ENS 43921
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ENS Event | |
|---|---|
04:02 Jan 20, 2008 | |
| Title | Automatic Reactor Trip Following Turbine Trip |
| Event Description | Initiating alarm received was a Turbine Trip. All on site buses 1, 2, 4, 5 and 6 swapped to the Reserve Auxiliary Transformer power supplies. Bus 3 did not swap as expected. The station has entered a Technical Specification 3.8.1.1 (a) 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> action statement for offsite power distribution with 345 kV Bus 3 unavailable.
All safety systems operated correctly. The station continues to troubleshoot the initiating cause of the Turbine Trip. The plant is stable in Mode 3. During the swap of non safety buses to the Reserve Auxiliary Transformer the Reactor Coolant Pumps (RCP) tripped. Following the loss of power to the RCPs the reactor stabilized in natural circulation. A Pressurizer PORV cycled following the trip. One RCP was restarted to restore forced circulation. Auxiliary Feedwater Pumps started as expected on the trip and were subsequently secured. All control rods fully inserted on the trip. The current decay heat removal path is Start-up Feedwater supplying water to the Steam Generators steaming to the Condenser Steam Dumps. The licensee notified the NRC Resident Inspector.
|
| Where | |
|---|---|
Seabrook  New Hampshire (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| LER: | 05000443/LER-2008-001 |
| Time - Person (Reporting Time:+-1.12 h-0.0467 days <br />-0.00667 weeks <br />-0.00153 months <br />) | |
| Opened: | Matt Forrest 02:55 Jan 20, 2008 |
| NRC Officer: | Pete Snyder |
| Last Updated: | Jan 20, 2008 |
| 43921 - NRC Website | |
Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | A/R |
| Before | Power Operation (100 %) |
| After | Hot Standby (0 %) |
Seabrook with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
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 565652023-05-06T19:52:0006 May 2023 19:52:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Actuations of Reactor Protection System ENS 565642023-04-12T15:07:00012 April 2023 15:07:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Actuation of "B" Emergency Diesel Generator Emergency Power Sequencer 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 517652016-03-02T18:12:0002 March 2016 18:12:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Valid Actuation of Emergency Feedwater 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 454032009-10-02T02:39:0002 October 2009 02:39:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unit Experienced a Valid Rps Actuation During Plant Cooldown on Low Steam Generator Levels 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 415932005-04-13T08:50:00013 April 2005 08:50:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation During Core Reload Reactor Trip Breakers Opened ENS 414282005-02-22T08:08:00022 February 2005 08:08:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Emergency Diesel Generator and Emergency Feedwater Auto Start on Vital Bus Failure to Transfer 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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