ML20154J267
| ML20154J267 | |
| Person / Time | |
|---|---|
| Site: | 07000734 |
| Issue date: | 09/16/1988 |
| From: | Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20154J265 | List: |
| References | |
| NUDOCS 8809220300 | |
| Download: ML20154J267 (5) | |
Text
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! MATERIALS LICENSE j Pursuant to the A tu.,ic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93 -433), and Title 10, I
! Code of Federal Regulations, Chapter I, Parts 30,31,32,33,34,35,40 and 70, and in reliance on statements and representauons heretofore made t y the licensee, a license is hereby issued authonzing the licenses to receae, acquire, possess, and transfer byproduct, 'ql source, and special nuclest material designated below; to use such material for the purpose (s) and at the placcis) designated below;to 'I deliser or transfer such material to persons authorized to receive it in sceordance wi h the regulations of the applicable Part(st T1is ~1 license shall be deemed to contain th conditions specined in Section 183 of the Atomic 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 effe conditions speci0ed below. y bcensee l
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- 1. 3. Ucense numb" SNH-696, General Atomics l Amendment No. 11 i mr. I 2, '
P. O. Box 85608 e .I San Diego, California 921 4 C i t gFgtg/', 4- December 31, 1989 l (/ 5.Reference Do:ketNo.or "/<A 70-734 i y
; 6. Byproduct, source, analor special nuclear material cW N
- 7. Chemical and/cr physical U Mastrnum amount that licensee I I
, form . . , nay possess at any one tirne v '?7 Jgder thi.: License l
D) k /, .( -f ' ' u A. Uraniumenriebin ik d[sh' ribe /.Mit A 985 kilograms I of j l U-235 isotope ( ticensee's Ou-235 , i_ - tiportfonofthe)d'redto
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I,4 D. Plutonium D. Bred bu' inseparated D. I kilogram total Pu 4
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E. Plutonium E. Plated calibration E. 5 grams total Pu y source > F. Plutonius F. Solutions, precipitates F. 5 grams total Pu > e and solids l t ad b.
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b I No store than 1,000 grams of U-235 will be in the forts of UF 6* I4 > 0809220300 000916 ' PDR ADOCK 07000734 I C PNV b
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i N cFe<m n u I U.S. NUCLE A2 CECuLATc;Y CoMMissio.1l L*n,e numtgr PAar 2 os 5 m[l g SNM-696, Amendment No, 11 I MATERIAIS LICENSE " * "
- f I SUPPL.EMENTARY SHEET g i 70-734 y
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'I I ,1 1 9. Authorized use: 'I I I l For use in accordance with statesents, representatione, and conditions contained in Part II "License Specifications" dated July 24, 1981, and svpplements dated j
i i l March 16, snd Dacomber 24, 1982; February 4, Novesbar 14, and Novesbar 15, 1983; i i April 10. April 12, June 28, September 4, and September 7,1964; December 5,1985; i I May 23, September 25, and Deceeber 10, 1986; December 21,1987; March 4 I March 9. (2), March 22 April 26, and September 8,1968. I l l10.AuthorizedPlaceofUse: ) 1 1 The licensee's San Diego, Cali Maktb 11220 Flintkote Avenue as spesi ed in the afores. hn Jay Hopkins Drive and lication and supplements.
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I (V l11.Recordsofallsafetyrelatedreportsandanalysesshallp retained as follows: l
. a. Copiesofcriticalhy-andradiationsafetyanalysephahberetainedforat f jl least2yearsop/ fbr 6 monQs i q after a project i tgpfinatad, whichever is i
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Copies of all other safety-re ed reconis
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b. additions, abneesal occurronc s' associated si radioactiv releases, l i audits and inspections, instMerfcaifbr . /Al.A M fi s, training 1 6 t aM retraining , personnti exposemenrest(am m diatfen and' vironmental i 1 surveys) shall be retained.for' at 144st q.yedrs or ledger (P required by ' I h regulations. . .
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'4; L A ,% i j 12. Notwithstanding the statements in Sec'tfon 5.4.2'in' the License? Specification [
3 Volume (Part II), if double batching is not credible, the maximum safe batch size i
- 1 shall be no more than 75 percent of the minimum criti;al mass independent of thJ t 1 degree of water moderation aM reflection. However, when the Th/U atoete ratio I i l 1 is > 3.6 and the N/U < 20, ... maximum safe batch size may be increased to 790 g i i contained U-235 independent of whether double batching is credible.
