ML20149F762
| ML20149F762 | |
| Person / Time | |
|---|---|
| Site: | 07001100 |
| Issue date: | 01/04/1988 |
| From: | Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20149F707 | List: |
| References | |
| NUDOCS 8801140324 | |
| Download: ML20149F762 (3) | |
Text
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_ _-- --- _-- y T NRQ Form 374
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PA OF Pacts g 15 04 U.S. NUCLE ARREGULATdRY COMMISSlo'N g
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MATERIALS LICENSE g
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Pursuant to the Atomic Energy Act of-1954, as amended, the Energy Reorganization Act of 1974 (Public Lawl93 -438),and. Title 10, f
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Code of Federal Regulations, Chapter I, Parts 30,31,32,-33,34,35,40 and 70, and in reliance on statements and representations -p h'eretofore made by the licensee, a license is hereby issued authorizing the licensee to receive, acquire, possess, and transfer byprodtret, ' y
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source, and special nuclear material designated below; to use such material for the purpose (s) and at the place (s) designated below; to li deliver or transfer such material to persons authorized to receive it in accordance with th'e regulations of the applicable Part(s). This N
license shall be deemed to contain the conditions specified in Section 183 of the Atomic Energy Act of 1954, as amended, and is N
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N subject to all applicable rules, regulations and orders of the Nuclear Regulatory Commission now or hereafter in effect and io any a
conditions specified below.
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Combustion Engineering, Inc.
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C-E Power Systems Amendment No. 11 5
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06095,Q.[V."\\'
2-E sf 1000 Proposect Hill Road
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February 29, 1988 l
Windsor, Connecticut h
- 5. Docket or N
h Reference No.
70-1100 g
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- 6. Byproduct, source, and/or
- 7. Chemical and/or physical
(.e8. Maximum amount that licensee CQ k 4, hay possess at any one tim special nuclear material form jfp, der this license
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A(.Cofcontainedu 2
m y A5 0,xid'ef,. po'wder jellets, 20,500 kilograms
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Uranium enrich to y
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Uranium enrich [d to h,y.Y A h 3 k;h"m a 1'[ B.Q: 4,800 grams contained
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<20 wt.% U-235 V ' "?
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Q 1; b[#fASy/ L J. -Ah IC? 10,000 kilograms C.
Natural and/or M
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total uranium
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Pu-238 O.
Encapsulated D.
5 sources, each neutron sources containing less than 2.0 grams Pu-238 ;
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160 micrograms l
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n as analytical 1
samples IrI!
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Uranium enriched in F.
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!g,t the U-235 isotope encapsulated U 0 containing less M
38 sources than 1.7 grams U-235 at any
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Uranium enriched.
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liOOO g U-235 s
more than 19.99 w/o U-235_
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--q T NRc Form 374A U.S. NUCLEAR REGULATORY COMMISSloN 2-4 g
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Lkense number SNM-1067
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MATERlhLS LICENSE Amen n N. 11_
_ N SUPPLEMENTARY SHE ET-
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. N O 4 1988
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9.
A~uthorized Use:
For use in accordance with statemen_ts, representat_ ions, and i
conditions contained in Part 1 of the -licensee's revised applicat. on dated y
l May 14, 1982, and supplements dated March' 23, September-16, and October 4, h
l 1982; September 16, and October 23, 1983; April 5, June 19, September 12, and y
i November 30, 1984; May 16, July 25, September 23, and December 16, 1985; E
N March 18, May 19, and June 20, 1986; and January 20, February 18, March 18, W
July 24, and December 15, 1987.
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- 10. Authorized Plar' of Use:
The licensee's existing facilities approximately 5 miles i
northwest of Windsor, Connecticut, as described in the referenced application.
N 11.TheNuclearSafetyCommitteememyerfo,rhpsht'anttotheCommitteewhoperformsthe N
independent criticality safety edidw shalPmeetilhe minimum qualifications of the I
l Nuclear Criticality Speci61jht@and shall neither be.tife. person who is authorized to conduct the monthly crgda'lity audits nor be the initipl reviewer.
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- 12. The Nuclear Safety Co,m.h.ttee member or consultant who perTppps the independent i
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radiological safet avi g all meet the minimum qualificat'ipns for the Manager l
Health Physics, an hallnet; be the person wh6his5 autherized to conduct the monthly radiologic safety ah nor be_the 'n'i.t'ihl reviewem) l F
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- 13. RESERVED.
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,2:5 of' the rpy, sed application dated d
- 14. Notwithstanding this statementsJad n Section i
ii.y/peErei$h'all'evalbstethe, individual'sinternall d
May 14, 1982, byOune30g19837.rth'e
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exposure to airboin'e radpi yny id'ne sajling data which are rsat.hin@ip'resence, in the work area where Q[q qriddaof his obtainedbycontinuTussamp p$d,MI,ftpemanentlyDiounted air sampling the unclad radioactive materi !s g
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'df equipment is used tVdetermTnIthe breathin'g, zone"air concent' ration levels, the i
k licensee shall evaluatecits representativeness 'atl-least onie' every 12 months and M
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whenever any licensed process or equipinent' change 'is madel.
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- 15. When the monitoring of airb;orne. concentration ofgradioactivity is required as j
specified in 10 CFR 20.103, theiair/ coo.centrationiof radioactivity in the Nuclear i
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Laboratories shall be analyzed within 24Thotifs after each operating shift.
