ENS 44237
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ENS Event | |
|---|---|
16:49 May 23, 2008 | |
| Title | Automatic Reactor Trip on Possible Generator Lockout |
| Event Description | The reactor automatically tripped at 1249 EDT on 05/23/08. The cause of the reactor trip signal is not positively known, but it is believed to be related to trip of the 346 negative sequence relay which caused a trip of the 386C generator independent trip (coastdown) lockout relay. All plant systems performed as designed with minor deficiencies noted. EOP-1, 'Standard Post Trip Actions', and EOP-2, 'Reactor Trip Recovery', performed.
All control rods fully inserted. All atmospheric steam dump valves lifted and reseated. CV-0780 (B Steam Generator ASDV) was identified as leaking and was manually isolated. There is no known primary to secondary leakage. Auxiliary feedwater system actuated automatically as designed in response to low steam generator water levels. AFW actuation consisted on AFW pump P-8A auto start and AFW valve operation. Steam generator water levels were subsequently restored to normal and are being maintained for primary coolant system heat removal via main steam isolation valves to main condenser (via the turbine bypass valves). Plant is at Normal Operating Pressure (2060 psia) and Temperature (533 degrees F). Grid is stable with safety bus station power being provided from Safeguards transformer. The licensee notified the NRC Resident Inspector. |
| Where | |
|---|---|
Palisades  Michigan (NRC Region 3) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| Time - Person (Reporting Time:+-0.72 h-0.03 days <br />-0.00429 weeks <br />-9.86256e-4 months <br />) | |
| Opened: | Michael Mlynarek 16:06 May 23, 2008 |
| NRC Officer: | Jeff Rotton |
| Last Updated: | May 23, 2008 |
| 44237 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | A/R |
| Before | Power Operation (100 %) |
| After | Hot Standby (0 %) |
Palisades with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
WEEKMONTHYEARENS 538192019-01-09T05:00:0009 January 2019 05:00:00
[Table view]10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Trip from Full Power Due to Rps Testing ENS 538132019-01-03T05:00:0003 January 2019 05:00:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Trip Due to Cycling of Turbine Governor Valve ENS 527642017-05-19T06:06:00019 May 2017 06:06:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Valid Reactor Protection System Actuation While Shutdown ENS 513972015-09-16T05:17:00016 September 2015 05:17:00 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 475232011-12-14T20:10:00014 December 2011 20:10:00 Other Unspec Reqmnt, 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 Both Main Feedpumps ENS 472902011-09-25T19:06:00025 September 2011 19:06:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Trip Due to Loss of Two 120 Volt Ac Instrument Busses ENS 465642011-01-22T22:35:00022 January 2011 22:35:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Due to Loss of Generator Load ENS 442372008-05-23T16:49:00023 May 2008 16:49:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip on Possible Generator Lockout ENS 439002008-01-13T10:21:00013 January 2008 10:21:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip After Loss of Main Feedwater Pump ENS 433512007-05-08T17:22:0008 May 2007 17:22:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip on Low Steam Generator Water Level ENS 425692006-05-11T19:14:00011 May 2006 19:14:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Actuation of Reactor Protection System Due to Failure of Control Rod to Withdraw ENS 425552006-05-04T21:50:0004 May 2006 21:50:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unexpected Reactor Protection System (Rps) Actuation During Testing ENS 419672005-09-01T14:25:0001 September 2005 14:25:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Trip Due to Main Generator Hydrogen Leak ENS 413192005-01-09T16:27:0009 January 2005 16:27:00 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 Lowering Main Condenser Vacuum ENS 410022004-08-31T11:18:00031 August 2004 11:18:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Rps Actuation Due to Fire in 2B Condensate Pump 2019-01-09T05:00:00 | |
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