Semantic search
| Start date | Reporting criterion | Title | Event description | System | LER | |
|---|---|---|---|---|---|---|
| ENS 56813 | 25 October 2023 01:59:00 | 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation 10 CFR 50.72(b)(3)(iv)(A), System Actuation | Automatic Reactor Trip | The following information was provided by the licensee via email: At 2159 on 10/24/2023, with Unit 3 in Mode 1 at 100 percent power, the reactor was automatically tripped due to an actuation signal into the Unit 3 reactor protection system protection rack during maintenance. The trip was uncomplicated with all systems responding normally post trip. Decay heat is being removed via auxiliary feed water system and the steam dump system. Unit 4 is not affected. This event is being reported pursuant to 10CFR50.72(b)(2)(iv)(B) and 10CFR50.72(b)(3)(iv)(A). The NRC Resident Inspector has been notified. The cause of the automatic reactor trip will be investigated by the licensee. | Reactor Protection System Auxiliary Feed Water | |
| ENS 56755 | 22 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 | The following information was provided by the licensee via email: At 1819 EDT on 9/22/2023, with Unit 3 in Mode 1 at 100 percent power, the reactor automatically tripped due to a main generator lockout. The probable cause of the main generator lockout was from a lightning strike. The trip was uncomplicated with all systems responding normally post-trip. Operations stabilized the plant in Mode 3. Decay heat is being removed by the steam dump system. Unit 4 is not affected. Auxiliary feed water was actuated as expected as a result of the reactor trip. This event is being reported pursuant to 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A). The NRC Resident Inspector has been notified. | Auxiliary Feed Water | |
| ENS 56658 | 4 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 | The following information was provided by the licensee via email: At 1320 (EDT) on 08/04/2023, with the Unit 3 in Mode 1 at 100 percent power, the reactor was manually tripped due to lowering level in the 3C steam generator. The trip was uncomplicated with all systems responding normally post-trip. Decay heat is being removed via the auxiliary feed water system and the atmospheric steam dumps. Unit 4 is not affected. This event is being reported pursuant to 10 CFR 50.72(b)(2)(iv)(B), and 10 CFR 50.72(b)(3)(iv)(A). The NRC Resident Inspector has been notified. The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance: The cause of lowering level in the 3C steam generator was unknown at the time of the notification and will be investigated by the licensee. | Steam Generator Auxiliary Feed Water | |
| ENS 55117 | 1 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 | On 3/1/21 at 1112 EST, with Unit 3 in Mode 1 at approximately 100 percent Rated Thermal Power (RTP), the reactor automatically tripped. Auxiliary Feedwater initiated as designed to provide Steam Generator (S/G) water level control. Emergency Operating Procedures (EOPs) have been exited and General Operating Procedures (GOPs) were entered. Unit 3 is stable in Mode 3 at normal operating temperature and pressure. This event is being reported pursuant to 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A). The NRC Resident Inspector has been notified. All rods are inserted, decay heat is being removed via S/G through normal secondary systems. The plant is in a normal electrical line-up. The cause of the automatic reactor trip is (unknown at this time and is) being investigated. There was no effect on Unit 4. | Steam Generator Feedwater Reactor Protection System | |
| ENS 54847 | 21 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 | On 08/20/20 at 2354 (EDT), with Unit 3 in Mode 1 at approximately 34% RTP (Rated Thermal Power), the reactor was manually tripped. This was due to Steam Generator Water Level control issues that resulted in the only Steam Generator (S/G) Feed Pump tripping on low suction pressure. Unit 3 reactor was tripped manually upon the loss of the last running feed pump. All other systems operated normally. Auxiliary Feedwater initiated as designed to provide S/G water level control. EOPs have been exited and General Operating Procedures (GOPs) were entered. Unit 3 is stable in Mode 3 at normal operating temperature and pressure. This event is being reported pursuant to 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A) The NRC Resident Inspector bas been notified. Decay heat removal is by the steam dumps to atmosphere. Unit 4 is not affected. The cause of the low suction feed pressure to the steam generator feed pump is under investigation. | Steam Generator Auxiliary Feedwater Decay Heat Removal | |
