ML20009G774

LER 81-012/03L-0:on 810624,valve 3PR-8 Failed in Closed Position,Isolating Radiation Monitors 3 RIA-47,48 & 49. Caused by Ruptured Diaphragm in Air Operator on Valve. Diaphragm Replaced

ML20009G774
Person / Time
Site:	Oconee
Issue date:	07/24/1981
From:	Jackie Jones DUKE POWER CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20009G764	List: ML20009G763 ML20009G774
References
LER-81-012-03L-01, LER-81-12-3L-1, NUDOCS 8108040644
Download: ML20009G774 (2)

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,o42, gOn June 25, 1981, valve 3PR-8 faTled in the closed position thus isolating ,

IITn I radiation monitors 3 RIA-47, -48, and -49. While the radiation monitors I i o i., I were out of service, the requirements of Technical Specification 3.1.6.8  ;

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istoil Valve 3 PR-8 failed to open due to a ruptured diaphragm in the air operator ;

m ion the valve. The air operator diaphragm was replaced, and the valve PR-8 ,

gi diaphragm replacement frequency has been increased to every refueling outage, nitalI I Et I

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,o DUKE POWER COMPANY OCONEE UNIT 3 Report Number: R0-287/81-12 Report Date: July 24, 1981 Occurrence Date: June 25, 1981 Facility: Oconee Unit 3 Seneca, South Carolina Identification of Occurrence:

Conditions Prior to Occurrence: 100% FP Description of Occurrence: At 0421 hours0.00487 days <br />0.117 hours <br />6.960979e-4 weeks <br />1.601905e-4 months <br /> on June 25, 1981, valve 3PR-8 failad in the closed position, thus isolating radiation monitors 3RIA-42, -48, and

-49 causing them to be inoperable. Subsequent investigation revealed that the diaphragm in the air operator on the valve had ruptured. This constitutes operation in a degraded mode per Technical Specification 3.1.6.8 and is thus reportable pursuant to Technical Specification 6.6.2.1.b(2) .

< Apparent Cause of Occurrence: The reason for the inoperability was a ruptured diaphragm in the air operator on the valve.

Analysis of Occurrence: Technical Specification 3.1.6.8. requires that two means of different operating principles shall be operable for detecting reactor coolant leakage when the reactor is critical and above 2% power with one of the systems sensitive to radioactivity. The system sensitive to radioactivity may be out of service for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> if there are two other means to detect leakage operable.

While RIA's 47, 48, and 49 were out of service, the above requirement was met by operability of the normal RB sump level indicator and the means described in Technical Specification 3.1.6 Bases Section d. Since 3PR-8 failed closed and 3PR-7 was locked closed, the R.B. isolation was not degraded by this incident.

Therefore, the health and safety of the puhlic were not endangered.

j Corrective Action: The air operator diaphragm was replaced, and the valve PR-8 diaphragm replacement frequency has been increased to every refueling outage.

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