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 Entered dateSiteRegionReactor typeEvent description
ENS 558318 April 2022 01:10:00Turkey PointNRC Region 2Westinghouse PWR 3-Loop

The following information was provided by the licensee via fax or email: At 1900 EDT on 04/07/22, while Unit 4 was in Mode 4 following a refueling outage, it was discovered that both trains of residual heat removal (RHR) were simultaneously inoperable due to gas voiding. At 2032 EDT corrective actions were completed and both trains of RHR were declared operable. This condition is being reported pursuant to 10 CFR 50.72(b)(3)(v)(B). The NRC Resident Inspector has been notified.

  • * * RETRACTION ON 04/11/22 AT 1022 EST FROM DAVID STOIA TO BRIAN SMITH * * *

The following information was provided by the licensee via email: On 4/8/2022 at 0110 EDT Turkey Point Unit 4 notified the (NRC Operations Center (NRCOC)) pursuant to 10 CFR 50.72(b)(3)(v)(B) that both trains of Residual Heat Removal (RHR) were simultaneously inoperable due to the presence of gas voids that were identified during scheduled system gas accumulation testing. Subsequent evaluation by (Florida Power & Light (FPL)) Engineering has concluded that both trains of RHR remained operable and capable of performing their specified safety function. This NRCOC notification is a retraction of EN# 55831. The licensee notified the NRC Resident Inspector. Notified R2DO (Miller)

ENS 5580428 March 2022 14:55:00SeabrookNRC Region 1Westinghouse PWR 4-LoopA non-licensed employee possessed a prohibited substance (alcohol) within the Protected Area. The employee's access to the plant has been placed on hold pending results of an investigation. The NRC Resident Inspector has been notified.
ENS 5578512 March 2022 06:56:00Turkey PointNRC Region 2Westinghouse PWR 3-Loop

The following information was provided by the licensee via email: At 0050 EST on 3/12/22, while shutting down for entry into a scheduled refueling outage, the station discovered that a single Main Steam Isolation Valve (4A MSIV) did not fully close on demand. All other equipment operated as expected. This condition is being reported pursuant to 10 CFR 50.72(b)(3)(v). The NRC Resident Inspector has been notified.

  • * * RETRACTION ON 04/26/22 AT 1422 EDT FROM DAVID STOIA TO BRIAN PARKS * * *

The following information was provided by the licensee via email: On 3/12/2022 at 0656 EDT Turkey Point Unit 4 notified the NRC pursuant to 10 CFR 50.72(b)(3)(v)(D) that a single Main Steam Isolation Valve (MSIV) did not fully close when manually demanded from the control room during shutdown of Unit 4 for a refueling outage. Following disassembly and inspection of the MSIV, Florida Power & Light Engineering identified the cause of the deficiency and determined that the valve would have fully seated under its design accident conditions. This notification is a retraction of EN# 55785. The NRC Resident Inspector has been notified of this retraction. Notified R2DO (Miller).

ENS 557685 March 2022 15:12:00Turkey PointNRC Region 2Westinghouse PWR 3-LoopThe following information was provided by the licensee via telephone and email: A licensed employee had a confirmed positive for alcohol during a random fitness for duty test. The employee's access to the plant has been terminated. The NRC Resident Inspector has been notified.
ENS 5575725 February 2022 14:53:00Turkey PointNRC Region 2Westinghouse PWR 3-LoopThe following information was provided by the licensee via telephone: A non-licensee contractor supervisor had a confirmed positive for a controlled substance during a fitness for duty test. The employee's access to the plant has been terminated. The NRC Resident Inspector has been notified.
ENS 556936 January 2022 20:51:00Saint LucieNRC Region 2CEOn January 6, 2022 at 1937 (EST), St Lucie Unit 2 commenced a reactor shutdown as required by Technical Specification 3.1.3.1 Action 'e', due to Control Element Assembly number 27 slipping from 133 inches to 120 inches withdrawn and unable to be recovered within the prescribed time limits. The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance: Unit 2 entered 6 hour LCO to shutdown to mode 3 at 1539 EST as required by Technical Specification 3.1.3.1 Action 'e'. There was no impact on Unit 1.
ENS 5564110 December 2021 13:35:00Saint LucieNRC Region 2CEOn 12/10/2021, at 1024 EST, with Unit 1 at 100 percent power, the reactor was manually tripped due to lowering level in the steam generators. All systems responded as expected following the trip. The reactor is currently stable in Mode 3 and operators restored steam generator level utilizing main feedwater. The cause of the reduction in feedwater flow is under investigation. St. Lucie Unit 2 was not affected and remains at 100 percent power. This event is being reported pursuant to 10 CFR 50.72(b)(2)(iv)(B) for the reactor trip. The NRC Resident Inspector has been notified. All rods inserted into the core during the trip. The plant is in its normal shutdown electrical lineup. Decay heat is being maintained by steam discharge to the main condenser using the turbine bypass valves.
ENS 5557412 November 2021 20:47:00Turkey PointNRC Region 2Westinghouse PWR 3-Loop

