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The query [[Category:ENS Notification]] [[Site::Turkey Point]] [[Scram::+]] was answered by the SMWSQLStore3 in 1.0145 seconds.


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 Entered dateSiteRegionScramReactor typeEvent description
ENS 5407218 May 2019 14:00:00Turkey PointNRC Region 2Manual ScramThis 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.
ENS 5296010 September 2017 22:20:00Turkey PointNRC Region 2Manual ScramWestinghouse PWR 3-LoopOn 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.
ENS 5213630 July 2016 03:52:00Turkey PointNRC Region 2Manual ScramWestinghouse PWR 3-Loop

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.

  • * * UPDATE AT 2141 EDT ON 07/30/16 FROM ERIC JUERGENS TO S. SANDIN * * *

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).

ENS 5106512 May 2015 05:48:00Turkey PointNRC Region 2Automatic ScramWestinghouse PWR 3-LoopThis 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.
ENS 5035411 August 2014 14:20:00Turkey PointNRC Region 2Manual ScramWestinghouse PWR 3-LoopThis 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.
ENS 5014025 May 2014 07:37:00Turkey PointNRC Region 2Automatic ScramWestinghouse PWR 3-LoopThis 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.
ENS 4902110 May 2013 12:42:00Turkey PointNRC Region 2Manual ScramWestinghouse PWR 3-LoopThis 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.
ENS 4881712 March 2013 17:31:00Turkey PointNRC Region 2Automatic ScramWestinghouse PWR 3-LoopUnit 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.
ENS 4876418 February 2013 03:19:00Turkey PointNRC Region 2Manual ScramWestinghouse PWR 3-LoopThis 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.
ENS 4874412 February 2013 00:45:00Turkey PointNRC Region 2Automatic ScramWestinghouse PWR 3-LoopThis 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.
ENS 466606 March 2011 19:38:00Turkey PointNRC Region 2Manual ScramWestinghouse PWR 3-Loop

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.

ENS 4647110 December 2010 01:25:00Turkey PointNRC Region 2Manual ScramWestinghouse PWR 3-LoopAt 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.
ENS 4641915 November 2010 07:06:00Turkey PointNRC Region 2Manual ScramWestinghouse PWR 3-LoopOn 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.
ENS 4624610 September 2010 19:46:00Turkey PointNRC Region 2Manual ScramWestinghouse PWR 3-LoopDuring a Unit 4 reactor startup on 9/9/2010 while the reactor was subcritical in Mode 3, the Control Bank C Group 1 Step Counter failed (due to a battery failure). The reactor trip breakers were opened in accordance with procedures as required by the Action of Technical Specification 3.1.3.3. All rods fully inserted. The unit remained in Mode 3. This was a manual actuation of the reactor protection system. This report is made in accordance with 10 CFR 50.72(b)(3)(iv)(A) - Valid actuation of the Reactor Protection System. This is a late report. Reportability was not recognized at the time of the event as a result of misleading guidance in 0-ADM-115 'Notification of Plant Events' (site specific) procedure. A condition report is being initiated (by the licensee) to evaluate procedure changes to avoid further occurrences. The licensee notified the NRC Resident Inspector.
ENS 462358 September 2010 15:52:00Turkey PointNRC Region 2Automatic ScramWestinghouse PWR 3-Loop

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.

ENS 4561911 January 2010 12:54:00Turkey PointNRC Region 2Manual ScramWestinghouse PWR 3-LoopAt 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.
ENS 4401629 February 2008 05:40:00Turkey PointNRC Region 2Manual ScramWestinghouse PWR 3-LoopWith 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.
ENS 4213711 November 2005 16:50:00Turkey PointNRC Region 2Manual ScramWestinghouse PWR 3-LoopDuring a reactor startup, while withdrawing the second shutdown bank, a failure of the 2BD rod control power cabinet occurred. Shutdown Bank B group 2 rods failed to withdraw. After gathering data and indications for troubleshooting, a manual reactor trip was initiated. All rods fully inserted. The Unit was and remains in mode 3. There were no other required or actual ESF actuations. The licensee will notify the NRC Resident Inspector.
ENS 4205615 October 2005 08:54:00Turkey PointNRC Region 2Manual ScramWestinghouse PWR 3-Loop

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.

