ML20140J312
| ML20140J312 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 05/07/1997 |
| From: | Graham P NEBRASKA PUBLIC POWER DISTRICT |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-89-10, NLS970069, NUDOCS 9705140043 | |
| Download: ML20140J312 (3) | |
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Nebraska Public Power District P.O. 00X 8 WN B
66321
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NLS970069 May 7,1997 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001
Subject:
Revision of Commitment; Motor Operated Valve Upgrade Cooper Nuclear Station, NRC Docket 50-298, DPR-46
References:
1)
Letter to G. R. Horn from T. P. Gwynn dated July 10,1996, "NRC Inspection Report 50-298/96-10" 2)
NRC Information Notice 96-48, dated August 21,1996," Motor-Operated Valve Performance Issues."
Gentlemen:
During the Cooper Nuclear Station (CNS) Generic Letter 89-10 closure inspection the Nebraska Public Power District (District) informed the NRC of plans to implement a modification to valve RCIC-MOV-MOl6 (RCIC-16) during refueling outage (RE17). This modification was planned in order to establish additional design margin with respect to the valves ability to close during a postulated high energy line break (IIELB) scenario. RCIC-16 is the Reactor Core Isolation Cooling system steam supply outboard isolation valve. This valve is designed, along with the inboard steam supply isolation valve, to close following a postulated break of the high energy j
piping downstream of the valve.
The referenced letter documented closure ofInspector Followup Item (IFI) 298/9502-01 in anticipation of NPPD's plan to modify valve RCIC-16 as described above. However, the District has recently established approximately 35% additional margin through a re-evaluation of the associated design basis electrical calculation for RCIC-16. As such, the modification planned for RCIC-16 during the current refueling outage has been suspended. The need for future modifications will be driven by criteria established and maintained by the CNS MOV Program.
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9705140043 970507 PDR ADOCK 05000298 P
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May 7,1997
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1 Should you have any questions concerning this matter, please contact me.
. Sincerely, De16L P. D. Graham Vice President of Nuclear Energy 4
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E cc:
. Regional Administrator USNRC - Region IV l
Senior Project Manager USNRC - NRR Project Directorate IV-1 Senior Resident Inspector USNRC - Cooper Nuclear Station NPG Distribution 4
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l ATTACHMENT 3 LIST OF NRC COMMITMENTS l
4 Correspondence No: NLS970069 4
The following table identifies those actions committed to by the District in this document.
Any other actions discussed in the submittal represent intended or planned actions by the District.
They are described to the NRC for the NRC's information and are not regulatory commitments.
Please notify the Licensing Manager at Cooper Nuclear Station of any questions regarding this document or any associated regulatory commitments.
l COMMITTED DATE COMMITMENT OR OUTAGE None i
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l PROCEDURE NUMBER 0.42 l
REVISION NUMBER 4 l
PAGE 4 OF 10 l