ENS 53217
From kanterella
Revision as of 21:51, 30 October 2018 by StriderTol (talk | contribs) (Created page by program invented by StriderTol)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
ENS Event | |
|---|---|
15:14 Feb 16, 2018 | |
| Title | Automatic Reactor Trip During Solid State Protection System Testing |
| Event Description | At 1014 [EST] hours on 2/16/18, with Unit 1 in Mode 1 at approximately 100 percent power, the reactor automatically tripped when the Reactor Trip Breakers opened during Train B Solid State Protection System (SSPS) testing. The trip was uncomplicated with all systems responding normally post-trip. Operations manually started the motor driven auxiliary feedwater
pumps. The turbine driven auxiliary feedwater pump (TDCAP) auto-started on low steam generator level. A Feedwater Isolation occurred as designed due to the Reactor Trip and Lo Tave condition. Operations stabilized the plant. Decay heat is being removed by the condenser. Unit 2 is not affected. Due to the Reactor Protection System actuation while critical, actuation of the TDCAP and motor driven auxiliary feedwater pumps along with the Feedwater Isolation, this event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B) and an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> non-emergency notification per 10 CFR 50.72(b)(3)(iv)(A). There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified. |
| Where | |
|---|---|
Mcguire  North 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:+-1.27 h-0.0529 days <br />-0.00756 weeks <br />-0.00174 months <br />) | |
| Opened: | Brian Jetton 13:58 Feb 16, 2018 |
| NRC Officer: | Dong Park |
| Last Updated: | Feb 16, 2018 |
| 53217 - NRC Website | |
Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | A/R |
| Before | Power Operation (100 %) |
| After | Hot Standby (0 %) |
McGuire with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
WEEKMONTHYEARENS 568022023-10-18T15:16:00018 October 2023 15:16:00
[Table view]10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Actuation of Auxiliary Feedwater System ENS 564512023-04-02T07:52:0002 April 2023 07:52:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Actuation of Auxiliary Feedwater Motor Driven Pumps ENS 557482022-02-18T09:59:00018 February 2022 09:59:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip and System Actuation ENS 554582021-09-13T04:11:00013 September 2021 04:11:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Specified System Actuation ENS 540472019-05-03T19:54:0003 May 2019 19:54:00 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 Over Temperature Delta Temperature ENS 532172018-02-16T15:14:00016 February 2018 15:14:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip During Solid State Protection System Testing ENS 514742015-10-07T10:55:0007 October 2015 10:55:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unplanned Afw Actuation During Refueling Outage Testing ENS 495382013-11-14T18:13:00014 November 2013 18:13:00 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 Indication of Dropped Control Rods ENS 487752013-02-21T14:57:00021 February 2013 14:57:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Due to Turbine Trip on Loss of Both Main Feed Pumps ENS 485492012-12-02T04:17:0002 December 2012 04:17:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Amsac Actuated at Lower than Expected Turbine Inlet Pressure ENS 467092011-03-30T04:10:00030 March 2011 04:10:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Control Rod Malfunction During Rod Testing Results in Operators Manually Opening Trip Breakers ENS 465592011-01-20T20:18:00020 January 2011 20:18:00 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 Both Main Feed Pumps During Shutdown ENS 460032010-06-12T10:44:00012 June 2010 10:44:00 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 a Control Rod Drop Indication ENS 448692009-02-23T09:06:00023 February 2009 09:06:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Inadvertent Actuation of the Turbine Driven Auxiliary Feedwater Pump ENS 446242008-11-03T07:07:0003 November 2008 07:07:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manually Opened Reactor Trip Circuit Breakers to Insert Control Bank "B ENS 446182008-10-31T16:52:00031 October 2008 16:52:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Due to Rod Control Malfunction ENS 443182008-06-26T21:32:00026 June 2008 21:32:00 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 Loss of 1B Reactor Coolant Pump ENS 422112005-12-17T08:11:00017 December 2005 08:11:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip from Full Power Due to a Failed Feed Flow Channel ENS 415782005-04-08T19:43:0008 April 2005 19:43:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Main Steamline Isolation Valves Closed on Valid Signal ENS 414572005-03-02T21:29:0002 March 2005 21:29:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Actuation of Motor Driven Afw Pumps During Outage ENS 414532005-03-01T20:45:0001 March 2005 20:45:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip During a Rapid Shutdown for Steam Leak Repair 2023-04-02T07:52:00 | |
Retrieved from "https://kanterella.com/w/index.php?title=ENS_53217&oldid=1160388"