ENS 49159
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ENS Event | |
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01:20 Jun 30, 2013 | |
Title | Automatic Reactor Trip Due to Reactor Coolant Pump Trip |
Event Description | Automatic trip of Reactor Coolant Pump 1-2 due to an electrical differential current fault resulted in an RPS actuation on Flux/Delta Flux/Flow. Startup Feedwater Valve 1 did not respond as expected post-trip and has been placed in manual control. All secondary side steam reliefs initially re-seated following reactor trip. Subsequent Main Steam Line #1 Safety Valve leakage mitigated during post-trip recovery actions. All other systems have functioned as expected. The plant is stable in Mode 3 - Hot Standby.
All rods inserted into the core during the trip. Decay heat is being removed via turbine bypass valves to the main condenser with normal feedwater to the steam generators. The plant is in its normal shutdown electrical lineup. The licensee characterized the trip as uncomplicated. The licensee will be notifying Lucas and Ottawa counties, the State of Ohio and will be issuing a press release. They have notified the NRC Resident Inspector. |
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:+-2.53 h-0.105 days <br />-0.0151 weeks <br />-0.00347 months <br />) | |
Opened: | Robert W. Oesterle 22:48 Jun 29, 2013 |
NRC Officer: | Howie Crouch |
Last Updated: | Jun 29, 2013 |
49159 - NRC Website | |
Unit 1 | |
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Reactor critical | Critical |
Scram | A/R |
Before | Power Operation (100 %) |
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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