ML20141F475
| ML20141F475 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 05/15/1997 |
| From: | Sorensen J NORTHERN STATES POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20141F481 | List: |
| References | |
| GL-95-05, GL-95-5, NUDOCS 9705210329 | |
| Download: ML20141F475 (2) | |
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Northern States Power Company Prairie Island Nuclear Generating Plant 1717 Wakonade Dr. East a
WeG. Minnesota 55089 May 15,1997 10 CFR Part 50 Section 50.90 U S 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 License Amendmut Request Dated May 15,1997 incorporation of Voltaae Based Steam Generator Tube Repair Criteria Attached is a request for a change to the Technical Specifications, Appendix A of the Operating Licenses, for the Prairie Island Nuclear Generating Plant. This request is submitted in accordance with the provisions of 10 CFR Part 50, Section 50.90.
This amendment request proposes changes to Technical Specifications 3.1.C,
" Reactor Coolant Systam Leakage" and 4.12, " Steam Generator Tube Surveillance".
The proposed changes would implement a voltage-based repair criteria per the requirements of NRC Generic Letter 95-05, " Voltage-Based Repair Criteria for Westinghouse Steam Generator Tubes Affected by Outside Diameter Stress Corrosion Cracking."
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Exhibit A contains a description of the proposed changes, the reasons for requesting h
the changes, the supporting safety evaluations and significant hazards determinations.
Exhibit B contains current and new Prairie Island Technical Specification pages marked
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up to show the proposed changes. Exhibit C contains the revised Technical Specification pages. Exhibit D contains the plan for implementation of the voltage-based repair criteria and Exhibit E contains the Westinghouse main steam line break
.g allowable leak rate analysis.
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We request that the propened license amendment request be issued by September 18, 1997 in order to support uw of the voltage-based repair criteria during the October 18, 1997 Unit 1 refueling outage.
200159 9705210329 970515
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USNRC NORTHERN STATES POWER COMPANY May 15,1997 Page 2 In this submittal we have made the following new Nuclear Regulatory Commission commitment-1 i
The voltage-based steam generator repair criteria will be implemented in accordance with the requirements of Generic Letter 95-05 as described in Exhibits j
A and D of this License Amendment Request.
Please contact Gene Eckholt (612-388-1121) if you have any questions related to this License Amendment Request.
oel P Sorensen Plant Manager Prairie Island Nuclear Generating Plant c: Regional Administrator-Ill, NRC NRR Project Manager, NRC Senior Resident inspector, NRC State of Minnesota, Attn: Kris Sanda J E Silberg Attechments:
Affidavit Exhibit A - Evaluation of Proposed Changes to the Technical Specifications Exhibit B - Proposed Changes Marked Up on Existing Technical Specification Pages Exhibit C - Revised Technical Specification Pages Exhibit D - Plan for Implementation of the Voltage-Based Repair Criteria Exhibit E - Westir.ghouse Main Steam Line Break Allowable Leak Rate Analysis e