ENS 41706
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ENS Event | |
|---|---|
05:54 May 18, 2005 | |
| Title | Loss Of Balance Of Plant Power Due To Transformers Lockout |
| Event Description | {{#Wiki_filter:At 0154, 5/18/2005, during performance of relay testing, differential lockout 86T3 was manually actuated resulting in lockout of transformers XTF 31 and XTF 32. This resulted in a loss of all balance of plant (BOP) buses, loss of vital bus 1DB, an auto start of 'B' Diesel Generator (DG), and the sequencing of required ESF loads.
At 0154, during relay testing, the 86T3 differential lockout was actuated. This resulted in a total isolation of XTF0031/32 which de-energized all of the BOP power to the plant and the XSW1 DB switchgear. Plant Engineered Safeguards Features (ESF) systems responded per design as the 'B' DG started and sequenced ESF loads. There were no major problems due to the event; however, the Diesel Fire Pump did not start as expected on a loss of BOP bus 1 C2. The Control Room entered AOP-304.3, 'Loss of All Balance of Plant Buses' and SOP-306, Section B, 'Operation of Diesel Generator 'B' After An Automatic Start And Load'. Preliminary review of plant response shows the RHR flow was in the process of coasting down and was restored to full flow within 20 seconds. The inlet temperature of the Residual Heat Removal (RHR) Heat Exchanger increased approximately 0.3 �F due to this event. There was no change in Reactor Coolant System level. V. C. Summer is currently shutdown in Mode 5 during Refueling Outage 15. All plant systems are currently restored to normal configuration for Mode 5 refueling activities and there were no reported reactivity issues associated with this incident. The licensee notified the NRC Resident Inspector and will notify the State, local and other government agencies. }} |
| Where | |
|---|---|
Summer  South Carolina (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| Time - Person (Reporting Time:+3.55 h0.148 days <br />0.0211 weeks <br />0.00486 months <br />) | |
| Opened: | Arnie Cribb 09:27 May 18, 2005 |
| NRC Officer: | Arlon Costa |
| Last Updated: | May 18, 2005 |
| 41706 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Not Critical |
| Scram | No |
| Before | Cold Shutdown (0 %) |
| After | Cold Shutdown (0 %) |
WEEKMONTHYEARENS 569782024-02-19T07:36:00019 February 2024 07:36:00
[Table view]10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Start of B Emergency Diesel Generator ENS 564532023-04-05T10:51:0005 April 2023 10:51:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip ENS 555802021-11-15T22:28:00015 November 2021 22:28:00 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 Main Transformer Fault ENS 531762018-01-18T17:02:00018 January 2018 17:02:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Emergency Diesel Generator Actuation Due to Loss of One of Two Offsite Power Supplies ENS 530602017-11-08T00:57:0008 November 2017 00:57:00 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 Turbine Trip ENS 529622017-09-11T20:48:00011 September 2017 20:48:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Emergency Diesel Generator Actuation on Low Voltage ENS 529322017-08-28T12:37:00028 August 2017 12:37:00 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 Turbine Trip ENS 528332017-06-29T12:57:00029 June 2017 12:57:00 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 a Loss of Normal Feedwater Flow to B Steam Generator ENS 502932014-07-22T08:14:00022 July 2014 08:14:00 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 Level ENS 488462013-03-24T08:58:00024 March 2013 08:58:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Start of an Emergency Diesel Generator Due to a Lightning Strike ENS 468992011-05-27T16:00:00027 May 2011 16:00:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge Safety Injection Initiated Due to a High Differential Pressure Between Main Steam Lines ENS 455772009-12-16T19:15:00016 December 2009 19:15:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Following a Failure of the Steam Dump System ENS 454042009-10-02T10:49:0002 October 2009 10:49:00 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 Turbine Trip Possibly Caused by a Faulted Main Generator Breaker ENS 442312008-05-21T21:04:00021 May 2008 21:04:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Emergency Diesel Generator Shifted to Emergency Start During Post Maintenance Test ENS 439322008-01-24T21:04:00024 January 2008 21:04:00 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 Failure of the "C" Feedwater Flow Control Valve ENS 431412007-02-05T08:07:0005 February 2007 08:07:00 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 Steam Leak During Main Feed Booster Pump Startup ENS 430042006-11-22T09:26:00022 November 2006 09:26:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Main Turbine Trip Due to High- High Steam Generator "B" Water Level During Feedwater Swap Over. ENS 429982006-11-09T19:44:0009 November 2006 19:44:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Emergency Diesel Generator Actuation During Testing ENS 417062005-05-18T05:54:00018 May 2005 05:54:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Loss of Balance of Plant Power Due to Transformers Lockout ENS 408112004-06-13T00:29:00013 June 2004 00:29:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Emergency Diesel Started and Loaded on Bus Undervoltage Signal ENS 406282004-03-30T16:29:00030 March 2004 16:29:00 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)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Automatic Reactor Trip Due to Lo-Lo Steam Generator Level ENS 403482003-11-21T14:10:00021 November 2003 14:10:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Control Bank "C" Rods Tripped Due to Incorrect Digital Rod Position Indication (Drpi) 2024-02-19T07:36:00 | |
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