ML19257A537

Application for Amend to Licenses DPR-42 & DPR-60,changing Auxiliary Feedwater Sys Tech Specs

ML19257A537
Person / Time
Site:	Prairie Island
Issue date:	12/31/1979
From:	Wachter L NORTHERN STATES POWER CO.
To:
Shared Package
ML19257A535	List: ML19257A534 ML19257A537 ML19257A538
References
NUDOCS 8001040581
Download: ML19257A537 (3)

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UNITED STATES NUCLEAR REGULATORY COMMISSION NORTilERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket No. 50-282 50-306 REOUEST FOR AMENDMENT TO OPERATING LICENSE NO. DPR-42 & DPR-60

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(License Amendment Request Dated December 31, 1979)

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. Exh ibi t B is a set of Technical Specification pages incorporating the proposed cha.ges.

This request contains no restricted or other defense information.

NORTilERN STATES POWER COMPANY By 0jfdj'jj, r3 Wachter

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Vice President, Power Production

& System Operation On this 31st day of December, 1979, before me a notary public in and for said County, personally appeared L J Wachter, Vice President, Power Production and System Operation, and br.ing first duly sworn acknowl-edged 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.

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EXHIBIT A Prairie Island Nuclear Generating Plant License Amendment Request dated December 31, 1979 Proposed Changes to the Technical Specifications Appendix A of Operating Licenses DPR-42 and -60 Pursuant to 10 CFR 50.59, the holders of Operating Licenses DPR-42 and DPR-60 hereby propose the following changes to Appendix A, Technical Specifications.

1. Table of Contents (page TS-i)

PROPOSED CHANGE Correct typographical errors,as indicated in Exhibit B, for TS Sections 3.10 and 3.14. Change title of 4.8 to " Steam and Power Conversion System".

REASON FOR CilANGE Self explanatory. Section 4.8 title should be changed to be con-sistent with the systems covered in the surveillance test specifica-tion.

SAFETY EVALUATION No ef fect on public health and safety.

2. Steam and Power Conversion System PROPOSED CHANGE Change pages TS 3.4-1 and -2 and TS 4.8-1 to read as shown on Exhibit B pages TS 3.4-1, TS 3.4-2, TS 4.8-1, and TS 4.8-2.

REASON FOR CHANGE Change s in these sections are being made to be consistent with an NRC request [ Letter, D Eisenhut (NRC) to L 0 Mayer (NSP), dated October 16, 1979)] which was discussed in Enclosure (1) of an NSP letter [L 0 Mayer (NSP) to Director of Nuclear Reactor Regulation (NRC), dated November 21, 1979]. In addition, system requirements are grouped together under system headings to more clearly highlight specific system requirements for the operations staf f.

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SAFETY EVALUATION Spe(Ification 3.4.A.2.a imposes a new requirement that a motor driven AFW pump and a turbine driven AFW pump be operable. Previously, for single unit operation two motor driven pumps cg; a motor driven and a turbine driven pump could meet the requirement of having two AFW pumps operable. Requirements for the turbine driven AFW pump provide assurance that AFW flow would be available in the highly unlikely event of a complete loss of AC power (normal and emergency). Reducing temperature to less than 350 F is consistent with the standarized Technical Specifications since AFW is not needed below that temperature.

Specification 3.4.A.2 imposes a new requirement that all valves that could result in a loss of system function be locked open. Previously many of these volves had been blocked and tagged (previous specifica-tion 3.4.A.)

Specification B imposes a new requirement that if the TD AFW pump is inoperable and cannot be restored to service that the unit be taken to hot shutdown, af ter a period of time consistent with the standardized technical specifications. If a MD AFW pump is inoperable a longer time period is allowed because the TD pump is available and the MD pumps can be directed to either unit.

Specification 4.8.A.6 requires new monthly inspections for critical valves outside containment. As noted in a letter, dated November 21, 1979 [L 0 Mayer (NSP) to Director of Nuclear Reactor Regulation (PRC)),

there is adequate confidence that valves inside containment vill not be repositioned during and after plant at artup.

Specification 4.8. A.7 is a new requirement requested in the NRC October 16, 1979 letter. The flow path verification is consistcet with operating practices carried out at the Prairie Island plant, as described in the November 21, 1979 NSP letter.

The section 4.8 basis is merely expanded to provide informat. ion to the operator as to the basis for the additional surveillance require-ments.

These changes, as requested by the NRC regulatory rtaf f, should not affect the health and safety of the pub?.ic.

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EXHIBIT B License Amendment Request dated December 31, 1979 Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 Exhibit B consists of revised pages of the Prairie Island Nuclear Generating Plant Technical Specifications, Appendix A, as listed below:

Pages (TS-)

i 3.4-1 3.4-2 4.8-1 and add new pages:

TS.3.4-3 TS.4.8-2 1691 049