ENS 52232
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ENS Event | |
---|---|
07:43 Sep 10, 2016 | |
Title | Automatic Unit Trip Due to Main Generator Lock-Out |
Event Description | At 0343 EDT, with the unit operating at approximately 100% full power, an automatic reactor trip occurred due to a Main Generator lock-out. The cause of the generator lock-out is being investigated at this time. All control rods fully inserted. Post trip, the Steam Feedwater Rupture Control System was actuated due to high Steam Generator 1 level. The cause of the high Steam Generator 1 level is being investigated at this time.
The unit is currently in Mode 3 (Hot Standby) and stable, at approximately 550 degrees F and 2155 psig. Steam is being discharged through the Atmospheric Vent Valves for decay heat removal. There is no known primary to secondary leakage, and all safety systems functioned as expected. The NRC Resident Inspector has been notified of the event. The licensee notified the State of Ohio, Ottawa and Lucas County. |
Where | |
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Davis Besse Ohio (NRC Region 3) | |
Reporting | |
10 CFR 50.72(b)(2)(iv)(B), RPS Actuation 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
LER: | 05000346/LER-2016-009 |
Time - Person (Reporting Time:+-0.33 h-0.0138 days <br />-0.00196 weeks <br />-4.52034e-4 months <br />) | |
Opened: | Tom Cobbledick 07:23 Sep 10, 2016 |
NRC Officer: | Jeff Herrera |
Last Updated: | Sep 10, 2016 |
52232 - NRC Website
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Unit 1 | |
---|---|
Reactor critical | Critical |
Scram | A/R |
Before | Power Operation (100 %) |
After | Hot Standby (0 %) |
Davis Besse with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
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 517022016-01-30T06:23:00030 January 2016 06:23:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unanticipated Sfrcs Actuation While Restoring Main Feedwater to Steam Generators 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 500862014-05-05T18:56:0005 May 2014 18:56:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Scram with Rod Motion While Shutdown ENS 500972014-05-04T12:32:0004 May 2014 12:32:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Initiation of the Reactor Protection System While Shutdown 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 413302005-01-13T14:49:00013 January 2005 14:49:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Entry Into Technical Specification Required Shut Down Due to Loss of Essential Bus 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 ENS 402082003-10-01T01:34:0001 October 2003 01:34:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Valid Specified System Actuation ENS 401612003-09-16T04:30:00016 September 2003 04:30:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Coolant System Pressure Increase Caused a Valid Signal 2021-07-09T01:54:00 | |
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