ENS 48676
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ENS Event | |
|---|---|
02:12 Jan 16, 2013 | |
| Title | Loss of a 4160 Volt Bus While Performing Testing |
| Event Description | On January 15, 2013 at 2112 EST while performing testing associated with the remote shutdown system at the James A. FitzPatrick Nuclear Power Plant, an unexpected loss of the 10600 bus 'B' division AC vital power system occurred. This loss of power to the 10600 bus resulted in an automatic actuation of the 'B' and 'D' Emergency Diesel Generators. The diesel generators started as expected, but did not close in to energize the 10600 Bus due to the configuration at the time of the event. As a result of the loss of the 10600 bus, the 'B' Reactor Protection System (RPS) lost power resulting in a half scram signal and a Group II Primary Containment Isolation System (PCIS) actuation. This actuation resulted in closing containment isolation valves in multiple systems and isolating Reactor Water Clean-Up (RWCU). Based on these system actuations, the event is reportable under criterion 10 CFR 50.72(b)(3)(iv).
Power to the 10600 Bus was restored January 16, 2013 at 0400 EST, and the half scram and isolation signals have been reset. Additional actions to restore systems to a normal operating line-up are on-going. Investigation into the cause of the unexpected power loss is on-going and will be addressed through the corrective action program. The NRC Resident Inspector has been notified. |
| Where | |
|---|---|
Fitzpatrick  New York (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| Time - Person (Reporting Time:+2.52 h0.105 days <br />0.015 weeks <br />0.00345 months <br />) | |
| Opened: | Steve Defillippo 04:43 Jan 16, 2013 |
| NRC Officer: | Mark Abramovitz |
| Last Updated: | Jan 16, 2013 |
| 48676 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
WEEKMONTHYEARENS 563732023-02-19T06:05:00019 February 2023 06:05:00
[Table view]10 CFR 50.72(b)(3)(iv)(A), System Actuation Specified System Actuation ENS 561192022-09-26T07:06:00026 September 2022 07:06:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Scram ENS 520422016-06-24T16:15:00024 June 2016 16:15:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Scram Due to Reactor Recirculation Pumps Degradation ENS 486762013-01-16T02:12:00016 January 2013 02:12:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Loss of a 4160 Volt Bus While Performing Testing ENS 483862012-10-05T17:03:0005 October 2012 17:03:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(3)(xiii), Loss of Emergency Preparedness Rps and Pciv Actuation Due to Loss of Offsite Power ENS 445462008-10-07T10:35:0007 October 2008 10:35:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Specified System Actuation Due to Loss of Power During Testing ENS 437522007-10-28T04:59:00028 October 2007 04:59:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Scram Due to Lowering Intake Level ENS 436352007-09-12T10:35:00012 September 2007 10:35:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Scram Following Intake Structure Traveling Screen Fouling ENS 419872005-09-14T06:13:00014 September 2005 06:13:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Scram on Low Reactor Vessel Water Level During Planned Maintenance ENS 400722003-08-14T20:26:00014 August 2003 20:26:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(a)(1)(i), Emergency Class Declaration, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unusual Event Declared Due to a Loss of Offsite Power. 2023-02-19T06:05:00 | |
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