ML20127N147

Special Rept:On 921017,channels 3 & 5 of Vibration & Loose Parts Monitoring Sys Declared Inoperable & on 921023, Channel 10 Declared Inoperable.Caused by Excessive Noise on Channel.Repairs Will Be Made During Future Outage

ML20127N147
Person / Time
Site:	Catawba
Issue date:	11/23/1992
From:	Tuckman M DUKE POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9212010011
Download: ML20127N147 (2)

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ouncrowen November 23,1992 U. S. Nuclear Regubtory Commission ATTN: Document Control Desk Washington, DC 20555

Subject:

Catawba Nuclear Station, Unit i Docket No. 50-413 Special Report Vibration and Loose Parts Monitoring System Pursuant to Technical Specification 3.3,3.9, find attached a Special Report concerning the inoperability of the Unit 1 Vibration and 140sc Parts Monitoring System channels 3 (Upper Reactor Vessel A),5 (Steam Generator A), atd 10 (Steam Generator B).

Very truly yours,

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A M. S. Tuckman CRUSR112392. LOP Attachment xc: S. D. Etneter Regional Administrator, Regica 11 R. E, Martin, ONRR W. T. Orders Senior Resident Inspector y,0.t G 4 9212010011 921123 PDR S

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SPdCIAL REPORT CATAWHA NUCLEAR STATION, UNIT 1 Vibration and Loose Parts Monitoring System Channels 3,5, r.nd 10 On October 17, 1992 channels 3 (Upper Reactor Vessel A) and 5 sSteam Generator A) were declared inoperable. Channel 3 was declared inoperable becaue there was no signal from the channel in the control room and channel 5 was declared inoperable due to excessive noite on the channel. On October 23,1992 channel 10 (Steam Genentor B) wa.s declared inoperable due to execssive noise on the channel. A work request has beeni written to re' fair these channels during a future outage of sufficient length. This is being scheduled for an outage because a containment entry is necessary to make the repairs. The following channels are operable and provide coverage as noted:

Channel 4:

Upper Reactor Vessel B Channel 9:

Steam Generator A Channel 6:

Steam Generator B Since these channels have been inopernb!c for more than 30 days, th:y are reportable to the NRC pursuant to Technical Specification 3.3.3.9.

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