ML20248H871
| 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: |
| References | |
| NUDOCS 8910120123 | |
| Download: ML20248H871 (4) | |
Text
{{#Wiki_filter:L,,,,_________________&______________________________. l.NRC Form 374 ' I pss u .. . U.S. NUCLEAR REIULAToRY COMMISSION NE 1 OF 4 N ES l
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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 withRl the source, and special nuclear material designated below; to use such material for the purpose (s) and at the place (s) designated below; to I 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 - I l
- 2. -Windsor *, Connecticut 06095 . - - -
May 31, 1988 I 41 Espiration date R i
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- 5. Docket or u .. 70-1100 l Reference No. / p
- 6. Byproduct 3ource, and/or '
- 7. Chemical and/or physical a m 8,. Maximum amount that licensee special nuclear material ,
form j may possess at any one time x A,p; :under this license q[O iN jre gy ^..; , t- p y y A. Uranium enriched to A M 0iide powderi, pellets, A.[500,000 kilograms y (rods,(and1finishedRfuel notmorethanM 1
-total uranium N 5.0 w/o U-235 y ,3 r ,
'assembliesy c & 2 ., 'W D i ,
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I B. Uranium enricheEi to a
- B.?? 4,800 grams contained less than ~
No s B. . L. AnMl at :} j j 'll! y& 3 D U-235 20 w/o U-235 i, ,> -
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, . C. 1 Any , . / .h1' j'4 Natural and/or C. 2 3 1 C. 10,000 kilograms ,
depleted uranium '
/a q !! g~ cy total uranium )
3 D. Pu-238 q?"/) D. Encapsulated Y 5 sources, each D. containing less ( :
'i,dneutron,sourcesQ F t
?, n4 ,Vs than 2.0 grams Pu-238 W: ,
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 sources 38 I than 1.7 grams U-235 I i
G. Uranium enriched to Residues I G. 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
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i une sem ma U.S. NUCLEAR REGULATORY COMMISSION g 15 84 License number
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! r'. I i . MATERIALS LICENSE S W-109 Amedm m h D I i SUPPLEMENTARY SHEET Docket or Reference number ' 70-1100 I g 4 . p 1 i OCT 4 1989 u I
- 9. Authorized Use:
g For use in accordance with statements, representations i u q conditions contained in Part 1 and Chapter 8, Part II of the licensee's, and jN i revised application dated May 14, 1982, E 1 September 16, and October 4,1982; September 16, and October 5,1983;and
~ April 5, June 19, September 12, and November s
i September 23, and December 30,1984; May 16, July 25, l { January 20, February 18, March 18, July 24, and December 16, 1985; March !p 18 g August 16, and August 15, 1987; January 7 , E
' 19, 1988; and June 23, and September 15, 1989, B I
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- 10. Authorized Place of Use: W I northweIst of Windsor, Connecticut, as described in the referenced l g
l 11. Reserved. ' N i i 1 12. Reserved. 8 E 8
- 13. Reserved. li 4 '
l l y 1 14. May Notwithstanding the_ statements made in Section 3.21of the revised application date 14, 1982, by June l 30, 1983,Etheilicensee shall' evaluate the individual's internal % 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 l I g
q equipment is used to determine the breathing zone air conc {' g whenever any licensed process or equipment change is made. l j l 15. When the monitoring of, airborne concentration of radioactivity is required as i y E specified in 10 CFR 20.103, the air concertruion of radioactivity in the Nuclear p Laboratories shall be analyzed within 24 hours after each operating shift. R (
- 16. The licensee shall conduct a leak _ test on all encapsulated sources in accordance j
N with the attached Contains Annex A, " License Condition for-Leak lesting Sealed Source Which Alpha Emitter."
- h l
g 17. Notwithstanding the stater 0ents made in Section 3.2.8.2 and Section 3.2.8.3 of 4 page I.3-14 and page I.3-15, respectively, of the application, revision 2, dated i April 6, 1982, release of equipment and material from the plant to offsite for l f with the attached Annex B, dated July 1982. unrestricted use or from conta p y
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- 18. The instruments measuring the liquid-waste level in each dilution tank prior to
.aischarge to the Farmington River shall be calibrated at least annually. /
i j19.NotwithstandingthestatementsinSection5.1.3,pageI.5-2oftheapplication, g y y revision 2 dated April 6, 1982, all wastes contaminated with radioactive material jp j to levels in excess of limits specified in Annex 8 shall be packaged in accordance k
! with the requirements of 10 CFR 71 and disposed of at a licensed radioactive burial ground.
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,,- --mmum==wm=--o=~-----n=#mmmmm U.S. NUCLEAR RE!ULATcRY CcMMISSCN EMEWM3 p NCC Fum 374A PAGE 3 op 4 pzc q_ E ;
( M3 Lcens number E SNM-1067 Amendment No. 15
! MATERIALS LICENSE *
- 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 j
$ petition the Nuclear Regulatory Commission for'a: variance'from the requirements l' 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 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 period of 2 years from the date of the change and shall furnish the Chief, Fuel lq p l Cycle Safety Branch, Division of Industrial and MedicallNuclear Safety, NMSS, U. S. p ; 4 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. flE
- 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, M submitted by letter dated March 23, 1982, is hereby incorporated as a condition of the lp j
r license. p i F 1
- 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 l than 350 g contained U-235 and shall maintain a minimum separation of 12 feet ll between batches. l w_-,m----- -
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L rf ~.~. 4 l NZC Frrm 374A p.m ________--__----------------------- U.S. NUCLEAR REcULATOZY COMMISSION PAGE 4 or 4 ,,ogs .
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g .'- ' uc nie number E 4 i MATERIALS LICENSE SNM-1067 Amendment No. 15 I l SUPPLEMENTARY SHEET pocket or Reference number I I . I 70-1100 t OCT i 4 1989 l 1 E I
- 25. Reserved. F 1 N
l N i 26. Hydrogenous materials shall not be stored on pellet storage tables or pellet Nstor racks where nuclear criticality safety is based on 4-inch safe slab limits. 4 i l1 i ra I 27. Hydrogenous materials shall not be stored between trays of fuel rods on storage I or shelves where nuclear criticality is based on 6-inch safe slab limits. g
' t s 28. Reserved. p 1 1
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- 29. Reserved.
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' 30. In addition to the experience requirement established in Section 2.2.11 of Part I of I>
y i the application, the Production Manager shall have, as a minimum, a bachelor's degree in science or engineering. 5 1 N i p 8 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
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8 M 1 4 F l FOR THE NUCLEAR REGULATORY COMMISSION N j gb e#
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DrigirialSigried # l y Date %{-{plyE4) 1 By Leland C. Rouse, q' N 1 Division of Industrial and Medical jh t Nuclear Safety l l Washington, DC 20555 @j ) 4 3 j>
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