ML17320A797
| ML17320A797 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 10/14/1983 |
| From: | Alexich M 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:0585G, AEP:NRC:585G, NUDOCS 8310200158 | |
| Download: ML17320A797 (6) | |
Text
J REGULATOR
'NFORMATION DISTRIBUTION rEM (RIOS)
ACCESS? ON NBR'e 8310200158 DOC, DATE: 83/10/14 NOTARIZEDt NO DOCKET ¹ FACIL!50-315 Donald C.
Cook Nuclear Power Pla'nti Unit,ii Indiana L
05500315 50-316 Donald CD Cook Nuclear Power Plantr Unit 2i Indiana 8
050003i6 AUTH,NAME AUTHOR Al-FILIATION ALEXICK,M,P, Indiana tt Michigan Electric Co.
RECIP ~NAME, RECIPIENT AFFILIATION DFNTONrH ~ RE Office of Nuclear Reactor Regulationr Director
SUBJECT:
Requests extension until 831215 to.submit -rept on plant~specific evaluation of relief L safety valves 8
associated piping sysgper NUREG-0737'tem II.D,1,2 ~
DISTRIBUTION CODE ~
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TITLE:
OR Submittal:
TMI Action Plan Rgmt NUREG'0737 8'NUREG-0660'OTES:
RECIPIENT IO CODE/NAME NRR ORB1 BC 01 COPIES LTTR ENCL
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1 04 INTERNAL; ELD/HDS3 IE/DEPER/EPB NRR PANLSON W,
NRR/DL DIR 14 NRR/DL/ORAB 18 NRR/DSI/AEB NRR/DS I/RAB IE/DEPER DIR 33 IE/DE PER/IRB NRR/OHFS/DEPY29 NRR/OL/ADL i6 NRR/DSI/ADRS ?7 NRR/DSI/ASB NRR/DST DIR 30 RGN3 1
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INDIANA8 MICHIGAN ELECTRIC COMPANY P.O. BOX 16631 COLUMBUS, OHIO 43216 October 14, 1983 AEP:NRC:05856 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.1.2 PWR SAFETY AND RELIEF VALVE TEST PROGRAM Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C.
20555
References:
(1) Letter No. AEP:NRC:0585C dated July 9, 1982 (2) Letter No. AEP:NRC:0585F dated May 27, 1983
Dear Mr. Denton:
The purpose of this letter is to request an extension to the submittal date of the Plant Specific Evaluation of the Relief and Safety Valves and associated piping system.
This extension would allow us to perform further analyses and investigate the possibility of alternate design modifications that could be implemented to meet the requirements of NUREG-0737.
In our letter of May 27, 1983 (AEP:NRC10585F),
we had requested an extension to the submittal date of the Plant Specific Evaluation from June 1, 1983 to September 15, 1983.
In that letter we informed the NRC that Teledyne Engineering Services (TES) had performed a preliminary evaluation, of the as-built piping, based on elastic analysis.
That evaluation showed that the discharge piping was overloaded during a safety valve transient and the resulting loop seal water discharge conditions.
The reason for considering alternate design modifications, as was discussed in telephone conversations with your staff, is that we recently learned that many Westinghouse PWR plants were able to retain the water in the loop seals and still meet the concerns of NUREG-0737, Item II.D.1.2 with relatively minor restraint modifications.
We have added a drain line and supports, necessary to meet the regulatory concerns of NUREG-0737, on Unit No. l.
As a first step in evaluating the possibilities of alternate modifications and in ensuring continued safe operation of Unit 2, we have authorized Teledyne to perform an analysis based on the inelastic behavior of the piping system.
This analysis assumes water still is in the loop.
Teledyne has performed a preliminary evaluation.
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Mr. Harold R.
ton AEP:NRC:0585G upon that evaluation, Teledyne has indicated that should a safety valve
- actuate, the pipe between the pressurizer and the. valve would not rupture and would not fail in such a way so as to restrict flow from the pressurizer.
Further, the preliminary evaluation allow'ed Teledyne to conclude that the discharge piping downstream of the safety valve would not fail so as to restrict flow from the safety valve.
It is anticipated that Teledyne will complete their analysis by mid-November, 1983.
We can then define our schedule for completion of review of the analysis, and define any modifications needed to meet the concerns associated with Item II.D.1.2 of NUREG-0737.
Therefore, we are requesting an extension on all safety and relief valve qualification report submittal dates, until the additional analyses can be completed and details of the modifications are finalized.
We anticipate that we can complete our review of the Teledyne report and submit the findings to you by December 15, 1983.
This should allow us to complete the modifications as necessary during the next Unit 2 refueling outage.
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, M. P. Alexich }@
Vice President MPA/cam cc:
John E. Dolan W. G. Smith, Jr. - Bridgman R. C. Callen G. Charnoff E. R. Swanson, NRC Resident Inspector - Bridgman D. Boyd NRC Region III
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