ML20205T624

Forwards Application for Amends to Licenses DPR-42 & DPR-60, Changing Tech Spec Sections 3.15 & 4.1 Re Inadequate Core Cooling Instrumentation,Per Generic Ltrs 82-28 & 83-37.Fee Paid

ML20205T624
Person / Time
Site:	Prairie Island
Issue date:	06/06/1986
From:	Musolf D NORTHERN STATES POWER CO.
To:	Office of Nuclear Reactor Regulation
Shared Package
ML20205T628	List: ML20205T624 ML20205T634 ML20205T637
References
RTR-NUREG-0737, RTR-NUREG-737 GL-82-28, GL-83-37, NUDOCS 8606160117
Download: ML20205T624 (2)

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Northern States Power Company 414 Nicollet Mall Minneapoks. Minnesota 55401 Telephone (612) 330-5500 June 6, 1986 Director Office of Nuclear Reactor Regulation U S Nuclear Regulatory Commission Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 License Amendment Request Dated June 6, 1986 Inadequate Core Cooling Instrumentation Changes Attached are three originals and 37 conformed copies of a request for a change to the Technical Specifications, Appendix A, of Operating Licenses DPR-42 and DPR-60. This request is submitted in accordance with the provisions of 10 CFR Part 50, Section 50.90. A check is attached in the amount of $150,00 in accordance with the requirements of 10 CFR Part 170 for the amendment application fee.

In response to Generic Letter 82-28, " Inadequate Core Cooling Instrumentation System", modifications were made to the Prairie Island plants to provide instrumentation for detection of inadequate core cooling, consisting of subcooling margin monitors, core-exit thermocouples and reactor vessel level instrumentation systems (RVLIS). Generic Letter 83-37, "NUREG-0737 Technical Specifications", identified NUREG-0737 items for which Technical Specifications are required and requested Technical Specification changes for the inadequate core cooling instrumentation. In response to that request, this submittal proposes changes to Sections 3.15 and 4.1 of the Prairie Island Technical Specifications.

Your May 13, 1985 Safety Evaluation and Request for Additional Information requested the submittal of model technical specifications specific for Prairie Island covering the requirements for the inadequate core cooling instrumentation. Model technical specifications, incorporating the inadequate core cooling instrumentation, were provided in our letters dated June 18, 1985, October 22, 1985 and April 4, 1986. Those proposed technical specifications were reviewed by the NRC Staff and were found to be acceptable in the NRC Implementation of the Inadequate Core Cooling Instrumentation System Safety Evaluation Report, dated May 8, 1986. The changes proposed by this License Amendment Request are the same as those g found acceptable in the May 8,1986 Safety Evaluation Report, with the exception of administrative changes required to fit the revisions into the current Technical Specification text and a revision to the Table of Contents resulting from the proposed change. L0/p 8606160117 860606 PDR ADOCK 05000282 PDR gb b ka P

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Director NRR Northem States Power Company June 6, 1986 Page 2 Exhibit A describes the proposed changes, reason for the changes and significant hazards considerations evaluation. Exhibit B contains the revised Technical Specification pages.

Please contact us if you have any questions concerning this License Amendment Request or if additional information is required to supplement it.

m David Musolf Manager - Nuclear Support Services DMM/EFE f efe c: Regional Administrator-III, NRC NRR Project Manager, NRC Resident Inspector, NRC MPCA Attn: F W Ferman G Charnoff Attachments L /