ML17320A247

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 3,411 Mwt

ML17320A247
Person / Time
Site:	Cook
Issue date:	12/09/1982
From:	Hunter R INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML17320A248	List: ML17320A247 ML17320A249
References
AEP:NRC:0637G, AEP:NRC:637G, NUDOCS 8212170179
Download: ML17320A247 (6)

Text

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INFORMATION DISTRIBUTIO YSTEM (RIDS)

ACCESS'ION NBR;8212170179 Doc.DATE: 82/12/09 NOTARIZED:

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SUBJECT:

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>>

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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

Dear Mr. Denton:

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 ("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.

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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. by the undersigned.

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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