ENS 56075
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ENS Event | |
|---|---|
07:29 Aug 28, 2022 | |
| Title | Manual Reactor Trip and Auxiliary Feedwater System Actuation |
| Event Description | The following information was provided by the licensee via email:
[On 8/28/2022] at 0329 Eastern Daylight Time (EDT), with Unit 1 in Mode 1 at 100% power, the reactor was manually tripped due to a 'B' train main feedwater pump trip. The trip was not complex with all systems responding normally post-trip. The auxiliary feedwater (AFW) system started automatically as expected. Operations responded and stabilized the plant. Steam generator levels are being maintained by AFW through the AFW flow control valves. Decay heat is being removed by using the steam generator power-operated relief valves. The reason for the 'B' train main feedwater pump trip is under investigation. Due to the reactor protection system actuation while critical, this event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B). This event is also being reported per 10 CFR 50.72(b)(3)(iv)(A) as an event that resulted in a valid actuation of the auxiliary feedwater system. There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified. The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance: The cause of the 'B' train main feedwater pump trip is suspected to be the result of an electrical transient due to the alarms that the operators received. In addition, the 'A' train main feedwater pump also tripped subsequent to the reactor trip and that cause is still under investigation. |
| Where | |
|---|---|
Harris  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:+-0.35 h-0.0146 days <br />-0.00208 weeks <br />-4.7943e-4 months <br />) | |
| Opened: | Michael Merletto 07:08 Aug 28, 2022 |
| NRC Officer: | Ernest West |
| Last Updated: | Aug 28, 2022 |
| 56075 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | Yes, Manual Scram |
| Before | Power Operation (100 %) |
| After | Hot Standby (0 %) |
Harris with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
WEEKMONTHYEARENS 571552024-05-30T23:49:00030 May 2024 23:49:00
[Table view]10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Trip ENS 561902022-10-31T00:57:00031 October 2022 00:57:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Specified System Actuation - Auxiliary Feedwater System Actuation ENS 561892022-10-30T10:53:00030 October 2022 10:53:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip and Auxiliary Feedwater System Actuation ENS 560752022-08-28T07:29:00028 August 2022 07:29:00 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 Auxiliary Feedwater System Actuation ENS 558682022-04-29T08:05:00029 April 2022 08:05:00 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 Auxiliary Feedwater System Actuation ENS 550382020-12-16T13:51:00016 December 2020 13:51:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Trip Due to Generator Lockout ENS 548342020-08-13T13:38:00013 August 2020 13:38:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip Due to Dropped Control Rod ENS 545992020-03-23T14:13:00023 March 2020 14:13:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Trip ENS 533182018-04-07T08:51:0007 April 2018 08:51:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Actuation of Auxiliary Feedwater System (Afw) ENS 523352016-10-26T15:42:00026 October 2016 15:42:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Containment Sump Suction Valve Opened During Containment Spray Pump Testing ENS 522912016-10-08T17:28:0008 October 2016 17:28:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 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)(3)(xiii), Loss of Emergency Preparedness Unusual Event Declared Due to Loss of Offsite Power ENS 522892016-10-08T05:50:0008 October 2016 05:50:00 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)(iv)(A), System Actuation - ECCS Discharge Unplanned Reactor Trip and Safety Injection Due to Turbine Control Valve Transient ENS 497422014-01-18T15:16:00018 January 2014 15:16:00 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)(3)(xiii), Loss of Emergency Preparedness Alert Declared Due to Fire in 480V Bus ENS 463962010-11-05T05:04:0005 November 2010 05:04:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Valid Actuation of an Emergency Diesel Generator Following Inadvertent De-Energization of Safety Bus ENS 454992009-11-16T03:42:00016 November 2009 03:42:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip Due to Main Generator Oil Leak ENS 444232008-08-19T13:05:00019 August 2008 13:05:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Rod Control System Malfunctioned ENS 444042008-08-11T04:49:00011 August 2008 04:49:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip Due to Degrading Condenser Vacuum ENS 436762007-09-29T02:32:00029 September 2007 02:32:00 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 a Startup Transformer ENS 428482006-09-19T14:00:00019 September 2006 14:00:00 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 Generator Lockout Signal ENS 416542005-05-01T04:21:0001 May 2005 04:21:00 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 Condensate Pump ENS 411792004-11-07T21:35:0007 November 2004 21:35:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation "a" Auxiliary Feedwater (Afw) Pump Manually Started Due to Decreasing Steam Generator Water Level. ENS 411292004-10-18T11:41:00018 October 2004 11:41:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unplanned Emergency Diesel Start ENS 407302004-05-06T16:52:0006 May 2004 16:52:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip and Actuation of Auxiliary Feedwater System ENS 400842003-08-17T19:51:00017 August 2003 19:51:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Due to Loss of "a" Condensate Pump. 2024-05-30T23:49:00 | |
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