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 Entered dateSiteRegionReactor typeEvent description
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 2A 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."
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 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 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 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 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 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 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 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 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 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 5252331 January 2017 15:39:00Saint LucieNRC Region 2CEAt 1200 (EST) on January 31, 2017, during investigation of potential 1B2 Reactor Coolant Pump seal degradation, a through wall defect was identified on Class 1 piping servicing the Lower Seal Heat Exchanger, which is part of the Reactor Coolant Pressure Boundary (RCPB). The reactor is presently in Mode 3 with decay heat being removed by the atmospheric steam dump valves. The plant is being maneuvered to Mode 5 to affect appropriate repairs. The licensee has notified the NRC Resident Inspector.
ENS 522804 October 2016 23:18:00Saint LucieNRC Region 2CE

A Hurricane Warning is in effect for St. Lucie County including the Plant Site. A Hurricane Warning was issued by the National Weather Service at 2250 (EDT). 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 10CFR50.72(a)(1)(i) due to the Notice of Unusual Event and 10CFR50.72(b)(2)(xi) due to the Offsite Notification. Notified DHS SWO, FEMA OPS Center, FEMA National Watch (email only), DHS NICC, Nuclear SSA (email only).

  • * * UPDATE FROM ANDY TEREZAKIS TO VINCE KLCO ON 10/7/16 AT 1112 EDT * * *

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 1044 (EDT) on 10/7/16, St. Lucie Nuclear Power Plant has terminated from the Unusual Event Classification. The licensee notified the NRC Resident Inspector, State and local authorities. Notified R2 (Jones) NRR EO (King), IRD (Grant), R2DO (Bonser), DHS SWO, FEMA OPS Center, FEMA National Watch (email only), DHS NICC, Nuclear SSA (email only).

ENS 5219121 August 2016 20:14:00Saint LucieNRC Region 2CE

At 35 percent power, a main generator lockout caused the main generator to trip, resulting in a reactor trip of Unit 1. Because of the lockout, power did not transfer to the startup transformers. Both emergency diesel generators started and aligned to the emergency busses. During the trip all control rods fully inserted and no safety or relief valves lifted. The plant is in Mode 3 steaming through the atmospheric relief valves and feeding the steam generators using auxiliary feedwater. There is no reported primary to secondary leakage. Primary coolant is being moved using natural circulation cooling. The trip of Unit 1 had no effect on Unit 2. The licensee notified the NRC Resident Inspector. Notified DHS SWO, FEMA, DHS NICC, and Nuclear SSA (via e-mail).

  • * * UPDATE AT 2140 EDT ON 08/21/2016 FROM GREG KRAUTZ TO MARK ABRAMOVITZ * * *

The Unusual Event was terminated at 2125 EDT after the plant restored normal offsite power. The licensee notified the NRC Resident Inspector. Notified the R2DO (Sandal), IRD (Gott), NRR EO (Miller), DHS SWO, FEMA, DHS NICC, and Nuclear SSA (via e-mail).

  • * * UPDATE AT 2315 EDT ON 08/21/2016 FROM ANDREW TEREZAKIS TO MARK ABRAMOVITZ * * *

On August 21, 2016 at 1926 EDT, St. Lucie Unit 1 experienced a reactor trip and a loss of offsite power due to a main generator inadvertent Energization Lockout Relay actuation. The cause of the lockout is currently under investigation. Coincident with the loss of offsite power, the four reactor coolant pumps deenergized. Both the 1A and 1B Emergency Diesel Generators started on demand and powered the safety related AC buses. All CEAs (Control Element Assemblies) fully inserted into the core. Offsite power to the switchyard remained available during the event, and at 2036, restoration of offsite power to St. Lucie Unit 1 was completed. Decay heat removal is being accomplished through natural circulation with stable conditions from Auxiliary Feedwater and Atmospheric Dump Valves. Currently maintaining pressurizer pressure at 1850 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 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. Notified the R2DO (Sandal).

  • * * UPDATE AT 0048 EDT ON 08/22/2016 FROM ANDREW TEREZAKIS TO DANIEL MILLS * * *

On August 21, 2016 at 2330 EDT, St. Lucie Unit 1 started two Reactor Coolant Pumps to establish Forced Circulation in order to enhance Decay Heat removal. Plant conditions remain stable with Auxiliary Feedwater and Atmospheric Dump Valves in service. This report is submitted in accordance with 10 CFR 50.72(c)(2)(ii) as a follow up notification of protective measures taken. The licensee notified the NRC Resident Inspector. Notified the R2DO (Sandal).

