ENS 52623
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ENS Event | |
|---|---|
15:07 Mar 18, 2017 | |
| Title | Reactor Trip and Loss of Ability for Unit 4 to Supply Power to Unit 3 |
| Event Description | On 3/18/17 at 1107 [EDT], the Unit 3 reactor tripped as a result of the loss of the 3A 4kV bus. All three reactor coolant pumps (RCP) tripped and the 3B RCP was restarted for forced recirculation. The reactor is stable in Mode 3. The 3A 4kV bus remains deenergized until troubleshooting and repairs are complete. In addition, Technical Specification 3.8.1.1, Action C requires a four hour report for the concurrent inoperability of the Unit 4 startup transformer to Unit 3 via the 3A 4kV bus and the Unit 3 3A diesel generator.
The NRC Senior Resident Inspector will be notified.
Update to previous report (EN 52623) to include additional reporting criteria. On 3/18/17 at 1107 [EDT] the Unit 3 reactor tripped as a result of the loss of the 3A 4kV bus. The 3A Emergency Diesel Generator (EDG) started on the loss of power signal but did not load, as designed, due to the bus fault. The 3A EDG was manually stopped at 1332. The Auxiliary Feedwater (AFW) System also initiated as expected. AFW was stopped at 1135. The actuations of the 3A EDG and AFW are reportable in accordance with 10 CFR 50.72(b)(3)(iv)(A). A loss of safety function affecting Units 3 and 4 occurred due to the loss of the 3A high head safety injection (HHSI) pump because it could not be powered from the faulted 3A 4kV bus with both Unit 4 HHSI pumps earlier (0624) removed from service due to planned maintenance. This caused three of the four HHSI pumps to be inoperable. The four HHSI pumps are shared by both Units 3 and 4. The safety function is achieved by two of the four HHSI pumps. Both Unit 4 HHSI pumps were restored to operable status at 1336. The loss of safety function is reportable in accordance with 10 CFR 50.72(b)(3)(v)(D). The Unit 3 reactor is stable in Mode 3. The 3A 4kV bus remains deenergized until troubleshooting and repairs are complete. Unit 4 remains operating at 100% power. The licensee will notify the NRC Resident Inspector. Notified R2DO (Ehrhardt) and NRR EO (Miller). |
| Where | |
|---|---|
Turkey Point  Florida (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown 10 CFR 50.72(b)(3)(iv)(A), System Actuation 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | |
| LER: | 05000250/LER-2017-001 |
| Time - Person (Reporting Time:+0 h0 days <br />0 weeks <br />0 months <br />) | |
| Opened: | Paul Czaya 15:07 Mar 18, 2017 |
| NRC Officer: | Mark Abramovitz |
| Last Updated: | Mar 18, 2017 |
| 52623 - NRC Website | |
Unit 3 | |
|---|---|
| Reactor critical | Critical |
| Scram | A/R |
| Before | Power Operation (100 %) |
| After | Hot Standby (0 %) |
Turkey Point with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown | |
WEEKMONTHYEARENS 568132023-10-25T01:59:00025 October 2023 01:59:00
[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 567552023-09-22T22:19:00022 September 2023 22:19:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip ENS 566582023-08-04T17:20:0004 August 2023 17:20:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip ENS 557852022-03-12T05:50:00012 March 2022 05:50:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Main Steam Isolation Valve Failed to Shut ENS 555132021-10-09T07:00:0009 October 2021 07:00:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Auxiliary Feedwater System AUTO-STARTED on Feedwater Isolation Signal ENS 551172021-03-01T16:12:0001 March 2021 16:12:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Trip Due to Reactor Protection System Actuation ENS 548472020-08-21T03:54:00021 August 2020 03:54:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip Due to Steam Generator Water Level Control ENS 548442020-08-19T17:25:00019 August 2020 17:25:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Trip During Startup ENS 548392020-08-18T01:13:00018 August 2020 01:13:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip Due to Rising Steam Generator Level ENS 547622020-07-06T01:09:0006 July 2020 01:09:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Reactor Trip Due to Turbine Trip ENS 540722019-05-18T15:08:00018 May 2019 15:08:00 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 Grid Disturbance ENS 529602017-09-10T22:55:00010 September 2017 22:55:00 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 Lowering Steam Generator Water Level ENS 526232017-03-18T15:07:00018 March 2017 15:07:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Reactor Trip and Loss of Ability for Unit 4 to Supply Power to Unit 3 ENS 521362016-07-30T07:33:00030 July 2016 07:33:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Turkey Point Unit 3 Shutdown Due to Water Hammer ENS 510652015-05-12T08:30:00012 May 2015 08:30:00 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 Generator Differential Trip ENS 507142015-01-02T14:25:0002 January 2015 14:25:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident High Head Safety Injection Inoperable Due to Voids Identified in Piping ENS 506452014-11-30T18:54:00030 November 2014 18:54:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Auxiliary Feedwater Actuation Due to Planned Reactor Trip ENS 504402014-09-09T23:36:0009 September 2014 23:36:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Failure of the Auto-Start Feature on Two Containment Coolers ENS 503542014-08-11T14:20:00011 August 2014 14:20:00 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 Loss of Instrument Air Followed by Safety Injection ENS 501402014-05-25T09:36:00025 May 2014 09:36:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Trip Due to Turbine Trip on Loss of Condenser Vacuum ENS 500542014-04-23T17:02:00023 April 2014 17:02:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Specified System Actuation During Rod Testing ENS 490212013-05-10T15:08:00010 May 2013 15:08:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Unit 3 Manual Reactor Trip Due to Malfunction of Turbine Valves ENS 489482013-04-19T21:20:00019 April 2013 21:20:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 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 Greater than 15 Minutes ENS 488212013-03-13T15:20:00013 March 2013 