ENS 49979
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ENS Event | |
|---|---|
04:26 Apr 1, 2014 | |
| Title | Automatic Reactor Trip Due to Electrical Issue |
| Event Description | At 0026 on 04/01/2014, following the turbine shutdown and removal of the main generator from service in preparation for refueling outage 16, Seabrook had a reactor trip and all control rods were fully inserted. The trip was caused by an electrical issue that caused 345 KV bus 6 to deenergize and power was lost to the Unit Auxiliary Transformers (UATs). The in-house busses transferred to the Reserve Auxiliary Transformer (RAT) supplies and the momentary loss of power to in-house Bus 1 caused 2 reactor coolant pumps to trip, generating a 2 loop loss of flow reactor trip signal. The exact cause of the initiating electrical issue is being investigated.
The NRC Resident Inspector has been notified. Emergency feedwater actuated at 0035 due to a low low water level in steam generator 'C'. Plant equipment response is being evaluated and the plant is stabilized in Mode 3 with decay heat removal through the steam dump system to the condensers. There was no release and the emergency feedwater system is being restored to standby. The event description is based on information currently available. If through subsequent reviews of this event, additional information is identified that is pertinent to this event or alters the information being provided at this time, a follow-up notification will be made via the ENS or under the reporting requirements of 10CFR50.73. |
| Where | |
|---|---|
Seabrook  New Hampshire (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation | |
| Time - Person (Reporting Time:+-1.7 h-0.0708 days <br />-0.0101 weeks <br />-0.00233 months <br />) | |
| Opened: | Paul Dunden 02:44 Apr 1, 2014 |
| NRC Officer: | Charles Teal |
| Last Updated: | Apr 1, 2014 |
| 49979 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | A/R |
| Before | Power Operation (15 %) |
| After | Hot Standby (0 %) |
WEEKMONTHYEARENS 574322024-11-19T18:50:00019 November 2024 18:50:00
[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 ENS 566452023-07-30T19:26:00030 July 2023 19:26:00 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 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 2024-11-19T18:50:00 | |
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