ML20151U327
| ML20151U327 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 09/04/1998 |
| From: | Sorensen J NORTHERN STATES POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20151U332 | List: |
| References | |
| NUDOCS 9809100359 | |
| Download: ML20151U327 (2) | |
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Northern States Power Company Prairie Island Nuclear Generating Plant 1717 Wakonade Dr. East Welch. Minnesota 55089 September 4,1998 10 CFR 50.59 U S Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 PRA!RIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 Licenae Amendment Request Dated September 4,1998 Reactor Coolant Vent System Attached is a request for a change to the Technical Specifications, Appendix A of the Operating Licenses, for the Prairie Island Nuclear Generating Plant. Northern States Power Company submits this request in accordance with the provisions of 10CFR50.90. This amendment request proposes to clarify the surveillance requirements and limiting conditions for operability for the Reactor Coolant Vent System. This submittal also satisfies a recent corrective action commitment made in LER 1-98-09.
The current Technical Specifications require that the reactor coolant vent valve testing should be performed at the end of each refueling outage to demonstrate vent system operability. Because the solenoid operated vent valves have on occasion failed their surveillance testing and required repairs, if the valve surveillance testing is performed at the end of the outage this situation has the potential to delay a unit's return to service.
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Unit 2 will begin a refueling outage on November 7,1998 that is scheduled to continue l
until December 22,1998. To reduce the probability that reactor coolant vent valve surveillance testing will delay the return to service of this unit after its refueling outage, p\\
98o9100359 980904 DR ADOCK 0500o282' PDR g
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License Amendment Request dated Sept mber 4,1998 Pag) 2
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NSP requests that this license amendment is granted prior to the completion of this Unit 2 outage.
1 Exhibit A contains a description of the proposed change, the reasons for requesting the change, the supporting safety evaluation, and the significant hazards determination.
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Exhibit B contains current Prairie Island Technical Specification pages marked up to show the proposed change. Exhibit C contains the revised Prairie Island Technical Specification pages incorporating the proposed change.
j If you have any questions related to this license amendment request, please contact John Stanton at 612-388-1121 x4083.
l Joel P. Sorensen
- Plant Manager Prairie Island Nuclear Generating Plant Attachments:
Affidavit Exhibit A, Evaluation of Proposed Changes to the Technical Specification Appendix A of Operation License DPR-42 and DPR-60.
Exhibit B, Marked Up Technical Specification Pages Exhibit C, Revised Technical Specification Pages c:
Regional Administrator-Ill, NRC NRR Project Manager, NRC Senior Resident inspector, NRC Kris Sanda, State of Minnesota J E Silberg
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