ENS 47327
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ENS Event | |
|---|---|
16:26 Oct 6, 2011 | |
| Title | Automatic Reactor Trip Due to Low Steam Generator Water Level |
| Event Description | At 1226 [EDT] today, Seabrook experienced an automatic reactor trip on low steam generator water levels. The low steam generator levels resulted following a trip of one of the two operating main feed pumps. Main feed pump 'A' tripped on low suction pressure while a condensate pump was being returned to service following maintenance on the pump. The emergency feedwater system actuated automatically and recovered steam generator levels. All systems actuated and functioned as designed. The wide range level indication on steam generator 'C' indicated erratically and was declared Inoperable. The plant is stable and being maintained in Mode 3. The station plans to cool the plant to Mode 5 for a previously planned forced outage.
This notification provides a four-hour report for an actuation of the reactor protection system while the reactor is critical and an eight-hour report for a valid actuation of the emergency feedwater system. All rods fully inserted. Emergency feedwater has been secured and placed in standby and startup feedwater is supplying the steam generators. Decay heat is being removed to the condenser via the turbine bypass valves. Electrical systems are in a normal shutdown alignment. There is nothing unusual or not understood and all systems functioned as required. The licensee has 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-2011-002 |
| Time - Person (Reporting Time:+-1.15 h-0.0479 days <br />-0.00685 weeks <br />-0.00158 months <br />) | |
| Opened: | Barry Bradbury 15:17 Oct 6, 2011 |
| NRC Officer: | Bill Huffman |
| Last Updated: | Oct 6, 2011 |
| 47327 - 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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