ML17333A274

Forwards SG-95-12-010, DC Cook Unit 1 1995 Interim Plugging Criteria 90 Day Rept, for Dec 1995

ML17333A274
Person / Time
Site:	Cook
Issue date:	01/19/1996
From:	Fitzpatrick E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17333A275	List: ML17333A274 ML17333A276
References
AEP:NRC:1166AC, NUDOCS 9601250139
Download: ML17333A274 (6)

Text

CATEGORY 1 REGULATOR INFORMATION DISTRIBUTION OSTEM (RIDE)

ACCESSION NBR:9601250139 DOC.DATE: 96/01/19 NOTARIZED: NO DOCKET ¹ FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 AUTH. NAME AUTHOR Indiana Michigan Power Co. (formerly Indiana & Michigan Ele

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AFFILIATION'ITZPATRICK,E.

RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Forwards SG-95-12-010, "DC Cook Unit 1 1995 Interim Pluggingg Criteria 90 Day Rept," for Dec 1995.

DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: OR Submittal: General Distribution NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR,ENCL ID CODE/NAME LTTR ENCL PD3-1 LA 1 1 PD3-1 PD <<1 1 HICKMANEJ 1 1 INTERN l FILE CENTER 1 1 1 NRR/DE/EMCB 1 1 HICB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS2 1 0 EXTERNAL: NOAC 1 1 NRC PDR 1 1'OTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTEl CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN SD-5(EXT. 415-2083) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED(

TOTAL NUMBER OF COPIES REQUIRED: LTTR 12 ENCL . 11

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Indiana Michigan Power Company P.O. Box 16631 Columbus, OH 43216 8

January 19, 1996 AEP:NRC:1166AC Docket Nos.: 50-315 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Gentlemen:

Donald C. Cook Nuclear Plant Unit 1 STEAN GENERATOR TUBE INSPECTIONS 90 DAY REPORT Amendment 200 to our unit 1 technical specifications, issued September 13, 1995, approved use of a 2.0 volt steam generator tube support plant interim plugging criterion for Cycle 15. The safety evaluation report that accompanied the amendment required that we perform an assessment of the effectiveness of the methodology described in WCAP-14277. The attachment to this letter contains this evaluation.

In summary, calculations performed for the assessment report for leak rates and probability of tube burst, based on actual end of cycle 14 bobbin coil voltage distributions were low, 0.23 gpm and 1.9 E-05, respectively. Projected end of cycle 15 leakrate and probability of tube burst were also low, 0.70 gpm and 3.1 E-05.

Sincerely, E. E; Fitzpatrick Vice President pit Attachment

t U. S. Nuclear Regulatory Commission AEP:NRC:1166AC Page 2 CC: A. A. Blind G. Charnoff H. J. Miller NFEM Section Chief NRC Resident Inspector - Bridgman J. R. Padgett

ATTACHMENT TO AEP:NRC:1166AC D. C. COOK UNIT 1 1995 INTERIM PLUGGING CRITERIA 90 DAY REPORT