ML19317D783
| ML19317D783 | |
| Person / Time | |
|---|---|
| Site: | Oconee |
| Issue date: | 07/15/1977 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML19317D775 | List: |
| References | |
| RO-269-77-19, NUDOCS 7912100538 | |
| Download: ML19317D783 (1) | |
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DUKE POWER COMPANY OCONEE UNIT 1 Report No.: R0-269/77-19 qqp Report Date: July 15, 1977 Occurrence Date:
June 15, 1977 Facility:
Oconee Unit 1, Seneca, South Carolina Identification of Occurrence: Feedwater containment isolation valve 1FDW-108 inoperable Conditions Prior to Occurrence: Unit at 100 percent full power Description of Occurrence:
On June 15, 1977, feedwater containment isolation valve 1FDW-108 failed to close under system pressure. This valve, located outside the reactor building, is part of the chemical sampling system and provides contain-ment isolation following a ES actuation. The redundant valve, 1FDW-107, located inside the reactor building, was closed and locked as required by Oconee Technical Specification 3.6.4.b.2.
The valve was repaired and returned to service within the time period allowed by Oconee Techni-cal Specification 3.6.4.b.l.
Apparent Cause of Occurrence:
Examination of the valve indicatei no definite reason for the inability of the valve to cycle properly.
Analysis of Occurrence:
Valve 1FDW-108 was properly isolated in compliance with Technical Speci-fication 3.6.4.b.2 by securing redundant valve 1FDW-107 in the closed position.
Valve 1FDW-108 was returned to serv $ce within the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> period allowed by Technical Specification 3.6.4.b.l.
In the event that containment isolation had been required prior to securing valve 1FDW-107, valve 1FDW-107 would have closed upon an ES actuation.
Containment integrity was not affected by this incident, and it is thus concluded that the health and safety of the public were not affected.
Corrective Action:
The stem of valve 1FDW-108 was lubricated and its operability verified.
To prevent recurrence of this incidence, the following action will be taken.
Valves 1FDW-108 and 1FDW-106 will be replaced on Oconee Unit 1 during the upcoming refueling outage. The FDW-108 and FDW-106 valves on Oconee Units 2 and 3 will also be replaced as delivery of the replacement valves and unit operation permit.
Until that time, a program to periodically examine and adjust or replace packing on the FDW-106 and FDW-108 valves will be utilized to assure proper valve operation.
This program will be initiated by July 15, 1977.
7912100 538
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