ML17331A265

Forwards WCAP-13517, Evaluation of PTS for DC Cook Unit 2. Analysis Revised to Consider Results of Surveillance Capsule U Analysis Contained in WCAP-13515

ML17331A265
Person / Time
Site:	Cook
Issue date:	04/12/1993
From:	Fitzpatrick E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17331A266	List: ML17331A265 ML17334B468
References
AEP:NRC:0561F, AEP:NRC:561F, NUDOCS 9304150162
Download: ML17331A265 (4)

Text

ACCELERANTP DOCUMENT DISTlgPUTION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9304150162 DOC.DATE: 93/04/12 NOTARIZED: NO DOCKET ¹ FACIL:50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana M 05000316 AUTH. NAME AUTHOR AFFILIATION FITZPATRICK,E. Indiana Michigan Power Co. (formerly Indiana 6 Michigan Ele RECIP.NAME RECIPIENT AFFILIATION MURLEY,T.E. Document Control Branch (Document Control Desk)

SUBJECT:

Forwards WCAP-13517, "Evaluation of PTS for DC Cook Unit 2."

Analysis revised to consider results of surveillance Capsule U analysis contained in WCAP-13515.

DISTRIBUTION CODE: A049D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: OR Submittal: Thermal Shock to Reactor Vessel NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 PD 1 1 DEAN,W 2 2 INTERNAL: AEOD/DOA NRR/DSSA/SRXB OGC/HDS2 1

1 1

1 1

0 NRR/DE t-/s G~L

~ Ol 1

1 1

0 0

1 RES DE 1 1 RES/DE MEB/MES 1 1 RES/DSIR/EIB 1 1 RES/DSIR/RPSIB 1 1 RES/DSR/RPSB 1 1 RGN1 ADMSTR 1 1 EXTERNAL: NRC PDR 1 1 NSIC 1 1 NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTEI CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'7 NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 17 ENCL 14

'I I

'0 i .i. 1 Pl 1

1 h ~

Indiana Michigan Power Company P.O. Box 16631 Columbus, OH 43216 AEP$ NRC:0561F 10 CFR 50.61 Donald C. Cook Nuclear Plant Unit 2 Docket No. 50-316 License No. DPR-74 UPDATED REFERENCE TEMPERATURE AND PRESSURIZED THERMAL SHOCK ANALYSES U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Attn: T. E. Murley April 12, 1993

Dear Dr. Murley:

This submittal is made pursuant to the recpxirements of 10 CFR 50.61, "Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events." The attachment to this letter is Westinghouse WCAP-13157, "Evaluation of Pressurized Thermal Shock for D. C. Cook Unit 2". The analysis was revised to consider the results of the surveillance Capsule U analysis contained in the WCAP-13515 report (see our submittal letter AEP:NRC:0894T dated March 12, 1993). The WCAP-13515 report concludes that for Cook Nuclear Plant, Unit 2, all the RTFm values for the reactor vessel material remain below the NRC screening values for the present time and up to 32 effective full power years (EFPY) of operation.

Sincerely, ZF Fi E. E. atrick Vice President dgr Attachment cc: A. A. Blind Bridgman G. Charnoff NFEM Section Chief J. R. Padgett A. B. Davis Region NRC Resident Inspector III Bridgman 9304i50262 930412 PDR' ADOCK 05000316 P PDR

Dr. T. E. Murley AEP:NRC:0561F bc: S. J. Brewer J. D. BenesiJ. R. JenseniB. Mickatavage J. B. KingseediT. Satyan Sharma V. D. VanderBurg D. H. Malin M. L. Horvath Bridgman J. B. Shinnock W. G. Smith, M. Dean, Jr.'.

NRC - Washington, DC AEP:NRC:0561F DC-N-6015.1