ENS 44546
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ENS Event | |
|---|---|
10:35 Oct 7, 2008 | |
| Title | Specified System Actuation Due to Loss of Power During Testing |
| Event Description | On October 7, 2008 at approximately 0635, the James A. FitzPatrick Nuclear Power Plant was shutdown and operating in the Cold Shutdown mode (Mode 4). Testing was in progress on the trip and lockout (86) relay associated with circuit breaker 71-10402, normal station service transformer T-4 feeder breaker to electrical bus 10400. While technicians were performing the test, the 10400 bus, which was feeding power to the 10600 Emergency Bus, lost power. This loss of power to the 10600 bus resulted in an automatic actuation of the 'B' and 'D' Emergency Diesel Generators. The generators started, force paralleled, and closed in to the 10600 Bus as designed. As a result of the loss of the 10600 bus the 'B' Reactor Protection System (RPS) also 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).
The event has been entered into the corrective action program and a Licensee Event Report (LER) will be filed within 60 days as required by 10 CFR 50.73(a)(2)(iv). The [NRC] Resident Inspector has been briefed and the State Public Service Commission (PSC) will also be notified. At the time of the event, the 'B' shutdown cooling system was in service. Shutdown cooling was lost for approximately 35 minutes which resulted in a 6 degree rise in water temperature. At that time, the licensee calculated 19.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> to boil. Shutdown cooling has been restored. |
| Where | |
|---|---|
Fitzpatrick  New York (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| LER: | 05000333/LER-2008-003 |
| Time - Person (Reporting Time:+2.63 h0.11 days <br />0.0157 weeks <br />0.0036 months <br />) | |
| Opened: | Eugene Dorman 13:13 Oct 7, 2008 |
| NRC Officer: | Howie Crouch |
| Last Updated: | Oct 7, 2008 |
| 44546 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Not Critical |
| Scram | No |
| Before | Cold Shutdown (0 %) |
| After | Cold Shutdown (0 %) |
WEEKMONTHYEARENS 573332024-09-23T11:20:00023 September 2024 11:20:00
[Table view]10 CFR 50.72(b)(2)(xi), Notification to Government Agency or News Release, 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Scram Due to Generator Trip ENS 563732023-02-19T06:05:00019 February 2023 06:05:00 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. 2024-09-23T11:20:00 | |
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