ML20154J267

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Amend 11 to License SNM-696 for General Atomics,Authorizing Possession of 16 Triga Fuel Elements at Univ of Missouri
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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CNE -{ OF Daces (s 841 U.s NUCLs AO CsGULATC0Y Commission MATERIALS LICENSE j I 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, 'ql ! 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, 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 eff conditions speci0ed below. y l bcensee I General Atomics SNH-696, l 1.

3. Ucense numb" Amendment No. 11 i

I mr. 2, .I P. O. Box 85608 e i t gFgtg/', 4-December 31, 1989 l San Diego, California 921 4 C (/

5. Do:ket or "/ A i

Reference No. 70-734 y

6. Byproduct, source, analor cW
7. Chemical and/cr physical U Mastrnum amount that licensee I

special nuclear material form nay possess at any one tirne I N l /,.( ' ' D) '?7 Jgder thi.: License v k -f u Uraniumenriebin ik d[sh' ribe /.Mit A 985 kilograms of j I A. ticensee's Ou-235 l U-235 isotope ( tiportfonofthe)d'redto i_

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n .::a f 'a ., f!f {te$ $ ;of[.Mit licente n;} < i B. U-23.5 B: Anij lIl. % 5 kilograms of l ( [i ,;.U-233 p C. Plutonium C. Encapsulated arW or C. 3 kilograms total Pu Sealed Sources t 8 I,4 D. Plutonium D. Bred bu' inseparated D. I kilogram total Pu 4 !4 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. 'g4 b I No store than 1,000 grams of U-235 will be in the forts of UF

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-===----_------_=--= --==.-- _- ___.,ys._=--_-, = i N cFe<m n u U.S. NUCLE A2 CECuLATc;Y CoMMissio.1l m[l PAar 2 os 5 I L*n,e numtgr g I MATERIAIS LICENSE SNM-696, Amendment No, 11 f I SUPPL.EMENTARY SHEET g i 70-734 y \\ \\ p I ~ 'I i ,1 1 9. Authorized use: 'I I I l For use in accordance with statesents, representatione, and conditions contained j i in Part II "License Specifications" dated July 24, 1981, and svpplements dated 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 l March 9. (2), March 22 April 26, and September 8,1968. I l10.AuthorizedPlaceofUse: ) The licensee's San Diego, Cali Maktb hn Jay Hopkins Drive and 1 11220 Flintkote Avenue as spesi ed in the afores. lication and supplements. 'l 1 I (V I l11.Recordsofallsafetyrelatedreportsandanalysesshallp retained as follows: l Copiesofcriticalhy-andradiationsafetyanalysephahberetainedforat f jl least2yearsop/ fbr 6 monQs after a project i tgpfinatad, whichever is i a. i 4 1onger. ../ q .g ,i

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h j hl ~. b. Copies of all other safety-re ed reconis aplant al ations and I f additions, abneesal occurronc s' associated si radioactiv

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i audits and inspections, instMerfcaifbr /Al.A M fi s, training 1 t aM retraining, personnti exposemenrest(am m diatfen and' vironmental i 6 1 surveys) shall be retained.for' at 144st q.yedrs or ledger (P required by I 'l11' ; L A ?-8 1 h regulations. N 1 '4 i 1 1 j 12. Notwithstanding the statements in Sec'tfon 5.4.2'in' the License? Specification [ Volume (Part II), if double batching is not credible, the maximum safe batch size i 3 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 4[ 1 release of radicactive saterial, loss or damage of property, or 1 non-compliance with the license or a regulation. 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 nor o 5 mars I i i 11 m y l Leenu numter i h SNM-696 Amendment No. 11 ,1 MATERIALS LICENSE 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 l worb San commence. A senior staff member shall be a Health Physics Technician I 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

16. Radiation safety training, appro'pgi%te\\ d $r-pe's needs, shall be given to

'I l 3 g i t I all cew employees. L. ' (., ^4 I I lt Q*' lh jl

17. Radiation safety traini 4 and indoctrination shall be con ted by the Health il Physics Manager or by arsiellarly qualified individual.

