ENS 43315
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ENS Event | |
|---|---|
06:10 Apr 24, 2007 | |
| Title | Automatic Reactor Scram with Eccs Injection on Lowering Reactor Vessel Water Level |
| Event Description | Limerick Unit 2 automatically shutdown on low reactor water level (+12.5 inches) at 0210 on 4/24/07. The cause is under investigation at this time.
All control rods inserted as required. HPCI and RCIC initiated, injected and restored reactor water level. Lowest reactor water level noted was -73 inches. Primary containment isolation signals on +12.5 inches and -38 inches occurred. All isolations completed as required. The plant is currently in hot shutdown maintaining normal reactor level with feedwater in service. Approximately 16000 gallons was injected in 4 minutes. There was no indication of RCS leakage. The licensee is investigating whether a feedwater runback had occurred. No SRVs lifted with the highest pressure observed at 1050 psi. The main condenser remains in service for decay heat removal. All EDGs are available, if needed. The licensee informed the NRC Resident Inspector and will inform both the State and Local authorities. |
| Where | |
|---|---|
Limerick  Pennsylvania (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| Time - Person (Reporting Time:+-2.1 h-0.0875 days <br />-0.0125 weeks <br />-0.00288 months <br />) | |
| Opened: | Ned Dennin 04:04 Apr 24, 2007 |
| NRC Officer: | Steve Sandin |
| Last Updated: | Apr 24, 2007 |
| 43315 - NRC Website
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Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | A/R |
| Before | Power Operation (100 %) |
| After | Hot Shutdown (0 %) |
Limerick 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 549962020-11-13T07:45:00013 November 2020 07:45:00
[Table view]10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram Due to High Reactor Pressure Signal ENS 540982019-06-04T05:45:0004 June 2019 05:45:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Scram During Rapid Plant Shutdown ENS 519682016-06-01T13:00:0001 June 2016 13:00:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Scram Due to Unexpected Core Flow Change ENS 516142015-12-19T12:02:00019 December 2015 12:02:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram Due to Low Reactor Water Level ENS 511682015-06-21T20:25:00021 June 2015 20:25:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Secondary Containment Isolation ENS 509812015-04-13T06:20:00013 April 2015 06:20:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Scram Initiated ENS 508472015-02-24T02:40:00024 February 2015 02:40:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram on Reactor High Pressure Signal ENS 498712014-03-05T04:34:0005 March 2014 04:34:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Unit 1 Manually Scrammed During a Rapid Shutdown in Response to a Turbine Ehc Failure ENS 489362013-04-17T01:42:00017 April 2013 01:42:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Specified System Actuation During Turbine Stop Valve Logic Testing While Shutdown ENS 481212012-07-19T19:37:00019 July 2012 19:37:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Protection Signal Actuation Due to Changing Mode Switch Position During Surveillance Testing ENS 481172012-07-18T12:15:00018 July 2012 12:15:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(a)(1)(i), Emergency Class Declaration Unusual Event Declared Due to Flashover in the Load Center Transformer Cabinet ENS 478882012-05-02T11:24:0002 May 2012 11:24:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Initiation of Secondary Containment Isolation ENS 478502012-04-19T11:53:00019 April 2012 11:53:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(xiii), Loss of Emergency Preparedness Manual Reactor Scram Following Loss of Recirculation Pumps ENS 469192011-06-03T14:21:0003 June 2011 14:21:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Scram Following a Turbine Trip ENS 469062011-05-30T15:50:00030 May 2011 15:50:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Specified System Actuation - Manual Reactor Scram Due to Dual Recirc Pump Trip During Startup ENS 469032011-05-29T09:02:00029 May 2011 09:02:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Trip Due to Low Pressure in Ehc System ENS 466412011-02-25T14:10:00025 February 2011 14:10:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Scram Due to Recirculation Pump Trip ENS 460422010-06-24T00:51:00024 June 2010 00:51:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Scram Following Loss of Both Recirculation Pumps ENS 449482009-03-31T22:50:00031 March 2009 22:50:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Valid Diesel Start Signal Received During Maintenance Testing of Diesel ENS 440882008-03-22T23:39:00022 March 2008 23:39:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Turbine Trip Resulting in a Reactor Scram ENS 439492008-02-01T09:45:0001 February 2008 09:45:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Scram as a Result of Turbine Trip ENS 438982008-01-12T14:04:00012 January 2008 14:04:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Valid Specified System Actuation During Edg Governor Testing ENS 433152007-04-24T06:10:00024 April 2007 06:10:00 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 Scram with Eccs Injection on Lowering Reactor Vessel Water Level ENS 432312007-03-13T11:30:00013 March 2007 11:30:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Low Main Condenser Vacuum Isolation Signal Received During Plant Shutdown ENS 421932005-12-09T14:01:0009 December 2005 14:01:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Trip of a Startup Bus Breaker Results in Start of Emergency Diesel Generators ENS 420542005-10-13T02:24:00013 October 2005 02:24:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Scram Due to Reactor High Pressure Signal ENS 418482005-07-18T13:52:00018 July 2005 13:52:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram ENS 415732005-04-06T21:55:0006 April 2005 21:55:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Partial Loss of Offsite Power Resulting in Autostart of Emergency Diesel Generators ENS 408322004-06-22T17:13:00022 June 2004 17:13:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram Following an Electrical Yard Manipulation 2020-11-13T07:45:00 | |
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