ML20100Q809

Informs of Inability to Devise Improvements Reducing Level Indication Errors Caused by High Drywell Temp within Time Allotted by Generic Ltr 84-23 Re Reactor Water Level Instrumentation Improvements

ML20100Q809
Person / Time
Site:	FitzPatrick
Issue date:	12/13/1984
From:	Corbin McNeil POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	Vassallo D Office of Nuclear Reactor Regulation
References
GL-84-23, JPN-84-83, NUDOCS 8412170228
Download: ML20100Q809 (2)

Text

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1. D NewWrkPbwer 4# Authority December-13, 1984 JPN-84-83 Director of~ Nuclear Reactor Reg'ulation U.S.. Nuclear-Regulatory Commission 1

Washington, D.C.

20555 Attention:

Mr. Domenic B. Vassallo, Chief Operating Reactors Branch No. 2 Division of Licensing 3

Subject:

James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Generic Letter No. 84-23 Reactor Vessel Water Level Instrumentation in BNRs

Reference:

1. NRC Generic Letter No. 84-23, " Reactor. Vessel Water Level Instrumentation in BNRs," dated October 26, 1984.

2.

NYPA letter, C.A. McNeill Jr. to D. B. Vassallo, dated-November 30, 1984 (JPN-84-77) regarding implementation of Regulatory Guide 1.97, Rev.

2.

Dear Sir:

Generic Letter No. 84-23 (Reference 1) requested plans and schedules related to reactor water level instrumentation improvements.

Three potential improvement categories were described in that letter.

The first category related to improvements that would reduce level indication errors caused by high deywell temperature.

The Authority has not been able to formulate a definite engineerlag solution for reducing these indication errors in the thirty days allotted by the generic letter.

Since this improvement is closely related to modifications currently planned for the implementation of Rev. 2 to Regulatory Guide 1.97, the Authority will integrate our final resolution of this improvement into our Regulatory Guide El.97 schedule. (Reference 2).

In accordance with the schedules l.

included in Reference 2, the necessary modifications will be

. completed thirty days after the end of the 1986 refueling outage (Reload 7/ Cycle 8) or December 31, 1986, whichever is later: (This is the same date committed to for type A variables in Reference 2).

Any changes to the Regulatory Guide 1.97 implementation schedule will result in identical changes to this schedule.

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Category 2 improvements concern the replacement of mechanical level indication equipment with analog level transmitters.

The Authority has purchased a Class IE Analog Transmitter Trip System (ATTS).

The ATTS is an electronic system that will replace electromechanical switches in the Reactor Protection System and Emergency Core Cooling System.

Approximately one hundred pressure, level and temperature switches will be replaced with' analog transmitter-trip unit combinations.

These new ATTS transmitter-trip units are designed for high availability.

In addition to providing continous monitoring of critical plant parameters, the ATTS will also perform basic trip logic.

Included as-part of this replacement program is the existing reactor water level instrumentation.

Installation is currently scheduled for the 1985 refueling outage (Reload 6/ Cycle 7).

The third category concerns changes to the protection system logic.

The Authority will address this area when the NRC staff-completes its evaluation and formal requirements have been promulgated.

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

Very t uly yours, i

C. A. McNeill, Jr.

Senior Vice President Nuclear Generation cc:

Office of the Resident Inspector f

U.S. Nuclear Regulatory Commission Post Office Box 136 Lycoming, New York 10393 l

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