ENS 43332
ENS Event | |
|---|---|
10:20 Apr 12, 2007 | |
| Title | Primary Containment Isolation Due to Loss of Rps Power Supply |
| Event Description | On April 12. 2007 at approximately 0620, with the James A Fitzpatrick Nuclear Power plant (JAF) operating at 100% reactor power, an equipment malfunction occurred, resulting in the tripping of one of the two 'B' Reactor Protection System (RPS) motor generator Electrical Protection Assembly (EPA) breakers. This caused a corresponding loss of power to the 'B' RPS bus, a half scram and primary containment isolation valve closures. Appropriate actions were taken in accordance with Abnormal Operating Procedure (AOP)-60, 'Loss of RPS Bus 'B' Power'. All equipment operated as designed as a result of the loss of power to the 'B' RPS bus.
At 0629, the 'B' RPS bus was placed on the alternate power supply. At approximately 0658 the RPS half scram was reset and at approximately 0702 Primary Containment Isolation System (PCIS) isolation signal was reset. Restoration of the various isolated systems commenced shortly thereafter. The reactor remained at 100% power throughout the event and Technical Specifications (TS) Limiting Condition for Operation (LCO) Actions were entered for the affected equipment as required. The above event meets the reporting criteria of 10 CFR 50 73(a)(2)(iv)(a) since the loss of RPS bus resulted in primary containment isolation signals affecting containment isolation valves in more than one system. The following systems or components isolated as a result of the loss of 'B' RPS bus: Reactor Water Cleanup, Reactor Building Ventilation 'B' Containment Atmosphere Dilution, Torus Vent and Purge, Drywall Equipment and Floor Drain Sumps 'B' Drywall Containment Atmospheric Monitors, Recirculation System Sample Line Main Steam Line Drains, Residual Heat Removal drain valve to radwaste, Standby Gas Treatment (auto initiated). Since the signal was invalid (the result of loss of power vs. an actual containment isolation condition), this event meets the criteria in 10 CFR 50.73 (a)(1) for being reported as a 60 day telephone notification in lieu of a written LER. The loss of the 'B' RPS bus was caused by the tripping of one of the two in-series 'B' RPS motor generator EPA breakers. An apparent cause evaluation of the failure is in progress (Condition Report CR-JAF-2007-01422). At this time the failure is attributed to the failure of a subcomponent (capacitor) on the EPA breaker logic card. The logic card was replaced, restoring the 'B' RPS motor generator to service. The licensee notified the NRC Resident Inspector. |
| Where | |
|---|---|
Fitzpatrick  New York (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.73(a)(1), Submit an LER, Invalid Actuation | |
| LER: | 05000333/LER-2023-002 Reactor Protection System Electric Power Monitoring System Trip Caused Primary Containment Isolation |
| Time - Person (Reporting Time:+457.05 h19.044 days <br />2.721 weeks <br />0.626 months <br />) | |
| Opened: | Eugene Dorman 11:23 May 1, 2007 |
| NRC Officer: | Jason Kozal |
| Last Updated: | May 1, 2007 |
| 43332 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
WEEKMONTHYEARENS 526452017-01-31T19:25:00031 January 2017 19:25:00
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