ML20077Q620
| ML20077Q620 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 01/13/1995 |
| From: | Wadley M NORTHERN STATES POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20077Q630 | List: |
| References | |
| NUDOCS 9501190304 | |
| Download: ML20077Q620 (2) | |
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4 Northern States Power Company Prairie Island Nuclear Generating Plant 1717 Wakonade Dr. East 1
Welch. Minnesota 55089
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January 13, 1995 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 Amendment Request Dated ?anuary 13, 1995 Extension of Residual Heat Removal Leakaze Test Interval 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 a revision to Technical Specification (TS) 4.4.D.1 to change the interval for the performance of the Residual Heat Removal (RHR) System leakage test from once every 12 months to perform the test during each refueling shutdown.
Exhibit A contains a description of the proposed changes, the reasons for requesting the changes, the supporting safety evaluations and significant hazards determinations.
Exhibit B contains current Prairie Island Technical Specification pages marked up to show the proposed changes.
Exhibit C contains the revised Technical Specification pages.
As discussed in the attached submittal, the RHR System Leakage Test, as currently performed, utilizes reactor coolant via the letdown line to pressurize the RHR System piping. The current activity levels in the Unit 2 reactor coolant system have raised some concerns with the performance of the RHR System Leakage Test during power operation before the March 24, 1995 due date. While there are alternative methods for performing the test that would not involve Unit 2 reactor coolant, it is preferred in the long term, as stated in the attached submittal, to perform this test during a refueling shutdown. Therefore, we would like to defer the performance of the Unit 2 RHR j
leakage test to the May 1995 refueling outage.
That deferral would require the attached license amendment request to be approved by March 24, 1995.
If Commission approval of the proposed license amendment is not possible, an alternate test method will be developed and the test will be performed by the March 24, 1995 due date.
9501190304 950113 g
PDR ADDCK 05000282 P
j USNRC Northern States Pewer Company i
January 13, 1995 Page 2 This letter contains no new NRC commitments. Please contact Gene Eckholt l
(612-388-1121, ext 4663) if you have any questions related to this License l
Amendment Request.
l
[)( lbAkL Mike Wadley i
Plant Manager l
Prairie Island Nuclear Generating Plant
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I c: Regional Administrator-III, NRC NRR Project Manager, NRC Senior Resident Inspector, NRC State of Minnesota (w/o proprietary attachment)
Attn: Kris Sanda J E Silberg (w/o proprietary attachment)
Attachments:
Affidavit Exhibit A - Evaluation of Proposed Changes to the Technical Specifications Exhibit B - Proposed Changes Marked Up on Existing Technical Specification Pages I
Exhibit C - Revised Technical Specification Pages b
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