ML20100B030

Forwards SPDS Parameter Safety Analysis Describing Basis That Selected Parameters Determined Both Necessary & Sufficient to Assess Safety Status for Wide Range of Events in Response to Generic Ltr 82-33 & Suppl 1 to NUREG-0737

ML20100B030
Person / Time
Site:	FitzPatrick
Issue date:	11/30/1984
From:	Corbin McNeil POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	Vassallo D Office of Nuclear Reactor Regulation
Shared Package
ML20100B034	List: ML20100B030 ML20100B058
References
RTR-NUREG-0737, RTR-NUREG-737 GL-82-33, JPN-84-79, NUDOCS 8412040167
Download: ML20100B030 (2)

Text

Y 123 Main Street White Plains, New York 10601 914 68US200

1. > NewYorkPbwer 4# Authority November 30,1984 JPN-84-79 Director of Nuclear Reactor Regulation U.S.

Nuclear Regulatory Commission Washington,.

D.C.

20555 Attention:

Mr. Domenic B.

Vassallo, Chief Operating Reactors Branch No. 2 Division of Licensing

Subject:

James A.

FitzPatrick Nuclear Power Plant Docket No. 50-333 Supplement No. 1 to NUREG-0737 Safety Parameter Display System (SPDS)

Safety Analysis (Generic Letter No.

82-33)

References:

1.

NRC December 17, 1982 Generic Letter No. 82-33 to All Licensees of Operating Reactors, includes supplement No. 1 to NUREG-0737.

2 PASNY April 15, 1983 letter, J.P.

Bayne to D.B.

Vassallo (JPN-83-33), regarding the same subject..

Dear Sir:

Generic Letter No. 82-33 (Reference 1) transmitted to the Authority Supplement No. 1 to NUREG-0737 which replaced the corresponding requirements for five NUREG-0737 items.

Via Reference 2,

the Authority submitted a schedule for completing each of the basic requirements and a description of our plans for the phased implementation and integration of these emergency response activities.

The NRC subsequently confirmed these commitments with a June 12, 1984 order (Reference 3).

DOCK 0 0 g

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In accordance with the Authority's commitments, attached is a document entitled " Safety Parameter Display System Parameter Safety Analysis for'the James A.

FitzPatrick Nuclear Power Plant" which describes the' basis on which the. selected parameters are determined to be both..necessary and sufficient to assess the safety status of the plant for a wide range of events including severe accident conditions.

In our April 15, 1983 letter (Reference 2), the Authority requested that the NRC perform a pre-implementation review of the SPDS Verification and Validation Program Plan.

The Authority hereby withdraws this request no pre-implementation review is expected.

We are proceeding with the implementation of this system in accordance with schedules transmitted separately.

Your prompt

-review of this safety analysis and associated implementation plan will be appreciated.

Based upon discussions with NRC staff members at public meetings, we expect that a letter regarding the acceptability of our plans will be issued within two months.

If you have any questions about this safety analysis, please contact Mr.

J.

A.

Gray, of my staff.

Very truly yours, C.A.

McNeill, Jr.

Senior Vice President Nuclear Generation cc: Office of the Resident Inspector U.S.

Nuclear Regulatory Commission P.O.

Box 136 Lycoming, New York 13093 i

l

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