ML20248H871

Amend 15 to License SNM-1067,adding Conditions 30 & 31 to Require Production Manager & Emergency Director to Have Bachelors Degree in Science or Engineering

ML20248H871
Person / Time
Site:	07001100
Issue date:	10/04/1989
From:	Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20248H870	List: ML20248H867 ML20248H871 ML20248H875 ML20248H877
References
NUDOCS 8910120123
Download: ML20248H871 (4)

Text

{{#Wiki_filter:L,,,,_________________&______________________________. l.NRC Form 374 ' 1 4 l I ps u NE OF N ES . U.S. NUCLEAR REIULAToRY COMMISSION s MATERIALS OCENSE I ~ y Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438). and Title 10, 1 Code of Federal Regulations, Chapter I, Parts 30,31,32,33,34,35,40 and 70, and in reliance on statements and representations y heretofore made by the licensee, a license is hereby 1: sued authorizing the licensee to receive, acquire, possess, and transfer byproduct. y ( deliver or transfer such material to persons authorized to rective it in accordance with the source, and special nuclear material designated below; to use such material for the purpose (s) and at the place (s) designated below; to l I R l license shall be deemed to contain the conditions specified 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 effect and to any conditions specified below. h g Licensee Combustion Engineering, Inc. SNM-1067 1. C-E ' Power Systems

3. License number knendment No.15

' 'p Il 1000 Prospect Hill Road Il 2. -Windsor *, Connecticut 06095 41 Espiration date May 31, 1988 I R i l ~

5. Docket or u..

70-1100 Reference No. / p

6. Byproduct 3ource, and/or

7. Chemical and/or physical 8,. Maximum amount that licensee a

m special nuclear material form j may possess at any one time q[O x A,p;

under this license iN jre y

gy ^..; t-p y A. Uranium enriched to A M 0iide powderi, pellets, A.[500,000 kilograms y notmorethanM (rods,(and1finishedRfuel -total uranium N 1 5.0 w/o U-235 y ,3 r, 'assembliesy c & 2 'W D i w se c a s., y ~ > m.vI. n 1 + B. Uranium enricheEi to ~ s B.. AnM :} j j 'll! y& - B.?? 4,800 grams contained I a less than No L. l at 3 D U-235 20 w/o U-235 i,,> '#fh$:QW< s n 8 -; A 't .h1' j 1 C. 10,000 kilograms ,. C. 1 Any,. / C. Natural and/or 2 3 depleted uranium /a q !! g~ '4 total uranium ) cy q? ) D. 3 "/ Encapsulated Y D. 5 sources, each ( D. Pu-238 d 'i, neutron,sourcesQ containing less t ?, 4,V F than 2.0 grams Pu-238 W: s n y E. Pu E. Any E. 160 micrograms E as analytical [ suples y E F. Uranium enriched in Contained in F. 20 sources, each r the U-235 isotope encapsulated U 0 containing less k 38 sources than 1.7 grams I U-235 Ii I G. Uranium enriched to G. Residues G. 1,000 g U-235 g or greater than t 20 w/o U-235 L L I L 8910120123 891004 [ PDR ADGM 07o01100 C PDC II-i 0 I, [ r I

.'%,,__---------------------------=-------------; i une sem ma U.S. NUCLEAR REGULATORY COMMISSION g 15 84 ,,oc 2 4 o, pacts i r'. License number I MATERIALS LICENSE S W-109 Amedm m h D I i i SUPPLEMENTARY SHEET Docket or Reference number 70-1100 I g 4 i OCT 4 1989 p 1 u I 9. Authorized Use: For use in accordance with statements, representations i conditions contained in Part 1 and Chapter 8, Part II of the licensee's, and jN g u revised application dated May 14, 1982, q September 16, and October 4,1982; September 16, and October 5,1983;and s E i 1 September 23, and December 30,1984; May 16, July 25, l ~ April 5, June 19, September 12, and November i January 20, February 18, March 18, July 24, and December 16, 1985; March 18 { 15, 1987; January 7 !p August 16, and August g 19, 1988; and June 23, and September 15, 1989, B E I

10. Authorized Place of Use:

W northweIst of Windsor, Connecticut, as described in the referenced l 1 I l

11. Reserved.

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12. Reserved.

8 E 8

13. Reserved.

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14. Notwithstanding the_ statements made in Section 3.21of the revised application date y

May 14, 1982, by June 1 30, 1983,Etheilicensee shall' evaluate the individual's internal l l exposure to airborne radioactivity based on breathing zone sampling data which are l obtained by continuous sampling for the period'of_his presence in the work area where the unclad radioactive material is handled. If permanently mounted air sampling I l equipment is used to determine the breathing zone air conc {' g whenever any licensed process or equipment change is made. q l g j l

15. When the monitoring of, airborne concentration of radioactivity is required as i

specified in 10 CFR 20.103, the air concertruion of radioactivity in the Nuclear E y Laboratories shall be analyzed within 24 hours after each operating shift. p R

16. The licensee shall conduct a leak _ test on all encapsulated sources in accordance

( N with the attached Annex A, " License Condition for-Leak lesting Sealed Source Which j Contains Alpha Emitter." h l

17. Notwithstanding the stater 0ents made in Section 3.2.8.2 and Section 3.2.8.3 of page I.3-14 and page I.3-15, respectively, of the application, revision 2, dated g

4 April 6, 1982, release of equipment and material from the plant to offsite for l i with the attached Annex B, dated July 1982. unrestricted use or from conta f p !M y p