ENS 521381 August 2016 06:33:00Saint LucieNRC Region 2CE

On August 1, 2016 at 0342 EDT St. Lucie Unit 1 commenced a unit shutdown required by Technical Specifications due to Reactor Coolant System Pressure Boundary Leakage in excess of the allowable limit of zero leakage. The leak was initially identified on July 31, 2016 at 2115 EDT as not Pressure Boundary leakage. After further analysis, the leak was determined to be Reactor Coolant System Pressure Boundary leakage at 0123 on August 1, 2016. The leakage is estimated as less than one tenth of a gallon per minute and is not impacting the ability to shut down the unit. Additional impact of the leak is under evaluation. This report is submitted in accordance with 10CFR50.72(b)(2)(i) as 'The initiation of any nuclear plant shutdown required by the plant's Technical Specifications.' The location of the leak is on the Instrumentation piping welded connection at Flow Element FE-3311 attached to (the) Emergency Core Cooling System Injection header to Reactor Coolant System Loop 1A2. The leak activity is 0.167 microCuries per ml. The NRC Resident Inspector has been notified.

  • * * RETRACTION AT 1335 EDT ON 09/23/16 FROM RICHARD SCISCENTE TO JEFF HERRERA * * *

The purpose of this notification is to retract a previous report made on EN 52138. NRC notification was initially made as a result of a plant shutdown required by technical specifications (TS) for Reactor Coolant System (RCS) pressure boundary leakage. Subsequent to the initial report, St. Lucie has determined that the RCS leakage was from a seal weld on a threaded connection that was not pressure boundary leakage. However, the leak was non-isolable and required RCS depressurization to allow immediate investigation to ensure there were no faults in a RCS component body or pipe wall. The leakage was estimated to be less than one tenth of a gallon per minute and did not impact the ability to shut down the unit. No TS limits were exceeded during this event. Therefore, the plant shutdown to investigate and correct leakage past the seal weld of a threaded connection 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 R2DO (Blamey).

ENS 5142324 September 2015 16:34:00Saint LucieNRC Region 2CEOn September 17, 2015, at 1222 hours, with Unit 2 in Mode 5 at the beginning of a refueling outage, an electrical fault on the 2A 6.9 kV bus resulted in the loss of the 2A startup transformer and its associated non-safety related 2A2 and safety related 2A3 busses. At the time of the event, the 2A Emergency Diesel Generator (EDG) had been properly removed from service for scheduled maintenance. The loss of the 2A start up transformer initiated the under voltage relays, which resulted in a valid actuation signal that would have started the 2A EDG. Additionally, the 2A train of shutdown cooling (SDC) was de-energized; the 2B (protected) train of SDC was not affected by the event and remained in service to remove decay heat. The 2A shutdown cooling train was restored and made available on September 19, 2015 at 0030. The 2B EDG and 2B startup transformer remained operable. St. Lucie did not report this event within 8 hours of occurrence, however, this event was subsequently determined to be reportable pursuant to 10CFR50.72(b )(3)(iv)(A). During this event, Unit 1 experienced a loss of the 1A startup transformer. There was no effect on Unit 1 operation, as its associated non-safety and safety-related busses remained powered by the auxiliary transformer. The 1A startup transformer returned to service on September 18, 2015 at 2103. The licensee informed the NRC Resident Inspector.
ENS 5130210 August 2015 00:23:00Saint LucieNRC Region 2CEOn August 9, 2015, during the performance of Reactor Protection System Logic Matrix Testing, a reactor trip occurred. All CEA's (control rods) fully inserted into the core. Decay Heat removal is from Main Feedwater and Steam Bypass to the Main Condenser. All equipment operated as expected. Currently maintaining pressurizer pressure at 2250 psia, temperature maintaining at 532 degrees F. Unit 2 was unaffected and remains in Mode 1 at 100% power. This event is reportable pursuant to 10CFR 50.72(b)(2)(iv)(B) for the Reactor Trip and 10CFR 50.72(b)(3)(iv)(A) for the Specified System Actuation. The plant is in its normal shutdown electrical lineup. No safety or relief valves lifted during this event. The cause of the trip is under investigation. The licensee notified the NRC Resident Inspector.
ENS 511951 July 2015 10:39:00Saint LucieNRC Region 2CEOn May 4, 2015 with Unit 1 in Mode 1 at 100 percent power, during performance of the 'A' channel Auxiliary Feedwater Actuation System (AFAS) monthly functional test, an invalid 'A' channel AFAS actuation occurred. The monthly functional test resulted with AFAS-1 in a half trip condition. Due to a poor contact on a manual actuation switch, a pathway was dropped out causing the partial AFAS actuation to occur. The faulty mechanical switch was replaced and the post maintenance testing was satisfactory. The partial AFAS actuation resulted in the successful start of 'A' AFW electric driven pump and the opening of its motor control valve, feeding the 'A' steam generator. The system responded to the invalid actuation as designed. In accordance with 10 CFR 50.73(a)(1), this notification of the invalid actuation is provided in lieu of a written LER. The licensee notified the NRC Resident Inspector.
ENS 5097711 April 2015 22:15:00Saint LucieNRC Region 2CE

During investigation of a small leak on the 2B2 Safety Injection Tank inside Saint Lucie Unit 2 containment, a through wall flaw was identified on Class 2 piping associated with the 2B2 Safety Injection Tank. The 2B2 Safety Injection Tank was declared inoperable on April 11, 2015 at 1204 EDT and Unit 2 entered a 24-hour shutdown action statement for Technical Specification 3.5.1.b. On April 11, 2015 at 2100 EDT, Unit 2 initiated a plant shutdown in compliance with Technical Specifications.

