ML20205Q019

Forwards Application for Amend to License DPR-42 & DPR-60, Relocating Shutdown Margin Requirements from TS to COLR

ML20205Q019
Person / Time
Site:	Prairie Island
Issue date:	04/12/1999
From:	Sorensen J NORTHERN STATES POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20205Q023	List: ML20205Q019 ML20205Q026 ML20205Q035
References
NUDOCS 9904210065
Download: ML20205Q019 (2)

Text

. l Northern States Power Company Prairie Island Nuclear Generating Plant 1717 Wakonade Dr. East Welch, Minnesota 55089 April 12,1999 10 CFR 50.90 U S Nuclear Regulatory Commission ,

Attn: Document Control Desk l Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 License Amendment Request Dated April 12,1999 l Relocation of Shutdown Margin Requirements l to the Core Operating Limits Report l

Attached is a request for a change to the Technical Specifications, Appendix A of the l Operating Licenses, for the Prairie Island Nuclear Generating Plant. Northern States l Power Company submits this request in accordance with the provisions of 10CFR50.90. f/

This License Amendment Request proposes to relocate the shutdown margin l requirements from the Technical Specifications to the Core Operating Limits Report &/

(COLR). The shutdown margin limits being incorporated into the COLR will be developed utilizing methodology described in NSPNAD-8102-P, Revision 7, " Prairie Island Nuclear Power Plant Reload Safety Evaluation Methods For Application to PI Units." Revision 7 of NSPNAD-8102-P was submitted for NRC review and approval on January 29,1999. That methodology will establish the minimum required shutdown margin for a dilution accident during MODES 3,4,5 and 6.

The refocation of the shutdown margin requirements to the COLR have been previously approved by the NRC for the Technical Specifications Task Force on September 18, 1996.

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l Exhibit A contains a description of the proposed changes, the reasons for requesting the changes, the supporting safety evaluation, and the significant hazards

! determination. Exhibit B contains current Prairie Island Technical Specification pages l marked up to show the proposed changes. Exhibit C contains the revised Prairie Island l Technical Specification pages incorporating the proposed changes. Exhibit D contains a sample of the shutdown margin requirements being incorporated into the COLR. )

Exhibits E and F contain a page from License Amendm'ent 141 that has been revised to l reflect a change proposed by this License Amendment Request.

If you have any questions related to this license amendment request, please contact John Stanton at 651-388-1121.

4 Joel P. Sorensen Site General Manager Prairie Island Nuclear Generating Plant c: Regional Administrator-lil, NRC NRR Project Manager, NRC Senior Resident inspector, NRC Steve Minn, State of Minnesota J E Silberg Attachments:

Affidavit Exhibit A, Evaluation of Proposed Changes to the Technical Specifications Appendix A of Operating Licenses DPR-42 and DPR-60.

Exhibit B, Marked Up Technical Specification Pages Exhibit C, Revised Technical Specification Pages Exhibit D, Sample of Core Operating Limits Report Shutdown Margin Requirements l Exhibit E, Marked Up Page From License Amendment 141 Exhibit F Revised Page From License Amendment 141 l