At 1605 EST on 11/12/21, it was determined that the RCS Pressure Boundary does not meet ASME Section XI, Table IWB-341 0-1, 'Acceptable Standards' due to a through wall leak of the Core Exit Thermocouple Nozzle Assembly. Measures have been taken to establish Mode 5 for corrective actions. This event is being reported pursuant to 10 CFR 50.72(b)(3)(ii)(A). The NRC Resident Inspector has been notified.

  • * * RETRACTION ON 3/28/2022 AT 0849 EDT FROM DAVID STOIA TO MIKE STAFFORD * * *

The following information was provided by the licensee via email: On 11/12/2021 EN 55574 reported possible evidence of pressure boundary through-wall leakage observed on a Core Exit Thermocouple (CET) tube. On 3/10/2022, based on laboratory analysis of the affected CET tube section, FPL Engineering determined that there was no pressure boundary through-wall leakage associated with this event. Analysis identified that the leakage likely originated from an adjacent threaded compression fitting on a tubing joint. This condition complies with ASME Section XI requirements and is therefore not reportable. This follow-up NRCOC notification is a retraction of EN 55574. The NRC Resident Inspector has been notified. Notified R2DO (Miller).

ENS 555139 October 2021 07:27:00Turkey PointNRC Region 2Westinghouse PWR 3-LoopAt 0300 EDT, with Unit 3 in Mode 3 at 0 percent power, an actuation of the Auxiliary Feedwater System occurred when steam generator water level rose to 80 percent causing a Feedwater Isolation signal, which tripped the last remaining Steam Generator Feed Pump during plant cooldown. The Auxiliary Feedwater System automatically started as designed when the feedwater isolation signal was received. This event is being reported pursuant to 10 CFR 50.72(b)(3)(iv)(A). The NRC Resident Inspector has been notified. The cause of the high steam generator level is under investigation.
ENS 5542624 August 2021 12:31:00Point BeachNRC Region 3Westinghouse PWR 2-LoopThe following was received from the Point Beach Station Radiation Protection Manager (RPM) via phone call to the Headquarters Operations Officer: Per 10 CFR 20.1906(d)(1), the Point Beach Station RPM reported to the NRC receipt of a package of radioactive material (new fuel shipment) with removable surface contamination greater than NRC reporting limits. The package was received Tuesday, August 24, 2021, at 0645 CDT. The package was surveyed and it was determined that the external surface of the package contained removable contamination that exceeded the regulatory limit of 240 dpm/cm2 for beta-gamma emitters. The measured level of removable contamination was 337.3 dpm/cm2 for beta-gamma emitters and contained Cobalt 60. The licensee's corrective actions were to conduct additional smears of the package, trailer, and truck, and to frisk the truck driver to ensure no further contamination. No contamination has been identified.
ENS 5541819 August 2021 18:14:00Point BeachNRC Region 3Westinghouse PWR 2-LoopA covered employee had a confirmed positive during a for-cause fitness-for-duty test. The employee's access to the plant has been terminated. The NRC Resident Inspector has been notified.
ENS 5539031 July 2021 21:37:00Point BeachNRC Region 3Westinghouse PWR 2-LoopAt 1646 (CDT) on 7/31/21, with Unit 1 in Mode 1 at 100 percent power, the reactor was manually tripped due to control board indications of a Unit 1 'B' Main Feed Pump trip. After the reactor trip, one of the Condenser Steam Dump valves cycled to intermediate and remained stuck. The Condenser Steam Dump Valve was isolated locally using manual isolation valves. The 'B' Feed Regulating Bypass Valve did not control in automatic and was taken to manual to control the level in 'B' Steam Generator. The Auxiliary Feedwater System automatically actuated as designed when the valid actuation signal was received. Operations stabilized the plant in Mode 3. Decay heat is being removed by atmospheric dump valves due to condenser unavailability. Unit 2 is unaffected. 