ENS 50847
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ENS Event | |
|---|---|
02:40 Feb 24, 2015 | |
| Title | Automatic Reactor Scram on Reactor High Pressure Signal |
| Event Description | At 2140 EST on 02/23/2015, Unit 1 reactor automatically scrammed on a valid reactor high pressure signal (1096#). The reactor high pressure signal was caused by the closure of the 1C inboard main steam isolation valve (MSIV), causing reactor pressure to rise, exceeding the reactor protection system (RPS) setpoint of 1096# pressure.
The shutdown was normal and the plant is stable in Hot Shutdown with normal pressure control via the main steam bypass valves to the main condenser and normal level control using the feedwater system. The closure of the 1C inboard MSIV appears to have been caused by a loss of primary containment instrument gas (PCIG) pneumatic supply to the valve. Instrument air was aligned to the remaining MSIV's. Limerick Unit 1 will remain in Hot Shutdown until repairs can be made. All rods inserted into the core during the scram. No relief or safety valves actuated during the transient. The electric grid is stable and supplying all plant loads. There was no affect on Unit 2. The licensee notified the NRC Resident Inspector, Pennsylvania Emergency Management Agency, and Berks, Chester and Montgomery counties. |
| Where | |
|---|---|
Limerick  Pennsylvania (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation | |
| LER: | 05000352/LER-2015-001 |
| Time - Person (Reporting Time:+-1.63 h-0.0679 days <br />-0.0097 weeks <br />-0.00223 months <br />) | |
| Opened: | Paul Marvel 01:02 Feb 24, 2015 |
| NRC Officer: | Howie Crouch |
| Last Updated: | Feb 24, 2015 |
| 50847 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | A/R |
| Before | Power Operation (100 %) |
| After | Hot Shutdown (0 %) |
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 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 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 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 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 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 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 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 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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