ENS 40072
ENS Event | |
|---|---|
20:26 Aug 14, 2003 | |
| Title | Unusual Event Declared Due to a Loss of Offsite Power. |
| Event Description | Automatic reactor scram due to a loss of offsite power. All rods fully inserted into the core. All emergency core cooling systems and the emergency diesel generators are operating properly.
NRC Resident Inspector was notified of this event by the licensee.
Reactor vessel pressure is 93 psig. Plant electrical loads have been shifted back to offsite power and the EDGs were secured. The licensee exited the Unusual Event at 0039. The licensee tentatively plans to remain shutdown for a brief period to do some maintenance work. Notified R1IRC and FEMA(Hyman).
This updated is being provided to note a correction to the previously submitted time information and provide additional clarification of information that did not get captured. The automatic reactor scram occurred due to a generator load rejection. All rods fully inserted into the core, all emergency core cooling systems and the emergency diesel generators operated properly. The incorrect "event time" was communicated to the NRC during the initial notification (at 1717 hours0.0199 days <br />0.477 hours <br />0.00284 weeks <br />6.533185e-4 months <br />) and subsequent updates. The event time listed was "1611" hours EDT. This was the actual time of the loss of offsite power. The declaration of the Unusual Event was at "1626" hours EDT, based on EAL 6.1.1, Loss of power to transformers T2/T3 for greater than 15 minutes (loss of offsite power). In addition, the initial notification of the Unusual Event was also used to document two reporting requirements under 10CFR50.72. Specifically, 10CFR50.72(b)(2)(iv)(B) for actuation of the reactor protection system (RPS) when the reactor is critical, and 10CFR50.72(b)(3)(iv)(A) for valid actuation of systems listed in paragraph (b)(3)(iv)(B). Various system actuations occurred as a result of the loss of offsite power. The NRC Resident Inspector was notified along with state and local agencies. Notified Reg 1 RDO(Meyer) |
| Where | |
|---|---|
Fitzpatrick  New York (NRC Region 1) | |
| Reporting | |
| Emergency class: | Unusual Event |
| 10 CFR 50.72(a) (1) (i), Emergency Class Declaration 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| Time - Person (Reporting Time:+1.85 h0.0771 days <br />0.011 weeks <br />0.00253 months <br />) | |
| Opened: | Tim Page 22:17 Aug 14, 2003 |
| NRC Officer: | John Mackinnon |
| Last Updated: | Aug 15, 2003 |
| 40072 - NRC Website | |
Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | A/R |
| Before | Power Operation (100 %) |
| After | Hot Shutdown (0 %) |
FitzPatrick with 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 | |
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 545032020-01-31T10:55:00031 January 2020 10:55:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram Due to Main Turbine Trip 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 516802016-01-24T03:41:00024 January 2016 03:41:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Scram Due to Lowering Intake Level 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 485012012-11-11T08:55:00011 November 2012 08:55:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(a)(1)(i), Emergency Class Declaration Reactor Scram Due to Turbine Trip Followed by Unusual Event Declared Due to Main Transformer and Bus Duct Fire ENS 484792012-11-05T02:53:0005 November 2012 02:53:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram from Full Power Following Turbine Trip 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 418152005-06-30T23:29:00030 June 2005 23:29:00 10 CFR 50.72(b)(2)(xi), Notification to Government Agency or News Release, 10 CFR 50.72(a)(1)(i), Emergency Class Declaration, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Primary Containment Inoperable Due to Small Crack in Torus 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 | |