ENS 54523
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ENS Event | |
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23:00 Feb 12, 2020 | |
Title | Automatic Reactor Scram Due to Main Turbine Trip |
Event Description | At 1800 EST, on February 12, 2020, with Unit 1 in Mode 1 at 100 percent power, the reactor automatically tripped due to a turbine trip. The trip was not complex, with all systems responding normally post trip. Because of the reactor trip, the Auxiliary Feedwater (AFW) System actuated as expected due to on ATWS Mitigation System Actuation Circuitry (AMSAC) signal. The AFW pumps started as designed when the valid system actuation was received.
Operations responded and stabilized the plant. Decay heat is being removed by discharging steam to the main condenser using the condenser steam dump valves. Due to the Reactor Protection System (RPS) actuation while critical, this event is being reported as an 4-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B). This event is also being reported as an 8-hour non-emergency notification per 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of the AFW system. There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified. The site remains in a normal electrical lineup. The cause of the turbine trip is under investigation. |
Where | |
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Catawba South Carolina (NRC Region 2) | |
Reporting | |
10 CFR 50.72(b)(2)(iv)(B), RPS Actuation | |
Time - Person (Reporting Time:+-1.15 h-0.0479 days <br />-0.00685 weeks <br />-0.00158 months <br />) | |
Opened: | Will Fowler 21:51 Feb 12, 2020 |
NRC Officer: | Kerby Scales |
Last Updated: | Feb 12, 2020 |
54523 - NRC Website
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WEEKMONTHYEARENS 573442024-09-27T11:46:00027 September 2024 11:46:00
[Table view]10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Due to Loss of Condenser Vacuum ENS 561772022-10-24T12:57:00024 October 2022 12:57:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip and Auxiliary Feedwater System Actuation ENS 558562022-04-23T06:24:00023 April 2022 06:24:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip During Control Rod Testing ENS 548882020-09-08T13:25:0008 September 2020 13:25:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Trip on Over Power Delta Temperature ENS 545232020-02-12T23:00:00012 February 2020 23:00:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram Due to Main Turbine Trip ENS 412462004-12-06T02:35:0006 December 2004 02:35:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Turbine Trip/Reactor Trip Due to Moisture Separator Reheater (Msr) High Level Trip Signal. ENS 411542004-10-28T04:52:00028 October 2004 04:52:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip After Shutdown Bank Dropped Into Core ENS 405382004-02-22T22:30:00022 February 2004 22:30:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unit 1 Manually Tripped After the "B" Sg Feedwater Isolation Valve Failed Closed ENS 401142003-08-29T06:03:00029 August 2003 06:03:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Catawba Unit 1 Automatic Reactor Trip Due to Reactor Protection System Actuation 2024-09-27T11:46:00 | |
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