ENS 50354
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ENS Event | |
|---|---|
14:20 Aug 11, 2014 | |
| Title | Manual Reactor Trip on Loss of Instrument Air Followed by Safety Injection |
| Event Description | This is an non-emergency notification to the NRCOC [Nuclear Regulatory Commission Operations Center] in accordance with 10 CFR 50.72(b)(2)(iv)(B) for a valid actuation of the reactor protection system (RPS) (four hour notification) and 10 CFR 50.72(b)(3)(iv)(A) for a valid Engineered Safeguards (ESF) actuation (eight hour notification) due to auxiliary feedwater (AFW) initiation , safety injection (SI) initiation, and emergency diesel generator (EDG) auto start.
On 8/11/14 at 1028 EDT, Unit 3 experienced a manual reactor trip due to a loss of instrument air. Auxiliary feed water automatically initiated as expected. Unit 3 is currently in Mode 3 and stable. Instrument air has been restored. At 1305 a safety injection signal [SI] occurred due to main steamline high differential pressure during a plant cooldown to 470 degrees Fahrenheit. High head safety injection (HHSI) pump, residual heat removal (RHR) pumps, and emergency diesel generators (EDGs) auto started as expected due to the safety injection signal. Based on plant conditions, the HHSI and RHR pumps did not inject into the reactor coolant system. The plant was stabilized after the reactor trip, however, the loss of instrument air resulted in a loss of letdown and PZR level continued to slowly increase to approximately 91%. All rods fully inserted and normal offsite power was maintained. Operators initiated a plant cooldown to stabilize and lower PZR level using the S/G atmospheric steam dumps. Unequal opening of the S/G atmospheric steam dumps caused the SI to occur due to main steamline high differential pressure. No RCS injection occurred and all SI equipment operated as expected and has been subsequently secured. Unit 3 is stable in mode 3 at 490 degrees Fahrenheit and RCS pressure is 1940 psig. There was no effect on Unit 4 which continues to operate at 100% power. The loss of instrument air is being investigated. The licensee has notified the NRC Resident Inspector. |
| Where | |
|---|---|
Turkey Point  Florida (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| LER: | 05000250/LER-2014-005 |
| Time - Person (Reporting Time:+0 h0 days <br />0 weeks <br />0 months <br />) | |
| Opened: | Michael Coen 14:20 Aug 11, 2014 |
| NRC Officer: | John Shoemaker |
| Last Updated: | Aug 11, 2014 |
| 50354 - 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)(iv)(A), System Actuation | |
WEEKMONTHYEARENS 568132023-10-25T01:59:00025 October 2023 01:59:00
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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 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 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 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 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 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 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 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 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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