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 Entered dateSiteRegionReactor typeEvent description
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 1

At 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 1

On 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.
ENS 5322020 February 2018 15:35:00Point BeachNRC Region 3Westinghouse PWR 2-LoopAt 0956 CST on 2/20/2018, an employee working in a non-contaminated section of the Radiological Control Area was transported offsite for a personal medical issue. The required radiological survey was not completed prior to the employee being transported offsite by ambulance. A radiological protection technician accompanied the employee and completed a survey during the transfer to the hospital, confirming no contamination of the employee. This event is reportable pursuant to 10 CFR 50.72(b)(3)(xii). The NRC Resident Inspector has been notified.
ENS 5316716 January 2018 10:06:00Duane ArnoldNRC Region 3GE-4This 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 a containment isolation signal affecting more than one system. At 2230 CST on November 30, 2017, with the Duane Arnold Energy Center (DAEC) operating at 100 percent power, an invalid Group 3 isolation on the 'B' side of the Primary Containment Isolation System (PCIS) occurred. Group 3 isolation signals were generated for Primary Containment Isolation Valves for Drywell and Torus Ventilation and Purge, Containment Nitrogen Compressor Suction and Discharge, Recirculation Pump Seals, and Post Accident Sample System. This event was caused by a fault on the 1D25 Instrument AC Inverter. The fault was caused by an insufficient design clearance to ground and was corrected by increasing the clearance. 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 DAEC's corrective action program for resolution. The NRC Resident Inspector has been notified.
ENS 5311111 December 2017 00:35:00Saint LucieNRC Region 2CESt. Lucie Unit 1 declared an Unusual Event due to a smoke detector alarm received in the Unit 1 Containment Building that was unable to be confirmed within 15 minutes. A Containment entry was completed and no evidence of fire was found. The Unusual Event was terminated at 00:26 on 12/11/17. State and local officials have been notified by the licensee. The NRC Resident Inspector has been notified of this by licensee. Notified DHS SWO, FEMA Operations Center, DHS NICC, FEMA NWC (email), and DHS Nuclear SSA (email).
ENS 5308522 November 2017 10:28:00Saint LucieNRC Region 2CE

St. Lucie Unit 2 declared an Unusual Event due to a smoke detector alarm received in the Unit 2 Containment Building that was unable to be confirmed within 15 minutes. A Containment entry is currently being planned to determine the validity of the alarm. State and local officials have been notified by the licensee. The NRC Resident Inspector has been notified. Notified DHS SWO, FEMA Operations Center, DHS NICC, FEMA NWC (email), DHS Nuclear SSA (email), and FEMA NRCC SASC (email).

  • * * UPDATE ON 11/22/17 AT 1143 EST FROM JULIUS FLETCHER TO JEFF HERRERA * * *

Personnel entered Containment to determine conditions and found no evidence of smoke, fire or damage to equipment. Event terminated at 1127 EST 11/22/17. The NRC Resident Inspector has been notified. Notified R2DO (Suggs), R2 DRA (Dudes), NRR (Brock), IRD (Gott), and NRR EO (Miller), DHS SWO, FEMA Operations Center, DHS NICC, FEMA NWC (email), DHS Nuclear SSA (email), and FEMA NRCC SASC (email).

ENS 5304230 October 2017 12:48:00Point BeachNRC Region 3Westinghouse PWR 2-LoopDuring a scheduled refueling outage, an inspection of components inside containment revealed a suspected weld defect on 1CV-309B, 1P-1B RCP Labyrinth Seal 1PT-124 Upper Root. 10 CFR 50.2 (2)(i) defines the reactor coolant pressure boundary as being connected to the reactor coolant system, up to and including the outermost containment isolation valve in system piping which penetrates primary reactor containment. The weld defect is located on the transmitter side of 1CV-309B. This can be isolated from the RCS by shutting 1CV-309B and 1CV-308B, 1P-1B RCP Labyrinth Seal 1PT-124 Lower Root. Based on the definition provided in 10 CFR 50.2, the condition is considered reportable under 50.72(b)(3)(ii). Unit 1 is currently in mode 3. Repairs for the condition are being determined. The NRC Resident Inspector has been notified.
ENS 5303626 October 2017 05:54:00Saint LucieNRC Region 2CEOn October 26, 2017 at 0212 EDT St. Lucie Unit 2 experienced a reactor trip due to a loss of load event resulting in an RPS (Reactor Protection System) actuation. The cause of the loss of load is currently under investigation. Following the reactor trip, an Auxiliary Feedwater Actuation Signal occurred due to low level in the 2A Steam Generator. One of the two Main Feed Isolation Valves to the 2A Steam Generator did not close on the Auxiliary Feedwater Actuation Signal. 2A Steam Generator level was restored by Auxiliary Feedwater. The 2B Steam Generator level is being maintained by Main Feedwater. All CEAs (Control Element Assemblies) fully inserted into the core. Decay heat removal is being accomplished through forced circulation with stable conditions from Auxiliary Feedwater/Main Feedwater and Steam Bypass Control System. Currently maintaining pressurizer pressure at 2250 psia and Reactor Coolant System temperature at 532 degrees F. 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 and 10 CFR 50.72(b)(3)(iv)(A) for the Specified System Actuation. The licensee notified the NRC Resident Inspector.
ENS 530049 October 2017 09:15:00Point BeachNRC Region 3Westinghouse PWR 2-Loop

