ML20077Q074
| ML20077Q074 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 01/13/1995 |
| From: | Link B WISCONSIN ELECTRIC POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| CON-NRC-95-004, CON-NRC-95-4 GL-93-04, GL-93-4, VPNPD-95-008, VPNPD-95-8, NUDOCS 9501190092 | |
| Download: ML20077Q074 (2) | |
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Wisconsin Electnc 231 W Michigon, PO Bon 2046. Mitwoukee, WI 53201-2046 (414)221 2345 VPNPD-95-008 NRC-95-004 January 13, 1995 Document Control Dark U.S. NUCLEAR' REGULATORY COMMISSION Mail Station P1-137 Washington, DC 20555 Gentlemen:
DOCKETS 50-266 AND 50-301 RESPONSE TO REOUEST FOR ADDITIONAL INFORMATION GENERIC LETTER 93-04. " ROD CONTROL SYSTEM FAILURE AND WITHDRAWAL OF ROD CONTROL ASSEMBLIES, 10 CFR 50.54(f)"
POINT BEACH NUCLEAR PLANT UNITS 1 AND 2 By letters dated August 5, 1993, and September 20, 1993, we responded to Generic Letter 93-04, " Rod Control System Failure and Withdrawal of Rod Control Assemblies, 10 CFR 50.54(f)."
In our September 20, 1993 letter,' we committed to performing modifications to the rod control system following successful demonstration of the changes by Westinghouse, to preclude asymmetric rod withdrawal should a Salem-type failure occur.
We also committed to implementing enhanced rod control system surveillance procedures to verify proper rod control system current timing orders.
Westinghouse subsequently demonstrated the recommended rod control system modifications and developed' suggested rod control system i
surveillance tests.
These were provided to licensees with Westinghouse solid state rod control-systems in Westinghouse Technical Bulletin NSD-TB-94-05-RO, " Rod Control CRDM Timing Change," and "WOG Recommended Rod Control System Surveillance Test," respectively.
i As requested in your DecemDer 12, 1994 letter,.this is to inform you that we implemented the recommended rod control system timing change on PBNP Unit 2 during its Fall 1994 refueling outage.
We presently plan to install the modification on Unit i during its Spring 1995 refueling outage scheduled for March 11 through April 16, 1995.
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We are also modifying our procedures to meet the intent of the "WOG Recommended Rod Control System Surveillance Test."
The revised procedures will be implemented prior to startup from the Unit 1 Spring 1995 refueling outage.
We believe this is responsive to your December 12, 1994, request.
If you have any questions, please contact us.
Sincerely, I
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Bob Link Vice President Nuclear Power TGM/jg cc:
NRC Resident Inspector 4
NRC Regional Administrator, Region III j
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