ML19317F009

From kanterella
Jump to navigation Jump to search
Unusual Event 287/74-04:on 741019,reactor Bldg Containment Valve 3FDW-108 Failed During Quarterly Performance Test. Cause Not Determined.Valve Manually Closed & Locked.Repairs Will Be Made During Next Maint Outage
ML19317F009
Person / Time
Site: Oconee Duke Energy icon.png
Issue date: 11/29/1974
From:
DUKE POWER CO.
To:
Shared Package
ML19317E999 List:
References
RO-287-74-04, RO-287-74-4, NUDOCS 8001080708
Download: ML19317F009 (1)


Text

,

Q.

\\_-

Duke Power Company Oconee Unit 3 Report No: UE-287/74-4 Report Date: November 29, 1974 Event Date:

October 19, 1974 Facility:

Ocones Unit 3, Seneca, South Carolina Identification of Event: Failure of Reactor Building Containment Valve 3FDW-108 Conditions Prior to Event: Unit at 40 percent full power.

Description of Event:

On October 19, 1974 the quarterly performance test of Engineered Safeguards valves was conducted en Oconee Unit 3.

The B Steam Generator sample line isolation valve, 3 FDW-108, failed to indicate closed after being given the close command.

The valve was manually closed and chain locked to insure con-tainment integrity until the valve could be repaired.

Designation of Apparent Cause of Event:

The air supply to the pneumatic operator and proper functioning of the electrical circuits have been verified to be operating correctly.

When tested, the valve opened remotely in less than one second; however, it took fifteen seconds to close.

Successive tests resulted in longer closing times. The valve has been closed and locked.

The actual cause of this valve failure has not been deter-mined.

Analysis of Event:

Valve 3 FDW-108 is one of two redundant valves which all' ova isolation of the B steam generator sample line in the unlikely event of an Engineered Safeguards actuation.

This valve is manually closed during operation, and is opened only for steam generator sampling.

The failure of this valve during test did not affect containment integrity as the redundant valve was operable.

It is con-cluded that the health and safety of the public was not affected.

Corrective Action:

This valve has been manually closed and locked to ensure containment integrity until repairs can be made during the next maintenance outage.

A determination of the failure mechanism cannet be determined 'until that time.

80 010 80 7M

._