ML20077R505

Forwards Application for Amends to Licenses DPR-42 & DPR-60, Revising Event Monitoring Instrumentation TS to Conform to Std TS for Post Accident Monitoring

ML20077R505
Person / Time
Site:	Prairie Island
Issue date:	01/10/1995
From:	Wadley M NORTHERN STATES POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20077R511	List: ML20077R505 ML20077R515 ML20077R522
References
NUDOCS 9501200307
Download: ML20077R505 (2)

Text

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l Nodhem States Power Company l 1

Pralrie Island Nuclear Generating Plant 1717 Wakonade Dr. East Welch, Minnesota 55089 l

January 10, 1995 10 CFR Part 50 Section 50.90 U S Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 PRAIRIE ISIAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 License Amendment Request Dated January 10, 1995 Post Accident Monitoring Technical Specifications Conformance to Standard Technical Specifications Attached is a request for 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. The requested amendment will revise the Prairie Island Event Monitoring Instrumentation Technical Specifications to conform to Standard Technical Specifications for post accident monitoring.

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

Please consider this License Amendment Request as a Cost Beneficial Licensing Action (CBLA) item in that these amendments may reduce NSF costs by more than

$100,000 over the life of the plant and deal with changes which improve plant safety or have low safety significance.

Prairie Island is submitting this conversion of the post accident monitoring Technical Specifications as the lead plant in a cooperative effort with the other Westinghouse two loop plants. Representatives from Rochester Gas and Electric (Ginna), Wisconsin Electric Power (Point Beach) and Wisconsin Public Service (Kewaunee) have reviewed and support this submittal.

I ereer 1uVUUd 9501200307 950110 PDR ADOCK 05000282 ii P PDR , \

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USNRC -

January 10, 1995 ,

Page 2 l If you have any questions related to this License Amendment Request please l contact myself or Dale Vincent at 612-388-6758 X4107.  ;

/h / hb t 6d bl M. D. Wadley j Plant Manager l Prairie Island clear Cenerating Plant i i

c: Regional Administrator-III, NRC NRR Project Manager, NRC  ;

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Senior Resident Inspector, NRC State of Minnesota ,

Attn: Kris Sanda J E Silberg  ;

Mark Flaherty, RC&E [

Tom Malinowski..WEP ,

Pat Michalkiewicz, WPS Attachments: ,

v Affidavit i

Exhibit A - Description of Proposed Changes the Reasons for Requesting the Changes, and the supporting Safety Evaluation /Significant  ;

llazards Determination Exhibit B.- Technical Specification Marked Up Pages  !

Exhibit C - Revised Technical Specification Pages I

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