ENS 52274
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ENS Event | |
|---|---|
10:12 Oct 1, 2016 | |
| Title | Automatic Reactor Trip Due to Inadvertent Closure of Main Steam Isolation Valve |
| Event Description | At 0512 [CDT] on October 1, 2016, Farley Nuclear Plant Unit 1 automatically tripped from 99 percent reactor power due to the inadvertent closure of a main steam isolation valve (MSIV). The closure of the MSIV caused a turbine trip resulting in an automatic reactor trip. Concurrent with the reactor trip, a safety injection (SI) occurred. The plant is stable in Mode 3 (Hot Standby) and auxiliary feedwater (AFW) autostarted as expected. The cause of MSIV closure and SI actuation is under investigation.
Cooldown will continue to Mode 5 (Cold Shutdown) as planned for entry into a scheduled refueling outage. Restart is not planned until the completion of the refueling outage. Unit 2 was not affected. The NRC Resident Inspector has been notified. The MSIVs are open with the steam generators discharging steam to the main condenser using the turbine bypass valves. SI was from high head injection which has been secured. |
| Where | |
|---|---|
Farley  Alabama (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| Time - Person (Reporting Time:+-0.5 h-0.0208 days <br />-0.00298 weeks <br />-6.849e-4 months <br />) | |
| Opened: | Douglas Hobson 09:42 Oct 1, 2016 |
| NRC Officer: | Dong Park |
| Last Updated: | Oct 1, 2016 |
| 52274 - NRC Website | |
Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | A/R |
| Before | Power Operation (99 %) |
| After | Hot Standby (0 %) |
Farley with 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 | |
WEEKMONTHYEARENS 569712024-02-16T11:34:00016 February 2024 11:34:00
[Table view]10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip and Automatic Actuation of Auxiliary Feedwater System ENS 568522023-11-14T16:41:00014 November 2023 16:41:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip ENS 563292023-02-01T15:56:0001 February 2023 15:56:00 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 and Automatic Actuation of Auxiliary Feedwater System ENS 560282022-08-03T17:58:0003 August 2022 17:58:00 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 Loss of Power to START-UP Transformer ENS 542872019-09-21T13:00:00021 September 2019 13:00:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Trip Due to Reactor Coolant Pump Vibration Alarm ENS 540402019-05-01T21:43:0001 May 2019 21:43:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation En Revision Imported Date 5/9/2019 ENS 523952016-11-27T06:26:00027 November 2016 06:26:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip with Automatic Auxiliary Feedwater System Actuation Due to Voltage Oscillations ENS 523562016-11-08T06:00:0008 November 2016 06:00:00 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 Steam Generator Reduced Feedflow ENS 522742016-10-01T10:12:0001 October 2016 10:12:00 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 Trip Due to Inadvertent Closure of Main Steam Isolation Valve ENS 519182016-05-11T11:53:00011 May 2016 11:53:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Farley Unit 2 Trip on Hi Hi Steam Generator Level ENS 510432015-05-05T09:22:0005 May 2015 09:22:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Auxiliary Feedwater Pump Auto Start Signal Initiated During Startup ENS 506182014-11-15T09:53:00015 November 2014 09:53:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Valid Actuation of the Reactor Protection System for Abnormal Rod Position Indication ENS 505332014-10-14T08:41:00014 October 2014 08:41:00 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 Loss of a Start-Up Transformer ENS 491062013-06-12T02:05:00012 June 2013 02:05:00 10 CFR 50.72(b)(2)(xi), Notification to Government Agency or News Release, 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unit 1 Automatic Reactor Trip Due to the Loss of a Start-Up Transformer ENS 478132012-04-06T19:44:0006 April 2012 19:44:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Valid Load Shed Signal Occurred Due to Loss of the 1B Startup Transformer ENS 478092012-04-05T17:20:0005 April 2012 17:20:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unplanned Systems Actuations While Performing a Surveillance Test ENS 466612011-03-07T07:40:0007 March 2011 07:40:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Inadvertant Auto-Start Signal to the 1B Diesel Generator During Testing ENS 459462010-05-22T21:34:00022 May 2010 21:34:00 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 Loss of Steam Generator Water Level Control ENS 458892010-05-01T02:00:0001 May 2010 02:00:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Inadvertent System Actuation Occurred During a Surveillance Test ENS 448552009-02-16T22:55:00016 February 2009 22:55:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Inadvertent Relay Actuation Results in Auto Start of 1C Emergency Diesel Generator ENS 446662008-11-19T10:25:00019 November 2008 10:25:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Trip ENS 436872007-10-03T19:10:0003 October 2007 19:10:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Trip on Loss of Forced Flow to Rcs Loop "a ENS 411752004-11-05T15:11:0005 November 2004 15:11:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Inadvertent Loss of "B" Train Site Power During Testing ENS 406672004-04-12T08:47:00012 April 2004 08:47:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Unit 2 Experienced a Reactor Trip During Startup Due to an Invalid Sr Trip Signal ENS 406662004-04-11T16:05:00011 April 2004 16:05:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Trip for Unknown Reasons During Plant Startup ENS 405582004-03-01T11:22:0001 March 2004 11:22:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unit 1 Experienced a Reactor Trip on Turbine Trip Due to a Feedwater System Problem ENS 403092003-11-10T16:36:00010 November 2003 16:36:00 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 False Rcp Breaker Open Signal 2024-02-16T11:34:00 | |
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