ENS 45851
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ENS Event | |
|---|---|
03:37 Apr 17, 2010 | |
| Title | Reactor Trip Due to Turbine Trip |
| Event Description | During a normal reactor shutdown for a refueling outage on Unit 2, a reactor trip occurred at approximately 13% power. This reactor trip was the result of a turbine trip due to high differential pressure between A & B condensers (greater than 2.5 inches). The cause for the vacuum difference between condensers is unknown at this time.
The reactor trip first actuated indication was a high flux rate trip and the turbine trip first out indication was not received. The reason for this difference is unknown at this time. The operating crew responded to the reactor trip utilizing emergency operating procedures for reactor trip and reactor trip recovery and transitioned into normal shutdown procedures. All rods inserted as expected and all other systems operated as expected. The licensee notified the NRC Resident Inspector. According to the licensee: The plant is in a normal post-trip electrical lineup. No automatic relief valve operations occurred. The motor driven auxiliary feed pump was manually started. The main steam isolation valves are open and decay heat is being removed by steam through the turbine bypass valves to the main condenser. |
| Where | |
|---|---|
Prairie Island  Minnesota (NRC Region 3) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation | |
| Time - Person (Reporting Time:+-1.3 h-0.0542 days <br />-0.00774 weeks <br />-0.00178 months <br />) | |
| Opened: | Terry Bacon 02:19 Apr 17, 2010 |
| NRC Officer: | Donald Norwood |
| Last Updated: | Apr 17, 2010 |
| 45851 - NRC Website
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Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | A/R |
| Before | Power Operation (13 %) |
| After | Hot Standby (0 %) |
WEEKMONTHYEARENS 570032024-03-03T17:42:0003 March 2024 17:42:00
[Table view]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 Loss of Main Feedwater Pump Suction ENS 568032023-10-19T16:10:00019 October 2023 16:10:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip ENS 565432023-05-27T23:34:00027 May 2023 23:34:00 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 Notification of Unusual Event Due to Multiple Fire Alarms in Containment Not Verified within 15 Minutes ENS 548592020-08-26T18:19:00026 August 2020 18:19:00 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 Flux Rate ENS 516092015-12-17T19:18:00017 December 2015 19:18:00 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 Fire Alarm in Containment Not Verified within 15 Minutes ENS 511362015-06-07T12:35:0007 June 2015 12:35:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Resulting from Turbine Trip on Low Oil Pressure ENS 511072015-06-01T03:20:0001 June 2015 03:20:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Due to Trip of Condensate and Main Feedwater Pump ENS 509502015-04-03T11:52:0003 April 2015 11:52:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Scram Due to Loss of Main Feedwater Pump ENS 476832012-02-22T05:42:00022 February 2012 05:42:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip Due to Feedwater Heater Hi Hi Alarm ENS 470172011-07-01T20:52:0001 July 2011 20:52:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unit 1 Manual Trip Due to Electro-Hydraulic Control Fluid Leak on Turbine Stop Valve ENS 468302011-05-09T12:22:0009 May 2011 12:22:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Upon Turbine Trip Due to Main Generator Lockout ENS 459522010-05-25T08:14:00025 May 2010 08:14:00 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 Turbine Trip ENS 458512010-04-17T03:37:00017 April 2010 03:37:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Reactor Trip Due to Turbine Trip ENS 450772009-05-18T18:05:00018 May 2009 18:05:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Turbine Trip/Reactor Trip Due to Condenser Vacuum ENS 446152008-10-30T19:17:00030 October 2008 19:17:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Reactor Manually Tripped Due to Failure in Rod Control System ENS 443772008-07-31T13:17:00031 July 2008 13:17:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Trip During Testing ENS 432802007-04-05T14:08:0005 April 2007 14:08:00 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 Trip Caused by Spurious Safety Injection During Testing ENS 425042006-04-14T19:25:00014 April 2006 19:25:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Due to Condensate Pump and Feedwater Pump Trip 2024-03-03T17:42:00 | |
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