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. During the transient, all control rods inserted into the core. There is no known primary to secondary leakage. During the transient, no relief valves or safeties lifted. The plant is currently maintaining normal operating temperature and pressure with all safety equipment available. The plant is in its normal shutdown electrical lineup.
ENS 5538428 July 2021 16:30:00SeabrookNRC Region 1Westinghouse PWR 4-LoopA licensed employee had a confirmed positive for alcohol during a random fitness-for-duty test. The employee's access to the plant has been suspended. The NRC Resident Inspector has been notified.
ENS 5515324 March 2021 22:06:00Turkey PointNRC Region 2Westinghouse PWR 3-LoopAn Unusual Event was declared at Turkey Point Unit 4 Nuclear Generating Station at 2129 EDT on 03/24/2021 due to a Fire Alarm in Containment. The licensee was not able to validate the alarm within 15 minutes. Following containment entry there was not smoke or fire present. At 2214 EDT, Turkey Point Unit 4 Nuclear Generating Station terminated the Unusual Event. The cause of the spurious fire alarm is under investigation. The licensee notified the NRC Resident Inspector. Notified IRD MOC (Gott), NRR EO (Felts), R2DO (Miller), DHS SWO, FEMA Operations Center, CISA Central, FEMA NWC (email), DHS Nuclear SSA (email), and FEMA NRCC SASC (email).
ENS 551171 March 2021 14:07:00Turkey PointNRC Region 2Westinghouse PWR 3-LoopOn 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.
ENS 5510920 February 2021 22:00:00Turkey PointNRC Region 2Westinghouse PWR 3-LoopAt 1830 (EST) on 02/20/21, Turkey Point Nuclear Station Security identified three distressed individuals, potentially drowning, in the bay just offshore of the Owner Controlled Area. The licensee contacted the U.S. Coast Guard and local sheriffs department for assistance. At 1852 all 3 individuals were reported as safe and onshore. This event is being reported pursuant to 10 CFR 50.72(b )(2)(xi). The NRC Resident Inspector has been notified.
ENS 5507820 January 2021 21:48:00Saint LucieNRC Region 2CEOn 1/20/2021 at 1822 EST, with Unit 2 in Mode 1 at 100 percent power, the reactor automatically tripped due to a loss of Motor Control Center 2B2. The trip was uncomplicated with all systems responding normally post trip. Operations stabilized the plant in Mode 3. Auxiliary feed-water automatically actuated on the 2A Steam Generator post trip. Current decay heat removal is the 2B main feedwater pump to both steam generators and the Steam Bypass Control System to the main condenser. Unit 1 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.
ENS 5503614 December 2020 20:21:00Turkey PointNRC Region 2Westinghouse PWR 3-Loop

At 1240 EST on 12/14/20, it was determined that all Unit 4 Charging Pumps and Boration Flowpaths were simultaneously inoperable. This condition is being reported pursuant to 10 CFR 50.72(b)(3)(v). The NRC Resident Inspector has been notified.

  • * * RETRACTION ON 2/10/2021 AT 1210 EST FROM DAVID STOIA TO BETHANY CECERE * * *

On 1/21/21 a past operability review was completed that assessed the event reported on 12/14/20. The evaluation concluded that the condition did not render any Unit 4 Charging Pump or all boration flowpaths inoperable, and that the 8-hour notification submitted on 12/14/20 was not required. This notification is a retraction of EN #55036. The NRC Site Resident has been notified of the EN #55036 retraction. Notified R2DO (Miller).