| ENS 54844 | 19 August 2020 17:25:00 | 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation | Automatic Reactor Trip During Startup | On 08/19/20 at 1325 EDT, during Unit 3 startup at approximately 0 percent rated thermal power, the reactor automatically tripped. The trip was automatically initiated from the Source Range Nuclear Power Instrumentation. All other systems operated normally. Operations stabilized the plant in Mode 3. Decay heat is being removed by Steam Dumps. Unit 4 is not affected. This event is being reported pursuant to 10 CFR 50.72(b)(2)(iv)(B). The NRC Resident Inspector has been notified. The cause of the Source Range Nuclear Power Instrumentation trip is under investigation. | ||
| ENS 54839 | 18 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 | On 08/17/20 at 2113 EDT, with Unit 3 in Mode 1 at approximately 92% (Rated Thermal Power) RTP, the reactor was manually tripped. This was due to a turbine runback caused by CV-3-2011, Low Pressure Feedwater Heater Bypass Control Valve, failing open, followed by rising Steam Generator (S/G) levels. Unit 3 reactor was tripped manually when the 3C S/G Level reached 78% narrow range. Unit 3 Main Steam Isolation Valves were closed manually in accordance with Emergency Operating Procedure (EOP) network due to 38 MSR Main Steam Stop valve position indication lost. All other systems operated normally. Auxiliary Feedwater initiated as designed to provide S/G water level control. EOPs have been exited and General Operating Procedures (GOPs) were entered. Unit 3 is stable in Mode 3 at normal operating temperature and pressure. This event is being reported pursuant to 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A). The NRC Resident Inspector has been notified. All rods are inserted, decay heat is being removed via S/G through normal secondary systems. The plant is in normal electrical line up. Lightning strike is believed to be the initial cause of the runback. | Steam Generator Feedwater Main Steam Isolation Valve Auxiliary Feedwater Main Steam | |
| ENS 54762 | 6 July 2020 01:09:00 | 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation | Reactor Trip Due to Turbine Trip | Reactor trip caused by turbine trip due to voltage regulator issues. Plant is stable. Exited the Emergency Operating Procedure Network. Auxiliary Feedwater automatically actuated and was subsequently restored to standby. The licensee notified the NRC Resident Inspector. | Auxiliary Feedwater | |
| ENS 54072 | 18 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 | This is a non-emergency notification to the NRC 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. Unit 3 manual reactor trip following grid disturbance. Following the grid disturbance, a manual reactor trip was initiated due to lowering steam generator water levels. All control rods fully inserted. AFW started as expected. All other systems responded as expected. Current reactor temperature is 547 degrees F. Current reactor pressure is 2235 psig. Decay heat is being removed through the Atmospheric Steam Dumps (no known primary to secondary Reactor Coolant System leakage exists). The unit is in a normal post-trip electrical lineup. There was no affect on Unit 4. The cause of the grid disturbance is under investigation. The licensee notified the NRC Resident Inspector. | Steam Generator Reactor Coolant System Reactor Protection System Auxiliary Feedwater Control Rod | |
| ENS 52960 | 10 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 | On 09/10/17 at 1855 (EDT), (Turkey Point) Unit 4 reactor was manually tripped from 88% RTP (Rated Thermal Power) due to a failure of 4C Steam Generator main feed regulating valve causing lowering S/G (Steam Generator) level. All other systems operated normally. Auxiliary Feed Water initiated as designed to provide S/G water level control. EOP's (Emergency Operating Procedures) have been exited and General Operating procedures (GOP'S) were entered. Unit 4 is stable in Mode 3 at NOT/NOP (Normal Operating Temperature/Normal Operating Pressure). The licensee is investigating the failure of the feed regulating valve. Offsite power is available. Decay heat is being removed via main feedwater with steam discharged to atmosphere using the ADVs (Atmospheric Dump Valves). There is no known primary-secondary steam generator tube leakage. The licensee informed the NRC Resident Inspector. | Steam Generator Feedwater Auxiliary Feedwater | 05000251/LER-2017-001 |
| ENS 52623 | 18 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 | 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). | Emergency Diesel Generator Auxiliary Feedwater | 05000250/LER-2017-001 |
| ENS 52136 | 30 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 | Power had been reduced for planned maintenance on the 3B feedwater heater. During isolation of the feedwater heaters, a repeated water hammer was experienced. A normal shutdown of Unit 3 was performed. Unit 4 was not affected by the water hammer. The decay heat is being removed via the condenser and all offsite and onsite electrical power is available. The investigation of the cause is underway. The licensee will notify the NRC Resident Inspector.
