ML17320A533
| ML17320A533 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 05/27/1983 |
| From: | Hunter R INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM AEP:NRC:0585F, AEP:NRC:585F, NUDOCS 8305310088 | |
| Download: ML17320A533 (6) | |
Text
REGUL Y INFORMATION DISTRIBUTI SYSTEM (RIDS)
ACCBSSI(N NBR;8305310088.
DOC,DATE: 83/05/27 NOTARI'ZEO; NO DOCKET FAGIL:50-315 Donald C.
Cook Nuclear Power Plant, Uni.t 1, Indiana 8
05000315
- 50-316 Donald C.
Cook Nuclear Power PlantE Unit 2E Indiana 8
05000316 AUTH ~ NAME AUTHOR AFFILIATION HUNTERER ~ ST Indiana L Michigan Electric Co,
>>'REICIP+NAME RECIPIENT AFFILIATION DENTONEH ~ RE Office of Nuclear Reactor Regulptioni Director SUBJECT; Discusses
.plant specific evaluation of.relief 8, safety valves 8 related dischar'ge piping analysis per 820709 l,tr.
<<Teledyne =analysis revealed that discharge tpiping sys will be over loaded 8, supports -stressed beyond allowable limits, OISTRIBUTION COBE: 'AOA6S COPIES RECEIVES:LTR ENCl SIZE:.
TITLE:
OR Submittal:
.TMI Action Plan Rgmt NUREG-0737 5'NUREG"0660 NOTES:
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INDIANA L MICHIGAN ELECTRIC COMPANY P. O.
BOX 18 BOWLING GREEN STATION NEW YORK, N. Y. 10004 May 27, 1983 AEP:NRC:0585F Donald C.
Cook Nuclear Plant Unit Nos.
1 and 2
Docket Nos. 50-315 and 50-316, License Nos.
DPR-58 and DPR-74 NUREG-0737, ITEM II.D.1 PWR RELIEF AND SAFETY VALVE TEST PROGRAM Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.
S. Nuclear Regulatory Commission Washington, D.
C.
20555
Reference:
(1)
Letter No. AEP:NRC:0585C dated July 9, 1982 (2)
Letter No. AEP:NRC:0585E dated February 25, 1983 (3)
Letter from Mr. S. A. Varga, NRC dated March 14, 1983
Dear Mr. Denton:
This letter concerns the plant specific evaluation of the Relief and Safety Valves and the related discharge piping analysis for the Donald C.
Cook Nuclear Plant detailed in Reference (1).
Teledyne Engineering Services (TES) is performing the analyses of the as-built piping system using the thermal-hydraulic code RELAP-5/MOD 1. While we have not yet received the final report, early notification from TES indicates that during the loop seal water discharge, the discharge piping system will be overloaded and the piping/supports will be stressed beyond the allowable stress limits.
To eliminate this concern AEPSC proposes to drain the water in the Safety Valve loop seals in both Units at their next respective refueling outages.
The preliminary analysis show that the thermal'hydraulic forces are substantially lower for the case when there is no water in the loop seal.
The qualification of the as-built piping system will be performed without the loop seal water and, if necessary, the supports will be modified.
The method to perform the seal water drainage is currently being evaluated.
In reference (2) we committed to submit the plant Specific Evaluation Report for the Donald C.
Cook Nuclear Plant by July 1, 1983.
8305310088 830527 PDR ADOCK 050003l5 P
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Mr. Harold R.
on A
RC:0585P This date was incorporated into the confirmatory order attached to Reference (3).
We are hereby requesting an extension to the submittal date of the Plant Specific Evaluation of the Relief and Safety Valves and associated piping system from July 1, 1983, to September 15,
- 1983, to perform the additional work which we now anticipate as being required to qualify the discharge piping system.
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.
Very truly yours,
/md nter Vice President cc:
John E. Dolan M. P. Alexich R.
W. Jurgensen W. G. Smith, Jr.
Bridgman R.
C. Callen G. Charnoff NRC Resident Inspector at Cook Plant Bridgman
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