ML20011F259

Amend 152 to License DPR-59,eliminating Requirement to Manually Scram Reactor from Control Rod Configuration of Less than or Equal to 50% Rod Density Once Per Operating Cycle

ML20011F259
Person / Time
Site:	FitzPatrick
Issue date:	02/15/1990
From:	Capra R Office of Nuclear Reactor Regulation
To:
Shared Package
ML20011F260	List: ML20011F259
References
NUDOCS 9003020266
Download: ML20011F259 (5)

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4*o UNITED STATES -

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_ 28 NUCLEAR REGULATORY COMMISSION o-

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I' WASHINGTON, D. C,20555 POWER AUTHORITY OF THE STATE OF NEW YORK-DOCKET N0.~50-333 JAMES A. FITZPATRICK NUCLEAR POWER PLANT-AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.152 License No. DPR-59 1.

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

A.

The application for amendment by Power Authority of the State of New York (the licensee) dated October 13, 1987, with amplifying information supplied by letter dated March 31, 1989, 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 Cosmission; C.

There is reasonable assurance (1) that the activities authorized by this-amendment can be conducted without e.tuangering 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 Comission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specificatione 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:

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_c (2)~ Technical Specifications The Technical Specifications-contained in Appendices

- A and B, as revised through Amendment No.152, 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 to be implemented within 30 days.

FOR THE NUCLEAR REGULATORY C0694!SSION 3 M G.. hp Robert A. Capra, Director Project Directorate I-1 Division of Peactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

. Changes-to the Technical Specifications

' Cate of Issuance:

February 15, 1990 e

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,S ATTACHMENT TO LICENSE AMENDMENT NO.152 i

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. FAC_TLITY' OPERATING LICENSE NO.' DPR-59 DOCKET N0. 50-333

'Pevise Appendix-A as'follows:

I Remove Pages Insert Pages 89a 89a 90-

-90

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33 (cont'd) 43 (cont'd) b.

The control rod directional control valves for e.

When it is initially determoed that a control rod is inoperable ccntrol rods shall be disarmed mcapable of normal insertion, an attempt to fully electrically.

msert the control rod shall be rnade. If the control r

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Control rods with scram times greater than those to wum-rate

%N permitted by Specification 33.C3 are inoperable, cae can M M h<p, h any.

but if they can be inserted with control rod drive reactW Ms W h rh m pressure they need not be disarmed electrically.

operating cycle with the analytically determmed, d.

Control rods with a failed " Full-in* or " Full-out" highest worth control rod capable of witt4rawal, fully position switch may be bypassed in the Rod withdrawn, and all other control rods capaths of.

Sequence Control System and considered operable msertion fully inserted. If Specificahon 33A1 and if the actual rod position is known. These rods must 43A1 are met, reactor startup may proceed.

be moved in sequence to their correct positions (full f.

The scram discharge volume drain and vent valves in on ' sertion W W on WawaQ.

m shall be fuu-travel cycled at least once per quarter to e.

Control rods with inoperable accumulators or those venfy that the valves close in less than 30 seconds whose position cannot be positively determined and to assure proper valve stroke and operahon.

shall be considered inoperable.

f.

Inoperable control rods shall be positioned such that Specification 3.3A1 is met. In addition, during reactor power operation, no more than one control rod in any 5 X 5 array may be inoperable (at least 4 operable control rods must separate any 2 inoperable ones). If this specification cannot be met the reactor shall not be started, or if at power, the reactor shall be brought to a cold condition wittia 24 hrs.

Amendment No. }s,C/[76,1pf 152 89a

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