ENS 54834
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ENS Event | |
|---|---|
13:38 Aug 13, 2020 | |
| Title | Manual Reactor Trip Due to Dropped Control Rod |
| Event Description | On August 13, 2020, at 0938 EDT, with Harris Nuclear Plant Unit 1 in Mode 1 at 100 percent power, a control rod dropped during control rod testing. This is considered to be an unanalyzed condition and requires a manual reactor trip in accordance with plant procedure. All safety systems functioned as expected. Auxiliary Feedwater started as designed and was secured. Steam generator levels are being maintained by Main Feedwater through the feedwater regulator bypass valves. Decay heat is being removed by using the condenser steam dump flow path. Due to the RPS actuation, this event is being reported as a four hour non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B). Due to the unanalyzed condition and unplanned Auxiliary Feedwater actuation, this event is also being reported as an eight hour non-emergency notification per 10 CFR 50.72(b)(3)(ii)(B) and 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 | |
|---|---|
Harris  North Carolina (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation | |
| Time - Person (Reporting Time:+-0.23 h-0.00958 days <br />-0.00137 weeks <br />-3.15054e-4 months <br />) | |
| Opened: | Lonnie Hickerson 13:24 Aug 13, 2020 |
| NRC Officer: | Brian P. Smith |
| Last Updated: | Aug 13, 2020 |
| 54834 - NRC Website | |
WEEKMONTHYEARENS 561892022-10-30T10:53:00030 October 2022 10:53:00
[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 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 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 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 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 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. 2022-08-28T07:29:00 | |
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