ML20091E964

Amend 79 to License DPR-59,revising Min Critical Power Ratio Operating Limits to Restore Safety Margin Which Was Reduced as Result of Changes in Control Valve Operation

ML20091E964
Person / Time
Site:	FitzPatrick
Issue date:	05/08/1984
From:	Vassallo D Office of Nuclear Reactor Regulation
To:	Power Authority of the State of New York
Shared Package
ML20091E971	List: ML20091E964 ML20091E972
References
DPR-59-A-079 NUDOCS 8406010428
Download: ML20091E964 (5)

Text

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NUCLEAR REGULATORY COMMISSION 3.y '

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POWER AUTHORITY OF THE STATE OF NEW YORK DOCKET NO. 50-333 JAMES A. FIT 2 PATRICK NUCLEAR POWER PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 79 License No. DPR-59 1.

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

A.

The application for amendment by the Power Authority of the State of New York (the licensee) dated December 28, 1983, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

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

There is reasonable assurance (1) 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 Comission's regulations; n

D.

The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specificaitons as indicated in the attachment to this license amendment and paragraph 2.C(2) of Facility Operating License No.

4 DPR-59 is hereby amended to read as follows:

8406010428 840508 PDR ADOCK 05000333 P

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. l (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 79, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

')hh Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: May 8, 1984 e

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ATTACHMENT TO LICENSE AMENDMENT N0. 79 FACILITY OPERATING LICENSE NO. DPR-59 DOCKET NO. 50-333 1.

Revise the Appendix "A" Technical Specifications as follows:

Remove Replace 31 31 47b 47b i

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3.1 (CONTItWED) 4 HCPR Operating Limit for Incremental C. MCPR shall be determined daily during Cycle Core Average Exposure reactor power operation at 3 25% of rated thermal power and following any change in power level or distribution At Rifi lii-trip DOC to EOC-2G0/t to DOC-1GiD/t that would cause operation with a limiting level mttinq 12r-2Go/t doc-loo /t to EOC control rod pattern as described in the bases for Specification.3.3.B.S.

l S=

.66W + 391 1.21 1.25 1.30 D. When it is determined that a channel has failed in the unsafe condition, the S '=.66W + 401 1.22 1.25 1.30 other RPS channels that monitor the same variable shall be functionally 5

S=.66W t 411 1.24 1.25 1.30 tested immediately before the trip

+

system containing the failure is tripped.

S=

.66W t 421 1.25 1.25 1.30 The trip system containing the unsafe failure may be placed in the untripped S=

.66W + 43%

1.27 1.27-1.30 condition during the period in which surveillance testing is being performed S=

.66W + 441 1.33 1.33

, 1.33 on the other RPS channels.

E. Verification of the limits set forth in specification 3.1.B shall be performed ac follows:

1.

The average scram time to notch position 38 shall be ggg 2.

The average scram time to notch position 38 is determined as follows:

I Ni fi Hi

=

AVE i=1 i=1 where: n = number of, surveillance tests performed to date in the cycle, Ni =

number of active rods measured in Amendn.entNo.[,

, 79 3g 3

Figura 3.1-2 Versus T (perating Limit MCPR O

defined in Section 3.1.B.2)

FOR ALL FUEL TYPES i

(1,1.42) i

- 1.40 1,40 l

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(1,1.37) 1 to

- 1.35 1.35 W

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3 1.30

- 1.30

l. (0,1.30)

(0.667,1.297) en m

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- 1.25

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c goc t (0.312,1.219) 1.20 -i

- 1.20 (0,1.20) l l

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Amendment No g,g, 79 47b p

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