ENS 56673
ENS Event | |
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04:39 Aug 10, 2023 | |
Title | Automatic Reactor Trip |
Event Description | The following information was provided by the licensee via email:
At 0039 [EDT] on 8/10/23, with Unit 1 in Mode 1 at 100 percent power, the reactor automatically tripped during a reactor protection system (RPS) bus shift. All systems responding normally post-trip. There was no equipment inoperable at the time of the trip. Operations responded and stabilized the plant. Reactor water level being maintained via feedwater. Decay heat is being removed by cycling safety relief valves. An actuation of high-pressure core spray, division 3 diesel generator, and reactor core isolation cooling occurred during the scram and main steam line isolation closure. The reason for the auto-start was reaching Level 2 (130 inches in the reactor pressure vessel) during the transient. The systems automatically started as designed and injected to the reactor vessel when the Level 2 signal was received. The RPS actuation is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B). The emergency core cooling system (ECCS) injection is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(3)(iv)(A). The ECCS actuation is being reported as a eight-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(A). There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified. |
Where | |
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Perry ![]() Ohio (NRC Region 3) | |
Reporting | |
10 CFR 50.72(b)(2)(iv)(B), RPS Actuation 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
Time - Person (Reporting Time:+-0.6 h-0.025 days <br />-0.00357 weeks <br />-8.2188e-4 months <br />) | |
Opened: | Terry Ginn 04:03 Aug 10, 2023 |
NRC Officer: | Ernest West |
Last Updated: | Aug 10, 2023 |
56673 - NRC Website
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Unit 1 | |
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Reactor critical | Critical |
Scram | A/R |
Before | Power Operation (100 %) |
After | Hot Shutdown (0 %) |
Perry ![]() | |
WEEKMONTHYEARENS 566732023-08-10T04:39:00010 August 2023 04:39:00
[Table view]10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge Automatic Reactor Trip ENS 562982023-01-05T17:42:0005 January 2023 17:42:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge Automatic Reactor Scram ENS 551722021-04-06T01:49:0006 April 2021 01:49:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Protection System (RPS) Actuation at Zero Percent Power ENS 541852019-07-27T23:29:00027 July 2019 23:29:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge Automatic Reactor Scram Due to Main Turbine Trip ENS 538962019-02-25T05:24:00025 February 2019 05:24:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram Due to Generator Trip ENS 517292016-02-11T20:04:00011 February 2016 20:04:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Start of Emergency Diesel Generator and Loss of Shutdown Cooling ENS 517162016-02-08T20:03:0008 February 2016 20:03:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Scram Following Spurious Opening of Two Safety Relief Valves ENS 516792016-01-24T02:22:00024 January 2016 02:22:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Ts Required Shutdown Due to Unidentified Leakage in Drywell ENS 506012014-11-07T13:47:0007 November 2014 13:47:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge Automatic Reactor Scram Due to Loss of Feedwater ENS 505512014-10-20T06:18:00020 October 2014 06:18:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge Automatic Reactor Scram on Loss of Feedwater ENS 486882013-01-22T08:32:00022 January 2013 08:32:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge Automatic Reactor Protection System Actuation ENS 477102012-03-01T05:00:0001 March 2012 05:00:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Protection System Actuation Due to Automatic Turbine Runback ENS 459182010-05-12T03:18:00012 May 2010 03:18:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Manual Reactor Scram Due to Loss of Control Rod Drive Charging Water Header Pumps ENS 454402009-10-16T04:48:00016 October 2009 04:48:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Scram Due to Reactor Recirculation Pump Trip ENS 451472009-06-21T21:50:00021 June 2009 21:50:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram Related to a Main Turbine Trip ENS 438082007-11-28T12:32:00028 November 2007 12:32:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge Reactor Scram and Eccs Injection ENS 433632007-05-15T04:58:00015 May 2007 04:58:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Reactor Scram During Testing ENS 430492006-12-13T09:35:00013 December 2006 09:35:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Reactor Scram - Loss of Instrument Air Resulting in Feedwater Transient and Manual Reactor Scram ENS 413102005-01-06T06:12:0006 January 2005 06:12:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Scram Due to Reactor Recirculation Pump Trip ENS 412902004-12-24T04:54:00024 December 2004 04:54:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Reactor Scram Following Down Shift of Both Recirc Pumps from Fast to Slow Speed 2023-08-10T04:39:00 | |