The licensee is retracting this report based on the following: At 0352 EDT on July 30, 2016, EN #52136 provided notification of a Reactor Protection System (RPS) actuation during a normal shutdown of Unit 3 in response to a secondary system equipment issue. Upon further investigation, the unit shutdown and manual RPS actuation were in accordance with general plant operating procedures. The manual RPS actuation was in accordance with the general operating procedure and not required to mitigate the consequences of the secondary system equipment issue. As such, the notification made by EN #52136 for a valid actuation of a specified system is hereby retracted. The NRC Resident lnspector will be notified. Notified R2DO (Rose). | Feedwater Reactor Protection System | |
| ENS 51065 | 12 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 | This is an non-emergency notification to the NRC (Headquarters) 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. On 5/12/15 at 0430 EDT, Unit 4 experienced an automatic reactor trip due to Generator Differential Trip. Investigation is underway to determine the cause. Auxiliary feedwater automatically initiated as expected. All systems operated correctly in response to the reactor trip. Unit 4 is currently in Mode 3 and stable. All control rods fully inserted. Normal offsite power is available with decay heat is being removed by the atmospheric steam dumps. There is no known primary to secondary reactor coolant system leakage. The licensee has notified the NRC Resident Inspector. | Reactor Coolant System Reactor Protection System Auxiliary Feedwater Control Rod | 05000251/LER-2015-002 |
| ENS 50354 | 11 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 | 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. | Reactor Coolant System Reactor Protection System Emergency Diesel Generator Auxiliary Feedwater Residual Heat Removal Auxiliary Feed Water | 05000250/LER-2014-005 |
| ENS 50140 | 25 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 | This is an non-emergency event notification to the NRC 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). On 05/25/2014 at 0536 EDT, as part of a planned maintenance outage to repair a leaking check valve inside the containment building, Unit 4 power level had been lowered to 19% reactor power for the planned opening of the reactor trip breakers. Unit 4 experienced a loss of condenser vacuum. An automatic turbine trip signal was generated which initiated a reactor trip signal. The reactor tripped as required on the automatic trip signal. Unit 4 is currently in Mode 3 and stable. The loss of vacuum is under investigation at this time. All other plant systems are working as designed. The reactor trip was uncomplicated with no other safety system actuations. Decay heat is being removed via steam dumps to atmosphere. There is no known primary to secondary leakage. The grid is stable and Unit 4 is in its normal shutdown electrical lineup. Unit 3 was not affected and continues to operate at 100% power. The licensee has notified the NRC Resident Inspector. | Reactor Protection System | 05000251/LER-2014-002 |
| ENS 49021 | 10 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 | This is a non-emergency event 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). On 5/10/13 (at 1108 EDT) Unit 3 was stabilizing at 25% (power) during a controlled shutdown from an initial power level of 38% (power). Prior to the planned insertion of the trip at 25% (power), a malfunction of the turbine valves (not yet understood) caused a loss of load and a manual reactor trip was performed at 1108 (EDT). Unit 3 is currently in Mode 3 (Hot Standby) and stable. Source Range Nuclear Instrument N-3-32 malfunctioned (loss of detector voltage). All other plant systems are working as designed. Unit 3 is stable in Mode 3 (Hot Standby) at normal operating temperature and pressure. All control rods fully inserted. All other Nuclear Instrumentation is operable. Decay heat removal is via main feedwater and atmospheric steam dumps however, the condenser steam dumps are available but not preferred for Tave control. There is no known primary to secondary leakage. Unit 3 is in a normal shutdown electrical lineup. The cause of the turbine valves malfunction is not known at this time. There is no impact on Unit 4. The licensee has notified the NRC Resident Inspector. | Feedwater Reactor Protection System Decay Heat Removal Control Rod | 05000250/LER-2013-007 |
| ENS 48948 | 19 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 | An Unusual Event was declared on Unit 4 at 1730 EDT due to a loss of offsite power for greater than 15 minutes. Emergency buses are being powered from the Emergency Diesel Generators. All rods inserted. The plant is stabilizing on natural circulation in Mode 3. Emergency buses failed to auto-transfer to the startup transformer. AFW initiated and is supplying water to the steam generators. There was no impact on Unit #3. The failure of the auto-transfer of the startup transformer is under investigation. Notified DHS, FEMA, NICC and NuclearSSA via email. The licensee notified State of Florida, Miami Dade county, the NRC Resident Inspector.
At 1854 EDT Turkey Point Unit 4 continues to be in an Unusual Event due to a loss of offsite power. The emergency buses were energized from the start up transformer at 1824 EDT. Two reactor coolant pumps have been started and are running. The plant is stabilizing in Mode 3. In addition, per 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A) notifications are being made for the Reactor Protection Actuation for loss of power and the Emergency Safety Function actuations of the Emergency Diesel Generators and Auxiliary Feedwater. The licensee notified State of Florida, Miami Dade county, the NRC Resident Inspector. Notified R2DO (Vias), NRR (Skeen), and IRD (Grant).
