ENS 43351
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ENS Event | |
|---|---|
17:22 May 8, 2007 | |
| Title | Automatic Reactor Trip on Low Steam Generator Water Level |
| Event Description | On May 8, 2007 at 1322 hours0.0153 days <br />0.367 hours <br />0.00219 weeks <br />5.03021e-4 months <br />, the reactor automatically tripped from approximately 100% power due to low level in the 'B' Steam Generator. The low level condition resulted from spurious closure of the 'B' feedwater regulating valve. The feedwater regulating valve closure appears related to an instrument and control troubleshooting work activity that was in progress at the time of the event. Investigation into the cause is continuing.
In additions an automatic actuation of the auxiliary feedwater system occurred, as designed, to restore steam generator levels. All systems functioned as designed. Decay heat is being removed via steaming through the turbine bypass valve to the main condenser. All control rods fully inserted. The licensee informed 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:+-1.98 h-0.0825 days <br />-0.0118 weeks <br />-0.00271 months <br />) | |
| Opened: | Todd Mulford 15:23 May 8, 2007 |
| NRC Officer: | Steve Sandin |
| Last Updated: | May 8, 2007 |
| 43351 - 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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