ML17325A553
| ML17325A553 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 12/16/1987 |
| From: | Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Murley T NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| AEP:NRC:0969K, AEP:NRC:969K, NUDOCS 8712230059 | |
| Download: ML17325A553 (5) | |
Text
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:8712230059 DOC.DATE: 87/12/16 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 MURLEY,T.E.
Document Control Branch (Document Control Desk)
SUBJECT:
Inservice test withdrawal of request for code relief of containment spray HX.
DISTRIBUTION CODE:
A047D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR Submittal: Inservice Inspection/Testing NOTES:
RECIPIENT ID CODE/NAME PD3-3 LA NIGGINGTON,D INTERNAL: AEOD/DOA ARM/DAF/LFMB NRR/DEST/MTB OGC/HDS1 RES/DE/EIB EXTERNAL: LPDR NSIC COPIES LTTR ENCL RECIPIENT ID CODE/NAME PD3-3 PD AEOD/DSP/TPAB NRR/DEST/MEB S ILRB EG FIL 01 NRC PDR COPIES LTTR ENCL Sj A
j A
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 19 ENCL
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V
4
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4 4t Indiana Michigan Power Company P.O. Box 16631
~
Coiumbus, OH 43216 AEP:NRC:0969K Donald C.
Cook Nuclear Plant Units 1 and 2
Docket Nos.
50-315 and 50-316 License Nos.
INSERVICE TEST (IST) - WITHDRAWAL OF REQUEST FOR CODE RELIEF OF CONTAINMENT SPRAY HEAT EXCHANGER U.S. Nuclear Regulatory Commission Attn:
Document Control Desk Washington, D.C.
20555 Attn:
T.
E. Murley December 16, 1987
Dear Dr. Murley:
The purpose of this letter is to withdraw our request for temporary code relief for the Donald C.
Cook Nuclear Plant Units 1
and 2 containment spray heat exchangers.
In our letter, AEP:NRC:0969J, dated October 29,
- 1987, we requested this temporary code relief to be granted until we could pressure test the heat exchangers in accordance with the ASME Boiler and Pressure Vessel Code Section XI, 1983 Edition, Subsection
- IWD, Article IWD-5000.
At that time we were planning to test the heat exchangers during the next scheduled
- outages, which are April 1988 for Unit 1 and May 1988 for Unit 2 In November 1987 the heat exchangers were pressure tested at the 1983 Code required value of 165 psig, which is 110% of the lowest safety valve setting (150 psig).
Therefore, the request for temporary code relief for the Cook Nuclear Plant Units 1 and 2
containment spray heat exchangers is being withdrawn.
8712230059 871216 PDR ADOCK 050003i5 P,
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Dr. T. E. Murley AEP:NRC:0969K This document 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.
. Alex'.ch Vice President cm cc:
John E. Dolan W.
G. Smith, Jr.
- Bridgman R.
C. Callen G.
Bruchmann G. Charnoff NRC Resident Inspector
- Bridgman A. B. Davis - Region III