All emergency buses are powered from offsite power. Unit 4 is stable in Mode 3. The Unusual Event was terminated at 1915 EDT on 4/19/13. The licensee notified State of Florida, Miami Dade county, the NRC Resident Inspector. Notified R2DO (Vias), NRR (Skeen), and IRD (Grant). Notified DHS, FEMA, NICC and NuclearSSA via email
In addition to the 10 CFR 50.72 sections initially identified, this event is also reportable in accordance with 10 CFR 50.72(b)(3)(v)(D). Turkey Point was performing a 3rd Harmonic Relay Power Ascension Test after an Extended Power Upgrade outage. Unit 4 was approximately 173 MW electric with the auxiliary transformer supplying the site safety related 4.16KV busses. The test required maneuvering the Unit 4 main generator voltage downward to place the generator in the lead. As the Unit 4 main generator voltage was lowered, the Load Center degraded voltage relays initiated sequencer operation, 4.16KV bus stripping, starting the EDGs, and loading the 4.16KV buses onto EDGs. Offsite power was available at all times. The licensee will notify the NRC Resident Inspector. R2DO (Sykes) notified. | Steam Generator Emergency Diesel Generator Auxiliary Feedwater | 05000251/LER-2013-002 |
| ENS 48817 | 12 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 | Unit 3 experienced an automatic reactor trip from approximately 3% power. The turbine was off-line and undergoing testing following a control valve position indication repair. A turbine inlet pressure channel perturbation momentarily actuated the 'Reactor Trip by Turbine Trip' protection, causing the Unit 3 reactor to trip. Unit 3 is currently stable in Mode 3. No other complications were noted following the reactor trip. The cause of the turbine inlet pressure channel perturbation is currently under investigations. All control rods fully inserted. Normal feedwater is supplying the steam generators and decay heat removal is to atmosphere via the atmospheric steam dumps. There is no primary to secondary leakage. Unit 3 is in a normal shutdown offsite electrical power alignment. There is no impact on Unit 4. The NRC Resident Inspector has been notified. | Steam Generator Feedwater Decay Heat Removal Control Rod | 05000250/LER-2013-005 |
| ENS 48764 | 18 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 | This is an non-emergency event notification to the NRCOC 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 due to Auxiliary Feedwater (AFW) initiation (eight hour notification). On 2/18/2013 at 0055 Unit 3 commenced a unit shutdown due to high # 1 seal leak-off on the 3A Reactor Coolant Pump (RCP). At 0129 3A RCP #1 seal leak-off exceeded operating limits. Unit 3 reactor was manually tripped. Auxiliary feedwater actuated as designed based on steam generator levels as a result of the trip. Unit 3 is currently in Mode 3 and stable. No complications were noted as a result of the reactor trip. Steam generator levels are being returned to normal level following the reactor trip. All other plant systems functioned as designed during and after the reactor trip. 3A RCP high #1 seal leak-off is under investigation. All control rods fully inserted on the trip. Decay heat was removed by AFW to the steam generators out the atmospheric reliefs. There was no primary to secondary leakage. Electrical buses are being supplied via offsite power. The licensee notified the NRC Resident Inspector. | Steam Generator Reactor Protection System Auxiliary Feedwater Control Rod | 05000250/LER-2013-003 |
| ENS 48744 | 12 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 | This is a non-emergency event 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 due to Auxiliary Feedwater (AFW) initiation (eight hour notification). On 2/11/2013 at 2236 EST Unit 3 experienced a loss of condenser vacuum. An automatic Turbine Trip signal was generated which initiated a Reactor Trip signal. The reactor tripped as required on the automatic trip signal. Auxiliary feedwater water actuated automatically based on low steam generator levels following the trip. Unit 3 is currently in Mode 3 and stable. Steam generator levels have been returned to normal levels . The loss of vacuum is under investigation at this time. All other plant systems are working as designed. The reactor trip was uncomplicated. All control rods fully inserted. The plant is stable at normal temperature and pressure. AFW has been secured and main feedwater is being used for Steam Generator water level control. The main condenser is unavailable and decay heat removal is to atmosphere via the atmospheric steam dumps. There are no indications of primary to secondary leakage. Unit 3 is in a normal offsite power electrical alignment. There is no impact on Unit 4. The licensee has notified the NRC Resident Inspector. | Steam Generator Feedwater Reactor Protection System Auxiliary Feedwater Decay Heat Removal Main Condenser Control Rod | 05000250/LER-2013-002 |
