ML20092C273

Responds to Request for Info Re Status of NUREG-0737,Item II.E.4.1 Concerning Dedicated Hydrogen Penetrations.Valve Leakage Acceptable.Containment Purge Sys Satisfies GDC-54 Requirements for Redundancy,Isolation & Test Capability

ML20092C273
Person / Time
Site:	FitzPatrick
Issue date:	06/15/1984
From:	Bayne J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	Vassallo D Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.E.4.1, TASK-TM JPN-84-37, NUDOCS 8406210102
Download: ML20092C273 (2)

Text

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June 15, 1984 JPN 37 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 NUREG-0737 Item II.E.4.1 Dedicated Hydrogen Penetrations

References:

1. PASNY letter, R.J. Pasternak to T.A. Ippolito, dated September 30, 1980 (JAFP-80-759).

2. NYPA letter, J.P. Bayne to D.B. Vassallo, 1 dated February 3, 1984 (JPN-84-07).

Dear Sir:

This letter responds to a verbal request from the Nuclear Regulatory Commission (NRC) staff to provide information on the status of NUREG-0737 Item II.E.4.1 with regard to the James A.

FitzPatrick facility. Although Item II.E.4.1 was previously discussed in References 1 and 2, the NRC requested that the Authority confirm the following items:

1. The JAF Containment Purge System meets General Design Criteria (GDC)S4 and 56;

2. The JAF procedures for use with degraded core have been reviewed;

3. JAF complies with Clarifications 1 and 2 of Item II.E.4.1 of NUREG-0737 8$

eg The FitzPatrick Containment Purge System satisfies GDC-54 m requirements for redundancy, leak detection, isolation, and test S* capability. Valve leakage has been found to be within acceptable s'h limits.

2* GDC 56 states that each line that connects directly to the fE"' containment atmosphere and penetrates primary reactor cintainment shall be provided with two isolation valves, one inside and one outside containment unless it can be demonstrated that trae f containment isolation provisions are acceptable on some other defined basis. f'AY

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The.FitzPatrick containment purge lines are provided with two

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isolation valves in eries outside the primary containment.

According to Standarc Review Plan Section 6.2.4., this is acceptable to satisfy GDC 56.

Emergency Operating /Special Procedure P-SP-02 " Post LOCA Venting of Containment and Operation of Main Steam Leakage Collection System" has been reviewed and updated to reflect the changes resulting from the modification, thereby complying with the requirements of NUREG-0737 Item II.E.4.1.

Clarifications 1 and 2 of Item II.E.4.1 of NUREG-0737 were addressed in References 1 and 2. Reference 1 provided the conceptual design for NRC pre-implementation review for Item II.E.4.1, and Reference 2 stated that the proposed modification was completed during the 1981-82 refueling outage except for providing Class IE redundant power to two motor operated valves. This portion of the modification is scheduled to be completed prior to

-July 1, 1985.

Upon completion of this final portion of the modification, the Authority will consider NUREG 0737 Item II.E.4.1 to be complete for the FitzPatrick plant.

If you have any questions, please contact Mr. J. A. Gray, Jr.

of my staff.

Very truly yours, 1

J P. ne xecutive Vice President Nuclear Generation cc: Office of the Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 136 Lycoming, New York 13093 1883a/0096a