ENS 52198
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ENS Event | |
|---|---|
17:38 Aug 24, 2016 | |
| Title | Reactor Trip Due Automatic Turbine Trip from 100 Percent Power |
| Event Description | At 1338 [EDT] on 08/24/2016, a turbine trip, and a subsequent reactor trip occurred. The cause is under investigation. Following the reactor trip, the Auxiliary Feedwater System actuated as expected on low steam generator level. At the time of the trip, the plant was in Mode 1. As of 1643 [EDT], the Plant is in Mode 3. The current RCS [Reactor Coolant System] Temperature is 548 degrees F (Average), and the Steam Generator Levels are in the range of 40 to 45% (normal range) with levels controlled by the Main Feedwater System. All systems and equipment operated as expected.
Due to the automatic actuation of the Reactor Protection System, this event is being reported as a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Non-Emergency per 10 CFR 50.72(b)(2)(iv)(B). Due to the valid actuation of Auxiliary Feedwater System, this event is also being reported as an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Non-Emergency per 10 CFR 50.72(b)(3)(iv)(A)(B)(6). At no time during this occurrence was the public or plant staff at risk as a result of this event. The NRC Resident Inspector has been notified. |
| Where | |
|---|---|
Robinson  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:+-0.72 h-0.03 days <br />-0.00429 weeks <br />-9.86256e-4 months <br />) | |
| Opened: | Joseph Rhodes 16:55 Aug 24, 2016 |
| NRC Officer: | Jeff Herrera |
| Last Updated: | Aug 24, 2016 |
| 52198 - NRC Website
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Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | A/R |
| Before | Power Operation (100 %) |
| After | Hot Standby (0 %) |
Robinson with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
WEEKMONTHYEARENS 565852023-06-22T14:35:00022 June 2023 14:35:00
[Table view]10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Occured During Protection System Testing ENS 542122019-08-11T12:40:00011 August 2019 12:40:00 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 Turbine Trip ENS 537452018-11-19T05:00:00019 November 2018 05:00:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Emergency Diesel Generator Actuation Due to Low Voltage Signal ENS 526622017-04-04T01:55:0004 April 2017 01:55:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Actuation of Auxiliary Feedwater System During Surveillance Testing ENS 522902016-10-08T17:17:0008 October 2016 17:17:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(a)(1)(i), Emergency Class Declaration, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unusual Event Declared Due to Loss of Offsite Power ENS 521982016-08-24T17:38:00024 August 2016 17:38:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Trip Due Automatic Turbine Trip from 100 Percent Power ENS 497082014-01-10T03:34:00010 January 2014 03:34:00 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 Turbine Trip ENS 495062013-11-05T23:00:0005 November 2013 23:00:00 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 Momentary Loss of 4 Kv Buses and Safety System Actuation ENS 495022013-11-05T05:41:0005 November 2013 05:41:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Actuation of the Auxiliary Feedwater System Due to Main Feed Pump Trip ENS 477812012-03-28T19:03:00028 March 2012 19:03:00 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 High Water Level Condition ENS 472932011-09-26T15:45:00026 September 2011 15:45:00 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 One Loop Low Flow Signal ENS 463132010-10-07T04:13:0007 October 2010 04:13:00 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 One Loop Reactor Coolant Low Flow ENS 462382010-09-09T18:37:0009 September 2010 18:37:00 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 Overtemperature Delta-T Signal ENS 457992010-03-28T22:52:00028 March 2010 22:52:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(a)(1)(i), Emergency Class Declaration, 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge Alert Declared Due to Fire Affecting Safety Related Equipment ENS 454832009-11-07T03:02:0007 November 2009 03:02:00 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 Feed Reg Valve Closure ENS 446602008-11-17T10:51:00017 November 2008 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 Scram Due to High Turbine Vibration ENS 433642007-05-15T15:16:00015 May 2007 15:16:00 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 Due to Differential Generator Protection ENS 429332006-10-25T06:48:00025 October 2006 06:48:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip After a 100% Load Rejection 2023-06-22T14:35:00 | |
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