ML20082L975

Forwards Addl Info to 831003 Tech Spec Change Request Re Turbine Overspeed Valve Test Interval & Possibility of Incident Caused by Backflow from Feedwater Heater Via Steam Extraction line.Four-month Interval Justified

ML20082L975
Person / Time
Site:	Farley
Issue date:	11/28/1983
From:	Clayton F ALABAMA POWER CO.
To:	Varga S Office of Nuclear Reactor Regulation
References
TAC-48973, TAC-52539, TAC-53434, NUDOCS 8312050631
Download: ML20082L975 (2)

Text

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Milling Addr:ss Alabama Power Company 6 000 North 18th Street Post Office Box 2641 Owmingham, Alabarna 35291 Telephone 205 783-6081 F. L Clayton, Jr.

Cernor Vice P'esident Fhrtod9e Bunding /Mahama POWCT November 28, 1983 Docket No. 50-364 Director, Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Mr. S. A. Varga Joseph M. Farley Nuclear Plant - Unit 2 Turbine Valve Technical Specification Change Request Gentlemen:

The following provides additional information concerning the Farley Nuclear Plant Unit 2 technical specification change request, dated October 3,1983, regarding Section 3/4.3.4 This information was requested during recent telephone conferences with NRC staff personnel.

One question raised by the NRC Staff was related to the possibility of a turbine overspeed incident resulting from backflow from a feedwater heater via a steam extraction line. This condition could result from failure of the existing non-return check valve and the power assisted isolation valve in the extraction line. Alabama Power Company has determined that insufficient energy is contained within any single feedwater heater to bring the turbine to overspeed under such conditions.

Tne second item discussed involved Alabama Power Company's basis for the proposed valve test interval. The administrative basis for the approximate four month test interval in the Turbine Overspeed Reliability Enhancement Program is as follows:

1. This interval will foster appropriate continuing attention to key components while providing added assurance of component reliability.

2. This intarval is consistent with expected system peak load requi rement s.

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Mr. S. A. Varga November 28, 1983 Nuclear Regulatory Commission Page 2

3. This interval will allow unexpected changes in plant condition to be reflected in changes to the valve testing schedule (i.e.,

recognition that shutdown and startup constitute a test of the valve closure mechanism).

If there are any questions, please contact us.

Your truly, Y

F . L. Cl ay t , J r.

FLCJ r/CLB:grs-013 cc: Mr. R. A. Thomas Mr. G. F. Trowbridge Mr. J. P. O'Reilly Mr. E. A. Reeves Mr. W. H. Bradford Dr. I. L. Myers s

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