[ l13.TheDirectorQACD,uponrr amendation of the appropriate manager within h' i QACD, shall have authority to require immediate termination of activities t 1 and/or corrective action in any situation which, in their judgment, could t f 1 lead to the unnecessary exposure of personnel to ionizing radiation, t 1 release of radicactive saterial, loss or damage of property, or 1 non-compliance with the license or a regulation. 4[ l14.TheCriticalityandRadiationSafetyCosmittee(CRSC),functioningasanALARA f 1 Committee, shall meet at least annually to review (1) reports of audits and t 1 inspections performed since the last ALARA review and (2) employee exposures and C 1 ef tiuent release data to determine (a) if there are any upward tWnds developing in t j personnel exposures for identifiable categories of workers, types of operations, or (
, ef fluent releases, (0) if esposuns and releases might be lowered in accordance with ;
4 the ALARA concept, and (c) if cauipment for effluent and exposure control is being [ 1 prcperly used, maintained, and inspected. t 3 i i . I i l I : [ l . s
i i nor o 5 mars I i 11 m y i l Leenu numter MATERIALS LICENSE SNM-696 Amendment No. 11 ,1 h ' """"" ' l SUPPLEMENTARY SHEET ll 70-734 y I 'I I I I I I The CRSC evaluation, recornendations, and corrective actions shall be 1 l documented and the report shall be sent to the appropriate operations J g managers and the Vice President Finance and Administration. y i I i 13. Radiological Work Permits (RWPS) shall be issued for all unplanned or i 1, non-routine work with licensed material not covered by a WA. The RWP shall I I be signed by Health Physics management or a senior staff member before related I worb San commence. A senior staff member shall be a Health Physics Technician I l i havi'.' a minimum of 5 years' experience in radiation safety. An avtluation of j q the safety effectiveness of the permit shall be made upon completion of the work, g 3 cs g l 3 i 16. Radiation safety training, appro'pgi%te\t d $r- pe's needs, shall be given to 'I I all cew employees. . L. ' (., ^4 I I lt 17. Radiation safety traini 4 Q*' lh and indoctrination shall be con ted by the Health ill Physics Manager or by arsiellarly qualified individual. 1 ealth Physics jl l i Manager may delegate, tetf,to training pressetsinit.that portion of the 's cour,se M.anindividualwho 1ll 1s uniquely qualif I J ?t) \N I f 18. Continuous air saaHing shall b'e coiduct46.in
/ff an'y area where I9ensed material
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- 19. The locationchanges or equipment of a> samplers
$are made shalP bg checked'amneally tor verify)ther and owhen@f work area air represe6tativeness a 1;
sagling. In addition, the location aq aid sasyters shall be chitcked at the 1 a I commencement of operations in any area tBati han> been shutdown fdr more than I j 6 months to verify tha representativeness of! ate sampling. l l 20. The laboratories in which plutonium in a rtispersible form say be used shall have f 4' exhaust ventilation systees separate free other building exhausts and shall provide 4 dual HEPA filtering of the effluent air. p 4 > 1 > l21.NotwithstandingthestatementsmadeinSection4.1.5oftherevisedapplication dated November 1983, the licensee shall conduct leak testing of sealed plutonium 1 sources and alpha sources in accordance with Annex A. "License Condition for Leak , , 4 Testing Sealed Plutonium Sources," dated November 1979, and Annex B. "License p 4 Condition for Plutonium Alpha Sources," respectively. > t > 1 > l22.ThelicenseeshallprepsreandsubmittotheChief,FuelCycleSafetyBranch, Divisicn of Industrial and Medicci Nuclear Safety, NMSS, U. S. Nuclear Regulatory 4 Commission, Washington, DC 20555, a report whenever there is any new residential ' 4 development within one mile around the site that constitutes a significant change 4 in parameters that may be affected by the release of radioactive materials into p 1 the environment. 1 > 1 > 4 > 4 D 4 D 1 > 1 > 1 9 p I 1 > 4 A-
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g I h MATERIALS LICENSE -Sg g 9 M ,*,n g t No 11 l '
$UPPLEMENTARY $HEET i \ l l I l l l ,1 1 23. The licensee shall implement,' maintain and execute the response measures of his I i I
3 l i i Radiological Contingency Plan submitted to the Commission on May 25, 1984, and supplement:<d on August 22, 1964. The licenses shall also maintain implementing procedures for his Radiological Contingency Plan as necessary to implement the
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i , 4 i Plan. The Plan shall be fully implemented by February 12, 1985. This l l l Radiological Contingency Plan and associated implementing procedures supersede i i the amergency planning requirements of 10 CFR 70.22(1) as they refer to onsite 1 l Planning and notification procedures. The Itcensee shall make no change in his I j j l i Radiological Contingency Plan that would decrease the response effectiveness of j ! i the Plan without prior Commission approval as evidenced by a license amendiment. l l lI The licensee may make changes to hiso ladf41egtee Contingency Plan without prior i I Commission approval if the changet'ehot dtcret tpe respocas effectiveness of I t I the Plan. The licensee shalkastntain records o As a that are made to the 1 l
' I Plan without prior approvabfor a period of 2 years f date of the change I .
l and shall furnish the CMaf, Fuel Cycle Safety Branch, i ton of Industrial [l and Medical Nuclear Safety, ! MSS, U. S. Nuclear Regulator < ission, , ,
,f a'nd the appropriate NRC Regional 0ff ppecified in .
