ML17326B560
| ML17326B560 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 03/14/1989 |
| From: | Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| AEP:NRC:1067C, NUDOCS 8903230074 | |
| Download: ML17326B560 (3) | |
Text
gc~~~TED DIRIBUTIOY DEMONS TI04
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REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
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ACCESSION NBR:8903230074 DOC.DATE: 89/03/14 NOTARIZED: NO DOCKET FACIL:50-315 Donald C.
Cook Nuclear Power Plant, Unit 1, Indiana 05000315 AUTH.NAME AUTHOR AFFILIATION ALEXICH,M.P.
(formerly Indiana
& Michigan Ele RECIP.NAME RECIPIENT AFFILIATION MURLEY,T.E.
Document Control Branch (Document Control Desk)
SUBJECT:
Provides addi info on reduced temp
& pressure program,per 890303 discussion w/NRC.
DISTRIBUTION CODE:
A001D COPIES RECEIVED LTR ENCL SIZE TITLE: OR Submittal:
General Distribution NOTES RECIPIENT ID CODE/NAME PD3-1 LA STANG,J INTERNAL: ARM/DAF/LFMB NRR/DEST/CEB 8H NRR/DEST/MTB 9H NRR/DEST/SICB NUDOCS-ABSTRACT FI 01 EXTERNAL: LPDR NSIC COPIES LTTR ENCL 1
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1 RECIPIENT ID CODE/NAME PD3-1 PD NRR/DEST/ADS 7E NRR/DEST/ES B 8 D NRR/DEST/RSB 8E NRR/DOEA/TSB 11 OGC/HDS 1 RES/DSIR/EIB NRC PDR COPIES LTTR ENCL 2
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IO EILIMZNATEKRR NME FRM DISKUBUTION LISTS FOR DOCUHENIS YOU DON'T NEEDf D
S TOTAL NUMBER OF COPIES REQUIRED:
LTTR 19 ENCL 16
Indiana Michigan~
Power Company ~
P.O. Box 16631 Columbus, OH 43216 R
INWANA
/AICMl6$lN PQMElR AEP NRC 1067C Donald C.
Cook Nuclear Plant Unit 1 Docket No. 50-315 License No.
ADDITIONALINFORMATION ON CONTAINMENT STRUCTURAL ANALYSIS U.S. Nuclear Regulatory Commission Attn:
Document Control Desk Washington, D.C.
20555 Attn:
T ~
E. Murley March 14, 1989
Dear Dr. Murley:
This letter provides additional information on the Reduced Temperature and Pressure (RTP) Program for Donald C.
Cook Nuclear Plant Unit 1, as requested by your staff during a discussion on March.3; 1989.
Our letter AEP:NRC:1067 dated October 14, 1988 transmitted, analyses performed by Westinghouse Electric Corporation to support the upcoming Unit 1 Cycle 11 under RTP conditions.
As discussed on Page 2 of Attachment 2 of AEP:NRC:1067, the Westinghouse analysis of containment subcompartment pressures resulting from a LOCA predicted pressures in excess of the containment design pressures stated in the FSAR (reference Unit 1 Updated FSAR Table 14 '.4-30)
~
AEP:NRC:1067 stated that we were evaluating the containment structure to ensure it could withstand the increased pressures.
The analyses have been completed and have confirmed the adequacy of the containment subcompartments for the RTP conditions.
The acceptance criteria used in the evaluation of the containment subcompartment structural elements subjected to the RTP conditions are those of Section 5.2.2.3 of the updated FSAR titled, "Containment Design Stress Criteria."
This document has been prepared following Corporate procedures that incorporate a reasonable set of controls to ensure its
,accuracy.and completeness prior to signature by the undersigned.
Sincerely, M. P. Alexich Vice President S903230074 8903L4 PDR ADOCK 05000315 P
Dr. T. E. Murley AEP:NRC:1067C ldp cc:
D. H. Williams, Jr.
W.
G. Smith, Jr.
- Bridgman R.
C. Callen G. Charnoff A. B. Davis NRC Resident Inspector
- Bridgman G. Bruchmann