At 0737 CDT on 10/9/17, Point Beach declared an Unusual Event with Emergency Action Level HU 3.1 due to report of toxic gas from a spill in a service building within the protected area. The spill is contained and cleanup operations are in progress. The spill was not in a contaminated area or vital area. The janitorial worker injured while mixing cleaning chemicals in a closet was taken to the hospital. The licensee notified the NRC Resident Inspector. Notified DHS SWO, FEMA Operations Center, DHS NICC, FEMA NWC (email), DHS Nuclear SSA (email), and FEMA NRCC SASC (email).

  • * * UPDATE ON 10/9/17 AT 1111 EDT FROM DENNY SMITH TO BETHANY CECERE * * *

Point Beach has terminated the Unusual Event at 0944 (CDT) on 10/9/2017. The Unusual Event condition is no longer warranted. The NRC Resident Inspector has been notified. Notified R3DO (Hills), NRR EO (King), IRD (Stapleton), DHS SWO, FEMA Operations Center, DHS NICC, FEMA NWC (email), DHS Nuclear SSA (email), and FEMA NRCC SASC (email).

ENS 5297619 September 2017 00:01:00Point BeachNRC Region 3Westinghouse PWR 2-LoopAt 1724 (CDT) on 9/18/17 during Control Room Ventilation testing Door-61, South Control Room Door, became wedged against its door stop and stuck open. Door-61 is a credited High Energy Line Break (HELB) / Fire / Flood Barrier in addition to its function to maintain the Control Room envelope. The door stop was subsequently unbolted from the floor and the door was free to close. Door-61, South Control Room Door, has since been inspected, and at 1750 (CDT), was declared functional as a HELB / Fire / Flood Barrier and Operational for purposes of maintaining the Control Room Envelope. During the 26 minutes the door was stuck open, the Control Room was in an unanalyzed condition with regards to protection from a High Energy Line Break. The licensee notified the NRC Resident Inspector.
ENS 5296010 September 2017 22:20:00Turkey PointNRC Region 2Westinghouse 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 529568 September 2017 17:51:00Saint LucieNRC Region 2CE

At time 1700 (EDT) today, the National Weather Service issued a Hurricane Warning for the area including the St. Lucie Nuclear Power Plant. On that basis, a Notice of Unusual Event was declared at time 1714 (EDT). In anticipation of severe weather, the site has completed proceduralized high wind preparations. Both units are currently stable at 100% power. The licensee notified both State and local agencies and has informed the NRC Resident Inspector. No safety-related systems are out of service. The electrical grid is stable. Notified DHS SWO, FEMA Operations Center, DHS NICC, FEMA NWC (email), DHS Nuclear SSA (email), and FEMA NRCC SASC (email).

  • * * UPDATE ON 9/9/17 AT 1743 EDT FROM DALE THOMAS TO S. SANDIN * * *

At 1701 (EDT) today (09/09/17), a 24-hour update was made to state and local governments following the National Weather Service issuing yesterday's hurricane warning for the area including St. Lucie Plant. On that basis, a Notice of Unusual Event was declared yesterday (09/08/17) at 1714 (EDT). There are no changes in plant status for either Unit. In anticipation of severe weather, the site previously completed high wind preparations. Our plants have been specifically built to withstand natural disasters such as hurricanes, tornadoes, earthquakes, flooding and tidal surges. This approach will ensure the safety of operations and our employees and the communities surrounding our plants. Both units are currently stable at 100% power level and will remain at that power since hurricane force winds are not currently projected to reach St. Lucie Plant. The NRC Resident Inspector has been informed. Notified R2DO (Michel).

  • * * UPDATE ON 9/10/17 AT 1730 EDT FROM DALE THOMAS TO DONG PARK * * *

At 1648 (EDT) today (09/10/17), a 24-hour update was made to state and local governments following the National Weather Service issuing Friday's hurricane warning for the area including St. Lucie Plant. On that basis, a Notice of Unusual Event was declared yesterday (09/08/17) at 1714 (EDT). There are no changes in plant status for either Unit. In anticipation of severe weather, the site previously completed high wind preparations. Our plants have been specifically built to withstand natural disasters such as hurricanes, tornadoes, earthquakes, flooding and tidal surges. This approach will ensure the safety of operations and our employees and the communities surrounding our plants. Both units are currently stable at 100% power level and will remain at that power since hurricane force winds are not currently projected to reach St. Lucie Plant. The NRC Resident Inspector has been informed. Notified R2IRC (Franke).

