ENS 52000
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ENS Event | |
|---|---|
00:13 Jun 13, 2013 | |
| Title | Technical Specification Required Shutdown and Reactor Trip |
| Event Description | At 2013 EDT on 6/12/16, Millstone Unit 3 commenced a Technical Specification (TS) required shutdown due to excessive Reactor Coolant System leakage from the "A" Reactor Coolant Pump (RCP) third stage seal. The leakage from the third stage seal was approximately two gpm which is greater than the Technical Specification (TS) limit of less than one gpm.
During the shutdown, oscillations developed in the Main Feedwater which required the operator to initiate a manual reactor trip. Unit 3 is currently stable in Mode 3. Decay heat is being released via the Steam Dumps to the Main Condenser. Normal offsite power is available and the unit is in a normal shutdown electrical line-up. The cause of the Main Feedwater oscillations is being investigated. The licensee notified the NRC Resident Inspector. The licensee notified State and local government agencies.
The following clarifies Feedwater isolation vs. Feedwater oscillation: At 2337 EDT on 6/12/16, a manual reactor trip was initiated on Unit 3 following feedwater isolation. As expected, Aux Feedwater system (AFW) initiated on the reactor trip. The trip was uncomplicated and the plant is currently in Mode 3 with a normal electric line-up and decay heat is being removed via steam dumps to the condenser. This is reportable under 10 CFR 50.72(b)(2)(iv)(B) - RPS Actuation - Critical and 10 CFR 50.72(b)(3)(iv)(A) - Valid Specific System Actuation." The Feedwater isolation occurred due to high Steam Generator water level. The licensee notified the NRC Resident Inspector. Notified R1DO (Arner). |
| Where | |
|---|---|
Millstone  Connecticut (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| Time - Person (Reporting Time:+-0.37 h-0.0154 days <br />-0.0022 weeks <br />-5.06826e-4 months <br />) | |
| Opened: | Walter Orf 23:51 Jun 12, 2013 |
| NRC Officer: | Daniel Mills |
| Last Updated: | Jun 13, 2016 |
| 52000 - 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, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown | |
WEEKMONTHYEARENS 565442023-05-30T08:46:00030 May 2023 08:46:00
[Table view]10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Trip ENS 546632020-04-13T19:50:00013 April 2020 19:50:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Trip Due to Low Condenser Vacuum ENS 546312020-04-01T20:25:0001 April 2020 20:25:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Trip Due to Circuit Fault ENS 544572019-12-27T12:04:00027 December 2019 12:04:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Trip Due to Feedwater Pump Trip ENS 544492019-12-18T00:29:00018 December 2019 00:29:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown ENS 521692016-08-11T13:59:00011 August 2016 13:59:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip Due to Loss of Two Circulating Water Pumps ENS 519292016-05-15T10:38:00015 May 2016 10:38:00 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 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 503132014-07-26T18:11:00026 July 2014 18:11:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown Due to Turbine Driven Afw Pump Failure 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 498602014-02-27T13:09:00027 February 2014 13:09:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Plant Shutdown Required by Technical Specification ENS 497792014-01-31T08:30:00031 January 2014 08:30:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown Due to Degradation of the Pressurizer Proportional Heaters Group 1 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 481812012-08-12T04:44:00012 August 2012 04:44:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown Due to Ultimate Heat Sink Exceeding Temperature Limit 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 472392011-09-03T19:30:0003 September 2011 19:30:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown Due to "a" Train Service Water Leak 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 424632006-04-01T03:20:0001 April 2006 03:20:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown Due to Inoperable Afw Turbine 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 2023-05-30T08:46:00 | |
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