ENS 42797
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ENS Event | |
|---|---|
14:35 Aug 23, 2006 | |
| Title | Manual Scram Due to Mismatch of Primary Power and Secondary Load Indications |
| Event Description | On August 23, 2006, at 1035 hours0.012 days <br />0.288 hours <br />0.00171 weeks <br />3.938175e-4 months <br />, the Reactor Protection System was manually actuated while at reduced load of approximately 68 percent reactor power upon indication of an apparent disparity in net electric load. It was determined that the cyclic operation of the condenser steam dumps varied steam to the turbine resulting in the indicated drop in electrical output power from about 500 Mwe to 150 Mwe. The manual trip is reportable under 10 CFR 50.72(b)(2)(iv). The event started when heater drain tank pumps 21 and 22 tripped, apparently due to a failure of the automatic heater drain level control valves that could not be manually corrected from the single controller. Reactor operators reduced load in accordance with station procedures to respond to the trip of the heater drain tank pumps and stabilized reactor power at 77%. As a result of the required load reduction delta flux was outside of the operational limit envelope specified at 77% reactor power. This required a further load reduction to less than 50 percent as per Technical Specification 3.2.3. At approximately 68% percent power the reactor was manually tripped due to the mismatch of primary power and secondary load indications. The Auxiliary Feedwater System actuated following the manual trip as expected. This is reportable under 10 CFR 50.72(b)(3)(iv)(A). A high-high water level signal was received on the 22 Steam Generator. This was due to a feedwater regulating valve that did not fully close. The feedwater isolation valves closed. All other safety systems actuated as required and safety equipment operated as expected. The Emergency Diesel Generators did not start as offsite power remained available and stable. No primary or secondary relief valves lifted. The plant is in Hot Standby at normal temperature and pressure with residual heat removal using auxiliary feedwater and normal heat removal through the condenser via steam dumps. There was no radiation released. A post trip investigation will be performed prior to restart.
The licensee notified the NRC Resident Inspector.
This is an update of non-emergency Event Notification 42797 that was previously made on August 23, 2006. Clarification is provided to include reporting of the Event Classification for actuation of a second system (automatic feedwater isolation) as an 8-Hr. Non-Emergency per 10 CFR 50.72(b)(3)(iv)(A). This update revises the wording as follows: The feedwater isolation valve was manually closed. After receipt of the high-high level trip signal, 21, 23, and 24 feedwater isolation valves automatically closed. This is also reportable under 10 CFR 50.72(b)(3)(iv)(A). The licensee notified the NRC Resident Inspector. Notified R1DO (Conte). |
| Where | |
|---|---|
Indian Point  New York (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:+-1.27 h-0.0529 days <br />-0.00756 weeks <br />-0.00174 months <br />) | |
| Opened: | Nick Lizzo 13:19 Aug 23, 2006 |
| NRC Officer: | John Knoke |
| Last Updated: | Aug 23, 2006 |
| 42797 - NRC Website
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Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | Yes, Manual Scram |
| Before | Power Operation (100 %) |
| After | Hot Standby (0 %) |
Indian Point with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
WEEKMONTHYEARENS 539542019-03-24T18:45:00024 March 2019 18:45:00
[Table view]10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Automatic Trip on Turbine Trip ENS 539372019-03-15T17:00:00015 March 2019 17:00:00 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 Turbine Generator Trip ENS 536112018-09-18T04:00:00018 September 2018 04:00:00 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 a Steam Leak on a High Pressure Feedwater Heater ENS 533482018-04-20T01:07:00020 April 2018 01:07:00 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 Turbine Issue ENS 532162018-02-16T07:01:00016 February 2018 07:01:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Trip Due to Loss of Excitation on Main Generator ENS 530522017-11-04T00:22:0004 November 2017 00:22:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Indian Point Unit 3 Reactor Trip on Low Steam Generator Level ENS 528292017-06-26T04:00:00026 June 2017 04:00:00 10 CFR 50.72(b)(2)(xi), Notification to Government Agency or News Release, 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 Feedpump ENS 520672016-07-06T13:38:0006 July 2016 13:38:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip While Performing Testing ENS 517752016-03-07T15:18:0007 March 2016 15:18:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Emergency Diesel Generators Auto-Started on Valid Actuation Signal ENS 516062015-12-15T00:06:00015 December 2015 00:06:00 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 Main Generator Lockout ENS 515862015-12-05T22:31:0005 December 2015 22:31:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Initiated Due to Multiple Dropped Control Rods ENS 512112015-07-08T18:25:0008 July 2015 18:25:00 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 Lowering Steam Generator Water Levels ENS 511562015-06-15T23:20:00015 June 2015 23:20:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Trip Due to Turbine Trip ENS 510602015-05-09T21:50:0009 May 2015 21:50:00 10 CFR 50.72(b)(2)(xi), Notification to Government Agency or News Release, 10 CFR 50.72(a)(1)(i), Emergency Class Declaration, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unusual Event Declared Due to Main Transformer Fire ENS 503612014-08-13T15:57:00013 August 2014 15:57:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip ENS 498022014-02-06T20:53:0006 February 2014 20:53:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unanticipated Auxiliary Feedwater Pump Start After Securing Emergency Diesel Generator ENS 496982014-01-07T02:15:0007 January 2014 02:15:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip on Low Steam Generator Water Level Due to a Failed Main Feedwater Reg Valve ENS 491712013-07-03T11:41:0003 July 2013 11:41:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Trip Following Loss of Instrument Air to Main Feedwater Regulating Valves ENS 488542013-03-27T10:01:00027 March 2013 10:01:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge Safety Injection Actuation During Testing ENS 487502013-02-13T18:55:00013 February 2013 18:55:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip on Low Steam Generator Water Level ENS 484542012-10-30T02:41:00030 October 2012 02:41:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Rps