  • * * UPDATE ON 9/11/17 AT 1405 EDT FROM BRIAN KELLY TO BETHANY CECERE * * *

The Hurricane Warning has been terminated by the National Weather Service for St. Lucie County including the Plant Site. At time 1313 (EDT) on 9/11/17, St. Lucie Nuclear Power Plant has terminated from the Unusual Event Classification. Unit 1 is currently shutdown in Mode 3, Hot Standby. Unit 2 continues to operate in Mode 1, 100 percent power. The licensee notified State and Local Government Agencies, and the NRC Resident Inspector. Notified R2IRC (Munday), R2DO (Michel), NRR EO (King), IRD MOC (Gott), DHS SWO, DOE Ops Center, FEMA Ops Center, HHS Ops Center, DHS NICC, USDA Ops Center, EPA Emergency Ops Center, FDA Emergency Ops Center (email), FEMA NWC (email), DHS Nuclear SSA (email), and FEMA NRCC SASC (email).

ENS 529528 September 2017 00:06:00Turkey PointNRC Region 2Westinghouse PWR 3-Loop

At 2300 today, the National Weather Service issued a hurricane warning for the area including Turkey Point Nuclear Units 3 & 4. On that basis, a Notice of Unusual Event was declared at 2314 (EDT). In anticipation of severe weather, the site has completed proceduralized high wind preparations. Our plants have been specifically built to withstand natural disasters such as hurricanes, tornadoes, earthquakes, flooding and tidal surges. This approach will ensure the safety of operations and our employees and the communities surrounding our plants. Both units are currently stable at 100% power level. The NRC Resident Inspector has been informed. No safety systems are out of service. The electrical grid is stable but grid risk is high. Notified DHS, FEMA, NICC, and NSSA (e-mail).

  • * * UPDATE AT 0458 EDT ON 09/11/17 FROM TIM JONES TO JEFF HERRERA * * *

At 0400 (EDT) on 09/11/17, conditions at Turkey Point Nuclear have met established exit criteria to downgrade the Notice Of Unusual Event (NOUE). The previously reported EAL (Emergency Action Level) has been exited. The NRC Resident Inspector has been informed. Notified the R2DO (Michel) and R2OC (Miller), IRDMOC (Gott), NRREO (Miller), DHS, DOE, FEMA, HHS, USDA, EPA, FDA, DHS NICC, and NSSA (e-mail).

ENS 528811 August 2017 17:00:00Duane ArnoldNRC Region 3GE-4

At 0934 CDT, while appropriately removed from service for pre-planned testing, the High Pressure Coolant Injection (HPCI) inboard steam isolation valve, MO-2238, valve position indication was found to be inadequate. As a result, MO-2238 was declared inoperable in accordance with Technical Specification (TS) 3.6.1.3. This resulted in a condition that caused the HPCI system to be inoperable. The cause of the inadequate valve position indication is currently being investigated. This report is being made pursuant to 10 CFR 50.72(b)(3)(v)(D). The NRC Resident Inspector has been informed.

  • * * RETRACTION ON 09/11/17 AT 1144 EDT FROM BOB MURRELL TO BETHANY CECERE * * *

The purpose of this notification is to retract a previous report made on 8/1/17 at 1700 (EDT) (EN 52881). NRC notification was initially made as a result of the High Pressure Coolant Injection (HPCI) inboard steam isolation valve, MO-2238, valve position found to be inadequate. Subsequent to the initial report, NextEra Energy Duane Arnold (NextEra) has determined that the condition observed on 8/1/17 for MO-2238 did not exist prior to removing the system from service for pre-planned testing, but was observed during post maintenance testing. Consequently, the failure does not meet the reporting requirements of 10 CFR 50.72 or 10 CFR 50.73. The NRC Resident Inspector has been notified. Notified the R3DO (Riemer).

