ML20212A242

Application for Amends to Licenses NPF-9 & NPF-17,deleting All References to Steam Line Low Pressure Safety Injection Function

ML20212A242
Person / Time
Site:	Mcguire, McGuire
Issue date:	10/06/1997
From:	Barron H DUKE POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20212A248	List: ML20212A242 ML20212A251
References
NUDOCS 9710230221
Download: ML20212A242 (5)

Text

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Duke Power Company A tal mamm A fu Amey respe' 0

12700 llagers Ferry Rd.

Ifuntersville, NC 28078-9340 H. B. Borron Yur besikns, Mdiuire (704) 875-4800 ornct Nu&ar Generation ikprement (704) 875-4809 fax October 6,1997 10 CFR 50.90 U.S. Nuclear Regulatory Commission Washington, D.C.

20555 Attention: Document Control Desk

Subject:

McGuire Nuclear Station Unit 1 Docket Number 50 369 McGuire Nuclear Station Unit 2 Docket Number 50-370 Attached is a proposed revision to the McGuire nuclear station technical specifications. The proposed revision involves a deletion of all references to the steam line low pressure safety injection function. The steam line low pressure safety injection actuation circuitry will be modified to remove the function upon approval of the technical specification change by the Nuclear Regulatory Commission.

Thera are no adverse nuclear safety consequences associated with the removal of the low steam pressure safety injection. A plant specific analysis has found that results of affected design basis accidents remain within acceptable limits. These analysis have been performed using Duke Power Company (now Duke Energy Corporation) methodologies previously approved by the NRC.

There is no adverse impact because the plant was equipped with redundant safety injection signals which actuate during design basis accidents.

- Westinghouse Electric Corporation has previously evaluated secondary side safety injection removal in WCAP-12762 " Secondary Side Safety injection Function Deletion Modification"

- submitted to the NRC in December 1990. In addition, WCAP 12114 "Si Reduction Feasibility Study" was also developed by Westinghouse Electric Corporation to evaluate the feasibility and benefits of secondary side safety injection removal. These evaluations were funded by the Westinghouse Owners Group. Catawba Nuclear Station which is operated by Duke Energy Corporation submitted a similar amendment which was previously approved by the NRC. #

9710230221 971006 () , f P" ^*" ""E ILElE!ElljIII,lill

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- U.S. Nuclear Regulatory Commission Page 2 -

The benefits available to Westinghouse pressurized water reactors is a reduction in spurious safety injections. A spurious safety injection has several consequences with regard to plant operation. Safety injections constitute a challenge to plant safety systems and can cause plant operating transients, in addition, spurious safety injections result to thermal cycles and present reactor operators with challenging operating conditions. An analysis of safety injections at Westinghouse plants indicate that approximately a 15% reduction in spurious safety injections result from elimination of secondary side safety injection. These benefits should be directly applicable to McGuire Nuclear Station.

Attachmont I contains_ final Technical Specification pagee for both current and standardized Technical Specifications. Attachment 11 contains marked up Technical Specifications for the current and standardized technical specifications. Attachment til contains a technical justification supporting the proposed change to technical specifications. Attachment IV contains a No Significard Hazards Evaluation and an environmental assessment.

This technical. specification amendment request has been reviewed by McGuire's Plant Operations Review Committee and Duke Energy Corporation's Nuclear Safety Review Board By copy of this letter the State of North Carolina has been notified of this proposed Technical Specification Amendment.

This submittal contains a regulatory commitment to revise the UFSAR following NRC approval of the requested amendment, This commitment is contained in Attachment 111. The plant modifications to support implementation of the Technical Specification must be implemented during an outage. The earliest implementation is currently scheduled for Unit 2 EOC 12 in February 1999. - Duke Energy r6 quests that NRC aoproval of the technical specification change reflect that each units change be implemented in the refueling outage associated with the plant hardware modifications.

Please contact Mike Cash (704) 375-4117 with questions regarding this submittal.

H.B. Barron, Jr.

- Site Vice President McGuire Nuclear Station l

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' U.S. Nuclear Regulatory Commission -

- Page 3 cc:

V. - Norses, Project Manager -

Office of Nuclear Reactor Regulation

U.S. Nuclear Regulatory Commission Mail Stop O 14 H35- '

1 Washington, DC E 20555 -

LA. Reyes, Regional Administrator U.S. Nuclear Regulatory Commission - Region 11 Atlanta Federal Center

61 Forsyth Street Suite 23T85 Atlanta, Georgia 30303-M. Sykes, Acting Senior Resident inspector

- Nuclear Regulatory Commission McGuire Nuclear Station -

Richard M. Fry, Chief

= Division of Radiation Protection State of North Carolina 3825 Bamett Drive -

Raleigh, North Carolina - 27609 7221-

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' U.S. Nuclear Regulatory Commission Page 4 _

H.B. Barron, Jr, , being duty swom, states that he is a Vice President of Duke Energy Corporation; _

that he is authorized on the part of said corporation to sign and file with the Nuclear Regulatory Commission revisions to the Facility Operating Licenses of McGuire Nuclear Station; and that all

' the statements and matter set forth herein are true and correct to the best of his knowledge, y

H.B. Barron, Jr. Vice President McGuire Nuclear Station Duke Energy Corporation Subscribed and swom before me this ,M N day of /)n /oL> >.1997

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Notary Public

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M.T. Cash (MNS)

P.R. Newton (General Office)

G.A. Copp (General Office)

NSRB Staff ELL o