Actuation on Generator Trip ENS 479992012-06-06T10:12:0006 June 2012 10:12:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unit 2 Experienced an Automatic Reactor Trip on Turbine Main Generator Trip ENS 475822012-01-10T09:36:00010 January 2012 09:36:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Excessive Leakage from Rcp Seal Return ENS 471772011-08-19T22:05:00019 August 2011 22:05:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Partial Loss of Offsite Power Resulting in Edg Autostart ENS 466492011-03-01T16:00:0001 March 2011 16:00:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Emergency Diesel Generators Start on a Loss of Power from 138 Kv Circuit ENS 464002010-11-07T23:39:0007 November 2010 23:39:00 10 CFR 50.72(b)(2)(xi), Notification to Government Agency or News Release, 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 Alert Declared Due to Explosion in the 21 Main Transformer ENS 462412010-09-10T01:29:00010 September 2010 01:29:00 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 Service Water Leak in the Main Generator Exciter Housing ENS 462292010-09-03T14:58:0003 September 2010 14:58:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unit 2 Experienced an Automatic Reactor Trip Due to High Steam Generator Level ENS 456242010-01-11T20:59:00011 January 2010 20:59:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Trip Due to Main Generator Electrical Trip ENS 454742009-11-03T02:41:0003 November 2009 02:41:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Trip Due to Turbine Trip Caused by a Generator Lock-Out Relay Actuation ENS 453062009-08-27T23:45:00027 August 2009 23:45:00 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 Turbine Trip ENS 452552009-08-11T00:32:00011 August 2009 00:32:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Indian Point Unit 3 Automatically Tripped During Thunderstorm ENS 450982009-05-28T10:25:00028 May 2009 10:25:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Resulting from a High Steam Generator Level Turbine Trip ENS 450692009-05-15T05:53:00015 May 2009 05:53:00 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 Failure of the Main Feedwater Regulating Valve ENS 449672009-04-03T15:36:0003 April 2009 15:36:00 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 21 Mbfp ENS 447492009-01-02T15:09:0002 January 2009 15:09:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unexpected Autostart of Emergency Diesel Generator During Surveillance Testing ENS 445542008-10-09T16:54:0009 October 2008 16:54:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Emergency Diesel Generator and Auxillary Feedwater Actuation Due to Bus Undervoltage ENS 443832008-08-04T16:00:0004 August 2008 16:00:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Specified System Actuation - Both Auxiliary Boiler Feedwater Pumps Started Unexpectedly ENS 441532008-04-21T15:25:00021 April 2008 15:25:00 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 Lowering Steam Generator Water Level ENS 440912008-03-25T15:18:00025 March 2008 15:18:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Inadvertent Actuation of Emergency Diesel Generator During Surveillance Testing ENS 440892008-03-24T02:16:00024 March 2008 02:16:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip - Loss of Speed on Mbfp ENS 432852007-04-06T15:11:0006 April 2007 15:11:00 10 CFR 50.72(b)(2)(xi), Notification to Government Agency or News Release, 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(a)(1)(i), Emergency Class Declaration Main Generator Transformer Explosion - No Impact on Plant Safety Related Systems ENS 432722007-04-03T08:16:0003 April 2007 08:16:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip While Performing Boiler Feed Pump Maintenance ENS 431992007-02-28T11:35:00028 February 2007 11:35:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Following Malfunction of Pressure Transmitter ENS 430162006-11-30T19:45:00030 November 2006 19:45:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Auxiliary Feedwater Pump Automatic Start ENS 429932006-11-15T19:00:00015 November 2006 19:00:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip During Electrical Main Generator Troubleshooting ENS 428002006-08-24T15:35:00024 August 2006 15:35:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Main Feedwater Pump Trip During Startup ENS 427972006-08-23T14:35:00023 August 2006 14:35:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Scram Due to Mismatch of Primary Power and Secondary Load Indications ENS 427202006-07-21T14:30:00021 July 2006 14:30:00 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 Sparks from Under Main Generator ENS 426872006-07-06T07:52:0006 July 2006 07:52:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Trip Due to Generator Differential ENS 423782006-03-01T19:35:0001 March 2006 19:35:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip as a Result of Dropped Control Rods ENS 422202005-12-22T10:50:00022 December 2005 10:50:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Valid Actuation Signal Due to High Steam Generator Water Level ENS 422172005-12-22T07:08:00022 December 2005 07:08:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Afw Start During Main Feedwater Pump Trip ENS 417622005-06-10T13:24:00010 June 2005 13:24:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip Due to Service Water Leak in Exciter Cabinet ENS 417012005-05-16T14:39:00016 May 2005 14:39:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Afw Actuation During Surveillance Testing ENS 416732005-05-06T14:32:0006 May 2005 14:32:00 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 Steam Flow/ Feed Flow Mismatch Signal ENS 412272004-11-26T18:22:00026 November 2004 18:22:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Rps Actuation Due to Turbine Trip Caused by Loss of Stator Cooling Water ENS 411872004-11-10T04:39:00010 November 2004 04:39:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Actuation of the Emergency Ac Electric Power System ENS 410662004-09-24T15:55:00024 September 2004 15:55:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip with No Complications Due to Lowering Steam Generator Water Level ENS 410032004-09-01T04:05:0001 September 2004 04:05:00 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 Oscillating Steam Generator Water Level ENS 400672003-08-14T20:25:00014 August 2003 20:25:00 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 Declared Due to Loss of Offsite Power Greater than 15 Minutes. ENS 400692003-08-14T20:23:00014 August 2003 20:23:00 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)(i), Tech Spec Required Shutdown Unusual Event Declared Due to Loss of Offsite Power Greater than 15 Minutes. 2019-03-24T18:45:00 | |
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