ML17321A908

Informs That Exxon Nuclear Co 851003 XN-NF-85-68(P), DC Cook Unit 2 Limiting Break Loca/Eccs Analysis... & Listed Submittals Constitute Basis for Cycle 6 Reload Licensing

ML17321A908
Person / Time
Site:	Cook
Issue date:	10/08/1985
From:	Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Harold Denton Office of Nuclear Reactor Regulation
References
AEP:NRC:0916H, AEP:NRC:916H, NUDOCS 8510160009
Download: ML17321A908 (6)

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I AOCESSION-NOR $ 85.10160009 DOC s DATEi 85/10/08 NOTARIZED:

NO DOCKET" 0 FACIL::50-316 Donald C,

Cook Nuclear power Planti Unit 2i Indiana 8

05000316 AUTH,NAME AUTHOR AFFILIATION ALEXICHRM~ P, Indiana 8 Michigan Electric Co, RECIP NAME'ECIPIENT AFFILIATION DENTONEH,RB Officei of Nuclear Reactor Regulationi Directori

SUBJECT:

Informs that Exxon Nuclear Co 851003 XN NF-85 68(P)g "DC!

Cook Unit 2 Limiting Break LOCA/ECCS Analysis..."

8 listed submittals Constitute basis for Cycle 6 reload licensing,<"'ISTRIBUTION CODE:

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TITLEt OR Submittal:

Steam Generator Sleeving. ReView for PHR's NOTES: OL'2/23/72 05000316

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TOTAL NUMBER'F COPIES REQUIRED'TTR 31 ENCL

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INDIANA 8 MICHIGAN ELECTRIC COMPAN Y P.O. BOX 16631 COLUMBUS, OHIO 43216 October 8, 1985 AEP:NRC:0916H Donald C.

Cook Nuclear Plant Unit No.

2 Docket No."50-316 L'icense'No.

DPR-74 "Donald C.

Cook Unit 2 Limiting Break LOCA/ECCS Analysis, 10$ Steam Generator Tube Plugging, and K(z) Curve," XN-NF-85-68(P)

Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D. C.

20555

Dear Mr. Denton:

On October 3, 1985, the Exxon Nuolear Company (ENC), our reload fuel vendor for Donald C.

Cook Nuclear Plant Unit 2, transmitted via letter (No.

RAC:067:85) report -XN-NF-85-68(P) entitled, "Donald C.

Cook Unit 2 Limiting Break LOCA/ECCS Analysis, 10$.Steam Generator Tube Plugging,.and K(z) Curve."

This report documents the result of a LOCA/ECCS analysis to support operation of D.C.

Cook Unit 2, Cycle 6 and future cycles; at a thermal power rating of 3425 MWt, with up to 10 percent of steam generator tubes plugged.

This information will be reviewed by the Plant Nuclear Safety Review Committee (PNSRC) and the Nuclear Safety and Design Review Committee (NSDRC) at their next regularly scheduled meeting.

In addition, as discussed with your staff, the following documents have been or will be submitted:

1)

"Exxon Nuclear Methodology for Pressurized Water Reactors:

Analysis of Chapter 15 Events-Appendix C-Westinghouse Four-Loop Plants,"

XN-NF-84-73(P), (submitted via ENC letter no. RAC:058:85 dated August 27, 1985 and noted in IMECo. letter AEP:NRC:0916B dated September 18, 1985);

2)

"D. C.

Cook Unit 2, Cycle 6, Safety Analysis Report: Disposition of Standard Review Plan Chapter 15 Events," XN-NF-85-28(P) (to be submitted);

3)

"Plant Transient Analysis for D. C.

Cook Unit 2 with 10$ Steam Generator Tube Plugging," XN-NF-85-64 (to be submitted);

and 4)

Technical Specification changes which result from the LOCA/ECCS

analysis, Disposition of Standard Review Plan Chapter Events, and the Plant Transient Analysis (to be submitted);-

OJ 8510i 60009 85i008 PDR ADOCK 050003ih j'DR

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,, AEP: NRC: 0916H I'I Al The above submissions constitute the basis for the. D. C.

Cook Unit 2, Cycle 6 reload licensing.

1d I /f This dooument has been prepared following Corporate procedures which incorporate a reasonable set, of controls to insure its,accuracy and oompleteness prior to signature by the. undersigned.~'ery truly yours, ad M.

. Ale ich Vice President

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John E. Dolan W. G. Smith, Jr. - Bridgman R.

C. Callen G. Bruchmann G. Charnoff NRC. Resident Inspector - Bridgman G. Ward, Exxon Nuclear Company,

Richland, WA

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