ENS 549303 October 2020 15:07:00Point BeachNRC Region 3During a scheduled refueling outage, a walkdown inside containment to investigate leakage revealed a pressure boundary leak upstream of 1RC-526B, HX-1B Steam Generator Channel Head Drain. This location would be considered part of the reactor coolant system as defined under 10 CFR 50.2. As such, this event is being reported pursuant to 10 CFR 50.72 (b)(3)(ii)(A). Unit 1 is currently in mode 4. Repairs for the condition are being determined. The NRC Resident Inspector has been notified. The leak rate was determined to be 0.138 gpm.
ENS 5484721 August 2020 03:12:00Turkey PointNRC Region 2On 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.
ENS 5484419 August 2020 15:57:00Turkey PointNRC Region 2On 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 5483918 August 2020 00:08:00Turkey PointNRC Region 2On 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.
ENS 5482610 August 2020 14:38:00Duane ArnoldNRC Region 3

At 1258 CDT on August 10, 2020, Duane Arnold Energy Center declared an Unusual Event due to a loss of offsite power due to high winds. The event at the single unit plant resulted in an automatic scram from 82 percent power (Mode-1) to zero percent power (Mode-3). They are headed to Mode-4. There is damage on site, but the Reactor Building is intact. All rods inserted and cooling is being addressed via Reactor Core Isolation Cooling (RCIC) for level control and Safety Relief Valves are removing decay heat to the torus. Both Standby Diesel Generator are running. The licensee notified the NRC Resident Inspector, the Iowa Department of Emergency Management, and the Linn County and Benton County Emergency Management agencies. Notified DHS SWO, FEMA Operations Center, CISA Central, FEMA NWC (email), DHS Nuclear SSA (email), and FEMA NRCC SASC (email).

  • * * UPDATE ON 08/10/2020 AT 1554 EDT FROM CURTIS HANSEN TO OSSY FONT * * *

This report is being made under CFR 50.72 (b)(2)(iv)(B) for an automatic reactor scram due to loss of offsite power due to high winds. In addition, this report is being made under CFR 50.72 (b)(3)(iv)(A) and (B) due to PCIS ((Primary Containment Isolation System)) Groups 1, 2, 3, 4 and 5 (activating) due to loss of offsite power. All isolations went to completion. RCIC injecting for level control. All rods fully inserted during the scram. The plant electrical line up is both SBDGs (Standby Diesel Generators) are running. Decay heat is being removed via SRVs (Safety Relief Valves) to the torus. Progress towards shutdown cooling. NRC Senior Resident (Inspector) notified at 1448. Notified R3DO (Pelke).

ENS 5480831 July 2020 17:40:00Saint LucieNRC Region 2

A Hurricane Warning is in effect for St. Lucie County including the plant site. A Hurricane Warning was confirmed with the State Watch Office at 1700 EDT. As a mater of procedure, St. Lucie Nuclear Power Plant entered an Unusual Event classification for the Hurricane Warning. State and local officials have been notified by the licensee. The NRC Resident Inspector was notified by the licensee. This report is submitted in accordance with 10 CFR 50.72(a)(1)(i) due to the Notice of Unusual Event and 10 CFR 50.72(b)(2)(xi) due to the Offsite Notification. Notified DHS SWO, FEMA OC, DHS NICC WO, CISA IOCC (email), DHS SWO (email); FEMA NWC (email), FEMA Ops Center (email), FEMA-NRCC-sasc (email), NRCC THD Desk (email), NuclearSSA (email).

  • * * UPDATE ON 8/2/20 AT 1456 EDT FROM LOUIS ENGELKE TO BETHANY CECERE * * *

The Hurricane Warning was downgraded to a Tropical Storm Warning by the National Weather Service for St. Lucie County, including the plant site. At time 1445 EDT, on 08/02/20, St. Lucie Nuclear Plant has terminated from the Unusual Event classification. There are no changes in plant status for either unit. Both units are stable at 100% power. The NRC Resident Inspector was notified of this by the licensee. The licensee notified State and County officials of the termination. Notified R2DO (M. Miller), IRD MOC (Kennedy), NRR EO (C. Miller), DHS SWO, FEMA OC, DHS NICC WO, CISA IOCC (email), DHS SWO (email); FEMA NWC (email), FEMA Ops Center (email), FEMA-NRCC-sasc (email), NRCC THD Desk (email), NuclearSSA (email)

