ML19276H000

LER 79-070/03L-0 on 790731:reactor Bldg Atmospheric Monitor RMA-6 Was Found Isolated.Caused by Damaged Wires to Control Switches for Containment Monitoring Isolation Valves WSV-5 & WSV-6.Wires Were Repaired

ML19276H000
Person / Time
Site:	Crystal River
Issue date:	08/21/1979
From:	Cooper J FLORIDA POWER CORP.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19276G996	List: ML19276G995 ML19276H000
References
LER-79-070-03L, LER-79-70-3L, NUDOCS 7908310309
Download: ML19276H000 (2)

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SUPPLEMENTARY INFORMATION Report No.: 50-302/79-070/03L-0 Facility: Crystal River Unit #3 Report Date: 21 August 1979 Occurrence Dates: 31 July 1979 and 1 August 1979 Identification of Occurrence:

Reactor Coolant leakage detection System (RMA-6) inoperable contrary to Technical Specification 3.4.o.1 a 5 c.

Conditions Prior to Occurrence:

Mode 2 (Rx Startup); Mode 1 (26% power operation)

Description of Occurrence:

At 1515 on 7/31/79 during routine inspection, RMA-6 vacuum pump was found isolated. Further investigation revealed that RMA-6 discharge isolation valve WSV-6 had failed closed.

Maintenance restored WSV-6 and RMA-6 was returned to service at 1740 on 7/31/79.

At 1130 on 8/1/79 it was discovered that RMA-6 discharge isolation ,

valve WSV-5 had failed closed, isolating RMA-6. Maintenance restored WSV-5 and RMA-6 was returned to service at 1440 on 8/1/79.

Designation of Apparent Cause:

The cause of this event is attributed to damaged wires which lead to the control switch for WSV-5 and WSV-6. The damage occurred as a result of modification (79-5-63) being installed in the vicinity of the switch wiring.

Analysis of Occurrence:

No e f fect upon the plant or general public as the plant remained in a stable condition.

Corrective Action:

The wiring to the control switches for WSV-5 and WSV-6 was repaired and RMA-6 was returned to service. Personnel were instructed of the importance of proper work techniques.

Failure Data:

This is the first occurrence of this type reported.

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