ML17333A954

Forwards Steam Generator 90-day Repts Performed in Support of GL 95-05

ML17333A954
Person / Time
Site:	Cook
Issue date:	07/21/1997
From:	Fitzpatrick E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17333A955	List: ML17333A954 ML17333A956 ML17333A957
References
AEP:NRC:1166AI, GL-95-05, GL-95-5, NUDOCS 9707300002
Download: ML17333A954 (4)

Text

CATE("ORY 1 REGULATO, INFOPMATIQN DISTRIBUTION STEM (RIDS)

ACCESSION NBR: 9707300002 DOC. DATE: 97/07/21 NOTARIZED: NO DOCKET if FACIL: 50-315 Donald C. Cook Nuclear Poeer Planti Unit ii Indiana M 05000315 AUTH. NAME AUTHOR AFFILIATION F:TZPATRICKi E. E American Electric Poeer Co. i Inc.

RECIP. NAME -

RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Forulards steam generator 90-dal) repts performed in support of GL '95-05.

DISTHIBUTIQN CODE: A047D COPIES RECEIVED: LTR ENCL SIZE:

TITLE: OR Submit ta 1: In servi c e/Tes t ing /Re 1 1 e f from ASME Code GL-89-04 RECIPIENT COPIES REC IP I ENT CGPIES ID CODE/NAME LTTR ENCL ID CQDE/NAME LTTR ENCL PD3-3 LA 1 1 , PD3 3 PD 1 1 HI CKMANi J 1 1 INTERNAL: AEQD/SPD/RAB 1 FILE CENT 1 NRR/DE/ENEB 1 '1 BSTRACT OGC/HD$ 2 1 0 RES/DET/EIB 1 1 RES/DET/EMMEB 1 1 EXTERNAL: LITCQ ANDERSON 1 1 NQAC NRC PDR 1 NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTEl CONTACT THE DOCUMENT CONTROL DESKS ROOM OWFN 5D-5(EXT. 415-2083) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDl TOTAL NUMBER OF COP I ES REQUIRED: LTTR 13 El'lCL 12

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Indiana Michigan Power Company 500 Circle Drive Buchanan, Ml 49107 1395 INSlAMSl MCNESA&f PQSVM July 21, 1997 AEP: NRC: 1166AZ Docket No.: 50-315 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Gentlemen:

Donald C. Cook Nuclear Plant Unit 1 STEAM GENERATOR 90 DAY REPORT This letter and attachments make up the Cook Nuclear Plant Unit 1 steam generator (SG) 90 day tube inspection report. The report consists, of four attachments.

Attachment 1 provides a condition monitoring and operation assessment evaluation of the as-found condition of the SGs with respect to burst and leakage concerns, as well as a forward looking assessment for the" potential con'ditions of the SGs at the end of the current cycle.

Attachment 2 provides a report on the required tube integrity calculations performed in support of generic letter (GL) 95-05 and the 2 volt alternate repair criteria.

Attachment 3 provides the available results of our tube sample metalographic examination that was conducted in support of GL 95-

05. This examination remains ongoing.

Attachment 4 provides an acronym listing for the terminology used throughout the overall report.

Sincerely, E. E. Fitzpatrick Vice President vlb Attachments A. A. Blind A. B. Beach MDEQ - DW Sc RPD NRC Resident Inspector R. Padgett 9707300002 97072K PDR =-ADOCK 05000$ i5 IIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIII P PDR

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