| ENS 46660 | 6 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 | This is a 4-hr Non-Emergency notification to the NRCOC (Nuclear Regulatory Commission Operations Center) for an event that results in actuation of the Reactor Protection System (RPS) when the reactor is critical in accordance with 10CFR50.72(b)(2)(iv)(B). On 3/6/11 at approx 16:20 (EST), Steam Generator sodium concentrations started to rise and exceeded 3-ONOP-071.1 (Secondary Chemistry Deviation from limits) Action Level 3 criteria (250 ppb Sodium). The plant power was reduced to 25% per 3-ONOP-100, Fast Load Reduction, and a manual plant trip (was) initiated per procedure at 16:44 (EST). Unit (3) is stabilized in Mode 3, and (the licensee) is performing secondary clean-up. All rods fully inserted. All safety systems functioned as required. The reactor trip was uncomplicated. Unit 4 was unaffected by this event. The licensee has notified the NRC Resident Inspector. | Steam Generator Reactor Protection System | 05000250/LER-2011-001 |
| ENS 46471 | 10 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 | At 2200 (EST) 12/09/2010, Unit 4 had indication of a condenser tube leak. A power reduction was commenced in accordance with plant procedures to allow isolation of the leaking waterbox. Sodium levels in the Steam Generators increased and a unit shutdown was required. Power was reduced to 20% and a manual reactor trip was initiated at 2258 (EST) 12/09/10, in accordance with plant procedures. All systems operated as required and the unit is stable in mode 3. The reactor trip was not complicated. All control rods inserted fully and decay heat is being removed by the atmospheric steam dumps. There is no indications of primary to secondary leakage. Normal offsite power is available and Unit 3 is unaffected. 3 of 3 steam generators are affected by the increase in sodium levels. The licensee is in progress of conducting steam generator blowdowns. The licensee has notified the NRC Resident Inspector. | Steam Generator Control Rod | 05000251/LER-2010-008 |
| ENS 46419 | 15 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 | On 11/15/10 at 0603 (hrs. EST), the Unit 3 reactor was manually tripped after receiving a report that there was an overheating packing gland on the 3A2 Circulating Water Pump. The 3A1 Circulating Water Pump was already tagged out for maintenance. This required Unit 3 to be tripped due to only two Circulating Water Pumps in operation. The Unit 3 reactor was stabilized in Mode 3. Auxiliary Feedwater automatically actuated. A train of normal feedwater remains available to feed Steam Generators. During the Unit 3 reactor trip, the 3B Steam Dump to Atmosphere failed to close on operator demand per procedure. It was locally isolated with a manual isolation valve stopping the cooldown. The RCS was stabilized at 487.56?F and was borated as required by procedure. All boration systems operated as designed. The RCS returned to normal operating temperature and pressure. During the trip, all rods inserted into the core. Other than the steam dump to atmosphere valve lifting, no other relief valves lifted. There is no known primary to secondary leakage. The electrical grid is normal and the plant is in a normal shutdown electrical line-up. Decay heat is being removed via the 3A and 3C steam dumps to atmosphere since the Main Steam Isolation Valves were closed. The plant is heating up to normal operating temperature at which time auxiliary feedwater will be secured. The licensee has notified the NRC Resident Inspector. | Steam Generator Feedwater Main Steam Isolation Valve Auxiliary Feedwater | 05000250/LER-2010-006 |
| ENS 46274 | 23 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 | Unit 3 reactor and turbine tripped due to Inadvertent Energization Generator Trip. All systems functioned as normal with the exception of Control Rod G5 in Control Bank A which remains at 18 steps. Entered and exited E-0 Reactor Trip and entered ES-0.1 Reactor Trip Response. All 4kV buses have power from the Unit 3 Start Up Transformer. Heavy weather conditions existed at the time of the reactor trip and is suspected as the cause for the Inadvertent Energization Generator Trip. Aux feed initiated during the trip recovery due to low steam generator level. Decay heat is being removed using condenser steam dumps and atmospheric steam dumps. There is no primary to secondary leakage. The plant is in its normal shutdown electrical lineup. There was no affect on unit-4 which is shutdown. The licensee will notify the NRC Resident Inspector.
