as further revised by the licensee consistent with the provisions of 10 CFR 70.32(i).
NRC FORC 374A U.S. NUCLEAR REGULATORY Commission PAGE 6 of 7 PAGEs Licmse Number SNM-696 MATERIALS LICENSE oocket or Reference Number !
SUPPLEMENTARY SHEET 70-734 1 Amendment No. 44 l
SAFEGUARDS CONDITIONS ,
SECTION 1.0 -- FACILITY ORGANIZATION Currently there are no license conditions in this section. The necessary information has been incorporated
-into an approved plan.
SECTION 2.0 - FACILITY OPERATION SG-2,1 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.
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SG-2.2 Deleted by Amendment K,\ September 1996/8 a plicable under a possession mly license. I
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SG-2.3 Deleted by Amendment 37, September 1996. Not appjcable under a possession only license.
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SG-2.4 Deleted by Amendment 37,' ptember 1996 - of appi able under a possession only license. j N I s s; 4 ,)
SECTION 3.0 - MEASUREMINTS ,
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SG-3.1 Deleted by Amen 8 men,l)7;Ssptd/M6996: licable under a posesion only license.
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l5 SG-3.2 Deleted by Amendment 37, September 'l9964Not applicable undu a possession only license.
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Ny f SG-3.3 Deleted by Amendment 37, September 1996. Nofapplicable under a possession only license.
SECTION 4.0 -- MEASUREMENT CONTkOLv g $ M SG-4.1 Deleted by Amendment 37, Septemoer 1996. Not applicable under a possession only license.
SG-4.2 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.
SG-4.3 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.
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 1996. Not applicable under a possession only license.
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.
NRC FORM 374A U.S. NUCLEAR REGULATORY CoMMisSloN PAGE of 7 7 PAGEs License Rumber SNM-696
' MATERIALS LICENSE Docket or Reference Number SUPPLEMENTARY SHEET 70-734 Amendment No. 44 SECIlORS.O -- INVENTORY SG-5.1 Deleted by Amendment 37, September 1996. Not applienble 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, September 1996. Not applicable under a possession only license, SECTION 7.0 -- INTERNAL CONTROft? c pS R E G f O f( g?,
SG-7.1 Deleted by Amendmerit 37, September 1996. Not applicable under a possession only license.
4 SECI1ON 8.0 -- MANAGEMENT', ;)
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SG-8.1 Deleted by Amenciment 37l Se'ptember 1996_j Not applibable under a possession only license.
c -3 ^p 27 SECTION 9.0 -- PHYSICAL PkOTECTIO'N REddlFiEskNTS FOR IORMULA QUANTITIES OF STRATEGI SEECIAL NUCf FAR MATERIAU j jlll't f'
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-y f; c _ p The licensee shall follow the measures desdrIbed in th'b physical protection plan entitled, " Fixed SG-9.1 Site and Transportatiofiflan for the PrStt '!on of Shecial Nuclear Material of Moderate and Low Strategic Significance," ddted May 1989, submitle"d by letter dated May 8,1989; and as it may be further revised in accordance%ith the pr6vis1bns 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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