ML20080B540
| ML20080B540 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 11/30/1994 |
| From: | Wadley M NORTHERN STATES POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20080B542 | List: |
| References | |
| NUDOCS 9412050284 | |
| Download: ML20080B540 (2) | |
Text
A7 Northern States Power Company Prairie latand Nuclear Generating Plant 1717 Wakonade Dr. East Welch, Minnesota 55089 l
November 30, 1994 10 CFR Part 50 Section 50.90 U S Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 l
PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR 42 50-306 DPR-60 Supplement to License Amendment Request Dated October 3, 1994 Emernency Diesel Generator Testing Requirements i
On October 3, 1994, we submitted a License Amendment Request.
The main i
purpose of this License Amendment Request is to provide a wider band during the 24-hour load test which is performed every 18 months. The specification currently calls for a 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> run at 105 - 110% of the continuous load rating of the diesel generator.
This range is too narrow when we consider the l
potential instrument error and the inherent load swings associated with running the diesel generator connected to the system grid.
The proposed specification provides a range of a load of 103 - 110% of the continuous rating.
During subsequent discussions with NRC staff we agreed to additional changes.
These additional changes are reflected in the attached revised page changes to the Technical Specifications, Appendix A of the Operating Licenses, for Prairie Island Nuclear Generating Plant, Units 1 and 2.
The attached Exhibit B, Rev 1 and Exhibit C, Rev 1 replace the original Exhibits B and C in their entirety.
The significant hazards analysis and safety evaluation submitted with the l
October 3, 1994 License Amendment Request still apply since the additional changes restate the proposed requirements in a way which preserves the intent of the originally submitted proposal. As discussed with Sheri Peterson, we want to note that there is an error on Page 3 of Exhibit A of the October 3, 1994 letter.
It states that the highest anticipated event load for Unit 1 is 2414 kW when, in fact it is 2510 kW.
This is a less conservative value but remains more conservative than the regulatory guidance for sizing emergency diesel generators and therefore represents an acceptable decrease in margin.
l Thus, the discussion in the significant hazards analysis and safety evaluation remains valid.
l 00 941205o2g4 941130 DR ADDCK 05000282 d
l PDR i
I Northem States Power Company USNRC Page 2 of 2 November 30, 1994 i
Please contact Jack Leveille (612-388-1121, Ext. 4662) if you have any j
questions concerning this License Amendment Request.
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f.et Michael D Wadley Site General Manager Prairie Island Nuclear Generating Plant c: Regional Admini9trator-Region-III, NRC NRR Project Manager, NRC Senior Resident Inspector, NRC State of Minnesota Attn:
Kris Sanda J E Silberg Attachments:
Affidavit Exhibit B, Rev 1 -
Proposed Changes Marked-up on Existing Technical Specification Pages Exhibit C, Rev 1 -
Revised Techr i cal Specifications Pages I
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