15:20:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Afw Actuation Due to Trip of 3B Feedwater Pump ENS 488172013-03-12T18:31:00012 March 2013 18:31:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Trip Due to Turbine Inlet Pressure Perturbation ENS 487642013-02-18T06:31:00018 February 2013 06:31:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip Due to High Seal Leakoff on Reactor Coolant Pump 3A ENS 487442013-02-12T03:36:00012 February 2013 03:36:00 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 on Loss of Condenser Vacuum ENS 471472011-08-11T20:31:00011 August 2011 20:31:00 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Loss of Intake Cooling Water for 20 Minutes ENS 466602011-03-06T21:44:0006 March 2011 21:44:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip Due to Secondary Sodium Concentrations Exceeding Chemistry Limits ENS 464712010-12-10T03:58:00010 December 2010 03:58:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip After Indications of a Condenser Tube Leak ENS 464192010-11-15T11:03:00015 November 2010 11:03:00 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 a Circulating Water Pump with Another Pump Out of Service for Maintenance ENS 463032010-10-01T13:51:0001 October 2010 13:51:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident High Head Safety Injection Reduced Capability ENS 462742010-09-23T21:14:00023 September 2010 21:14:00 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 Inadvertent Energization Generator Trip ENS 462652010-09-22T00:17:00022 September 2010 00:17:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip ENS 462462010-09-09T19:34:0009 September 2010 19:34:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip During Startup Due to a Control Bank Step Counter Failure ENS 462352010-09-08T17:45:0008 September 2010 17:45:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip During Maintenance on a Reactor Protection System Relay ENS 457912010-03-25T19:40:00025 March 2010 19:40:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident High Head Safety Injection Inoperable Due to Voids Identified in Piping ENS 456192010-01-11T15:55:00011 January 2010 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 Initiated Due to High Steam Generator Level ENS 455222009-11-27T04:40:00027 November 2009 04:40:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Two Shutdown Bank Rods Were Dropped from Fully Withdrawn Position ENS 450432009-05-05T07:30:0005 May 2009 07:30:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown 3C Main Steam Isolation Valve Problems ENS 444182008-08-15T20:04:00015 August 2008 20:04:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Shut Down Required by Technical Specifications ENS 441882008-05-05T16:37:0005 May 2008 16:37:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident High Head Safety Injection Manual Valve to Cold Leg Found Mispositioned During Heatup ENS 440162008-02-29T09:51:00029 February 2008 09:51:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip Due to High Steam Generator Water Level ENS 440092008-02-26T18:09:00026 February 2008 18:09:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Units 3 and 4 Tripped Due to Grid Fluctuations ENS 439192008-01-18T22:44:00018 January 2008 22:44:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown Due to Two Inoperable Rod Position Indicators in the Same Rod Group ENS 438962008-01-12T10:41:00012 January 2008 10:41:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown Due to Two Rod Position Indicators (Rpis) Out in One Rod Bank ENS 438882008-01-10T10:02:00010 January 2008 10:02:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown Due to Two Rod Position Indicators (Rpis) Out in One Rod Bank ENS 434082007-06-06T11:45:0006 June 2007 11:45:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown Initiated on Unit 3 ENS 423992006-03-08T20:53:0008 March 2006 20:53:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Valid Actuation of Emergency Diesel Generators ENS 421372005-11-11T20:02:00011 November 2005 20:02:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip During Startup Following Failure of Rod Control Power Cabinet ENS 421042005-11-01T03:27:0001 November 2005 03:27:00 10 CFR 50.72(a)(1)(i), Emergency Class Declaration, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unusual Event Declaration: Loss of Offsite Power Due to Loss of Startup Transformer ENS 420562005-10-15T11:02:00015 October 2005 11:02:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Auxiliary Feedwater Actuation on a Manual Reactor Trip ENS 418002005-06-27T07:16:00027 June 2005 07:16:00 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 Declaration of an Unusual Event Due Transformer Fire >10 Minutes ENS 415162005-03-24T00:56:00024 March 2005 00:56:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Reactor Manually Tripped from 20% Power During Load Reduction. ENS 415112005-03-22T08:47:00022 March 2005 08:47:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Manually Tripped Following Loss of Main Feed Pump ENS 412982004-12-29T03:46:00029 December 2004 03:46:00 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 Generator Exciter Cooling Water Leak ENS 412922004-12-25T12:36:00025 December 2004 12:36:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Unit4 Manually Tripped Due to Lowering Condenser Vacuum ENS 412572004-12-14T16:45:00014 December 2004 16:45:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Reactor Manually Tripped Due to Fire on Unit 3 Hp Turbine ENS 412322004-11-30T13:50:00030 November 2004 13:50:00 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 Due to Dropped Control Rod ENS 412292004-11-29T05:09:00029 November 2004 05:09:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specifications Required Shutdown Due to Dropped Control Rod ENS 411022004-10-07T18:00:0007 October 2004 18:00:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition, 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Single Point Vulnerability in Emergency Containment Filter Dousing System ENS 407522004-05-14T21:29:00014 May 2004 21:29:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Scram Due to Lowering Steam Generator Level 2023-09-22T22:19:00 | |
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