ML19317F438: Difference between revisions
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| document report number = RO-270-75-22, NUDOCS 8001140676 | | document report number = RO-270-75-22, NUDOCS 8001140676 | ||
| package number = ML19317F427 | | package number = ML19317F427 | ||
| 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 | ||
}} | }} | ||
| Line 18: | Line 18: | ||
=Text= | =Text= | ||
{{#Wiki_filter:.. | {{#Wiki_filter:.. | ||
c (j | c(j DUKE POWER COMPANY OCONEE UNIT 2 | ||
'_ Report g : | |||
Low | UE-270/75-22 Report Date: | ||
On December 26, 1975, Low Pressure | February 9, 1976 Event Date: December 26, 1975 Facility: Oconee Unit 2, Seneca, South Carolina Identification'of Event: | ||
Low Pressure Injection System valves manually inoperable Conditions Prior to Event: Unit at 100% full power Description of Event: | |||
for | On December 26, 1975, Low Pressure Injection System valves LP-17 and LP-18 (LP1 he valves). | ||
This annual surveillance test was performed at this time bec problem had existed on Oconce Unit The valves were cycled electrically to verify their operability in the1 (Se Engineered Safeguards mode. | |||
Designation of Apparent Cause of Event: | |||
for valve LP-18 had been set too high which prevented ma r | |||
the valve.. Valve LP-17 brake release buttons were discovered jammed which prevented the opprator from engaging the manual handwheel. | |||
Analysis of Event: | Analysis of Event: | ||
Periodic testing as required by Oconee Technical Specification 4.5.1 | Periodic testing as required by Oconee Technical Specification 4.5.1 2 2 c b | ||
is performed on these valves to assure that they can be manually operated to provide long-term emergency core cooling should electrical operation be possible. | |||
In this event, an Engineered Safeguards actuation signal been received.both valves would not The manual operability of the valves was restored within approximately seven hours of discovery. | |||
It is concluded that the health and safety of the public was not affected by this incident. | |||
Corrective Action: | Corrective Action: | ||
1 and the brake release mechanism on valve LP-17 | 1 and the brake release mechanism on valve LP-17 has been r have.been tested electrically and manually. | ||
_ performed satisfactorily on the similar LPI valves on Oconee Unit 3. Surveillanc Additionally, a change has been made to the maintenance procedure to require verification | Both valves | ||
_ performed satisfactorily on the similar LPI valves on Oconee Unit 3. Surveillanc Additionally, a change has been made to the maintenance procedure to require verification of manual operability of LPI system valves after adjustment of the torque switch setting. | |||
4 8001140 b 7b | |||
_}} | _}} | ||
Latest revision as of 21:44, 1 January 2025
| ML19317F438 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 02/09/1976 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML19317F427 | List: |
| References | |
| RO-270-75-22, NUDOCS 8001140676 | |
| Download: ML19317F438 (1) | |
Text
..
c(j DUKE POWER COMPANY OCONEE UNIT 2
'_ Report g :
UE-270/75-22 Report Date:
February 9, 1976 Event Date: December 26, 1975 Facility: Oconee Unit 2, Seneca, South Carolina Identification'of Event:
Low Pressure Injection System valves manually inoperable Conditions Prior to Event: Unit at 100% full power Description of Event:
On December 26, 1975, Low Pressure Injection System valves LP-17 and LP-18 (LP1 he valves).
This annual surveillance test was performed at this time bec problem had existed on Oconce Unit The valves were cycled electrically to verify their operability in the1 (Se Engineered Safeguards mode.
Designation of Apparent Cause of Event:
for valve LP-18 had been set too high which prevented ma r
the valve.. Valve LP-17 brake release buttons were discovered jammed which prevented the opprator from engaging the manual handwheel.
Analysis of Event:
Periodic testing as required by Oconee Technical Specification 4.5.1 2 2 c b
is performed on these valves to assure that they can be manually operated to provide long-term emergency core cooling should electrical operation be possible.
In this event, an Engineered Safeguards actuation signal been received.both valves would not The manual operability of the valves was restored within approximately seven hours of discovery.
It is concluded that the health and safety of the public was not affected by this incident.
Corrective Action:
1 and the brake release mechanism on valve LP-17 has been r have.been tested electrically and manually.
Both valves
_ performed satisfactorily on the similar LPI valves on Oconee Unit 3. Surveillanc Additionally, a change has been made to the maintenance procedure to require verification of manual operability of LPI system valves after adjustment of the torque switch setting.
4 8001140 b 7b
_