ENS 54740
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ENS Event | |
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13:20 Jun 6, 2020 | |
Title | Manual Reactor Trip When Group One, Bank 'B' Control Rods Inserted Into the Core |
Event Description | At 0920 [EDT], with the unit in Mode 1 and 100 percent power, the reactor was manually tripped due to group 1 of control rod bank 'B' fully inserting into the core. All systems responded normally post trip. Operations has stabilized the plant in mode 3 at NOP/NOT [normal operating pressure and temperature]. Decay heat removal is being accomplished via the steam dumps in the steam pressure mode to the main condenser.
Emergency feedwater actuated due to low low steam generator level as expected. This event is being reported pursuant to 10CFR50.72(b)(2)(iv)(B) and 10CFR50.72(b)(3)(iv)(A) The senior NRC Resident Inspector has been notified. The plant response to the trip was uncomplicated. All safe shutdown equipment is available. There were no reliefs or safeties actuated during the transient. The licensee manually tripped eight days ago for the same condition. See EN #54731. |
Where | |
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Seabrook New Hampshire (NRC Region 1) | |
Reporting | |
10 CFR 50.72(b)(2)(iv)(B), RPS Actuation | |
Time - Person (Reporting Time:+-0.92 h-0.0383 days <br />-0.00548 weeks <br />-0.00126 months <br />) | |
Opened: | Mike Taylor 12:25 Jun 6, 2020 |
NRC Officer: | Howie Crouch |
Last Updated: | Jun 6, 2020 |
54740 - NRC Website
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WEEKMONTHYEARENS 566452023-07-30T19:26:00030 July 2023 19:26:00
[Table view]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 LOW Main Turbine ELECTRO-HYDRAULIC Control (EHC) Oil Level ENS 547402020-06-06T13:20:0006 June 2020 13:20:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip When Group One, Bank 'B' Control Rods Inserted Into the Core ENS 547312020-05-29T18:03:00029 May 2020 18:03:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Trip Due to Rod Bank Unexpectedly Inserting ENS 527182017-04-29T22:44:00029 April 2017 22:44:00 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 Steam Generator Hi-Hi Level Signal and Feedwater Isolation ENS 517622016-03-02T07:53:0002 March 2016 07:53:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Turbine Trip Causing a Reactor Trip ENS 499792014-04-01T04:26:0001 April 2014 04:26:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Trip Due to Electrical Issue ENS 483102012-09-15T00:25:00015 September 2012 00:25:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Trip Due to Low Steam Generator Water Level ENS 473272011-10-06T16:26:0006 October 2011 16:26:00 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 Water Level ENS 439212008-01-20T04:02:00020 January 2008 04:02:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Following Turbine Trip ENS 416552005-05-01T15:09:0001 May 2005 15:09:00 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 Turbine High Vibration ENS 402862003-11-01T00:48:0001 November 2003 00:48:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Trip on Low Steam Generator Water Level 2023-07-30T19:26:00 | |
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