ENS 54560
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ENS Event | |
|---|---|
03:50 Mar 4, 2020 | |
| Title | Reactor Trip Due to Low Steam Generator Level |
| Event Description | At 2050 MST on March 3, 2020, Unit 2 reactor automatically tripped on Low Steam Generator (SG) Number 1 level signal from the Reactor Protection System. The low SG level occurred as the result of a trip of both Main Feedwater Pumps, which tripped during restoration of power to the Main Feedwater Pump Lube oil control panel. Auxiliary Feedwater (AFAS-1 and AFAS-2) actuated due to low SG levels in both SG post reactor trip as designed. This event is being reported as a reactor protection system and a specified system actuation in accordance with the reporting criteria of 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A).
Following the reactor trip, all [control element assemblies] CEAs inserted fully into the core. All systems operated as expected. No emergency plan classification was required per the Emergency Plan. Safety related busses remained powered during the event from offsite power and the offsite power grid is stable. Unit 2 is stable and in Mode 3. Steam Generators are being fed via the class 1E powered motor driven auxiliary feedwater pump. The NRC Senior Resident Inspector has been informed. Units 1 and 3 were unaffected by the trip and remain at 100 percent power.
The event reported on March 4, 2020 (EN 54560) also included actuations of the Emergency Diesel Generators in response to the AFAS-1 and AFAS-2 actuations. The Class 4.16kV buses remained energized from off-site power. The NRC Senior Resident Inspector has been informed. Notified R4DO (Drake). |
| Where | |
|---|---|
Palo Verde  Arizona (NRC Region 4) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation | |
| Time - Person (Reporting Time:+-1.72 h-0.0717 days <br />-0.0102 weeks <br />-0.00236 months <br />) | |
| Opened: | Anton Pestka 02:07 Mar 4, 2020 |
| NRC Officer: | Jeffrey Whited |
| Last Updated: | May 4, 2020 |
| 54560 - NRC Website | |
WEEKMONTHYEARENS 565512023-06-02T11:05:0002 June 2023 11:05:00
[Table view]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 564592023-04-09T04:44:0009 April 2023 04:44:00 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 Reactor Coolant Pumps ENS 556262021-12-06T19:03:0006 December 2021 19:03:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Unit 3 Automatic Trip ENS 552652021-05-19T10:15:00019 May 2021 10:15:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Trip Due to High Pressurizer Pressure ENS 551142021-02-26T17:33:00026 February 2021 17:33:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Reactor Trip Due to Loss of Two Reactor Coolant Pumps ENS 545602020-03-04T03:50:0004 March 2020 03:50:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Reactor Trip Due to Low Steam Generator Level ENS 542242019-08-16T15:21:00016 August 2019 15:21:00 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 534772018-06-27T07:00:00027 June 2018 07:00:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip on Low Steam Generator Water Level ENS 534242018-05-23T18:28:00023 May 2018 18:28:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Trip on Low Departure from Nucleate Boiling Ratio ENS 532152018-02-16T04:53:00016 February 2018 04:53:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(xiii), Loss of Emergency Preparedness Automatic Reactor Trip Due to Low Departure from Nucleate Boiling Signal ENS 522262016-09-08T04:31:0008 September 2016 04:31:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip Due to Stuck Open Pressurizer Main Spray Valve ENS 496002013-12-03T00:58:0003 December 2013 00:58:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Trip Following the Loss of the 1A Reactor Coolant Pump ENS 478372012-04-15T19:20:00015 April 2012 19:20:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip Due to Control Rod Deviation During Startup ENS 474722011-11-23T02:25:00023 November 2011 02:25:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip Due to Control Element Deviation ENS 471332011-08-06T18:19:0006 August 2011 18:19:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Trip Due to Dropped Control Element Assembly ENS 465562011-01-20T01:41:00020 January 2011 01:41:00 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 Main Feedwater Pump Trip ENS 457482010-03-07T18:24:0007 March 2010 18:24:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(a)(1)(i), Emergency Class Declaration Notification of Unusual Event Due to Electrical Fault Causing Damage to Equipment ENS 455372009-12-03T11:30:0003 December 2009 11:30:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip After Loss of Instrument Air to Containment ENS 449702009-04-04T06:54:0004 April 2009 06:54:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Scram Due to High Vibrations in the Turbine ENS 445252008-09-28T04:51:00028 September 2008 04:51:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Unit 3 Reactor Manually Tripped Following Automatic Turbine Trip on High Vibration ENS 444962008-09-16T21:00:00016 September 2008 21:00:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip During Troubleshooting of Control Rod Drive Mechanism Motor Generators ENS 442462008-05-29T04:34:00029 May 2008 04:34:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip Due to Improper Movement of Cea'S ENS 436972007-10-06T17:59:0006 October 2007 17:59:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip Due to Condenser Tube Rupture ENS 429252006-10-21T22:48:00021 October 2006 22:48:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Trip Due to Control Element Assembly Position Transmitter Output Deviations ENS 429202006-10-19T18:47:00019 October 2006 18:47:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip Following the Trip of Secondary Condensate Pumps ENS 427302006-07-26T14:35:00026 July 2006 14:35:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Variable Overpower Reactor Trip Following Turbine Control Valve Maintenance ENS 426812006-07-02T02:28:0002 July 2006 02:28:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip Following Large Leak in Condensate System ENS 423872006-03-05T14:10:0005 March 2006 14:10:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Trip Due to Low Departure from Nucleate Boiling Ratio. ENS 419512005-08-27T01:24:00027 August 2005 01:24:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Rps Actuation - Reactor Scram on High Steam Generator Level ENS 408702004-07-14T08:35:00014 July 2004 08:35:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Trip Following a Main Generator Trip ENS 408162004-06-14T14:44:00014 June 2004 14:44:00 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 Unusual Event Due to Reactor Trip Due to Loss of Off Site Power ENS 408152004-06-14T14:44:00014 June 2004 14:44:00 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 Unusual Event Declared Due to Reactor Trip Due to Loss of Off Site Power ENS 408142004-06-14T14:44:00014 June 2004 14:44:00 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 - Reactor Trip Due to Loss of Off Site Power ENS 407952004-06-07T21:58:0007 June 2004 21:58:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Reactor Trip Due to Main Turbine Electro-Hydraulic Control System Failure ENS 407372004-05-09T03:39:0009 May 2004 03:39:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip During Physics Testing Due to Control Element Assembly Slipping 6 Inches. 2023-06-02T11:05:00 | |
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