ENS 547625 July 2020 23:05:00Turkey PointNRC Region 2Reactor 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.
ENS 547406 June 2020 12:25:00SeabrookNRC Region 1At 0920 (EDT), with the unit in Mode 1 and 100 percent power, the reactor was manually tripped due to group 1 of control rod bank 'B' fully inserting into the core. All systems responded normally post trip. Operations has stabilized the plant in mode 3 at NOP/NOT (normal operating pressure and temperature). Decay heat removal is being accomplished via the steam dumps in the steam pressure mode to the main condenser. Emergency feedwater actuated due to low low steam generator level as expected. This event is being reported pursuant to 10CFR50.72(b)(2)(iv)(B) and 10CFR50.72(b)(3)(iv)(A) The senior NRC Resident Inspector has been notified. The plant response to the trip was uncomplicated. All safe shutdown equipment is available. There were no reliefs or safeties actuated during the transient. The licensee manually tripped eight days ago for the same condition. See EN #54731.
ENS 5473129 May 2020 16:41:00SeabrookNRC Region 1At 1403 EDT, with the unit in Mode 1 and 100 percent power, the reactor was manually tripped due to Group 1 of Control Rod Bank 'B' unexpectedly inserting. All systems responded normally post-trip. Operations stabilized the plant in Mode 3 at 557 degrees Fahrenheit. Decay heat removal is being accomplished via the steam dumps in the steam pressure mode to the main condenser. Emergency feedwater actuated due to low low steam generator level as expected. This event is being reported pursuant to 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR (b)(3)(iv)(A). The NRC Senior Resident Inspector has been notified.
ENS 545695 March 2020 21:14:00SeabrookNRC Region 1On March 05, 2020, at 2100 EST, the site commenced a planned upgrade of the main plant computer system (MPCS). During this upgrade, the normal computer data will not be available to the emergency response facilities, but compensatory capabilities will be in place. The scheduled duration for the MPCS upgrade is 96 hours. Since the compensatory measures will be in place in excess of 72 hours, this condition is being reported pursuant to 10 CFR 50.72(b)(3)(xiii). The NRC Resident Inspector has been notified.
ENS 5452817 February 2020 14:51:00Duane ArnoldNRC Region 3At 0850 CST, on 2/17/2020, the Control Room was notified of a personnel medical event. The individual was transported to a local hospital via ambulance. At the time of transport, the individual was considered to be potentially contaminated because complete surveys could not be performed prior to transfer. Upon arrival at the hospital, the individual and clothing were surveyed by an accompanying Site Radiation Protection Technician and no contamination was found. This report is being made pursuant to 10 CFR 50.72(b)(3)(xii). The NRC Resident Inspector has been notified. The individual was not performing any work related activities at the time of event.
ENS 544235 December 2019 13:30:00Turkey PointNRC Region 2This 4-hour non-emergency notification to the NRC is being made on a notification to another government agency per 10 CFR 50.72(b)(2)(xi). On 12/5/2019, at 0719 EST, a deceased manatee was identified in the Owner Controlled Area. The Federal Fish and Wildlife Service and the Florida Fish and Wildlife Conservation Commission (FWCC) were notified on 12/5/2019, at 1220 EST. Miami-Dade County was notified on 12/5/2019, at 1245 EST. A courtesy call to the Florida Department of Environmental Protection was made on 12/5/2019, at 1300 EST. The NRC Resident Inspector has been notified.
ENS 5436230 October 2019 01:20:00Saint LucieNRC Region 2

On 10/30/19 at 0026 EDT, an Unusual Event (HU3) was declared due to a release of flammable gas to the Unit 1 Pipe Penetration area (Reactor Auxiliary Building). The hydrogen supply valve to the area has been isolated. The area is being ventilated and follow-up air sampling will be performed. The NRC Resident Inspector has been notified. Notified DHS SWO, FEMA Ops Center, DHS NICC, FEMA NWC (email), DHS Nuclear SSA (email), and FEMA NRCC SASC (email).

  • * * UPDATE FROM FRED POLLAK TO DONALD NORWOOD AT 0521 EDT ON 10/30/2019 * * *

The Notice of Unusual Event was terminated at 0454 EDT on 10/30/19. The area has been purged and normal access restored. The licensee notified the NRC Resident Inspector. Notified R2DO (McCoy), NRR EO (Miller), and IRD (Grant). Notified DHS SWO, FEMA Ops Center, DHS NICC, FEMA NWC (email), DHS Nuclear SSA (email), and FEMA NRCC SASC (email).