Control Rod G5 in Control Bank A has been verified to be fully inserted. The Rod Position Indicator for Rod G5 currently indicates zero steps after being adjusted. The licensee will notify the NRC Resident Inspector. Notified the R2DO (Hopper). | Steam Generator Control Rod | 05000250/LER-2010-003 |
| ENS 46265 | 22 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 | At 2017 (EDT) on 9/21/10, Turkey Point Unit 4 spuriously tripped. The cause of the reactor trip is currently under investigation. At the time of the trip, reactor power was 100%. Auxiliary feedwater (AFW) was automatically initiated when steam generator levels lowered below the actuation setpoint. Steam generator levels are now stable at their normal Mode 3 band and auxiliary feedwater is secured. Unit 4 has been stabilized in Mode 3 on normal off-site power. This event is reportable per 10 CFR 50.72(b)(2)(iv)(B) - actuation of the reactor protection system with the reactor critical and 10 CFR 50.72(b)(3)(iv)(A) - valid actuation of an ESF system (AFW). All control rods inserted into the core. Decay heat is being removed through the steam dumps to atmosphere. There was no activation of PORVs or SRVs. The reactor is at shutdown NOP and NOT. The reactor trip response was uncomplicated and there was no impact on Unit 3. The licensee notified the NRC Resident Inspector. | Steam Generator Reactor Protection System Auxiliary Feedwater Control Rod | 05000251/LER-2010-006 |
| ENS 46235 | 8 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 | At 1345 (EDT) on 9/8/10, Turkey Point Unit 4 automatically tripped during the repair of a failed Turbine Stop Valve Relay which inputs into the Reactor Protection System. During the replacement of this relay, the logic condition was met causing a Reactor Trip and Turbine Trip. At the time of the trip, reactor power was 100%. Auxiliary Feedwater was automatically initiated when Steam Generator levels lowered below the actuation setpoint. Steam Generator levels are now stable at their normal band and Auxiliary Feedwater is now secured. Additionally, the Source Range Detectors did not automatically energize and were manually energized and are operating correctly. Unit 4 has been stabilized in Mode 3 on normal off-site power. This event is reportable per 10CFR50.72(b)(2)(iv)(B) - actuation of the Reactor Protection System with the reactor critical and 10CFR50.72(b)(3)(iv)(A) - valid actuation of an ESF system (AFW). The trip was characterized as uncomplicated. All rods fully inserted. No relief valves lifted during the transient. Normal feedwater has been re-established to the steam generators and decay heat is being removed via the turbine bypass valves to the condenser. The unit is in a normal shutdown electrical lineup. There was no impact on Unit 3. The license has notified the NRC Resident Inspector. | Steam Generator Feedwater Reactor Protection System Auxiliary Feedwater | 05000251/LER-2010-004 |
| ENS 45619 | 11 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 | At 1055 on 1/11/2010, Turkey Point Unit 4 was manually tripped on high steam generator level. Steam generator level was high due to plant response to a turbine runback. The runback was manually initiated by stopping the 4A Steam Generator Feed Pump from the Control Room due to mechanical seal failure. At the time of the trip, reactor power was 30%. Auxiliary Feedwater was not required since Steam Generator levels were maintained above the low level actuation setpoint. Unit 4 has been stabilized in Mode 3 on normal off-site power. No significant equipment problems were encountered. This event is reportable per 10 CFR 50.72(b)(2)(iv)(B) - actuation of the Reactor Protection System with the reactor critical. All rods inserted during the trip. There were no relief or safety valves that lifted during the transient. Decay heat is being removed via steam dumps to atmosphere. There is no known primary to secondary leakage. Unit 4 is in a normal shutdown electrical lineup. Unit 3 was not affected by the transient. The licensee has notified the NRC Resident Inspector. | Steam Generator Reactor Protection System Auxiliary Feedwater | |
| ENS 44016 | 29 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 | With the Unit 4 reactor in Mode 1 at approximately 10% power and immediately following main turbine start-up and synchronizing the main generator to the grid, the reactor and turbine were manually tripped due to 4A steam generator water level rising uncontrollably. The reactor was manually tripped prior to reaching the reactor protection trip point for high steam generator water level. An investigation is in progress to determine the cause of the high water level in the 4A steam generator. All rods fully inserted upon the trip and all systems functioned as required. There were no complications and the 4A steam generator water level is currently within the normal water level band. The licensee will be notifying the Resident Inspector. | Steam Generator Main Turbine | 05000251/LER-2008-001 |
| ENS 44009 | 26 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 | At 1309 both U-3 and U-4 tripped from 100% power due to a momentary power fluctuation caused by grid instabilities. All systems responded normally with the exception of the 4C non-vital 4KV bus which deenergized. All vital 4KV busses on both units are supplied from offsite power and both units are stable with Auxiliary Feed Water supplying feed to all steam generators. Current information from system indicates the grid is stable. 4C non-vital 4KV bus restoration is complete. No relief valves or safeties lifted. Decay heat path is AFW to S/G's with normal heat sink to the condenser and canal. All safety related equipment is operable and in standby. No ECCS actuation. FPL has not given a cause of the grid disturbance. The licensee is investigating the cause of the non-vital bus deenergizing. The Florida State Warning Point has been notified. The licensee notified the NRC Resident Inspector.
