ML17328A878: Difference between revisions
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This letter has been prepared following Corporate procedures which incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned. | This letter has been prepared following Corporate procedures which incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned. | ||
Sincerely, M. P. Alexich Vice President ldp cc: D. H. Williams, Jr. | Sincerely, M. P. Alexich Vice President ldp cc: D. H. Williams, Jr. | ||
A. A. Blind - Bridgman J. R. Padgett G. Charnoff A. B. Davis - Region III NRC Resident Inspector - Bridgman | A. A. Blind - Bridgman J. R. Padgett G. Charnoff A. B. Davis - Region III NRC Resident Inspector - Bridgman NFEM Section Chief}} | ||
NFEM Section Chief}} | |||
Revision as of 00:47, 4 February 2020
| ML17328A878 | |
| Person / Time | |
|---|---|
| Site: | Cook |
| Issue date: | 01/30/1991 |
| From: | Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| AEP:NRC:1086C, IEB-88-011, IEB-88-11, NUDOCS 9102050240 | |
| Download: ML17328A878 (6) | |
Text
ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR: 9102050240 DOC. DATE: 91/01/30 NOTARIZED: NO DOCKET FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana & 05000315 50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana & 05000316 AUTH. NAME AUTHOR AFFILIATION ALEXICH,M.P. Indiana Michigan Power Co. (formerly Indiana & Michigan Ele RECIP.NAME RECIPIENT AFFILIATION HURLEY,T.E. Document Control Branch (Document Control Desk)
SUBJECT:
Requests addi time to prepare plant-specific evaluation of surge line in order to complete ongoing work, perform reviews
& prepare submittal, in response to NRC Bulletin 88-011.
Evaluation will be submitted by 910401.
COPIES RECEIVED:LTR ENCL ~ SIZE:
g DISTRIBUTION CODE: IE30D
, E NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 LA PD3-1 PD COLBURN,T.
INTERNAL: AEOD/DOA AEOD/DS P/TPAB AEOD/ROAB NRR CHAN,T NRR HOU,S NRR KUO,P NRR/DET/EMEB 7E NRR/DOEA/OEAB11 NRR/DOEA/OGCB11 NRR/DREP/PEPB9D NRR/DS3~- NRR/PMAS/ILRB12 REG fVKLE 0.2 RES/DSIR/EIB RGN~FIEE 01 EXTERNAL: NRC PDR NSIC NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOii! Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 20 ENCL
indiana Michigan Power Company P,O. Box 16631 Columbus, OH 43216 INDIANA MICHlGAM POWER AEP:NRC:1086C Donald C. Cook Nuclear Plant Units 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 JUSTIFICATION FOR CONTINUED OPERATION REGARDING PRESSURIZER SURGE LINE STRATIFICATION U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Attn: T. E. Murley January 30, 1991
Dear Dr. Murley:
References:
- 1) B. J. 'Coslow, "Westinghouse Owners Group Bounding Evaluation for Pressurizer Surge Line Thermal Stratification," WCAP-12277 (Westinghouse Proprietary Class 2), WCAP-12278 (Non-Proprietary Version),'une 1989.
- 2) B. J. Coslow, "Westinghouse Owners Group Pressurizer Surge Line Thermal Stratification Generic Detailed Analysis Program MUHP-1091 Summary Report," WCAP-12639 (Westinghouse Proprietary Class 2), WCAP-12640 (Non-Proprietary Version), June 1990.
- 3) SER from NRC on WCAP-12277 as per WOG letter OG-90-56, September 4, 1990.
In order to address the issue of surge line thermal stratification and respond to NRC Bulletin 88-11, the Westinghouse Owners Group (WOG) implemented a program to generically evaluate the effects of stratification on surge line integrity (Reference 1). This bounding evaluation compared WOG plants to those for which detailed plant-specific analysis had been performed. Since Reference 1 provided less than full design life verification, a generic justification for continued operation (JCO) was,developed for use by each of the WOG plants. This JCO was reviewed and accepted by the NRC (Ref. 3). Subsequent to the bounding evaluation and generic 9102050240 910130 PDR ADOCK 05000315 PDR Q
4 II'
Dr. T; E. Murley AEP:NRC:10860 JCO, the WOG performed a generic, detailed analysis on groupings of plants based on their similarity of response to thermal stratification, (Reference 2). The results of this generic, detailed analysis could not .show acceptable fatigue life for the Cook Nuclear Plant units. Therefore, a plant-specific JCO was developed by Westinghouse which justified continued power operation of the Cook Nuclear Plant for an addftional 10 heatup and cooldown cycles.
The WOG detailed analysis (Reference 2) was completed in July of 1990 and was reviewed by the NRC in November of 1990. By November 1990, we had already initi'ated a program to complete the plant-specific evaluation of the surge line, required by NRC Bulletin 88-11 to be submitted by January 31, 1991, Although this program was initiated prior to November 1990, completion could not be planned until NRC feedback on the WOG detailed analysis (Reference 2) was obtained, Based on the NRC's November review of Reference 2, we can now complete the program. In order to do-so, however, we request additional time to allow for completion of on-going work, review by appropriate parties, and preparation and submittal of the reports. Accordingly, we request that the date for our plant-specific submittal be extended to April 1, 1991.
This letter has been prepared following Corporate procedures which incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned.
Sincerely, M. P. Alexich Vice President ldp cc: D. H. Williams, Jr.
A. A. Blind - Bridgman J. R. Padgett G. Charnoff A. B. Davis - Region III NRC Resident Inspector - Bridgman NFEM Section Chief