ML20205T634

Application for Amends to Licenses DPR-42 & DPR-60,changing Tech Spec Sections 3.15 & 4.1 Re Inadequate Core Cooling Instrumentation

ML20205T634
Person / Time
Site:	Prairie Island
Issue date:	06/06/1986
From:	Musolf D NORTHERN STATES POWER CO.
To:
Shared Package
ML20205T628	List: ML20205T624 ML20205T634 ML20205T637
References
RTR-NUREG-0737, RTR-NUREG-737 GL-82-28, GL-83-37, NUDOCS 8606160119
Download: ML20205T634 (4)

Text

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UNITED STATES NUCLEAR REGULATORY COMMISSION NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket No. 50-282 50-306 REQUEST FOR AMENDMENT TO OPERATING LICENSE NOS. DPR-42 & DPR-60 License Amendment Request Dated June 6, 1986 Northern States Power Company, a Minnesota corporation, requests authorization for changes to the Technical Specifications as shown on the attachments labeled Exhibit A and Exhibit B. Exhibit A describes the proposed changes along with reasons for the change. Exhibit B is a set of Technical Specification pages incorporating the proposed changes.

This letter contains no restricted or other defense information.

NORTHERN STATES POWER COMPANY By 3 kw David Musolf \

Manager - Nuclear Support Servicds On this 4-f/ day of dw , /9/[a before me a notary public in and for said County, personallf/ appeared David Musolf, Manager - Nuclear Support Services, and being first duly sworn acknowledged that he is authorized to execute this document on behalf of Northern States Power Company, that he knows the contents thereof and that to the best of his knowledge, information and belief, the statements made in it are true and that it is not interposed for delay.

8606160119 860606 PDR ADOCK 05000282 P PDR Sedu Du .k V

___ _______'_ _____________ __ ~

IfY ll BODY .BROSE NOTARY PUDLIC - MINNESOTA ll U

HENNEPIN COUNTY :

jj My commissiori Empires Dec. :6,1989 l ,

Exhibit A Prairie Island Nuclear Generating Plant License Amendment Request Dated June 6,1986 Evaluation of Proposed Changes to the Technical Specifications Appendix A of Operating License DPR-42 and DPR-60 Pursuant to 10 CFR Part 50, Sections 50.59 and 50.90, the holders of Operating Licenses DPR-42 and DPR-60 hereby propose the following changes to Appendix A, Technical Specifications:

Proposed Changes Technical Specification Sections 3.15 and 4.1 are being modified to incorporate operability and testing requirements associated with the inadequate core cooling instrumentation required by Generic Letter 82-28.

The specific changes are provided in Exhibit B.

Reason For Changes In response to Generic Letter 82-28, " Inadequate Core Cooling Instrumentation System", modifications were made to provide instrumentation for detection of inadequate core cooling (ICC). 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. These proposed technical specification changes are being submitted in response to that request.

Safety Evaluation and Determination of Significant Hazards Considerations Model technical specifications, incorporating the inadequate core cooling instrumentation requirements requested by the May 13, 1985 NRC safety evaluation and request for additional information , were provided to the Commission in our letters dated June 18, 1985, October 22, 1985 and April 4, 1986. Those proposed model technical specifications were reviewed by the NRC Staff and were found to be acceptable by the NRC in their Safety Evaluation Report, dated May 8, 1986. The changes proposed by this License Amendment Request are the same as those 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 changes.

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T The proposed change to the Operating License has been evaluated to determine whether it constitutes a significant hazards consideration as required by 10 CFR Part 50, Section 50.9 t using the standards provided in Section 50.92. This analysis is provided below:

1. The proposed amendment will not involve a significant increase in the probability or consequences of an accident previously evaluated.

The inadequate core cooling instrumentation required by Generic Letter 82-28, was installed to improve the reliability of plant operators in diagnosing the approach of inadequate core cooling and in assessing the adequacy of responses taken to restore core cooling. The proposed amendment incorporates operability and testing requirements designed to assure the operability of the inadequate core cooling instrumentation should it be required, and as such will not involve a significant increase in the probability or consequences of an accident previously evaluated.

2. The proposed amendment will not create the possibility of a new or different kind of accident from any accident previously analyzed.

The proposed amendment incorporates operability and testing requirements designed to assure that the inadequate core cooling instrumentation is available to aid plant operators in responding to accident conditions, and as such no different type of accident is created. No safety analyses are affected. The accident analyses presented in the Updated Safety Analysis Report remain bounding.

3. The proposed amendment will not involve a significant reduction in the margin of safety.

Because the proposed amendment is designed to assure the operability of the inadequate core cooling instrumentation, its incorporation into the Prairie Island Technical Specifications will not result in a reduction in the plant's margin of safety.

The Commission has provided guidance (March 6,1986 Federal Register) concerning the application of the standards in 10 CFR 50.92 for determining whether a significant hazards consideration exists by providing certain examples of amendments that will likely be found to involve no significant hazards considerations. The changes to the Prait t e Island Technical Specifications proposed in this amendment request are equivalent to NRC l example (ii), because they involve changes that constitute an additional i

limitations, restrictions or controls not presently included in the Technical Specifications.

For the reasons discussed above and because the NRC has already found the proposed technical specification changes to be acceptable in their May 8,1986 SER, we have concluded that the proposed inadequate core cooling instrumentation Technical Specifications do not involve a significant hazards consideration.

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Exhibit B Prairie Island Nuclear Generating Plant License Amendment Request Dated June 6, 1986 Proposed Changes to the Technical Specifications Appendix A of Operating Licenses DPR-42 and DPR-60 Exhibit B consists of revised pages of Appendix A Technical Specifications as listed below:

Page TS-iii TS.3.15-2 Table TS.3.15-1 Table TS.3.15-3 Table TS.4.1-1 (Page 4 of 5) i

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