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- 16. The licensee shall conduct a leak test on all encapsulated sources in accordance l
l.i with the attached Annex A, "License Condition for Leak Testing Sealed Source Which l
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Contains Alpha Emitter."
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- 17. Notwithstanding the statements made in Section 3.2.8.2 and Section 3.2.8.3 of il page I.3-14 and page I.3-15, respectively, of the application, revision 2, dated April 6, 1982, release of equipment and material from the plant to offsite for 9
unrestricted use or from contaminated to clean areas onsite shall be in.accordance l,
'with the attached Annex,8', dated'J_ufy 1982.
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'y-18. The instruments measuring -the liquid-waste lev'el in-each dilution tank prior-to ~
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d discharge to the Farmington River shall be calibrated at least annually.
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NRC Form 374A U.S. NUCLEAR REGULATORY CoMMISSloN 3
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R ucense nwnder SNM-1067 l
l Amendment No. 11 I
MATERIALS LICENSE i
SUPPLEMENTARY SHEET i
70-1100 j
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JAN 0 41988 l
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- 19. Notwithstanding the statements in Section 5.1.3, page'I.5-2 of the application, i
I revision 2 dated April 6, 1982, all wastes contaminated with radioactive material l
to levels in excess of limits specified in Annex B shall be packaged in accordance y
with the requirements of 10 CFR 71 and disposed of at a licensed radioactive burial l
g ground.
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- 20. The licensee shall take the following action on plant gaseous effluent releases:
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l (a) If the radioactivity in the plant gaseous effluents exceeds 18 pCi gross alpha activity in total uranium per calendar quarter, the licensee shall, within l
g 30 days,prepareandsubmittotheCo f
j causeforexceedingthelim).t,,and}thhpsignareportwhichidentifiesthe g
Ifthepa(i,veactionstobetakenbythe corrdc l
f licensee to reduce rel ramete.rs important to a dose assessment change, asr, ease,ra"es.eport shall be submitted wiltiin 30 days which describ s
l the changes in parameters and includes an estimate of the resultant changes f
in parameters andcincludes an estimate of the resultantfci ange in dose h
commitment.
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(b)Intheeventth'aythecal'e(ateddosetoanymemb'er'ofthepublicinany i
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consecutive Ipmonth perisddi,s about;diate 'te'psdo reduce em,1ssio h
N 190.10, the licensee shalT'ta imms b
comply with 4 FCFR 190.1d^."
rov'igdhn O y 190.11,gthe licensee may 3
petition the Nuclear Regu o
C6/nmi ssio ota, variance"D~omtherequirements i
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of 40 CFR 190M.
I$afpetit:io fo_rgajvargaitjs^is',anticipped, the licensee y
a shall submit the requehtkat~lca
'90rdays p,rior tosex6eed 4 the limits specified v
s in 40 CFR 190.1 7
- 21. The licensee shall nidi'ntain[alidiqxec hsponspfmeasuhofhisRadiolcgical l
t on4fge7,1 D The licensee shall ContingencyPlansubm(p'tedtothetCofoceduresfor ological C gency Plan as necessary i
maintain implementing to implement the Plan. 'Th'e-Jicenseesh make no chaq in his Radiological Contingency Plan that woult}/ decrease the respons effec iveness of the Plan without prior Commission approval as ev}denc d by a luice amendment.
The licensee shall g
1 maintain records of changes that areynadetto*3the an without prior approval for a
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period of 2 years from the date of the change and shall furnish the Chief, Fuel r
l Cycle Safety Branch, Division of Industrial and Medical Nuclear Safety, NHSS, U. S.
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Nuclear Regulatory Commission, Washington, DC 20555, and the appropriate NRC y
Regional Office specified in Appendix D of 10 CFR Part 20, a report containing a i
description of each change within 6 months after the change is made.
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- 22. At the end of plant life, the licensee shall decontaminate the facility and site i
g in accordance with the general decommissioning plan submitted with the renewal i
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application dated May.14, 1982, so that;these facilities and grounds can be released
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N for unrestricted use.
The financial commitment assuring funds for decommissioning, N-submitted by letter dated May 23, 1982, is_ hereby incorporated as.a condition of the l
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I A report or petition should be submitted to the Director, Office of Nuclear Material _
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q Safe _ty-and Safeguards, with a copy ~ to the. Ad~ministrator of Region ~.I.
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tmc Feem 374A'
~_._ - U.S. NUCLE AR REGU LAT@RY COMMISSION I
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SUPPLEM ENTARY_ SHEET -
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' MATERIAL 5-LICENSE ~
Amendment No 11
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- 23.- Upon discovery of residuss at the' licensed facility containing uranium enriched to g
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>20 wt percent' U-235, action shall be initiated within 30 days to remove the material i
l from the premises in a timely manner.
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- 24. Notwithstanding the statement made in Section 1.6 of the application dated November 30, 1984, the-licensee shall separate the residues in batches no larger l
l than 350 g contained U-235 and shall maintain a minimum separation of 12 feet y
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between batches.
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03Ati 0 4 7388 '
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_ By Leland C. Rouse, F
4 Division of Industrial.and Medical
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Nuclear Safety h
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Washingtori, DC 20555 4.-
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