ML20195B831
| ML20195B831 | |
| Person / Time | |
|---|---|
| Site: | 07000734 |
| Issue date: | 11/01/1998 |
| From: | Emeigh C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20195B830 | List: |
| References | |
| NUDOCS 9811160292 | |
| Download: ML20195B831 (8) | |
Text
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A R PAGES U.S. NUCLEAR REGULATORY COMMISSION MATERIALS LICENSE Pursuant to the Atomi$ Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10, Code of Federa L 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 matenal for the purpose (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). 'lhis license shall be deemed to contain the conditions snecified in Section 183 of the Atomic Energy Act of 1954, as amended, and is subject to all applicable rules, regulations, and orders of the Nuclear Regulatory Commission now or hereafter in effect and to any conditions specified below.
Licensee l
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- 1. General Atomics 3. License Number SNM-696, Amendment 51 I
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- 2. P.O. Box 85608 4. Expiration Date December 31,1989 San Diego, Califomia 92186-9784 5. Docket No.70-734 l g gg, ,
Reference No.
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- 6. Byproduct Source, and/or 8 N . Maximum May Possess amount at Any One that Time Licensee Special Nuclear Material
@D(,jChemical and/or Form Physical O under This License A. Uranium y ;A. riched up toll /} AS 200 kilograms U-235 Lv l
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< {" 235 / 3 )O.4 o l B. Uranium l-- JB. y W , B.13ss than 5000 gm*
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, ' C. U-233 ' W C.' m p eh"[ C2 Less than 2000 gm yf (
41 6 U-233*
D. Plutonium Encapsulated ndM D. Less than 2000 gm l
O. hi$x1 pup total Pu*
i L E. Plutonium E. Bred but unsoparated E. Less than 1000 gm l total Pu*
l F. Plutonium F. Plated calibration F. Less than 5 grams j source total Pu*
I G. Plutonium G. Solutions, precipicates G. Less than 5 grams i solids and total Pu*
i 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 = grarns U-235 in uranium enriched to 20% cr more plus 2.5 (grams U-233 + grams plutonium)
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NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION PAGE 2 of 8 PAGES l.icense Number SNM-696 l
' MATERIALS LICENSE Docket or Reference Number SUPPLEMENTARY SHEET 70-734 l
Amendment No. 51 i
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- 9. Authorized place of use: The licensee's San Diego, Califomia site as specified in the aforesaid application and supplements.
I
- 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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FORdE NUC REGULATORY COMMISSION
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D;te:D ad.I,I W By: C arl W'.Em g hief Division cf Fuel Cycle Safety and Safeguards, NMSS Washington, DC 20555 (Provided w/ Amendment 31)
Enclosures:
- 1. License Condition for Leak Testing Sealed Plutonium Sources, dtd 4/93 e
- 2. License Condition for Plutonium Alpha Sources, dtd 4/93
- 3. Guidelines for Decontamination of Facilities..., did 4/93 s.
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I NRC FORM 374 A U.S. NUCLEAR REGULATORY CONIN11SSION PAGE 3 of 8 PAGES License Number SNM-696 !t MATERIALS LICENSE D eket r Reference Number k SUPPLEMENTARY SHEET 70-734 j Amendment No. 51 i
l SAFETY CONDITIONS i 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 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, j 1986; December 21,1987; March 4, March 9 (2), March 22, April 26, August 22, September 8, and j 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 15x19,92 July 12 and August 23,1994; Group 6 Laboratories i unrestricted use request dated AugyhtM2,N990 gch 1,1995; Group 7 Laboratories unrestricted use ;
request dated December 5,11;K}5;' Group 8B Laboratories unrestricted use request dated August 23,
~
l 1996; October 15,1996; Agdl 30,1997; Group 9 Laborat ries uniestricted use request dated July 17, 1997; Building 30 Laboratories unrestricted use release d July 25,1997; and January 29,1998; l Site Decommissioning pen d(t October 11 and cem 5,1996; April 18,1997; January 15, 1998; Hot Cell Decommissioni an dated April 998, fa Building 27 Roof releap dated { ft 25(end g 30 -g(oup 10 Labs dated Augus ase 11 dated September 4,1998.
S-2. Records of all safety-rhte[rgp rY shall,be re$ned as follows:
- a. Copies of criticality'3tnd r lio ys all retained for at least 2 years or for 9
h 6 months after/ a p%ct is!teri@ iia {W E g,IIer is lper.
- b. Copies of all other saf erplated recoids (e.g.,alterationsplah. N and additions, abnormal occurrences associated withgdioactivity regl gises, audits and inspections, instrument calibrations, ALARA findings, training and tetidinidg,Mrsonnel exposures, routine radiction 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 apprcpriate 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, re' ease of radioactive material, loss or damage of property, or nol-compliance with the license or a regulation.
NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION PAGE 4 of O PAGES License Number SNM-696
' 51ATERIALS LICENSE Docket r Reference Number SUPPLEMENTARY SHEET 70-734 Amendment No. 51 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.
.cp3 Reef, S-6. Radiological Work Permits (RW material not covered byRWP
. The a @J8J shall be shall be signedpy Healthissued logall unplanned Physics management or a senior or n staff member before related work can commence. A sengtaff member shall be a Healin Physics Technician having a mipumloQ' years' experience in radf 1,3 ion safety. An evaluation of the safety effectiveness of the perniit shall. rqade upon t- sq 4 ion oL(he C work.