ENS 4180027 June 2005 04:19:00Turkey PointNRC Region 2Automatic ScramWestinghouse PWR 3-Loop

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.

  • * * UPDATE ON 06/27/05 @ 05:13 BY SPEICHER TO GOULD * * *

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)

  • * * UPDATE 0915 EDT ON 6/27/05 BY S. SANDIN * * *

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).

ENS 4151623 March 2005 22:29:00Turkey PointNRC Region 2Manual ScramWestinghouse PWR 3-Loop

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.

  • * * UPDATE FROM V. BARRY TO M. RIPLEY 1125 EST 03/24/05 * * *

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.

ENS 4151122 March 2005 04:21:00Turkey PointNRC Region 2Manual ScramWestinghouse PWR 3-LoopThe 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.
ENS 4129828 December 2004 23:51:00Turkey PointNRC Region 2Manual ScramWestinghouse PWR 3-LoopUnit 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.
ENS 4129225 December 2004 08:50:00Turkey PointNRC Region 2Manual ScramWestinghouse PWR 3-LoopManual 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.
ENS 4125714 December 2004 12:45:00Turkey PointNRC Region 2Manual ScramWestinghouse PWR 3-LoopU3 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.
ENS 4123230 November 2004 10:22:00Turkey PointNRC Region 2Manual ScramWestinghouse PWR 3-Loop

During low power physics testing, Shutdown Bank B, rod E-11 dropped from 227 steps (ARO (all rods out) 230) to 135 steps. Technical Specification 3.0.3 was entered. Unit 3 Reactor was tripped at 0920 and stabilized in mode 3. The licensee will notify the NRC Resident Inspector. See also similar event EN # 41229 11/29/04.

  • * * UPDATE AT 1838 EST ON 1/11/05 FROM MICHAEL KOHL TO S. SANDIN * * *

The purpose of this update is to clarify that the reactor was not critical at the time of reactor trip. The dropped rod added sufficient negative reactivity to render the reactor subcritical prior to the manual reactor trip. The cause of the dropped rod was an intermittent contact in a pin connector associated with rod E-11. The licensee will inform the NRC Resident Inspector. Notified R2DO (Landis).

ENS 4122929 November 2004 01:36:00Turkey PointNRC Region 2Manual ScramWestinghouse PWR 3-Loop

Dropped rod E-11 in Shut Down Bank 'B' at 2334 on 11/28/04 while performing Low Power Physics Testing after refueling. Shutdown bank not fully withdrawn with dropped rod placed Unit 3 in Tech Spec Action Statement 3.0.3. RX trip breakers were opened at 0009 (11/29/04). Unit 3 entered 3-EOP-E.O, Reactor Trip or Safety Injection, the unit was placed in Mode 3 and transitioned to 3-EOP-ES-0.1, Reactor Trip Response and then into 3-GOP-301. All plant equipment responded as required and the unit remains stable in mode 3 while the Rod Control failure is investigated. The licensee notified the NRC resident inspector.

  • * * UPDATE AT 1838 EST ON 1/11/05 FROM MICHAEL KOHL TO S. SANDIN * * *

The purpose of this update is to clarify that the reactor was not critical at the time of reactor trip. The dropped rod added sufficient negative reactivity to render the reactor subcritical prior to the manual reactor trip. The cause of the dropped rod was an intermittent contact in a pin connector associated with rod E-11. The licensee will inform the NRC Resident Inspector. Notified R2DO (Landis).

ENS 4075214 May 2004 18:26:00Turkey PointNRC Region 2Manual ScramWestinghouse PWR 3-LoopAt 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.