ENS 52764
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ENS Event | |
---|---|
06:06 May 19, 2017 | |
Title | Valid Reactor Protection System Actuation While Shutdown |
Event Description | Pursuant to 10CFR50.72(b)(3)(iv)(A), notifications are being performed for a valid actuation of the reactor protection system resulting in a full scram. The actuation was a result of pre-startup testing. The generator coastdown protective relay was left in service which needed to be bypassed to facilitate the testing. This resulted in a reactor scram occurring.
The reactor was subcritical with all rods inserted at the time of the actuation. All systems functioned as designed. The licensee notified the NRC Resident Inspector. |
Where | |
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Palisades Michigan (NRC Region 3) | |
Reporting | |
10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
Time - Person (Reporting Time:+2.7 h0.113 days <br />0.0161 weeks <br />0.0037 months <br />) | |
Opened: | Jarrod Miller 08:48 May 19, 2017 |
NRC Officer: | Bethany Cecere |
Last Updated: | May 19, 2017 |
52764 - NRC Website | |
Unit 1 | |
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Reactor critical | Not Critical |
Scram | No |
Before | Cold Shutdown (0 %) |
After | Cold Shutdown (0 %) |
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 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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