ML20010G128

Deficiency Rept Re Vol Control Tank Level Control Sys, Originally Reported on 810522.Postulated Event Sequence Evaluation Indicates That Malfunction Would Not Cause Safety Hazard.Reportable Under Part 21 But Not Under 10CFR50.55e

ML20010G128
Person / Time
Site:	Comanche Peak
Issue date:	06/19/1981
From:	Gary R TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:	Madsen G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
REF-PT21-81-491-000 10CFR-50.55E, PT21-81-491, PT21-81-491-000, TXX-3311, NUDOCS 8109150365
Download: ML20010G128 (1)

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Mr. G. L. Madsen Reactor Projects Branch ( v V 7

U. S. Nuclear Regulatory Commission y .-

9l Office of Inspection & Enforcement , G r i gt n a bl p $

COMANCHE PEAK STEAM ELECTRIC STATION VOLUE CONTROL TANK LEVEL CONTROL SYSTEM FILE NO: 10110

Dear Mr. Madsen:

On May 22, 1981 we verbally inforweJ your Mr. W. Hubacek of a deficiency regardinc; the Volume Control Tank Level Control System. Westinghouse had previously reported this item to the NRC under 10 CFR 21 in their May 21, 1981 letter logged NS-TMA-2451.

We have reviewed this Westinghouse letter and their recommended corrective actions. In addition we have evaluated the postulated sequence of events in light of the CPSES operating procedures and have concluded that a malfunction of the VCT level control system would not result in a safety hazard.

We therefore conclude that the problem identified by Westinghouse regarding the VCT Level Control System is not reportable under 10 CFR 50.55(e).

Very truly yours, R. J. Gary RJG:med cc: NRC Region IV - (0 + 1 copy)

Director, Inspection & Enforcement - (15 copies) c/o Distribution Services Branch, DDC, ADM.

U. S. Nuclear Regulatory Commission f 6/Y y

Washington, D. C. 20555

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