ML20096D630

Forwards Application for Amends to Licenses DPR-42 & DPR-60, Requesting Relocation of Containment Penetration List from Section 4.4 of Ts,Per Generic Ltr 91-08, Removal of Component Lists from Tech Specs

ML20096D630
Person / Time
Site:	Prairie Island
Issue date:	05/07/1992
From:	Parker T NORTHERN STATES POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20096D632	List: ML20096D630 ML20096D679 ML20096D685
References
GL-91-08, GL-91-8, NUDOCS 9205180164
Download: ML20096D630 (2)

Text

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Northem States Power Company 414 Nicollet Mall Minneapohs. Minnesota 55401 1927 Telephone (612) 330-5500 May 7, 1992 10 CFR Part 50 Section 50.90 U S Nuclear-Regulatory Commission Attn: Document Control Desk ,,

Washington, DC 20555 PRAIRIE ISIAND NUCLEAR GENERATING PiANT Docket Nos. 50 282 License Nos. DPR-42 50-306 DPR-60 License Amendment Request Dated May 7, 1992 Containment Penetration List Removal and Miscellaneous Charmes Attached are requests for changes to the Technical Specifications, Appendix A of the Operating Licenses, for the Prairie Island Nuclear Generating Plant. These requests are submitted in accordance with the provisions of 10 CFR Part 50, Section 50.90.

The first license amendment request proposes the relocation of the Containment Penetration List from Section 4.4 of the Prairie Island Technical Specifications -

into plant procedures per the guidance in Generic Letter-91-08, " Removal of Component Lists From Technice' Specifications".

The second license amendment request proposee. changes to Section 3.6.C of the Prairie Island Technical Specifications which will clarify when non-automatic containment isolation valves are required to be operable and what actions are to be taken - in response to the inoperability of a non-automatic containment isolation valve.

The third license amendment request proposes the deletion of condensate cross 3

connect valve C-41-1 from-Section 3.4.B. l .g of the Prairie Island Technical Specifications.

Exhibit A contains a description of the proposed changes, the reasons for requesting the changes and the supporting safety evaluation /significant hazardr r

determination. Exhibit B contains current Prairie Island Technical Specification pages marked up to show the proposed changes. Exhibit C contains the revised Technical Specification pages.

920'180164 920507 5 q\ l PDR ADOCK 05000282 l I g P PDR

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Northern States Power Company USNRC May 7, 1992 s Page 2 Please contact us if you have any questions related to these License Amendment Requests,

/ '550 $1 Thomas M Parker Manager c Nuclear Support Services _

c: Regional Administrator-III, NRC NRR Project Manager, NRC Senior Resident Inspector, NRC State of Minnesota Attn: Kris Sanda J E Silberg Attachments:

Affidavit Exhibit A Evaluation of Proposed Chenges to the Technical Specifications Exhibit B - Proposed Changes Marked Up on Existing Technical Specification Pa60s Exhibit C - Revised Technical Specification Pages _

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