ML17324B277

Application for Amend to License DPR-74,allowing Repair of Steam Generator

ML17324B277
Person / Time
Site:	Cook
Issue date:	03/12/1987
From:	Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
AEP:NRC:0980B, AEP:NRC:980B, NUDOCS 8703180100
Download: ML17324B277 (7)

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I'703)80100 87/03/12 NOTARIZED: NO 'OCKET ¹ j FAC I L: 50-316 Donald C. Cook Nuclear Paver Plant~ Unit 2> Ind iana 5 05000316 AUTH. NAl'>E AUTHOR AFFIL'IATI ON ALEXICHiN. P. Indiana h Nichigan Electric Co.

REC IP. RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Application for amend to License DPR-74i to allow repair o0 steam generator.

DISTRIBUTION CODE: AOOID COPIES RECEIVED: LTR / ENCL J SIZE:

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INDIANA 8 MICHIGAN ELECTRIC COMPANY P.O. BOX 16631 COLUMBUS, OHIO 43216 March 12, 1987 AEP:NRC:0980B Donald C. Cook Nuclear Plant Unit No. 2 Docket No. 50-316 License No. DPR-74 STEAM GENERATOR REPAIR PROJECT (LICENSE AMENDMENT REQUEST)

U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555

Dear Sirs:

On November 7, 1986, the Indiana & Michigan Electric Company submitted the Donald C. Cook Nuclear Plant Unit No. 2 Steam Generator Repair Report to the Nuclear Regulatory Commission. This report described the process and associated activities that would be implemented to repair the Unit No. 2 steam generators. In the November 7 submittal, it was stated that the Repair Project did not constitute an unreviewed safety question as defined in 10CFR50.59 and, therefore, did not require an amendment to the Unit No. 2 operating license.

Since that time, the Indiana 6 Michigan Electric Company has had discussions with the NRC staff, those discussions indicated that NRC approval of the Repair Project is required. Therefore, please consider the November 7, 1986 submittal and this letter as an application for license amendment to the Donald C. Cook Nuclear Plant Unit No. 2 Operating License to allow the repair of the Unit No. 2 steam generators. Proposed wording for the license amendment is provided as an attachment to this letter.

In compliance with the requirements of 10 CFR 50.91(b)(1), copies of this letter and its attachments have been transmitted to Mr. R. C.

Callen of the Michigan Public Service Commission and Mr. G. Bruchmann of the Michigan Department of Public Health.

The November 7, 1986 submittal also included a check in the amount of $ 150.00. Please consider that check as the license amendment application fee pursuant to 10CFR170.12(c).

8703180100 870312 PDR P

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. Document Control R m AEP:NRC:0980B A revision to the Steam Generator Repair Report is planned for later in March, 1987.

This document has been prepared following corporate procedures which incorporate a reasonable set of controls to insure its accuracy and completeness prior to signature by the undersigned.

Very truly yours, M. Alexi h Vice resi ent edg cc: John E. Dolan W. G. Smith, Jr. - Bridgman R. C. Callen G. Bruchmann G. Charnoff NRC Resident Lnspector - Bridgman

Attachment to AEP:NRC:0980B PROPOSED LICENSE AMENDMENT Accordingly, the Facility Operating License No. DRP-74 is hereby amended by adding paragraph 3.J as follows:

J STEAM GENERATOR REPAIR PROGRAM (1) The licensee is authorized to repair Unit 2 steam generators by replacement of major components. Repairs shall be conducted in accordance with the Licensee's commitments identified in the Commission approved Donald C. Cook Nuclear Plant Unit No. 2 Steam Generator Repair Report dated November 7, 1986, as revised, and additional commitments identified in the Staff's related Safety Evaluation.

(2) Changes to the steam generator repair activities are authorized if the Licensee determines pursuant to 10 Section 50.59 that prior Commission approval is not CFR required.

(3) Changes to the steam generator repair activities described in the Steam Generator Repair Report, as revised, may be authorized by the Commission without further amendment to the Facility Operating License if it can be demonstrated that such changes are bounded by the considerations described in the Staff's related Safety Evaluation.

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