ENS 42024
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ENS Event | |
|---|---|
17:10 Sep 29, 2005 | |
| Title | Manual Reactor Trip Due to Loss of Circulating Water Pumps |
| Event Description | The licensee reported that high wind and wave action at the site has resulted in sea weed and related debris buildup at the Unit 3 intake structure. The traveling screens were unable to keep pace with the debris buildup and two out of six circulating water pumps tripped on high differential pressure across the traveling screens. Based on procedural requirements, the licensee is required to manually trip the plant due to the loss of the two circ water pumps. The reactor trip was characterized as uncomplicated with all systems functioning as required. All rods fully inserted. No primary or secondary relief valves lifted. Auxiliary feedwater automatically started as expected and is supplying cooling water to the steam generators. Decay heat is being discharged to the condenser via the turbine bypass valves. The plant is stable in hot standby at no-load temperature and pressure. The plant trip had no impact on Unit 2. The debris buildup on the Unit 2 intake is being monitored but is less of a problem due to the orientation of the Unit 2 intake structure.
The NRC Resident Inspector has been notified by the licensee. The licensee has also notified State and local authorities and has made a press release. |
| Where | |
|---|---|
Millstone  Connecticut (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| Time - Person (Reporting Time:+-2.35 h-0.0979 days <br />-0.014 weeks <br />-0.00322 months <br />) | |
| Opened: | Fred Nygard 14:49 Sep 29, 2005 |
| NRC Officer: | Bill Huffman |
| Last Updated: | Sep 29, 2005 |
| 42024 - NRC Website
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Unit 3 | |
|---|---|
| Reactor critical | Critical |
| Scram | Yes, Manual Scram |
| Before | Power Operation (100 %) |
| After | Hot Standby (0 %) |
Millstone with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
WEEKMONTHYEARENS 576942025-05-07T01:08:0007 May 2025 01:08:00
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RPS System Actuation, 10 CFR 50.72(a)(1)(i), Emergency Class Declaration, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unusual Event Due to Main Generator Hydrogen Leak in Turbine Building ENS 516822016-01-25T06:47:00025 January 2016 06:47:00 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 Reactor Coolant Pump Trip ENS 515212015-11-08T07:30:0008 November 2015 07:30:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip Due to Reactor Coolant Pump Oil Leak ENS 501422014-05-25T11:02:00025 May 2014 11:02:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(a)(1)(i), Emergency Class Declaration, 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(3)(xiii), Loss of Emergency Preparedness Unusual Event Due to Loss of Offsite Power ENS 501412014-05-25T11:02:00025 May 2014 11:02:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(a)(1)(i), Emergency Class Declaration, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unusual Event Due to Loss of Offsite Power ENS 495252013-11-09T20:13:0009 November 2013 20:13:00 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 Condenser Vacuum ENS 492602013-08-10T01:19:00010 August 2013 01:19:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip on Low Steam Generator Water Level ENS 520002013-06-13T00:13:00013 June 2013 00:13:00 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)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown and Reactor Trip ENS 490392013-05-16T06:56:00016 May 2013 06:56:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip During Control Rod Testing ENS 474612011-11-20T22:58:00020 November 2011 22:58:00 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 Condenser Vacuum During Startup ENS 469712011-06-20T15:52:00020 June 2011 15:52:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unit 2 Reactor Trip Following the Loss of the "B" Main Feedwater (Mfw) Pump ENS 464412010-11-28T20:15:00028 November 2010 20:15:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip After Turbine Trip Due to Loss of Condenser Vacuum ENS 459452010-05-22T20:45:00022 May 2010 20:45:00 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 Steam Generator Water Level Control ENS 459312010-05-17T14:17:00017 May 2010 14:17:00 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 457292010-02-26T16:25:00026 February 2010 16:25:00 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 Two Circulating Water Pumps ENS 455832009-12-20T03:53:00020 December 2009 03:53:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Caused by a Turbine/Generator Electrical Fault ENS 451832009-07-03T17:05:0003 July 2009 17:05:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Reactor Trip Resulting from Turbine Trip ENS 445642008-10-12T02:36:00012 October 2008 02:36:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Turbine Trip/ Automatic Reactor Trip on Low Steam Generator Level ENS 443262008-06-28T15:46:00028 June 2008 15:46:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip Due to Loss of Both Feedwater Pumps ENS 442382008-05-24T13:54:00024 May 2008 13:54:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(a)(1)(i), Emergency Class Declaration Loss of Offsite Power ENS 442342008-05-22T18:20:00022 May 2008 18:20:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Reactor Trip Due to Lightning Strike ENS 427252006-07-25T13:45:00025 July 2006 13:45:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Reactor Trip Breakers Opened During Maintenance on Steam Generator Wide Level Channels ENS 423672006-02-23T15:22:00023 February 2006 15:22:00 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 Main Feedwater ENS 421802005-12-01T19:45:0001 December 2005 19:45:00 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 Level ENS 420242005-09-29T17:10:00029 September 2005 17:10:00 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 Circulating Water Pumps ENS 416072005-04-17T12:42:00017 April 2005 12:42:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(a)(1)(i), Emergency Class Declaration, 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge Alert Declared Due to Unit 3 Main Steam Relief Valves Not Reseating After Actuation ENS 405912004-03-16T01:20:00016 March 2004 01:20:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip at Millstone 2 Due to Spurious Loss of One Main Feed Pump ENS 405702004-03-06T05:50:0006 March 2004 05:50:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip at Millstone 2 Due to Spurious Trip of the "B" Feed Pump ENS 403612003-11-29T03:05:00029 November 2003 03:05:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip from 11% Power Due to Turbine Vibration ENS 403582003-11-27T11:29:00027 November 2003 11:29:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Plant Had a Manual Reactor Trip from 23% Power Due to Turbine Vibration 2025-05-07T01:08:00 | |
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