18. The instruments measuring the liquid-waste level in each dilution tank prior to g

.aischarge to the Farmington River shall be calibrated at least annually. / i j19.NotwithstandingthestatementsinSection5.1.3,pageI.5-2oftheapplication, revision 2 dated April 6, 1982, all wastes contaminated with radioactive material g y to levels in excess of limits specified in Annex 8 shall be packaged in accordance jp yj with the requirements of 10 CFR 71 and disposed of at a licensed radioactive burial k f@i ground. l W i

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,,- --mmum==wm=--o=~-----n=#mmmmm EMEWM3 p NCC Fum 374A U.S. NUCLEAR RE!ULATcRY CcMMISSCN PAGE 3 4 pzc q_ E op ( M3 Lcens number E MATERIALS LICENSE SNM-1067 Amendment No. 15 4 SUPPLEMENTARY SHEET h 70-1100 p p j OCT 4 1989 s 4 E l

20. The licensee shall take the following action on plant gaseous effluent releases:

h i 4 (a) If the radioactivity in the plant gaseous effluents exceeds 18 pCi gross alpha y activity in total uranium per calendar quarter, the licensee shall, within 30 days, prepare and submit to the Commission a report which identifies the ,1 cause for exceeding the limit and the corrective actions to be taken by the j licensee to reduce release rates. If the parameters important to a dose assessment change, a report shall be submitted within 30 days which describes the changes in parameters and includes an estimate of the resultant W change in dose commitment. The report or petition should be submitted to the I! Director, Office of Nuclear Material-Safety and Safeguards, with a copy to the f ^ administrator of Region I. c i { (b) In the event that the calculated dose to any member of the public in any i i consecutive 12-month' period is about to exceed the limits specified in 40 CFR i 190.10, the licensee shall take immediate steps to reduce emissions so as to E id comply with 40 CFR 190.'10. As provided in 40 CFR 190.11, the licensee may l' j petition the Nuclear Regulatory Commission for'a: variance'from the requirements I 1 of 40 CFR 190.10.' If a petition for a variance <is anticipated, the licensee j l shall submit the request at least 90: days prior to exceeding the limits specified g in 40 CFR 190.10. 4 1 d

21. The licensee shall maintain and execute the response measures of his Radiological l

I Contingency Plan submitted to the Commission on June 7, 1982. The licensee shall l' maintain implementing procedures for.his Radiological Contingency Plan as necessary to implement the Plan. The licensee-shall make no change in his Radiological E Contingency Plan that would decrease the~ response effectiveness of the Plan without E lq prior Commission approval as evidenced by a license amendment. The licensee shall N maintain records of changes that are madetto the Plar, without prior approval for a p l period of 2 years from the date of the change and shall furnish the Chief, Fuel p 4 Cycle Safety Branch, Division of Industrial and MedicallNuclear Safety, NMSS, U. S. E 4 Nuclear Regulatory Commission, Washington, DC 20555, and the appropriate NRC E A Regional Office specified in Appendix D of 10 CFR Part 20, a report containing a f description of each change within 6 months after the change is made. fl E

22. At the end of plant life, the licensee shall decontaminate the facility and site p

in accordance with the general decommissioning plan submitted with the renewal E h, application dated May 14, 1982, so that these facilities and grounds can be released E k for unrestricted use. The financial commitment assuring funds for decommissioning, l M submitted by letter dated March 23, 1982, is hereby incorporated as a condition of the p i j license. p F 1 r

23. Upon discovery of residues at the licensed facility containing uranium enriched to P

4 mcre than 19.99 wt percent U-235, action shall be initiated within 30 days g to remove the material from the premises in a timely manner. j i> l

24. Notwithstanding the statement made in Section 1.6 of the application dated I'

l November 30, 1984, the licensee shall separate the residues in batches no larger ll l than 350 g contained U-235 and shall maintain a minimum separation of 12 feet between batches. l w_-,m-----

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J L l i NZC Frrm 374A U.S. NUCLEAR REcULATOZY COMMISSION 4 4 p.m uc nie number E 4 PAGE or ,,ogs .g g 4 i MATERIALS LICENSE SNM-1067 Amendment No. 15 I l SUPPLEMENTARY SHEET pocket or Reference number I I I 70-1100 t OCT 4 1989 l i E 1

25. Reserved.

F I 1 N l

26. Hydrogenous materials shall not be stored on pellet storage tables or pellet sto N

N racks where nuclear criticality safety is based on 4-inch safe slab limits. l1 i i 4

27. Hydrogenous materials shall not be stored between trays of fuel rods on storage ra i

I or shelves where nuclear criticality is based on 6-inch safe slab limits. g I t s

28. Reserved.

p 1 1 N ) 1

29. Reserved.

i E y I i

30. In addition to the experience requirement established in Section 2.2.11 of Part I of the application, the Production Manager shall have, as a minimum, a bachelor's I

y degree in science or engineering. 5 i N 1 p i

31. The Emergency Director shall have, as a minimum, a bachelor's degree in science or i 8

engineering, followed by 5 years experience in management positions in the nuclear g i 8 industry. p I E l g '4' W j ') 4

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i: y I r I N 8 R R 8 l a s y 4' N 7 1 +r ^ f y- (( r' g F l, 1 5 ( 4 N h i E 8 M 1 4 FOR THE NUCLEAR REGULATORY COMMISSION F l N j gb e# l M DrigirialSigried # g g. l Date %{-{plyE4) 1 y By Leland C. Rouse, q' N Division of Industrial and Medical t Nuclear Safety jh 1 @j l ) l Washington, DC 20555 4 3 j>

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