ML20059L343

Forwards Application for Amends to Licenses DPR-42 & DPR-60, Revising Tech Spec Section 6.7.A.6.b

ML20059L343
Person / Time
Site:	Prairie Island
Issue date:	09/13/1990
From:	Parker T NORTHERN STATES POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20059L347	List: ML20059L343 ML20059L356 ML20059L358
References
NUDOCS 9009260251
Download: ML20059L343 (2)

Text

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, ., A Nonham gemens Power company 414 Nicol 6et Mall Minneapohs. Minnesota 554011927 Telephone (612) 330 5N September 13, 1990 10 CFR Part 50 Oection 50.90 Director of Nuclear Reactor Regulation U S Nuclear Regulatory Commission Attn: Doct s ent Control Desk Washington, DC 20555 PRAIRIE ISTAND NUCLEAR GENERATING PLANT Docket Nos. 50 282 License Nos. DPR 42 50 306 DPR-60 License Amendment Request Dated September 13, 1990 Addition of Referente to Accroved Methodolorv 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 rabmitted in accordance with the provisions of 10 CFR Part 50, Section 50.90.

Docum nts that describe the NRC approved analytical methods used to determine the core operating limits are specified in Technical Specification Section 6.7.A 6.b. Westinghouse Topical ' ; port WCAP-10924-P, Volume 1. Addenda 4,

" Westinghouse Large Break LOCA Bost Estimate Methodology", August, 1990, describes model revisiens to the approved WCOBRA/ TRAC code to address an error found in the WCOBRA/ TRAC decay heat model. The topical was submitted for NRC review and approval by Westinghouse Electric Corporation letter dated September 5, 1990.

This license amendment has been submitted to incorporate a reference to the revised methodologies described in WCAP 10924 P into the Prairie Island Technical Specifications following approval by the NRC Staif. The revised methodologies must be incorporated into Section 6.7. A.6.b so the model revisions can be used in the determination of the core operating limits.

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Director of NRR

• September 13, 1990 Page 2 Exhibit A contains a description of the proposed change, the reasons for requesting the change and a Safety Evaluation / Determination of Significant Hazards Considerations. Exhibit B contains a current Te.hnical Specification page marked up to show the proposed changes. Exhibit 0 contains the revised Technical Specification pages.

Because the proposed Technical Specification change is incorporating a reference to a Westinghouse topical report presently under review by the NRC Staff, we request that the review and approval of this License Amendment Request be coordinated with the review and approval nf WCAP 10924 P.

Please contact us if you have any questions related to this request.

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Thomas M Parker Manager Nuclear Support Services c: Regional Administrator Region III, NRC Senior Resident Inspector, NRC NRR Project Manager, NRC MPCA Attn: J W Ferman C Charnoff Attachments:

Affidavit  !

Exhibit A Evaluation of Proposed Changes to the Technical Specifications i

Exhibit B - Proposed Changes Marked Up on Existing Technical Specification l Page

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Exhibit C - Revised Technical Specification Page

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