ML17055B714

Agrees W/Assessment & Approves Withdrawal of Tech Spec Changes for Containment Vent & Purge Valves.Licensee Committed to Provide Control During Startup & Shutdown When Dry Well Entry Required

ML17055B714
Person / Time
Site:	Nine Mile Point
Issue date:	05/28/1986
From:	Zwolinski J Office of Nuclear Reactor Regulation
To:	Mangan C, Seibert C NIAGARA MOHAWK POWER CORP.
References
TAC-55465, TAC-59921, NUDOCS 8606020367
Download: ML17055B714 (6)

Text

May 28, 1986 Docket No. 50-220 Niagara Mohawk Power Corporation Attn:

Mr. C. V. Mangan Senior Vice President c/o Miss Catherine R. Seibert 300 Erie Blvd. West

Syracuse, New York 13202 Distribution NRC 5 Local PDR BWR¹1 Reading JZwolinski

'Bernero GLainas OELD Gray File EJordan BGrimes Partlow CJamerson JKelly GHolahan ACRS(10)

RDiggs

SUBJECT:

CHANGE IN THE TECHNICAL SPECIFICATION REQUIREMENTS FOR CONTAINMENT VENT AND PURGE VALVES (TAC 59921, 55465)

Re:

Nine Mile Point Nuclear Station, Unit No.

1

/

By letters dated February 17, 1982 and January 14,

1986, Niagara Mohawk Power Corporation proposed changes to Section 3.3.4 and 4.3.4, Primary Containment Isolation Valves, of the Appendix A Technical Specifications (TS).

The proposed amendment reflected a change in the Technical Specification require-ments relating to the operating status of primary containment isolation valves (including containment vent and purge valves) for Nine Mile Point Unit 1. It was submitted for compliance with NUREG-0737.

Upon further review, you determined that certain testing requirements and limiting operational conditions would be better managed outside the scope of the TS, within other administrative controls.

Niagara Mohawk, therefore, withdrew the request for amendment to Operating License No.

DPR-63 dated February 17, 1982, as supplemented January 14, 1986, in a letter dated April 30, 1986.

The items being withdrawn are as follows:

1.

The first proposed item involves replacing the containment vent and purge valve seals every 10 years.

Given a once an operating cycle local leak rate test, the valve manufacturer has recommended a 10-year replacement program for the resilient seals.

This program will be appropriately addressed in written procedures in accordance with "Administrative Controls," Section 6, of the current Technical Specifications.

2.

The remaining proposed items involve actions to be taken if one or both of the containment isolation valves in series are inoperable.

The proposed actions are inconsistent with the TS requirements for other isolation valves.

Traditionally, if an isolation valve is found inoperable, immed-iate action would be taken to fix the problem.

These operational limits addressing inoperable isolation valves, are addressed in TS Section 3.3.4 and remain for these valves.

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Mr. C. V. Mangan May 28, 1986 The staff agrees with your assessment and approves your withdrawal of these two items.

Based on conversations with the staff you have provided information on two related items:

the amount of time that these isolation valves are open during normal operations and the installation of a high radiation trip signal.

The amount of time the isolation valves would be open during normal operations would be limited to a few activities which would include:

a)

Inerting and deinerting at the beginning and end of an outage that requires drywell entry, and b)

Controlling containment

pressure, during significant atmospheric pressure changes.

The valves are not planned to be used during normal operations for more than 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> per year.

In addition the system will not be used for temperature or humidity control.

The licensee has committed to provide administrative controls to ensure this condition, excluding their use for inerting and deinerting during startup and shutdown when drywell entry is required.

The second item discussed involves the installation of high radiation trip signals to automatically close these isolation valves.

Considering the additional closing signals and the safety classification of the high radiation

,signal, it is our understanding that the licensee intends to test these signals and provide an amendment application to reference the high radiation closure signal for consistency and clarity reasons.

Sincerely, ORIGINAL SIGNED BY John A. Zwolinski, Director BWR Project Directorate 81 Division of BWR Licensing cc:

See next page NAME CJamerson DATE :5/3 /86

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Mr. C. V. Manqan Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station, Unit No.

1 CC:

Troy B. Conner, Jr., Esquire Conner 8 Wetterhahn Suite 1050 1747 Pennsylvania

Avenue, N.

W.

Washington, D.

C.

20006 Frank R. Church, Supervisor Town of Scriba R.

D. 82

Oswego, New York 13126 Niagara Mohawk Power Corporation ATTN:

Mr. Thomas Perkins Plant Superintendent Nine Mile Point Nuclear Station Post Office Box 32

Lycoming, New York 13093 Resident Inspector U. S. Nuclear Regulatory Commission Post Office Box 126

Lycoming, New York 13093 John W. Keib, Esquire Niagara Mohawk Power Corporation 300 Erie Boulevard West

Syracuse, New York 13202 Regional Administrator, Region I U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19406 Mr. Jay Dunkleberger Division of Policy Analysis and Planning New York State Energy Office Agency Building 2 Empire State Plaza

Albany, New York 12223

-N o

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