ENS 48121
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ENS Event | |
|---|---|
19:37 Jul 19, 2012 | |
| Title | Reactor Protection Signal Actuation Due to Changing Mode Switch Position During Surveillance Testing |
| Event Description | During surveillance testing, the reactor mode switch was moved from the locked shutdown position and placed in the refuel position without the minimum required operable source range monitors per Limerick Generating Station Technical Specifications.
Upon discovery of the issue, the reactor mode switch was returned to the locked shutdown position causing an expected but valid RPS actuation. No control rod motion occurred because all control rods were already inserted at the time of the event. The licensee has notified the NRC Resident Inspector. |
| Where | |
|---|---|
Limerick  Pennsylvania (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| Time - Person (Reporting Time:+2.32 h0.0967 days <br />0.0138 weeks <br />0.00318 months <br />) | |
| Opened: | John Weissinger 21:56 Jul 19, 2012 |
| NRC Officer: | Bill Huffman |
| Last Updated: | Jul 19, 2012 |
| 48121 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Not Critical |
| Scram | A |
| Before | Cold Shutdown (0 %) |
| After | Cold Shutdown (0 %) |
WEEKMONTHYEARENS 511682015-06-21T20:25:00021 June 2015 20:25:00
[Table view]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 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 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 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 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 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 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 2015-06-21T20:25:00 | |
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