ENS 542627 September 2019 12:01:00Saint LucieNRC Region 2On September 09, 2019 at 0824 EDT, with St. Lucie Unit 1 in Mode 1 at 100 percent power, the reactor automatically tripped on Low Reactor Coolant System Flow due to a trip of the 1A1 reactor coolant pump. The trip was uncomplicated with all systems responding normally post-trip. Operators responded and stabilized the plant in Mode 3. The cause of the loss of the 1A1 reactor coolant pump is currently under investigation. St. Lucie Unit 2 was unaffected and remains in Mode 1 at 100 percent power. This report is submitted in accordance with 10 CFR 50.72(b)(2)(iv)(B) for the reactor trip. Decay heat removal is being accomplished by main feed water and the main condenser using the turbine steam bypass valves. The licensee notified the NRC Resident Inspector.
ENS 542531 September 2019 17:44:00Saint LucieNRC Region 2

EN Revision Text: NOTIFICATION OF UNUSUAL EVENT DUE TO DECLARATION OF HURRICANE WARNING A hurricane warning is in effect for St. Lucie County including the plant site. A hurricane warning was confirmed with the State Watch Office at 1717 EDT. As a matter of procedure, St. Lucie Nuclear Power Plant entered an Unusual Event classification for the hurricane warning. State and local officials have been notified by the licensee. The NRC Resident Inspector was notified of this by the licensee. This report is submitted in accordance with 10 CFR 50.72(a)(2)(i) due to the Notice of Unusual Event and 10 CFR 50.72(b)(2)(xi) due to the offsite notification.

  • * * UPDATE AT 1835 EDT ON 9/3/19 FROM SARAH LOGSDON TO JEFF HERRERA * * *

The Hurricane Warning was downgraded to a Tropical Storm Warning by the National Weather Service for St. Lucie County including the Plant Site. At time 1818 EDT on 9/3/19, St. Lucie Nuclear Power Plant has terminated from the Unusual Event Classification. There are no changes in plant status for either unit. Both units are stable at 100 percent power. The NRC Resident Inspector was notified. Notified the R2DO (Shaeffer), IRDMOC (Kennedy), NRR EO (Walker), R2RA (Dudes via email), NRR (Nieh via email), DHS SWO, FEMA Ops Ctr., DHS NICC, FEMA NWC (email), DHS Nuclear SSA (email), FEMA NRCC (email).

