ENS 54263
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ENS Event | |
---|---|
17:09 Sep 7, 2019 | |
Title | Automatic Reactor Trip |
Event Description | At 1309 EDT on September 7, 2019, with the unit in Mode 1 at approximately 95 percent power, the reactor automatically tripped during main turbine valve testing. The trip was not complex with all systems responding normally post-trip.
Operations responded and stabilized the plant. Decay heat is being removed by the turbine bypass valves discharging steam to the main condenser. Due to the reactor protection system actuation while critical, this event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B). The cause of the reactor protection system actuation is under evaluation. 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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Davis Besse ![]() Ohio (NRC Region 3) | |
Reporting | |
10 CFR 50.72(b)(2)(iv)(B), RPS Actuation | |
Time - Person (Reporting Time:+-1.27 h-0.0529 days <br />-0.00756 weeks <br />-0.00174 months <br />) | |
Opened: | Tim Thompson 15:53 Sep 7, 2019 |
NRC Officer: | Andrew Waugh |
Last Updated: | Sep 7, 2019 |
54263 - NRC Website
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Unit 1 | |
---|---|
Reactor critical | Critical |
Scram | A/R |
Before | Power Operation (95 %) |
After | Hot Standby (0 %) |
WEEKMONTHYEARENS 553462021-07-09T01:54:0009 July 2021 01:54:00
[Table view]10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Trip Due to Main Turbine Trip ENS 546112020-03-25T16:40:00025 March 2020 16:40:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Trip Due to Loss of Reactor Coolant Pumps ENS 542632019-09-07T17:09:0007 September 2019 17:09:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Trip ENS 522322016-09-10T07:43:00010 September 2016 07:43:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Unit Trip Due to Main Generator Lock-Out ENS 516962016-01-29T18:22:00029 January 2016 18:22:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Due to Reactor Protection System Actuation ENS 510612015-05-09T22:55:0009 May 2015 22:55:00 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 Steam Leak in the Turbine Building ENS 491592013-06-30T01:20:00030 June 2013 01:20:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Trip Due to Reactor Coolant Pump Trip ENS 428282006-09-06T06:31:0006 September 2006 06:31:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip on Loss of Condenser Vacuum ENS 409212004-08-04T14:24:0004 August 2004 14:24:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Unexpected Reactor Trip During Maintenance Activities 2021-07-09T01:54:00 | |
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