ML20002E385

Comments on Draft SER Re Auxiliary Feedwater Control Sys. Auxiliary Feedwater Sys Design Will Be Modified to Remove Power Source Dependence

ML20002E385
Person / Time
Site:	Farley
Issue date:	01/22/1981
From:	Clayton F ALABAMA POWER CO.
To:	Schwencer A, Varga S Office of Nuclear Reactor Regulation
References
TAC-12391, TAC-12963, NUDOCS 8101270696
Download: ML20002E385 (2)

Text

a Algbima Power Company 600 North 18th Street Post O'f tes Box 2641 Birmingham, Alacama 35291 Te;ephone 205 250-1000 F. L CLAYToN, JR.

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January 22, 1981 8'

Ih Docket 'io. 50-348

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No. 50-364 3,

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• k Director, Nuclear Reactor Regulation

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'J. S. Nuclear Regulatory Ccnmission

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4 Attention:

Mr. S. A. Varga

/Li\\'N Mr. A. Schwencer Gen tl emen:

JOSEPH M. FARLEY NUCLEAR PLANT - UNITS 1 AND 2 C0i'MENTS ON AFW SAFETY EVALUATION REPORT As requested by the NRC staff December 19, 1980, the following are Alabama Power Company's comments on the draft Safety Evaluation Report concerning the auxiliary feedwater centrol system for Farley Nuclear Plant Units 1 cnd 2.

1.

Second paragraph under 7.X.(1) should read as follows:

The design of the AFW system will be modified to remove the power source dependence which could result in failures that preclude the capability to regulate AFW flow. Loss of this power could cause both the motor and turbine driven pump discharge valves to fail open resulting in loss of the capability to modulate AFW flow using any of the pump dis-charge valves. The logic and failure nodes of the solenoid valves should be nodified such that the loss of single power supply will not cause the pump discharge valves to open.

Alabana Power Company will implement the above modifications or will provide, for NRC staff review and concurrence, an alternate design which will provide equivalent auxiliary feedwater initiation capability. The above modifications or Alabama Power Company's equivalent design will be completed for Unit 2 during the first refueling outage and during the third refueling outage fer Unit 1.

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Director, fluclear Reactor Regulation January 22, 1981 U. S. Nuclear Regulatory Commission Page 2 2.

Second paragraph under 7.X.(2) should read as follows:

The protection systen logic will be modified such that all automatic initiation signals for the AFU system will autonatically open the motor driven pump discharge control valves regardless of the position of the valve operating made switches. Alabama Power Company will implement the above modification or will provide, for NRC staff review and concurrence, an alternate design which will provide equivalent design which will provide equivalent auxiliary feedwater initiation capability. The above modification or Alabama Power Corpany's equivalent design will be completed for Unit 2 during the first refueling outage and during the third refueling outage for Unit 1.

If you have any questions, please advise.

Yours very truly, im

.ks+ # A.

F.f.)Clayton,.Jr.

FLC/RUS:de cc: f tr. R. A. Thon.as ifr. G. F. Trowbridge Mr. J. P. O'Reilly fir. L. L. Kintner tir. E. A. Reeves l1r. W. H. Bradford