ML20198G733
| ML20198G733 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 01/06/1998 |
| From: | Sorenson J NORTHERN STATES POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-96-01, GL-96-1, NUDOCS 9801130105 | |
| Download: ML20198G733 (2) | |
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Northem states Power company 1717 Wakonade Dr, East Welch. Minnew.a $5089 l
i January 6,1998 Generic Letter 96-01 US Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 Respo.ce to Generic Letter 96-01 Testing of Safetv-Related Logic Circuits This letter is in response to Generic Letter 96-01: Testing of Safety-Related Logic Circuits. The Generic Letter requests a written response confirming completion. By this letter we are indicating completion of Generic Letter 96-01 activities for Prairie Island Nuclear Generating Plant (PINGP) Unit 1 and Common Systems. The review results for Unit 2 were submitted earlier by letter dated March 27,1997.
The review of Generic Letter 96-01 for PINGP Unit 1 and Common Systems was completed in accordance with the commitment made in our letter dated 4/7/96 -
" Response to Generic Letter 96-01, Testing of Safety Reiated Logic Circuits." The results of this review indicated, with two minor exceptions, that Prairie Island was correctly implementing and documenting the Unit 1 and common systems surveillance testing program for the reactor protection system, emergency diesel generator load shadding and sequencing funcuons and the actuation logic for the engineered safety features as outlined in the Prairie Island Technical Specifications.
The two exceptions were documented in LER 1-07-11 " Failure to Test the Low Pressure Auto-start Function of 121 Motor Driven Cooling Water Pump and inadequate Separation Between Trains A and B Low Pressure Auto-start Switches,"
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and LER 1-97-18 " Failure to Test the Auto-brt Feature of the Control Room gi Ventilation System Air Handlers due to Procedure Deficiency." In addition, enhancements were made to other surveillance testing procedures to more e: sily and completely identify ccmpliance with the Technical Specifications.
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The original review process called for the Generic Lotter 96-01 review to be
"... coordinated with tiie development of the Prairie Island ITS [ Improved Technical Specifications)." This was subsequently altered such that Generic Letter 96-01 reviews were based upon the current custom Technical Specifications. The reason for this change was that the schedule for the Improved Technical Specifications conversion project could not support the review schedule for our response to Generic Letter 96-01, in this letter we have made no new Nuclear Regulatory Commission commitments.
Please contact Jack Leveille (612-388-1121, Ext. 4662) if you have any questions related to this letter.
oel Sorenson Plant Manager Prairie Island Nuclear Generating Plant c:
Regional Administrator - Region lil, NRC Senior Resident inspector, NRC NRR Project Manager, NRC J E Silberg
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