ML17325A397
| ML17325A397 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 10/29/1987 |
| From: | Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Murley T NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| AEP:NRC-0969J, AEP:NRC-969J, NUDOCS 8711030294 | |
| Download: ML17325A397 (4) | |
Text
ACCESSION NBR FAC IL:50-315 50-316 AUTH. NAME ALEXICH. M. P.
RECIP. NAME MURLEYiT. E.
REGULATOR NFORMAT1ON DISTRIBUTION TEM (RIDS) 8711030294 DQC. DATE: 87/10/29 NOTARIZED:
NO DOCKET Donald C.
Cook Nuclear Poeer Planti Unit ii Indiana h
05000315 Donald C.
Cook Nuclear Power Planti Unit 2i Indiana 5
05000316 AUTHOR AFFILIATION Indiana Michigan Potuer Co.
RECIPIENT AFFILIATION Document Control Branch (Document Control-Desk) t
SUBJECT:
Requests temporary code relief from testing containment spray heat exchangers be granted unitl next outage of sufficient duration> Apr 1988 for Unit 1 5 May 1988 for Unit 2I to alloe testing. Fee paid.
DISTRIBUTION CODE:
A047D COPIES RECEIVED: LTR i ENCL Q SIIE:
TITLE:
OR Submittal:
lnservice Inspection/Testing NOTES:
REC IP IENT ID CODE/NAME PD3-3 LA WIGGINGTONi D INTERNAL: AEQD/DQA ARM/DAF/LFMB NRR/DEBT/MTB OGC/HDS1 RES/DE/EIB EXTERNAL'PDR NSIC COPIES LTTR ENCL REC IP IENT ID CODE/NAME PD3-3 PD AEOD/DSP/TPAB NRR/DEST/MEB N A~M* /ILRB REG F LE 01 NRC PDR COPIES LTTR ENCL w c.l E,gg 4 igg crz>
TOTAL NUMBER QF COPIES REQUIRED:
LTTR 19 ENCL 0
d lt t
Indiana Michigan Power Company One Summit Square P.O. Box 60 Fort Wayne, IN 46801 219 425 2111 AEP:NRC:0969J Donald C.
Cook Nuclear Plant Units 1 and 2
Docket Nos.
50-315 and 50-316 License Nos.
DPR-58 and DPR-74 INSERVICE TEST (IST)
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 October 29, 1987
Dear Dr. Murley:
The purpose of this letter, submitted in accordance with 10 CFR 50.55a(g)(6)(i), is to request temporary code relief for testing the D.
C.
Cook Units 1 and 2 containment spray heat exchangers.
Following the installation of two flushing ports on the heat exchangers'hell
- side, pressure testing in accordance with the ASME Boiler and Pressure Vessel Code Section XI, 1983 Edition, Subsection IWD Article IWD-5000 was required.
The heat exchangers were pres ure tested to 118 psig, 110$ of design pressure (105 psig) rather than the 1983 Code required value'f 165 psig, 110% of t:he lowest safety valve setting (150 psig).
The 118 psig test pressure meets the requirements of the 1974 Code edition which was in effect at the Cook Plant until July 1,
- 1986, and it exceeds the expected pressure on the shell side of the containment spray heat: exchanger.
The source of the cooling wat:er for the shell side of the heat exchangers is the essential service water (ESW) syst: em.
The highest pressure sources for the FSW system are the ESW pumps which have a maximum discharge pressure of 105 psig.
Pressurization above this value could only occur if the cooling source were isolated while the heated tube side fluid continued to flow through the heat exchanger or if a tube leak allowed pressurization from the containment spray system.
Either of these would require an unlikely combination of equipment malfunction and operator errors.
S7iiOSOi94 87S0a9 PDFt O'DOCK 05000315 I
P PDR tt~ 'J ~(c W~~
Dr. T. E. Murley AEP:NRC:0969J Because of the foregoing, we consider the containment spray system to be operable and capable of performing its intended function.
Our alternatives are to pressure test the containment spray heat exchangers while the reactor is in operation or to reset the relief valve liftpoint so that the test already conducted is in compliance with the code.
Both of these alternatives will require entering technical specification action statements and could potentially cause a reactor shutdown if the time limits were not complied with.
We are planning to test these heat exchangers to the correct hydrostatic pressure at the earliest opportunity.
We request that this temporary relief be granted until the next outage of sufficient duration to allow testing.
Currently, the next scheduled outages are April 1988 for Unit 1 and May 1988 for Unit 2.
A check in the amount of $150.00 is attached with this letter for the NRC processing of the aforementioned request.
This letter has been reviewed by the PNSRC and will be reviewed by the NSDRC at the next regularly scheduled meeting.
We will inform you if any changes are made as a result of the NSDRC review.
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.
. Alexic Vice President cm Attachment 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