ML20235J298

Responds to Questions Posed by D Kubicki in Telecon Re Fire Protection Supervisory Circuits & Schedule for Completion

ML20235J298
Person / Time
Site:	Beaver Valley
Issue date:	07/06/1987
From:	Carey J DUQUESNE LIGHT CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
2NRC-7-172, TAC-62935, NUDOCS 8707150483
Download: ML20235J298 (2)

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%s 2NRC-7-172 Beav: t Vahey No. 2 Unit Project Organization (412) 643-5200 S.E.G. Building Telecopy (412) 643 5200 Ext.160 bSpp1ngpo ,PA15077 b' United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

SUBJECT:

Beaver Valley Power Station Unit No. 2 Docket No. 50-412 Fire Protection Supervisory Circuits and Schedule for Completion

REFERENCE:

Letter to NRC from J. J. Carey 2NRC-7-166, dated June 24, 1987 Gentlemen:

In response to our recent conversation with your reviewer Mr. D. Kubicki, we are providing the following information:

1. Is the power supply circuitry supervised such that, on a loss of power to the fire protection panels, indication would be provided?

Response: The power circuits to the fire protection panels are supervised. If power is lost to the local panels, the " trouble" indication is sent to the Building Services Panel (BSP) annunciator window and the plant computer output, both of which can be acknowledged in the control room. The power supply for the annunciator window and the plant computer are independent from each other, such that if one is lost, the indication would appear at the other location.

2. Are there any devices upstream of the local water panels, such as water flow devices, trip circuits, etc., that provide indication and are these circuits supervised?

Response: The trip circuitry associated with the actuation of the water suppression systems is supervised. Pressure switches are provided for the water flow systems, but are not associated with the actu-ation portion of the system. The circuitry for the pressure switches are not supervised; however, loss of this circuitry does not prevent normal operation of the system in the event of a fire.

Alternate means are available to detect system discharge, i.e., fire pump start, and fire and trouble annunciation in the control room.

Prnently, as part of the fire suppression system testing program, pressure switches associated with the water system actuation are tested monthly, 8707150483 870706 f Oh PDR ADOCK 05000412 F PDR I' I g i

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.o United States Nuclear Regulatory Commission Fire Protection Supervisory Circuits and Schedule for Completion Page 2

3. Are the actuating circuits for the CO2 and halon systems supervised?

Response: The CO2 and halon actuation circuitry is supervised. This is from the detectors, to the local and/or XL-3 panel, to the CO2 supply tank or halon bottles, and to the control room. A failure in this circuitry would appear as a " trouble" alarm on the BSP and the plant computer out-put.

4. Provic schedule of completion of unfinished fire protection items identified in June 24, 1987 letter.

Response: Fire wrap - estimated to be entirely complete by July 31, 1987.

Acceptance testing of CO2 suppression system-proposed modifications including pressure relief paths to be completed by September 30, 1987.

An additional C02 storage tank to provide adequate reserve capacity in one of the eight areas will be installed by December 31, 1987. The remaining seven areas presently have adequate reserve capacity.

Testing of fire dampers - modifications will be completed by July 31.

i DUQUESNE LIGHT COMPANY i

By J. JT Carey v i Senior Vice President i

JDH/JD0/ijr l NR/JDH/JD0/LTR  ;

AR/NAR 2 l

cc: Mr. P. Tam, Project Manager j Mr. J. Beall, NRC Sr. Resident Inspector 4 Mr. L. Prividy, NRC Resident Inspector INP0 Records Center 1

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