i l Washington, Appendix D of 10DCCFA 20555,,hrt 20,x a report containing scriptida of each change i , within 6 months aftes the che l is made. / I li ,, N Q / ; C nate therWte and facilities, I '
; 24. At the end of plant life, the-11 n&esshalfd4 l i
f[l f authorized as a place of use for.speciel nutlear general decommissioning plan submMed by your~.htter deted JMf 25,1986, and its terial, in Wcordance with the , i l 1, supplement dated October lit, 1985',vse,;thehthese foi:llities anebrounds can be a I released for unrestricted use The cometqtes coenitment* that f#nds will be made i 1, available for decossissioning the factMijJ provided by,1stterdated September 10, I 3 1986, is hereby incorporated as a condities of the Ucense. g - l f 1
! 25. Notwithstanding the statements made in Sectfsn 4.3Iof the revised application dated November 1983, the release of tho' facilities and equipment for unrestricted use from the plant site or to unrestricted areas onsite shall be in accordance li t
t , i 1 with the enclosed Annex C, "Guidelines for Decontamination of Facilities and F - 1 Equipment Prior to Release for Unrestricted Use or Termination of Licenses for I i f 1 By-product, Source or Special Nuclear Haterial", dated July 1982. [ t 1 26. The licensee is hereby exempted from the provisions of 10 CFR 70.24 during the t
- 1 modification of the SV A criticality alars systes insofar as this section applies I !
j 1 to materials held in the SV-A building under this license subject to the following: [ I j a. The criticality alare system shall be in service in all areas where the [ l 1 quantity of special nuclear satorial (SNM) does not meet the exemption criteria y ! 1 in Section 4.2.1.4 of the specification volume with the exception of the SNM i 1 storage vaults in the SV-A building, t ' l 1 t , There shall be no movement of any special nuclear material (SNM) into, out of, I [l 3 b. l or within the SV-A building S W storage vaults while the criticality alarm l 3 systes is not in service. g j 1 I l 1 i i ' 1 i j 1 > I i i n l ! i i . i i _ __ _ E _ ___ _ _ . _ _ _ _ . _ _ . . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ l__._
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, 0 N c poem 3H4 U.S. NUCLE AR REoVLATcCY CoMWS$loN l p7ag $ c;, $ r*o g I l Lxen,e numtwr g
.S h21-69_6 Amendpent No, 11 I
! MATERIALS LICENSE "
3 l i SUPPLEMENTARY SHEET ! 4 70-734 y li i I -l l 1 l27.NotwithstandingthestatementinSection4.2.1.4,PartIIofthelicense,the trip levels will be readjusted after each monthly test of the criticality alarm b j system if the alare point fails to activate within approximately 5 seconds, more l l than once out of four trials. ; I I I 28. Notwithstanding the statemen'.s in Section 4.2.1.4, Part II of the license, no I i material handling shall be allowed in any area in which the required criticality I l alare system is inoperative. l l 29. The licensee may reduce the radiation safety, nuclear criticality safety, and l l environmental surveillance requireseets within thq HTGR fuel fabrication and i i storage areas in the SV-A Build @$7RIGA fdell cahufacturing building, and in 'I I the GA Hot Cell possessingrfi.NJMe and/or other ra196ap$1ve material, during a I I period of reduced activiMes/as specified in the appliblityn dated April 23, 1985, [l
; subjecttothefollowingsodification):
Thesurveyfrequenhasandcontaminationcontrolmeasurhspecifiedinthe. l h a. ! 1 license shall by*Gled'wheriner work iw perforst orbo'r win equipment which l I handles radioacidhe materk
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, hich hand 7ed radioactive u 0 ily b. Any work performed on equipee authorized by and performed'u der a radfati6riwork permit. gerials shall be 1 : ,
- 1. c. All openings of, ventilation' doc %t.s, a n+ ace lo. - + -oerd which are ndt cospletely i i sealed shall be maintained.with a sinf>us airflow.ref 25 LFMP The licensee i 1 shall determine, on at least'a semiannual basis, that this rinimum airflow I j, is maintained. -l , .
8 l d. If air sample results indicate an increase in airborne contamination to l 1 10 percent or more of the appropriate HPC, survey frequencies shall be p 1 increased to the levels specified for Type II laboratories, p 1 > i
- e. The Manager, Nuclear Safety, or his designee shall perform a criticality l inspection, at least annually, of all areas specified. [
1 > 1 30. The Itcensee is hereby authorized to possess 16 TRIGA fuel elements at the University g i i of Missouri for purpose of packaging the elements for delivery to a carrier as t k 1 specified in the amendment application dated September 8, 1988. i > 1 k l FOR THE NUCLEAR REGULATORY COM ISSION [ i l Original Signed Br l 1
- SEP ! 6 7998 By: Leland C. Rouse b 1 Date: I l 1 Division of Industrial and j Medical Nuclear Safety [
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