ML20210H993

Amend 253 to License DPR-59,changing TS Which Extend EDG Allowed Outage Time from 7 to 14 Days.Changes Also Include Revised Requirements for EDG Testing at Power & Revised AC Power Requirements for Cold Shutdown & Refueling Modes

ML20210H993
Person / Time
Site:	FitzPatrick
Issue date:	07/30/1999
From:	Bajwa S NRC (Affiliation Not Assigned)
To:
Shared Package
ML20210H996	List: ML20210H993 ML20210J006
References
NUDOCS 9908040160
Download: ML20210H993 (7)

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j NUCLEAR REuvLA.'ORY COMMISSION t

WASHINGTON, D.C. 20555-0001 49.....,o POWER AUTHORITY OF THE STATE OF NEW YORK DOCKET NO. 50-333 JAMES A. FITZPATRICK NUCLEAR POWER PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 253 License No. DPR-59

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1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by the Power Authority of the State of New York (the licensee) dated January 25,1996, as supplemented on April 26,1996, September 12, 1996, March 17,1997, September 9,1997, December 30,1998, and May 19,1999, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment

)

can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations-D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and i

E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-59 is hereby amended to read as follows:

9900040160 990730 PDR ADOCK 05000333 p

PDR

. (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 253and the Environmental Protection Plan contained in Appendix B are incorporated into Facility License No. DPR-59. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

2.

This license amendment is effective as of the date of its issuance, to be implemented within 60 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION ff.

S. Singh Bajwa, Chief,Section I Project Directorate l Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: July 30, 1999 J

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l.I' ATTACHMENT TO LICENSE AMENDMENT NO 253 FACILITY OPERATING LICENSE NO. DPR-59 l

DOCKET NO.60-333 f

i Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

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224 224 258f f

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JAFNPP 6.21 CONFIGURATION RISK MANAGEMENT PROGRAM The Configuration Risk Management Program (CRMP) provides a proceduralized risk-l informed assessment to manage the risk associated with equipment inoperability.

l The program applies to technical specification structures, systems, or components I

l for which a risk-informed allowed outage time has been granted. The program is to l

include the following:

Provisions for the control and implementation of a Level 1 at-power internal a.

events PRA-informed methodology. The assessment is to be capable of evaluating the applicable plant configuration.

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b.

Provisions for performing an assessment prior to entering the plant

)

configuration described by the Limiting Conditions for Operation (LCO)

Action Statement for preplanned activities,

)

Provisions for performing an assessment after entering the plant c.

configuration described by the LCO Action Statement for unplanned entry

}

into the LCO Action Statement.

d.

Provisions for assessing the need for additional actions after the discovery of additional equipment-out-of-service conditions while in the plant configuration described by the LCO Action Statement.

Provisions for considering other applicable risk-significant contributors such.

e.

as Level 2 issues and external events, qualitatively or quantitatively, i

l l

l Amendment No. 253 l

1 258f f