ML17333A954
| 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: |
| 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 ID CODE/NAME PD3-3 LA HICKMANiJ COPIES REC IP IENT LTTR ENCL ID CQDE/NAME 1
1 PD3 3 PD 1
1 CGPIES LTTR ENCL 1
1 INTERNAL: AEQD/SPD/RAB NRR/DE/ENEB OGC/HD$2 RES/DET/EMMEB 1
1
'1 1
0 1
1 FILE CENT BSTRACT RES/DET/EIB 1
1 1
EXTERNAL: LITCQ ANDERSON NRC PDR 1
1 1
NQAC 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 IES REQUIRED:
LTTR 13 El'lCL 12
1 J
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Indiana Michigan Power Company 500 Circle Drive Buchanan, Ml 49107 1395 INSlAMSl MCNESA&f PQSVM July 21, 1997 Docket No.:
50-315 AEP: NRC: 1166AZ 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
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