ENS 5407218 May 2019 14:00:00Turkey PointNRC Region 2This 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 540463 May 2019 16:43:00Turkey PointNRC Region 2A non-licensed contract supervisor had a confirmed positive during a for-cause fitness-for-duty test. The individual's authorization for site access has been terminated. The NRC Resident has been notified.
ENS 5402725 April 2019 12:04:00Saint LucieNRC Region 2At 0918 (EDT) on 4/25/19, with (Saint Lucie) Unit 1 in Mode 1 at 100% power, the reactor automatically tripped due to a Turbine Trip. The reactor trip was uncomplicated with all systems responding normally. Operations is maintaining the plant stable in Mode 3. Decay heat removal is being accomplished by main feed water and the main condenser using the turbine steam bypass valves. Unit 2 is not affected and remains at 100% power. This event is being reported pursuant to 10 CFR 50.72(b)(2)(iv)(B). The NRC Resident Inspector has been notified.
ENS 5401220 April 2019 09:54:00Duane ArnoldNRC Region 3At 0507 (CDT on April 20, 2019), the DAEC (Duane Arnold Energy Center) experienced a trip of both reactor feed pumps. Operators inserted a manual scram. All control rods inserted, as required. As a result of the feed pump trips and scram, HPCI and RCIC automatically injected. Also, containment isolations occurred, as expected for this event. All systems responded as designed. Operators are currently taking the unit to cold shutdown conditions. Vessel level is being controlled by RCIC with Condensate System available. Pressure is being controlled using Main Steam Line drains and the Main Condenser is available. Normal electrical lineup remains. The cause of the reactor feed pumps tripping is believed to be an instrument air leak to flow control valves, causing loss of suction to both feed pumps. The licensee notified the NRC Resident Inspector.
ENS 5389725 February 2019 11:59:00SeabrookNRC Region 1A non-licensed, licensee supervisory employee failed a for-cause FFD test for alcohol. The individual's authorization for site access has been denied. The NRC Resident Inspector has been notified.
ENS 5385431 January 2019 17:06:00SeabrookNRC Region 1On 1/31/2019, the Medical Review Officer for Seabrook was notified of an error made by the HHS (Health and Human Services) certified lab resulting in a false negative Fitness for Duty quality assurance test result. The test lab, Quest Diagnostics-Norristown, was provided an adulterated sample specimen that was part of a blind performance test, which tested negative. This false negative test result will be investigated and the results reported as required. This event is being reported in accordance with 10 CFR 26.719(c)(3). NRC Resident Inspector has been notified.
ENS 537795 December 2018 20:07:00Point BeachNRC Region 3At 1539 (CST) December 5, 2018, with Unit 1 at 100 percent power, the reactor was manually tripped due to degrading condenser vacuum. The trip was uncomplicated with all systems responding normally, post-trip. An actuation of the auxiliary feedwater system occurred during the manual trip. The auxiliary feedwater system automatically started as designed when the valid actuation signal was received. Operations stabilized the plant in mode 3 (hot standby). Decay heat is being removed by atmospheric dump valves. Unit 2 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 loss of condenser vacuum resulted because one of two circulating water pumps was running and its discharge valve shut. The cause for the valve shutting is under investigation. There is no primary to secondary leakage. The licensee notified the NRC Resident Inspector
ENS 5376029 November 2018 12:56:00SeabrookNRC Region 1This 60-day telephone notification is being made under reporting requirements specified by 10 CFR 50.73(a)(2)(iv)(A) to describe an invalid actuation of the Reactor Protection System (RPS). At 0147 (EST) on October 1, 2018, Seabrook Unit 1 was in Mode 3 shutdown, when an invalid Reactor Protection System actuation occurred due to a high Source Range detector. All equipment responded in accordance with the plant design. Specifically, all actuations were complete and successful. There were no safety consequences or impacts on the health and safety of the public. The event was entered into Seabrook's corrective action program for resolution. The NRC Resident Inspector has been notified. The Source Range detector which gave the invalid input has been replaced.
ENS 5370329 October 2018 16:47:00Saint LucieNRC Region 2On October 29, 2018 at 1317 EDT, with St. Lucie Unit 1 in Mode 1 at 100% power, the reactor was manually tripped due to inadequate feedwater flow to both 1A and 1B Steam Generators (S/Gs). The trip was uncomplicated with all systems responding normally post-trip. (All control rods fully inserted and there were no specified system actuations.) Operators responded and stabilized the plant in Mode 3. The cause of the inadequate feed flow to the 1A and 1B Steam Generators is currently under investigation. Decay Heat removal is being accomplished through forced circulation with stable conditions from Main Feedwater and the Steam Bypass Control System to the Main Condenser. Currently maintaining Pressurizer pressure at 2250 psia and Reactor Coolant System temperature at 532 degrees F. St. Lucie Unit 2 was unaffected and remains in Mode 1 at 100% power. This report is submitted in accordance with 10CFR50.72(b)(2)(iv)(B) for the reactor trip. The NRC Senior Resident Inspector has been notified.
