ML20196G009

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Amend 246 to License DPR-59,changing TSs in Response to 980803 Application,As Supplemented on 981020,requesting Rev of Note to Allow Applicability of MCPR Safety Limit to Cycle 14
ML20196G009
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 11/25/1998
From: Bajwa S
NRC (Affiliation Not Assigned)
To:
Shared Package
ML20196G011 List:
References
NUDOCS 9812070190
Download: ML20196G009 (4)


Text

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UNITED STATES j

NUCLEAR REGULATORY COMMISSION 2

WASHINGTON, D.C. enama anni

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POWER AUTHORITY OF THE STATE OF NEW YORK l

DOCKET NO. 50-333 JAMES A. FITZPATRICK NUCLEAR POWER PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 246 License No. DPR-59 1.

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

A.

The application for amendment by Power Authority of the State of New York (the licensee) dated August 3,1998, as supplemented on October 20, 1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and 1

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 Comrnission*

i 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 E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Cornmission'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:

9812070190 981125 PDR ADOCK 05000333 P

PDR i

2 (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment 4

No. 246 and the Environmental Protection Plan contained in Appendix B are incorporated into Facility License No. DPR-59. PASNY shall operate the facility in I

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 before startup for Cycle 14.

FOR THE NUCLEAR REGULATORY COMMISSION S. Singh Bajwa, Director Project Directorate 1-1 Division of Reactor Projects - 1/11 1

Office of Nuclear Reactor Regulation j

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Attachment:

Changes to the Technical l

Specifications Date of issuance:

November 25, 1998 1

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ATTACHMENTTO LICENSE AMENDMENT NO. 246 FACILITY OPERATING LICENSE NO. DPR-59 DOCKET NO. 50-333 Revise Appendix A as follows:

Remove Paae Insert Paae j

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JAFNPP 1.1 FUEL CLADDING INTEGRITY 2.1 FUEL CLADDING INTEGRITY Acolicability:

Anoticabilitv:

Tha Safety Limits established to preserve the fuel cladding The Limiting Safety System Settings apply to trip settings of the int:grity apply to those variables which monitor the fuel thermal instruments and devices which are provided to prevent the fuel beh vior, cladding integrity Safety Limits from being exceeded.

Obiective:

Obiective:

The objective of the Safety Limits is to establish limits below The objective of the Limiting Safety System Settings is to define which the integrity of the fuel cladding is preserved.

the level of the process variables at which automatic protective action is initiated to prevent the fuel cladding integrity Safety Limits from being exceeded.

Soecifications:

Soecifications:

A.

Trio Settinas A.

Reactor Pressure >785 osia and Core Flow > 10% of Rated The limiting safety system trip settings shall be as specified below:

The existence of a minimum critical power ratio (MCPR) less than 1.09 shall constitute violation of the fuel cladding 1.

Neutron Flux Trio Settinas integrity safety limit, hereafter called the Safety Limit. An MCPR Safety Limit of 1.10 shall apply during single-loop a.

IRM - The IRM flux scram setting shall be set at operation.

s:120/125 of full scale.

l Not:: TS 1.1.A is applicable for Cycle 14 only.

1 Amendment No. 14, 21, 00, 43, 00, 117, 157, 200, 246 7

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