The licensee provided the following update to report a valid specified System actuation per 10CFR50.72(b)(3)(iv)(A) that occurred at 1614 EST on 02/26/08. At 1614, an inadvertent initiation of the Auxiliary Feedwater (AFW) System occurred on Unit 4. During the Unit 4 reactor trip, the 4C 4KV bus de-energized due to grid transient. This caused the 4B Steam Generator Feed Pump (SGFP) breaker to trip with control switch in 'mid after start' position. Later, with the control switch for the 4B SGFP still in 'mid after start' position, operators performed a procedure to swap feed source for the steam generators from SGFP to Standby SGFP. As part of this procedure, the 4A SGFP was secured. When the control switch for the 4A SGFP was taken to stop, the logic for start of the Auxiliary Feedwater System was met due to loss of last running SGFP. The AFW system responded as expected for an auto initiation. Initiation of the AFW system was noted by the operators, and actions were taken to control feed flow rate and Reactor Coolant System temperature, pressure and inventory. The AFW system has been restored to standby status. The licensee has notified the NRC Resident Inspector. Notified the R2DO (Munday). | Steam Generator Reactor Coolant System Auxiliary Feedwater | |
| ENS 42056 | 15 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 | Auxiliary Feedwater actuation due to low steam generator level following a manual reactor trip. At 0702 on 10/15/05, a manual reactor trip was initiated due to decreasing level on the 3C steam generator. Auxiliary Feedwater system actuated as expected due to post-trip steam generator level decrease. 3C steam generator level was restored using Auxiliary and Main feed. The cause of the loss of steam generator level control is under investigation. The plant is stable in Mode 3 with the Auxiliary Feedwater system in standby. All control rods fully inserted. The decay heat removal path is normal feedwater through the steam generators and out the atmospheric relief valves. There are no primary to secondary steam generator tube leaks. Safety related electrical busses are powered via normal offsite power. Emergency diesel generators are available if needed. There was no impact on Unit 4. The licensee notified the NRC Resident Inspector. * * * UPDATE AT 1147 ON 10/19/05 FROM E. TREMBLAY TO P. SNYDER * * * Updated to include notification under 10 CFR 50.72 (b)(2) for manual reactor trip. The licensee notified the NRC Resident Inspector. R2DO (Ernstes) notified. | Steam Generator Feedwater Emergency Diesel Generator Auxiliary Feedwater Decay Heat Removal Control Rod | |
| ENS 41800 | 27 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 | UNUSUAL EVENT (EAL #16 - Fire) declared at 0327 on 6/27/05 due to uncontrolled fire in the Unit 4 Main Transformer lasting longer than 10 minutes. Unit 4 experienced an automatic reactor trip from 100% on a turbine trip due to a fire in the Main Transformer. The fire was extinguished after approximately 25 minutes. On-site fire brigade and Miami-Dade fire department responded. The cause of the fire is under investigation. The reactor is stable in Mode 3. No safety systems were affected. All rods fully inserted, no ECCS actuations, no relief valves lifted and no personnel injuries occurred. Offsite power is still available and no emergency diesels auto started, however, there was an auxiliary feedwater actuation. Hazardous Material response is being implemented due to discharge of transformer oil. There may be a possible press release on this event. The NRC Resident Inspector was notified along with State and local agencies.
The NOUE was terminated at 05:00 due to the fire being extinguished and the emergency no longer existing. The NRC Resident Inspector was notified. Notified RDO 3 (Evans), EDO (Case), IRO (Frant), FEMA (Bagwell), DHS (Reed)
Received a call from a member of the Turkey Point Communications Group. The licensee does not plan on issuing a press release at this time. Notified R2DO (Evans). | Auxiliary Feedwater Main Transformer | |
| ENS 41516 | 24 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. | Unit 4 reactor was manually tripped from 20 percent power per 4 - GOP - 103 "Power Operation to Hot Standby" (normal shutdown procedure), during a load reduction to take the unit off line. The reason for the load reduction was an oil leak of approximately 100 drops per minute on the "4B" steam generator feed pump. The reactor was tripped when directed by 4 - GOP - 103. All rods fully inserted, no relief valves lifted, and all other systems functioned normally. The licensee notified the NRC Resident Inspector.