ENS 5367619 October 2018 21:44:00Duane ArnoldNRC Region 3At 1725 CDT, a Feedwater Regulating valve failed closed, resulting in a reactor level transient, which initiated a reactor trip, Primary Containment Isolation System signals to valves in Groups 2, 3, and 4 and initiation of High Pressure Coolant Injection and Reactor Core Isolation Cooling. All control rods inserted and level has been restored to normal. The cause of the feedwater valve failure is under investigation. All other systems responded as expected. This report is being made under 10 CFR 50.72 (b)(2)(iv)(B), (b)(3)(iv)(A) and (b)(2)(iv)(A). The Senior Resident Inspector has been informed. Decay heat is being removed via the main condenser and reactor vessel water level is being maintained by the condensate and feedwater systems.
ENS 5366512 October 2018 16:54:00Saint LucieNRC Region 2On October 12, 2018 at 1353 EDT, St. Lucie Unit 2 experienced an automatic RPS actuation and Reactor Trip due to a fault on the 2A1 6.9kv bus during a transfer of the bus power supply from the 2A Auxiliary Transformer to the 2A Startup Transformer. The bus fault caused a fire in the 2A1 6.9kv switchgear that has been extinguished. Offsite support was not required to extinguish the fire. The specific cause of the fault is currently under investigation. Following the reactor trip, both Steam Generators are being supplied by main feedwater. All (Control Element Assemblies) (CEAs) fully inserted into the core. Decay Heat removal is being accomplished through forced circulation. Main Feedwater and Steam Bypass Control Systems are maintaining stable conditions in Mode 3. St. Lucie Unit 1 was unaffected and remains in Mode 1 at 100 percent power. This report is submitted in accordance with 10 CFR 50.72(b)(2)(iv)(B) for the Reactor Trip. The fire was extinguished within 28 minutes. Plant loads are being supplied by the 2B Auxiliary Transformer. The licensee notified the NRC Resident Inspector.
ENS 5361924 September 2018 14:06:00Duane ArnoldNRC Region 3On September 22, 2018, at approximately 0050 (CDT), Duane Arnold Energy Center (DAEC) Security was contacted by a site assigned contractor that they had located what appeared to be drug paraphernalia inside the Protected Area. Local Law Enforcement was contacted and responded to DAEC. The Linn County Sheriff's office took the items into evidence for testing to determine if there was any presence of a controlled substance. On September 24, 2018, at 1013, the Linn County Sheriff's office notified DAEC that the items tested positive for the presence of a controlled substance. Therefore, this is being reported in accordance with 10 CFR 26.719. DAEC Site security is working with NextEra Corporate security regarding the investigation into this incident. The Resident Inspector has been notified.
ENS 5359811 September 2018 23:23:00Saint LucieNRC Region 2At 2200 EDT on September 11, 2018, during inspections as part of the pressurizer bare metal inspection program, an apparent weld defect was identified on Class 1 pressurizer level piping at the piping to pressurizer interface. The reactor is currently defueled in a refueling outage. Appropriate repairs will be made during the refueling outage. NRC Resident Inspector has been notified.
ENS 5350011 July 2018 03:58:00Duane ArnoldNRC Region 3On July 11, 2018, as part of pre-planned maintenance, the site meteorological tower will be removed from service. The tower will be out of service for approximately 11 days. As a result, this is reportable under 10CFR 50.72 (b)(3)(xiii). During the time the data is not available from the meteorological tower; compensatory measures will be in place to obtain the data from the National Weather Service if necessary. The (NRC) Resident Inspector has been notified.
ENS 534969 July 2018 16:25:00Duane ArnoldNRC Region 3At approximately 1334 CDT on 7/9/18, both doors of a Secondary Containment Airlock were reported to be open simultaneously for a period of less than 3 seconds. The brief time that the doors were simultaneously open constituted an inoperable condition of Secondary Containment. Secondary Containment was immediately restored to operable by closing the airlock doors. Subsequently, the airlock interlock was verified to operate correctly. This event is being reported pursuant of 10 CFR 50.72(b)(3)(v)(C). The Senior NRC Resident Inspector has been notified.
ENS 5326014 March 2018 09:34:00Saint LucieNRC Region 2CEA non-licensed contract supervisor had a confirmed positive for illegal drugs during a pre-access drug test. The individual's access has been denied. The NRC Resident Inspector has been notified.
ENS 532391 March 2018 20:05:00Point BeachNRC Region 3Westinghouse PWR 2-LoopDuring review of protection of equipment from damaging effects of tornados, Point Beach Nuclear Plant identified a potential vulnerability for the turbine driven auxiliary feedwater pumps due to steam supply piping that is not routed through a Class 1 structure. Immediate compensatory measures were taken to mitigate the potential consequences of a tornado generated missile impact. This condition is reportable per 10 CFR 50.72(b)(3)(ii)(B) and per 10 CFR 50.72(b)(3)(v)(A) and (D). The identified vulnerability is being addressed in accordance with EGM 15-002 and DSS-ISG-2016-01, enforcement discretion memorandum and interim guidance document for resolution of noncompliance with tornado-generated missile protection. The NRC Resident Inspector has been notified.