ML17325A123

Forwards Steam Generator Tube Integrity - Apr 1987: Assessment of Next Operating Interval Length, Providing Evaluation of Mar 1987 Facility Steam Generator Tube Leak Event.Fee Paid

ML17325A123
Person / Time
Site:	Cook
Issue date:	05/22/1987
From:	Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Murley T NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML17325A124	List: ML17325A123 ML17325A125
References
AEP:NRC:0936J, AEP:NRC:936J, NUDOCS 8706020163
Download: ML17325A123 (7)

Text

REGULATORY Ii Rl'lATI ON'I S7R I BUT I ON BYB1 < R IDB)

ACCESSION NOR 8706020163 DOC. DATE: 87/05/22 NOT*R I ZED: NO DOCKET FAC IL: 50-316 Donald C. Cook Nuclear Paver Planti Unit 2. Indiana 050003ih AUTH. NAl'lE AUTHOR AFFILIATION ALEXICH N. R. Indiana Zc Nichigan Electri c Co.

RECIP. NANE RECIPIENT AFFILIATION NURLEY> T. E. Document Control Branch (Document Control Desk)

SUBJECT:

Forwards "Steam Generator Tube Integritg ApT 1987:

Assessment oF Next Operating Interval Lengthi" providing evaluation oF l'lar 1987 Facility steam generator tube leak event. Fee paid.rl DISTRIBUTION CODE: *CA&CORI S ECEIVED: LTR J ENCL I SI IE:

TITLE: OR/Licensing/Generic Submittal: Steam Generator Tube Integritg (Water NOTES:

REC IP IENT I COP ES RECIPIENT COPIES ID CODE/NAl'lE LTTR ENCL ID CODE/MANE LTTR ENCL PD3-3 LA 1 PD3-3 PD 1 1 WI QQINQTON. D INTERNAL: NRR/DEBT/CEB NR R /DEST/ P SB 1 1 NRR/DEBT/RBB NR DOEA/QCB 1 NRR/PNAS/ ILRB E Oi EXTERNAL: LPDR NRC PDR 1 1 NBIC

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r'1 TOTAL NUNBER OF COPIES REQUIRED: LTTR 12 ENCL 12

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INDIANA 8 NICHIGAN ELECTRIC CONPANY P.O. BOX 16631 COLUMBUS, OHIO 43216 May 22, 1987 AEP:NRC:0936J Donald C. Cook Nuclear Plant Unit No. 2 Docket No. 50-316 License No. DPR-74 STEAM GENERATOR TUBE INTEGRITY U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Attn: T. E. Murley

Dear Mr. Murley:

Pursuant to the commitment in letter AEP:NRC:0936G, dated April 9, 1987 transmitted herewith as Attachment 1 is a report entitled "Steam Generator Tube Integrity - April 1987: An Assessment of the Next Operating Interval Length," which provides an evaluation of the March 1987 Unit 2 steam generator tube leak event and presents justification for an operating interval of 140 effective full-power days before the next scheduled steam generator surveillance. Selection of this interval is based on information in Attachment 1 and is aimed at minimizing the potential for a forced outage due to steam generator tube leakage.

During the maintenance outage following the March 1987 tube leak, two

'other steam generator issues arose and were discussed with your staff.

Details of these events are documented in Attachment 2 and 3 to this letter. Attachment 2 deals with the difficulty encountered in removing steam generator manway bolts and the subsequent repairs that were made.

Attachment 3, prepared by Westinghouse, provides a discussion and safety evaluation of the loose mechanical tube plug that was discovered in steam generator 22.

Pursuant to 10 CFR 170.12(f), we have enclosed an application fee of

$ 150.00 for the NRC review of the attached information.

8706020163 870522 ADOCK 05000316 I'DR 8 PDR 6$

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a Mr. T. E. Murley 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,,

Ale ich Vi e President cm Attachments cc: John E. Dolan W. G. Smith, Jr. - Bridgman R. C. Callen G. Bruchmann G. Charnoff NRC Resident Inspector - Bridgman A. B. Davis - Region III

Mr. T. E. Murley 'P:NRC:0936J bc: J. G. Feinstein/B. P. Lauzau S. H. Horowitz/T. 0. Argenta/R. C. Carruth J. J. Markowsky/S. H. Steinhart/P. G. Schoepf M. Marrocco/D. R. Hafer R. W. Jurgensen R. F. Kroeger M. L. Horvath - Bridgman E. A. Morse - Bridgman C. A. Erikson J. B. Shinnock D. L. Wigginton, NRC - Washington, D.C.

AEP:NRC:0936J DC-N-6015.1

Attachment 1 to AEP:NRC:0936J Steam Generator Tube Integrity Report