The licensee provided the following information via facsimile (licensee text in quotes): Upon review, the manual reactor trip from 20 percent power is not reportable in accordance with 10 CFR 50.72(b)(2)(iv)(13) since it was part of the pre-planned sequence of reactor shutdown steps contained in procedure 4-GOP-103, "Power Operation to Hot Standby." In addition, the reactor shutdown was not required by Technical Specifications. The NRC Resident Inspector will be notified of this retraction. | Steam Generator | |
| ENS 41511 | 22 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 | The licensee provided the following information via fax (licensee text in quotes) The 4A SGFP (Steam Generator Feed Pump) tripped, initiating a Turbine Runback. Operators manually inserted a Reactor Trip at 15% Steam Generator level. The reactor tripped and all control rods inserted. Auxiliary Feedwater automatically initiated as expected. All systems operated as expected except the 4A SGFP discharge MOV which has no (position) indication (in the main control room and is being) investigated. Decay heat is being removed by atmospheric steam dumps. The licensee will notify the NRC Resident Inspector. | Steam Generator Auxiliary Feedwater Control Rod | |
| ENS 41298 | 29 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 | Unit 3 unplanned Manual Reactor trip from 70% due to Generator Exciter cooling water leak. Leak caused voltage regulator transfer to manual. Cooling water leak was isolated after the manual reactor trip. Water was noted in the 3B 4kv safety related bus room affecting 3B Residual Heat Removal Pump breaker. This component is considered inoperable pending corrective action. Plant is stable in mode 3. Auxiliary Feed Water actuated automatically, as expected, and operated normally following the reactor trip. All control rods fully inserted. The MSIV's were manually closed to prevent excessive RCS cooldown and decay heat is being removed via the atmospheric steam dumps. Unit 4 was unaffected. The licensee will notify the NRC Resident Inspector. | Auxiliary Feedwater Residual Heat Removal Control Rod | |
| ENS 41292 | 25 December 2004 12:36:00 | 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation | Unit4 Manually Tripped Due to Lowering Condenser Vacuum | Manual reactor trip at 21.5" Hg and lowering. AFW initiated and operated as designed. On 12/25/04 Unit 4 at Turkey Point experienced a declining vacuum in the main condenser. When the condenser vacuum reached 21.5 Hg, manual trip criteria was reached and the plant was manually shut down. Decay heat is being removed via the Atmospheric Steam Dumps. There is no known primary to secondary tube leakage. The AFW system started as expected. All rods inserted correctly and all systems functioned as designed. The licensee will notify the NRC Resident Inspector. | Main Condenser | 05000251/LER-2004-004 |
| ENS 41257 | 14 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 | U3 manually tripped (Shift Manager decision). Fire in U3 HP turbine near bearing housing (offsite assistance not required). All plant equipment functioned as designed. A fire broke out near the #2 bearing housing on Unit 3 HP turbine and lasted about 9 minutes in length. Exact character of fire was not available at time of reporting. No unusual vibration readings or visual indications were observed prior to fire. Onsite fire brigade personnel responded to the turbine area without assistance of offsite emergency personnel. Five minutes into the event Unit 3 reactor was manually tripped. Nine minutes into the event, shift supervisor declared the fire was out. Fire personnel indicated the fire was "easily" put out. Licensee is evaluating action to be taken. When Unit 3 reactor was manually tripped, all rods inserted fully. No primary or secondary power relief valves actuated. AFW activated as expected. Licensee chose to close the MSIV to slow down the cooldown rate. Presently, decay heat is being removed via the steam dump into the atmosphere. Fire did not affect operational ability of Unit 4 or cause instability on the electrical grid. The licensee has notified the NRC Resident Inspector. | 05000250/LER-2004-006 | |
| ENS 40752 | 14 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 | At 1728 EDTon 05/14/04, while performing maintenance on Turbine 1st stage steam pressure transmitter (PT-447), feedwater regulating valve (FRV) 4A was observed to close. At 1729, an automatic actuation of RPS occurred on Low Steam Generator level in the 4A Steam Generator. This was followed shortly by a manual reactor trip by the operator. All control rods fully inserted. All 3 turbine driven AFW pumps started as expected and are supply steam generators through both feedwater supply headers. The electric plant remains in a normal lineup. RCPs are in operation transferring decay heat to the steam generators. The MSIVs are open with the steam generators discharging steam to the main condenser using the condenser steam dump valves. All steam generator atmospheric dump valves opened on the reactor trip and closed. The plant is investigating the cause of the FRV closure and intends to stay in Mode 3 until the cause is determined and appropriate repairs are made. There was no impact on the other operating unit. The licensee will notify the NRC Resident Inspector. | Steam Generator Feedwater Main Condenser Control Rod |