S-7. Radiation safety trainih, ejitnj approdrifty l ['s nee ;t shall be given to all new employees.
S-8. Radiation safety trainik an c d dlYa e et by the Health Physics Manager or by a similarly qualified indiviSal. 'T$t'j LF r
er pu delegate training in that portion of the course to an individual is(in esentM2 y W S-9. Continuous air sampling sh conduc hir$ any ar here licensed material can become airborne.
S-10. The location of air samplers shall h dkeakedMnkally 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 ac. ions 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 Commisdon, 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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l NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION PAGE 5 of C PAGES License Number SNM-696
' ' MATERIALS LICENSE D cket r Reference Number SUPPLEMENTARY SIIEET 70-734 Amendment No. 51 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 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 condition8of the license.R EG S-16. Release of equipment, facilities ackages to th t e,stricted area or to uncontrolled areas onsite shall be in accordance withgth attached " Guidelines fer- . contamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of L ses for Byproduct, Source, or Special 993.
Nuclear Material," 4/ dated 4pril]Q jh<.> .
2 has been decommissioned and S-17. released Deleted byuse.
for general Amendmerh7, s
- b i)Sepf Jj { (pr f996! T 8VA faci S-18. Notwithstanding the s em nS Of[ D ar ' f th license, the trip levels will be readjusted after each monthly tests the crMpaQ t'he ppa'rm point fails to activate within approximately 5 secondpore thag oncept, r trialp ,
1~ N S-19. Notwithstanding the state in Sectioh's 9 4.2.1.4, PaQ of the license, no material handling shall be allowed in any area in which t e rguired criticagalarm system is inoperative.
Y*Y S-20. Deleted by Amendment 37, September 1996. The SVA facility has been decommissioned and released for general use.
S-21. Defated 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(l).
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.
l S-25 The licensee must submit for review and approval to NRC residual contamination and characterization data and planned decommissioning procedures for areas where i
NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION PAGE 6 of Q PAGES License Number SNM-696
' MATERIALS LICENSE D eket r Reference Number SUPPLEMENTARY SHEET 70-734 Amendment No. 51 1
- 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 Decomraissioning Plan dated October 11,1996, as amended December 5,1996; April 18,1997; and January 15, 1993;
- 2. Workers would be entering areas where surface contamination and radiation levels are significantly higher than routinely encountered during previous decommissioning operations;
- 3. Procedures could result in significantly greater airborne concentrations of radioactive materials than have been present in previous decommissioning operations; or
- 4. environment Procedures could than thojs es result ig'sociated with previous decommissioni Y
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I NRC FORM 374A ' U.S. NUCLEAR REGULATORY COMMISSION PAGE 7 of 8 PAGES l 5 Liceme Number l t
SNM-696 b ' MATERIALS LICENSE DocW w Refunce Number
, SUPPLEMENTARY SHEET 70-734 Amendment No. 51 SAFEGUARDS CONDITIONS SECTION 1.0 - FACILITY ORGANIZATION Currently there is no license condition in this section. The necessary information has been incorporated into en approved Fundamental Nuclear Material Control Plan, dated February 1998.
1 SECTION 2.0 - FACILITY OPERATION SG-2.1 Deleted by Amendment 37, Septemg 1996. Not applicable under a possession only licensa.
SG-2.2 Deleted by Amendment p ember 99 40 pplicable under a possession only license.
SG-2.3 Deleted by Amendmektt 37, September 1996. Not kcable under a possession only license.
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SG-2.4 Deleted by Amepnt SQ terntgr 19 appligble under a possession only license.
SECTION 3.0 - MFASUREh8NTS ( 1 0 3 SG-3.1. Deleted by Amen nk EEi1 ble under a possession only license.
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SG-3.2 Deleted by Amendhjd t 54 l
d y1 ot a ble under a possession only license.
SG-3.3 ' Deleted by Amendmerk, Sept 1 96. plicable under a possession only license. ,
SECTION 4.0 - MEARllREMENT CON Od W M SG-4.1 Deleted by Amendment 37, September 1996. Not applicable under a possession only license. 4 SG-4.2 Deleted by Amendment 37, September 1996. Not applicable under a posseasion 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.
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.
v SG-4.8 . Deleted by Amendment 37, September 1996. Not applicable under a possession only license.
,NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION PAGE Q of Q PAGES License Number SNM-696
' MATERIALS LICENSE D eket r Reference Number SUPPLEMENTARY SHEET 70-734 Amendment No. 51 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 applicabie under a possession only license.
SECTION 6.0 - RECORDS AND REPORTS SG-6.1 1996. Not applicable under a possession only license.
GECTION 7.0 - INTERNAL 9 8 CONTROLb .6 Deleted by Amendment a
SG-7.1 Deleted by Amendmsht 37, September 1996. Not cable under a possession only license.
SECTION 8.0 - MANAGEMEfD sn % s
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SG-8.1 Deleted oy Amefent(Dbet119 .
- 37. ' dot appii ble under a possession only license.
SECTION 9.0 - PHYSICAL MOTk lOkRNI b k ORJORMULA QUANTITIES OF STRATEGIC SPECIAL NUCf'kAR-lhTERihL .
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SG-9.1 The licensee sha!! f the(mea , %,'dei physical protection plan entitled, " Fixed Site and Transportatio Pjpn for the action cial Nuclear Material of Moderate and Low Strategic Significance," dategiay 1989 by letter dated May 8,1989; and as it may be further revised in accordance wi0tthkprM, /is ons of 10 sujpi 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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