ENS 52681
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ENS Event | |
|---|---|
17:57 Apr 14, 2017 | |
| Title | Unplanned Emergency Diesel Generator Start Due to Loss of a 4160 V Bus |
| Event Description | At 1357 [EDT] on April 14, 2017, an unplanned automatic start signal was generated for the 2C Emergency Diesel Generator (EDG). The station was in the process of transferring the 2C 4160 volt vital bus from the 24 Station Power Transformer (SPT) to the 23 SPT, which are the offsite power in-feeds for the 2C 4160 volt vital bus. The 24 SPT infeed breaker opened as expected; however, the 23 SPT infeed breaker failed to close. The failure to swap from the 24 SPT to 23 SPT resulted in a momentary loss of power to the 2C 4160 volt vital bus generating the automatic start signal for the 2C EDG. The 2C 4160 volt vital bus was automatically re-energized by the 2C EDG as expected.
Abnormal operating procedures were entered for loss of the 2C 4160 volt vital bus. Salem Unit 2 was in Mode 1 operating at 100% power. All equipment operated as expected. At 1555 [EDT], 2C 4160 volt vital bus was reenergized from 24 SPT, and the 2C EDG was secured in accordance with station implementing procedures. There was no impact to the health and safety of the public. The Resident Inspector has been notified. The Lower Alloways Creek Township, State of New Jersey, and State of Delaware will be notified. |
| Where | |
|---|---|
Salem  New Jersey (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| LER: | 05000311/LER-2017-001 |
| Time - Person (Reporting Time:+-1.2 h-0.05 days <br />-0.00714 weeks <br />-0.00164 months <br />) | |
| Opened: | Matthew Mog 16:45 Apr 14, 2017 |
| NRC Officer: | Dong Park |
| Last Updated: | Apr 14, 2017 |
| 52681 - NRC Website
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Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
WEEKMONTHYEARENS 562862022-12-24T07:22:00024 December 2022 07:22:00
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System Actuation Automatic Reactor Trip Due to Main Turbine Trip ENS 512902015-08-05T19:38:0005 August 2015 19:38:00 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 Reactor Coolant Flow ENS 505502014-10-20T00:51:00020 October 2014 00:51:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Resulting in Aux Feedwater Actuation ENS 500922014-05-07T08:56:0007 May 2014 08:56:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Trip Due to Generator Protection Relay ENS 500322014-04-14T01:13:00014 April 2014 01:13:00 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 Actuation of Main Generator Protection Relay ENS 500122014-04-09T01:14:0009 April 2014 01:14:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unit 1 Manually Tripped Following the Loss of an Operating Steam Generator Feed Pump (Sgfp) ENS 486172012-12-21T10:28:00021 December 2012 10:28:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unit 1 Automatic Reactor Trip on Turbine Trip ENS 485342012-11-25T16:30:00025 November 2012 16:30:00 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 Steam Generator Feedwater Regulator Valve Not Responding to Demand Signal ENS 484572012-10-30T05:09:00030 October 2012 05:09:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip from 100% Power ENS 477662012-03-23T18:28:00023 March 2012 18:28:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Turbine Trip Followed by Automatic Reactor Trip ENS 469922011-06-26T04:00:00026 June 2011 04:00:00 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 Reactor Coolant Pump ENS 467742011-04-21T20:01:00021 April 2011 20:01:00 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 Circulating Water Pumps Out of Service ENS 463372010-10-17T09:12:00017 October 2010 09:12:00 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 4 Kv Group Bus Undervoltage Condition ENS 463362010-10-16T03:21:00016 October 2010 03:21:00 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 a Turbine Trip ENS 460752010-07-07T15:17:0007 July 2010 15:17:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Caused by Main Generator and Turbine Trip ENS 458482010-04-16T20:41:00016 April 2010 20:41:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unplanned Emergency Diesel Generator Start Due to Loss of a 4160 V Bus ENS 456472010-01-21T23:20:00021 January 2010 23:20:00 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 Low Steam Generator Water Level ENS 456042010-01-03T13:04:0003 January 2010 13:04:00 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 Loss of Circulators After Uptake of River Ice ENS 446292008-11-05T05:57:0005 November 2008 05:57:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Emergency Diesel Generator Start Due to Unexpected Esf Signal ENS 438732007-12-28T22:54:00028 December 2007 22:54:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Trip on Failure of Station Power Transformer ENS 435502007-08-06T17:10:0006 August 2007 17:10:00 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 Spurious Interlock Signal to Feedwater Regulating Valves ENS 432592007-03-28T00:50:00028 March 2007 00:50:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Low Steam Generator Water Level Initiated Auxiliary Feedwater Signal and a Reactor Trip Signal ENS 429462006-10-30T01:11:00030 October 2006 01:11:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Start of Auxiliary Feedwater During Msiv Testing ENS 423952006-03-08T16:09:0008 March 2006 16:09:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip as a Result of a Turbine Generator Trip ENS 408752004-07-15T23:44:00015 July 2004 23:44:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Trip from 8% Power Due to Lowering Water Level on 23 Steam Generator ENS 408652004-07-13T17:05:00013 July 2004 17:05:00 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 Low Steam Generator Water Level. ENS 406652004-04-11T04:23:00011 April 2004 04:23:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Plant Had a Valid Esf Signal to Start 1C Emergency Diesel Generator ENS 406392004-04-03T15:50:0003 April 2004 15:50:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Valid Actuation of Auxiliary Feedwater System During Maintenance 2022-12-24T07:22:00 | |
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