ENS 5287931 July 2017 18:32:00Saint LucieNRC Region 2CEAt 1400 (EDT), St. Lucie completed a review of Unit 1 Hot Leg Injection scenarios. St. Lucie Unit 1 was licensed with a Hot Leg Injection capability that relies upon manual actions to accomplish the function. This review concluded that some postulated single electrical train failure scenarios were not fully addressed in plant procedures. Because of the potential to extend Hot Leg Injection initiation beyond the analysis start time, St. Lucie is reporting this condition under 10 CFR 50.72(b)(3)(ii)(B). The affected off-normal procedures were immediately revised to include necessary instructions to restore power to selected valves during a postulated loss of electrical power to restore the Hot Leg Injection strategy. Unit 1 remained at 100% power. The NRC Resident Inspector has been notified. A review found this condition was not applicable for Unit 2.
ENS 527969 June 2017 10:17:00Turkey PointNRC Region 2Westinghouse PWR 3-LoopThis 60-day telephone notification is being made in accordance with the reporting requirements specified by 10 CFR 50.73(a)(2)(iv)(A) and 10 CFR 50.73(a)(1) to describe an invalid actuation of several safety systems. On April 10, 2017 at 1347 hours (EDT) with Unit 3 in Mode 6 during performance of the Train B Engineered Safeguards Integrated Test, safety system actuations occurred prior to the expected point in the test procedure when a loss of continuity resulted while the seismic clips were being removed from a fuse. The actuations were supposed to occur at a subsequent step when the fuse was to be pulled to actuate the Hi Containment Pressure signal. As a result, the following equipment actuated: 3B, 4A and 4B High Head SI pumps; 3B Containment Spray pump; Containment Isolation and Containment Ventilation Isolations; 3A and 3B Emergency Diesel Generators; Emergency Containment Coolers. Because an actual high containment pressure signal did not exist at the time of the actuation, the actuation is considered invalid. All equipment responded as expected. The NRC Resident Inspector has been notified.
ENS 527916 June 2017 15:48:00Turkey PointNRC Region 2Westinghouse PWR 3-LoopThis notification is in accordance with Turkey Point Technical Specification (TS) 3.7.1.6, Action b.1 to report the inoperability of both Standby Steam Generator Feedwater Pumps (SSGFPs) for greater than 24 hours. On 6/6/17 at 1751 hours (EDT) both SSGFPs will be inoperable for greater than 24 hours in support of planned valve repairs that require isolation of the common suction and discharge piping. TS 3.7.1.6, Action b.1 requires a report within four hours if both SSGFPs have been inoperable for 24 hours providing the cause of the inoperability and restoration plans. The valve repairs are currently planned for completion on or about 2300 hours on 6/9/17 which will restore the 'A' pump to service and allow TS 3.7.1.6, Action b.1 to be exited. The diesel-driven 'B' pump will remain out of service for radiator repair which is currently planned for completion on or about 0800 hours on 6/14/17. The function of the Standby Steam Generator Feedwater System is as a backup to the Auxiliary Feedwater System and is not credited in the safety analysis. The NRC Resident Inspector has been notified. Both pumps were taken out of service at 1751 EDT on 6/5/17.
ENS 5275716 May 2017 00:17:00Saint LucieNRC Region 2CEOn May 15, 2017 at 1800 hours EDT, the '2A3' 4.16 KV safety related bus unexpectedly de-energized. The '2A' emergency diesel generator (EDG) system received a valid start signal from the undervoltage condition on the '2A3' bus but did not start as the EDG had been removed from service for maintenance. Loss of the '2A3' 4.16 KV bus resulted in a valid actuation of the undervoltage protection relays. The direct cause of the de-energization was determined to be failed secondary side potential transformer fuses. The 'B' train safety related electrical busses were unaffected by the event. The '2A3' 4.16 KV bus was reenergized at 2340. This event was determined to be reportable pursuant to 10CFR50.72(b)(3)(iv)(A). During the electrical transient, the licensee briefly entered Technical Specification 3.0.3 but plant conditions were restored, all required LCOs were satisfied, and Technical Specification 3.0.3 was exited before the plant was required to downpower. The licensee notified the NRC Resident Inspector.
ENS 5271829 April 2017 21:19:00SeabrookNRC Region 1Westinghouse PWR 4-LoopAt 1844 (EDT) on 04/29/2017, while the unit was in a low power condition exiting from a refueling outage, the reactor was manually tripped following a P-14 signal (Steam Generator Hi-Hi Level) and a resulting feedwater isolation signal. All control rods were verified to be fully inserted. The cause of the ('B') steam generator high level is currently being investigated. Emergency feedwater actuated at 1845 due to a low-low water level in steam generator 'D'. Plant equipment response is being evaluated and the plant is stabilized in Mode 3 with decay heat removal through the steam dump system to the condensers. There was no release and the emergency feedwater system has been restored to standby. The event description is based on information currently available. If through subsequent reviews of this event, additional information is identified that is pertinent to this event or alters the information being provided at this time, a follow up notification will be made via the ENS or under the reporting requirements of 10 CFR 50.73. The licensee notified the NRC Resident Inspector.
ENS 5263623 March 2017 21:06:00Point BeachNRC Region 3Westinghouse PWR 2-LoopOn 3/23/17, at 0325 hours CDT, it was discovered that a prohibited item was present in the protected area from 0508-1718 hours on 3/22/17, which resulted in a reportable condition pursuant to 10 CFR 26.719(b)(1). The licensee has notified the NRC Resident Inspector.