ML19329A718: Difference between revisions
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| document report number = RO-287-77-04, RO-287-77-4, NUDOCS 8001090694 | | document report number = RO-287-77-04, RO-287-77-4, NUDOCS 8001090694 | ||
| package number = ML19329A717 | | package number = ML19329A717 | ||
| document type = REPORTABLE OCCURRENCE REPORT (SEE ALSO AO | | document type = REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER), TEXT-SAFETY REPORT | ||
| page count = 1 | | page count = 1 | ||
}} | }} | ||
=Text= | =Text= | ||
{{#Wiki_filter:. | {{#Wiki_filter:.- | ||
f~T | f~T e | ||
* DUKE POWER COMPANY | ly ' | ||
OCONEE UNIT 3 m | * DUKE POWER COMPANY OCONEE UNIT 3 m | ||
Report No.: R0-287/77-4 Report Date: April 20, 1977 Occurrence Date: March 22, 1977 Facility: Cconee Unit 3, Seneca, South Carolina Identification of Occurrence. E-odwater containment isolation valve 3FDW-106 inoperable Conditions Prior to Occurrence: Unit at 100 percent full power Description of Occurrenes: | Report No.: R0-287/77-4 Report Date: April 20, 1977 Occurrence Date: March 22, 1977 Facility: Cconee Unit 3, Seneca, South Carolina Identification of Occurrence. E-odwater containment isolation valve 3FDW-106 inoperable Conditions Prior to Occurrence: Unit at 100 percent full power Description of Occurrenes: | ||
OnMarc$ 22, 1977, following chemical sampling of the "3A" once-through steam generator, feedwater containment isolation valve 3FDW-106 ; ailed to close under system pressure. This valve, located outside thc Reactor Building, is part of the checical sampling system and provides containment isolation following an ES actuation. The redundant valve, 3FDW-105, located inside the Reactor Building was closed and locked as required by Oconee Technical Specification 3.6.4.b.2. | OnMarc$ 22, 1977, following chemical sampling of the "3A" once-through steam generator, feedwater containment isolation valve 3FDW-106 ; ailed to close under system pressure. This valve, located outside thc Reactor Building, is part of the checical sampling system and provides containment isolation following an ES actuation. | ||
The redundant valve, 3FDW-105, located inside the Reactor Building was closed and locked as required by Oconee Technical Specification 3.6.4.b.2. | |||
Apparent Cause of Occurrence: | Apparent Cause of Occurrence: | ||
The inability of valve 3FDW-106 to cycle properly was determined to have resulted irom hardening of the valve packing, jnalysis of Occurrence: | The inability of valve 3FDW-106 to cycle properly was determined to have resulted irom hardening of the valve packing, jnalysis of Occurrence: | ||
| Line 30: | Line 31: | ||
Corrective Action: | Corrective Action: | ||
Valve 3FDW-106 was repacked and its operability verified. To prevent recurrence of this incident, the following action will be taken. | Valve 3FDW-106 was repacked and its operability verified. To prevent recurrence of this incident, the following action will be taken. | ||
A program will be developed to periodically adjust or replace packing on u5 FDW-106 and FDW-108 valves on all three units. This program will aclude examination and, as necessary, replacement of the packing. At present, all FDw-106-and -108 valves have been repacked during the last 4 months except 1FDW-106, 2FDW-108 and 2FDW-106. | A program will be developed to periodically adjust or replace packing on u5 FDW-106 and FDW-108 valves on all three units. This program will aclude examination and, as necessary, replacement of the packing. At present, all FDw-106-and -108 valves have been repacked during the last 4 months except 1FDW-106, 2FDW-108 and 2FDW-106. | ||
A review will also be made of different types of. packing | These valves will be examined and repacked as necessary during each units n, ext.-gef,ueling outage. | ||
A review will also be made of different types of. packing which could eliminate hardening problems, git '.a To determine if these valves need to be changed to a different design and/or different operator, the operation and maintenance histories of 0 90 dh these valves are being reviewed and evaluated.}} | |||
Latest revision as of 07:07, 31 December 2024
| ML19329A718 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 04/20/1977 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML19329A717 | List: |
| References | |
| RO-287-77-04, RO-287-77-4, NUDOCS 8001090694 | |
| Download: ML19329A718 (1) | |
Text
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f~T e
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- DUKE POWER COMPANY OCONEE UNIT 3 m
Report No.: R0-287/77-4 Report Date: April 20, 1977 Occurrence Date: March 22, 1977 Facility: Cconee Unit 3, Seneca, South Carolina Identification of Occurrence. E-odwater containment isolation valve 3FDW-106 inoperable Conditions Prior to Occurrence: Unit at 100 percent full power Description of Occurrenes:
OnMarc$ 22, 1977, following chemical sampling of the "3A" once-through steam generator, feedwater containment isolation valve 3FDW-106 ; ailed to close under system pressure. This valve, located outside thc Reactor Building, is part of the checical sampling system and provides containment isolation following an ES actuation.
The redundant valve, 3FDW-105, located inside the Reactor Building was closed and locked as required by Oconee Technical Specification 3.6.4.b.2.
Apparent Cause of Occurrence:
The inability of valve 3FDW-106 to cycle properly was determined to have resulted irom hardening of the valve packing, jnalysis of Occurrence:
Valve 3FDW-106 was properly isolated in compliance with Technical Specifi-cation 3.6.4.b.2 by securing redundant valve 3FDW-105 in the closed position.
In the event that containment isolation had been required prior to securing valve 3FDW-105, valve 3FDW-105 would have closed upon an ES actuation.
Containment integrit', was not affected by this incident and it is this concluded that the health and safety of the public were not affected.
Corrective Action:
Valve 3FDW-106 was repacked and its operability verified. To prevent recurrence of this incident, the following action will be taken.
A program will be developed to periodically adjust or replace packing on u5 FDW-106 and FDW-108 valves on all three units. This program will aclude examination and, as necessary, replacement of the packing. At present, all FDw-106-and -108 valves have been repacked during the last 4 months except 1FDW-106, 2FDW-108 and 2FDW-106.
These valves will be examined and repacked as necessary during each units n, ext.-gef,ueling outage.
A review will also be made of different types of. packing which could eliminate hardening problems, git '.a To determine if these valves need to be changed to a different design and/or different operator, the operation and maintenance histories of 0 90 dh these valves are being reviewed and evaluated.