1 ealth Physics l 1ll Manager may delegate, training in that portion of the cour,se M.anindividualwho l i 's I 1s uniquely qualif tetf,to pressets it. /ff J ?t) \\N .I f 18. Continuous air saaHing shall b'e coiduct46.in an'y area where I9ensed material I I canbecomeairborng [/ \\ 2 g e

19. The location of a> samplers shalP bg checked'amneally and when@f work area air er any process y

l 1 or equipment changes $are made tor verify)ther represe6tativeness o a 1; 1 sagling. In addition, the location aq aid sasyters shall be chitcked at the 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 I p 1 4 A-

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

i l Radiological Contingency Plan submitted to the Commission on May 25, 1984, and I i supplement:<d on August 22, 1964. The licenses shall also maintain implementing )' 3 i procedures for his Radiological Contingency Plan as necessary to implement the i i Plan. The Plan shall be fully implemented by February 12, 1985. This l 4 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 l Planning and notification procedures. The Itcensee shall make no change in his I j Radiological Contingency Plan that would decrease the response effectiveness of j j i l i the Plan without prior Commission approval as evidenced by a license amendiment. 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 ton of Industrial [l l and shall furnish the CMaf, Fuel Cycle Safety Branch, i and Medical Nuclear Safety, ! MSS, U. S. Nuclear Regulator <

ission,

,f a'nd the appropriate NRC Regional 0ff ppecified in Washington, DC 20555,,hrt 20, a report containing scriptida of each change i i Appendix D of 10 CFA l x l within 6 months aftes the che is made. / I li N Q / C I f[l

24. At the end of plant life, the-11 n&esshalfd4 nate therWte and facilities, l

authorized as a place of use for.speciel nutlear terial, in Wcordance with the i f general decommissioning plan submMed by your~.htter deted JMf 25,1986, and its 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 3 1, available for decossissioning the factMijJ provided by,1stterdated September 10, I l 1986, is hereby incorporated as a condities of the Ucense. -g

25. Notwithstanding the statements made in Sectfsn 4.3Iof the revised application li f

dated November 1983, the release of tho' facilities and equipment for unrestricted t 1 use from the plant site or to unrestricted areas onsite shall be in accordance t i 1 with the enclosed Annex C, "Guidelines for Decontamination of Facilities and F I i 1 Equipment Prior to Release for Unrestricted Use or Termination of Licenses for f By-product, Source or Special Nuclear Haterial", dated July 1982. [ 1 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 to materials held in the SV-A building under this license subject to the following: [ 1 a. The criticality alare system shall be in service in all areas where the [ I j 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 I[l 3 b. There shall be no movement of any special nuclear material (SNM) into, out of, 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

s' W "._ E* "J"L"M M "_M * * "_m. AE M , 0 N c poem 3H4 U.S. NUCLE AR REoVLATcCY CoMWS$loN l p7ag c;, r*o g I l Lxen,e numtwr g MATERIALS LICENSE .S h21-69_6 Amendpent No, 11 I 3 l SUPPLEMENTARY SHEET i 4 70-734 y li i I -l l l27.NotwithstandingthestatementinSection4.2.1.4,PartIIofthelicense,the 1 trip levels will be readjusted after each monthly test of the criticality alarm b system if the alare point fails to activate within approximately 5 seconds, more l j 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 l i storage areas in the SV-A Build @$7RIGA fdel cahufacturing building, and in 'I I the GA Hot Cell possessingrfi.NJMe and/or other ra196ap$1ve material, during a I period of reduced activiMes/as specified in the appliblityn dated April 23, 1985, I [l subjecttothefollowingsodification): l h Thesurveyfrequenhasandcontaminationcontrolmeasurhspecifiedinthe. a. 1 license shall by*Gled'wheriner work iw perforst orbo'r win equipment which l I handles radioacidhe materk Qf I ),.

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/qr C I il Any work performed on equipee , hich hand 7ed radioactive u 0 authorized by and performed'u der a radfati6riwork permit. gerials shall be b. y All openings of, ventilation' doc %t.s, a n+ ace lo. - + -oerd which are ndt cospletely i 1 1. c. 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 8 j, is maintained. -l d. If air sample results indicate an increase in airborne contamination to l 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 The Manager, Nuclear Safety, or his designee shall perform a criticality e. 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 of Missouri for purpose of packaging the elements for delivery to a carrier as t i 1 specified in the amendment application dated September 8, 1988. k i 1 k l FOR THE NUCLEAR REGULATORY COM ISSION [ i l Original Signed Br l 1 SEP ! 6 7998 b 1 Date: By: Leland C. Rouse I l 1 Division of Industrial and f Medical Nuclear Safety [ j /. j q washiastoa. oc ansss ygg g v y k 1 9 l !,W l i i I 4 -.}}