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| {{#Wiki_filter:REGULAT F INFORMATION DISTRIBUTIO YSTEM (RIDS)ACCESS'ION NBR;8212170179 Doc.DATE: 82/12/09 NOTARIZED: | | {{#Wiki_filter:}} |
| NO DOCKET 0 FACIL:50<<316 Donald C, Cook Nuc/ear Power Plant~Unit 2~Indiana L OS000316 AUTH BYNAME AUTHOR Af FILIATION HUNTERrR,ST Indiana 8 Michigan Electric Co, REC IP~NAME RECIPIE,NT AFFILIATION DENTONiH,RE Office of Nuclear Reactor Regulationg Director t
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| ==SUBJECT:==
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| Application for amend to License DPR-74~consisting of proposed changes.to Tech Specs allowing Cycle 4 operation w/Exxon fuel at reactor thermal power level of 3p011 MNt>>DISTRIBUTION CODE: A001S COPIES RECEIVED:LTR ENCL J SIZE~a+~o TITLE: OR Submittal:
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| General Distribution NOTES+RECIPIENT ID CODE/NAME NRH ORB1 BC 01 COPIES LTTR ENCL 7 7 RECIPIENT ID CODE/NAME COPIES LTTR ENCL INTERNAL: ELD/HDS3 N AB wEG FILE EXTERNAL: ACRS NRC PDR NT?S 04 09 Od 1 0 1 0 1 6 6 1 1 1 NRR/DL D IR NRR/DSI/gAB RGN3 LPDR NSIC 03 05 TOTAL NUMBER OF COPIES REQUIRE.D:
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| LTTR 23 ENCL 21 II>>ll)t/jt lf>>>>ao4ayzr'f q fr>f fi,lur<<p)J lf')'>>(I">f'1 Vi S f rosa sf>)foal((lf JJI)f(>>>><<<<$1'l (<<,f Pf(F)"'<<S>><<>f lc>>I'f C>><<J'1>>>>r<<II>>, a t c yf F$r Il>><<>>1>>
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| INDIANA L MICHIGAN ELECTRIC COMPANY P~0.BOX 18 BOWLING GREEN STATION NEW YORK, N.Y.10004 December 9, 1982 AEP:NRC:0637G Donald C.Cook Nuclear Plant, Unit No.2 Docket No.50-316 License No.DPR-74 ECCS ANALYSIS TECHNICAL SPECIFICATION Mr.Harold R.Denton, Director Office of Nuclear Reactor Regulation U.S.Nuclear Regulatory Commission Washington, D.C.20555
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| ==Dear Mr.Denton:==
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| Attachments 1 and 2 to this letter contain the remaining Unit 2 Appendix A Technical Specification (T/S)changes necessary to permit Cycle 4 operation with Exxon Nuclear Company (ENC)fuel at the reactor thermal power level of 3411 MWt.Attachment 1 contains a descr'iption of the proposed T/S changes.Attachment 2 contains the revised T/S pages.All changes from the current Unit 2 T/S are indicated by a vertical line on the right'and margin of the page.The T/S changes contained in Attachment 2 to this letter have been reviewed and approved by the Plant Nuclear Safety Review Committee (PNSRC)and by the AEPSC Nuclear Safety and Design Review Committee (NSDRC).As noted in our letter No.AEP:NRC:0637E dated September 30, 1982, the proposed T/S changes have been updated to reflect an FO value of 2.04, obtained from the Emergency Core Cooling System (ECCC)reanalysis utilizing maximum safeguards, as modeled by ENC's evaluation model EXEM/PWR.This reanalysis is summarized in ENC's Report No.XN-NF-82-35, Supplement 1,"Donald C.Cook Unit 2 Cycle 4 Limiting Break LOCA-ECCS Analysis Using EXEM/PWR," dated November 1982.ENC has recently transmitted to the NRC twenty-five (25).copies of Reports No.XN-NF-82-35, Supplement 1 (" Donald C.Cook Unit 2 Cycle 4 Limiting Break LOCA-ECCS Analysis Using EXEM/PWR"), No.XN-NF-82-32, Revision 1 (" Plant Transient Analysis for the Donald C.Cook Unit 2 Reactor at 3425 MWt"), and No.XN-NF-82-90
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| (" Donald C.Cook Unit 2 Potential Radiological Consequences of Incidents Involving High Exposure Fuel").We request incorporation of the above-mentioned reports into Docket No.50-316 for Unit No.2 of the Donald C.Cook Nuclear Plant.82i2170i79 82i209 PDR ADOCK 050003ih P PDR
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| ~,~4'I jf P K P a~*" (>>e g/gs 4'J~r<His*~ij Mr.Harold R.Denton AEP:NRC:0637G Payment for NRC processing of this information has previously accompanied our"Application for Cycle 4 Reload and Uprate License Amendment" contained in our letter No.AEP:NRC:0637A wherein we'inter-preted'this application for a license amendment to constitute a Class IV Amendment as defined in 10 CFR 170.22.This document has been prepared following Corporate Procedures which incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature.
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| by the undersigned.
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| Very truly yours, S.Hunter Vice President cc:'ohn-E.Dolan M.P.Alexich R.W.Jurgensen W.G.Smith, Jr.-Bridgman R.C.Callen G.Charnoff NRC Resident Inspector at Cook Plant-Bridgman
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