ENS 52833
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ENS Event | |
|---|---|
12:57 Jun 29, 2017 | |
| Title | |
| Event Description | On 6/29/2017 at 0857 [EDT], VC Summer Nuclear Station automatically tripped due to a loss of normal feed water flow to the B Steam Generator.
There were no complications with the trip. All control rods fully inserted. All emergency feedwater pumps automatically started and recovered steam generator levels. The plant is stable in Mode 3. Station personnel are investigating the cause of the loss of normal feedwater to the B Steam Generator. This is reportable per 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A). The NRC Resident Inspector has been notified. The licensee notified the State of South Carolina as well as Fairfield, Lexington, Richland and Newberry Counties regarding the event. |
| Where | |
|---|---|
Summer  South Carolina (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| Time - Person (Reporting Time:+-0.23 h-0.00958 days <br />-0.00137 weeks <br />-3.15054e-4 months <br />) | |
| Opened: | Beth Dalick 12:43 Jun 29, 2017 |
| NRC Officer: | Jeff Herrera |
| Last Updated: | Jun 29, 2017 |
| 52833 - NRC Website | |
Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | A/R |
| Before | Power Operation (100 %) |
| After | Hot Standby (0 %) |
Summer with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
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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