05000287/LER-1978-001-03, /03L-0:on 780105,Valve FDW-108 Failed to Close After Sample Removal.Similar Valve Failures Occured Previously.Probably Caused by Inability to Withstand environ.FDW-1-6,108 Replaced W/Appropriately Designed Valve

/03L-0:on 780105,Valve FDW-108 Failed to Close After Sample Removal.Similar Valve Failures Occured Previously.Probably Caused by Inability to Withstand environ.FDW-1-6,108 Replaced W/Appropriately Designed Valve

ML19322C160
Person / Time
Site:	Oconee
Issue date:	02/03/1978
From:	Ken Wilson DUKE POWER CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19322C149	List: 05000287/LER-1978-001, Forwards LER 78-001/03L-0 05000287/LER-1978-001-03, /03L-0:on 780105,Valve FDW-108 Failed to Close After Sample Removal.Similar Valve Failures Occured Previously.Probably Caused by Inability to Withstand environ.FDW-1-6,108 Replaced W/Appropriately Designed Valve
References
LER-78-001-03L, LER-78-1-3L, NUDOCS 8001090571
Download: ML19322C160 (2)

LER-1978-001, /03L-0:on 780105,Valve FDW-108 Failed to Close After Sample Removal.Similar Valve Failures Occured Previously.Probably Caused by Inability to Withstand environ.FDW-1-6,108 Replaced W/Appropriately Designed Valve

Event date:
Report date:
2871978001R03 - NRC Website

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DUKE POWER C0!!PANY OCONEE UNIT 1 Report No.:

R0-287/78-2 Report Date:

February 3,1978 Occurrence Date:

January 4, 1978 Facility:

Oconce Unit 3, Seneca, South Carolina Identification of Occurrence:

WW-108 failed to close following sample Conditions Prior to Occurrence:

100 percent full power Descript' ion of Occurrence:

- On January 4 at 1040 af ter tak~ing a sample f rom the OTSG, 3FDW-103. f ailed to close.

Redundant value FDW-107 was locked closed and its associated circuit breakers were locked open as required by Technical Specification.

3.6,3b(2).

After repacking, the valve was cycled several times without incident and was declared operable.

Apparent Cause of Occurrence:

This type of valve and identical valves have failed to operate several times previously.

Corrective actions sugges ted by the manuf acturer have been unsuccessful in stopping the failures.

Evidently, the valves a re not suitable for long-ters operation in the system environment.

Analysis of Occurrence:

3FDW-108 is an isolation valve on the steam generator sample lines.

The failure of the valve did not violate containment integrity as the redundant valve was operable and would have performed its Engineered Safeguard function if necessary.

Thus, the health and safety of the public were not endangered.

Corrective ActLon:

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Valve was' repacked and valve was cycled.to insure operability.

This. failure is one 'of: several similar failures which have been occurring:

at the' Oconee. Nuclear Station and no corrective-actions have been success-ful thus ' far.

Therefore, the valves (FDW 106, 108) will be~ replaced by others of ' suitable design -at the first appropriate outage for each unit'

af ter September 1,1978.

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