This condition is being reported pursuant to 10 CFR 50.72(b)(2)(i) The electrical grid is stable and no safety-related equipment that would affect a safe shutdown was out of service at the time of the report. The licensee has notified the NRC Resident Inspector.

ENS 509523 April 2015 14:17:00Saint LucieNRC Region 2CE

On April 3, 2015, at 1500 EDT, the Control Room Emergency Ventilation System on St. Lucie Unit 1 will be declared inoperable due to pre-planned maintenance during the current refueling outage. The Technical Support Center (TSC) ventilation system is part of the Unit 1 Control Room Emergency Ventilation System, therefore, the TSC ventilation system has been rendered non-functional during the course of the work activities. The TSC ventilation is expected to be returned to service in approximately 24 hours. If an emergency is declared requiring TSC activation during this period, the TSC will be staffed and activated using existing emergency planning procedures. Should the TSC become uninhabitable, the TSC staff will relocate to an alternate TSC location in accordance with applicable site procedures. This notification is being made in accordance with 10 CFR 50.72 (b)(3)(xiii) due to the potential loss of an emergency response facility. An update will be provided once the TSC ventilation system has been restored to normal operation. The NRC Resident Inspector has been notified.

  • * * UPDATE PROVIDED BY DAVE FIELDS TO JEFF ROTTON AT 2240 EDT ON 4/03/2015 * * *

The TSC ventilation system has been restored to normal operation as of 2230 EDT on April 3, 2015. The NRC Resident Inspector has been notified. Notified R2DO (Walker).

ENS 507822 February 2015 16:54:00Saint LucieNRC Region 2CEAt 2/2/15, at approximately 0919 EST, a non-licensed employee supervisor had a confirmed positive for alcohol during a random fitness-for-duty test. Due to the confirmed positive test, the employee's access to the plant has been revoked. The NRC Resident Inspector has been informed.
ENS 5060712 November 2014 18:31:00Saint LucieNRC Region 2CEOn November 12, 2014 at 1548 (EST), Unit 2 was manually tripped due to a lowering 2B steam generator level caused by the spurious (slow) closure of 2B Main Feedwater Isolation Valve, HCV-09-2B. All CEAs (control element assemblies) fully inserted into the core. All safety systems responded as expected with the 2B Auxiliary Feedwater Actuation System Channel 2 (AFAS 2) actuating on low 2B steam generator level. Decay heat removal is from main feedwater to the 2A steam generator and manual control of auxiliary feedwater to the 2B steam generator, with steam bypass to the main condenser. This event is reportable pursuant to 10 CFR 50.72(b)(2)(iv)(B) for the reactor trip and 10 CFR 50.72(b)(3)(iv)(A) for the AFAS 2 actuation. During the transient, no relief or safety valves lifted. The grid is stable and the plant is in its normal shutdown electrical lineup at normal operating pressure and temperature. The cause of the feedwater isolation valve malfunction is under investigation. There was no effect on Unit 1. The licensee has notified the NRC Resident Inspector.
ENS 5047822 September 2014 09:34:00Saint LucieNRC Region 2CE

On September 22, 2014, at 1000 EDT, the Technical Support Center (TSC) will be unavailable due to pre-planned maintenance impacting the TSC ventilation envelope. The TSC is expected to be restored to operational status on September 23, 2014. If an emergency is declared requiring TSC activation during this period, the TSC will be staffed and activated using existing emergency planning procedures, and the TSC staff will assemble at a preplanned alternate location in accordance with applicable site procedures. This notification is being made in accordance with 10 CFR 50.72(b)(3)(xiii) due to the loss of an emergency response facility (ERF). An update will be provided once the TSC has been restored to operational status. The NRC Resident Inspector has been notified. The maintenance is expected to be completed within 36 hours.

  • * * UPDATE FROM TIMOTHY MILLER TO HOWIE CROUCH AT 1638 EDT ON 9/23/14 * * *

The TSC ventilation envelope has been restored. The TSC is returned to operational status on September 23, 2014 at 1600 EDT. The NRC Resident Inspector has been notified. Notified R2DO (Widman).

ENS 503487 August 2014 06:59:00Saint LucieNRC Region 2CE

On August 7, 2014 at 0730 EDT, the Unit 2 Radiation Monitoring Computer System will be inoperable and unavailable due to pre-planned maintenance to implement an upgrade to the system. Alternate methods for monitoring are being utilized. The Radiation Monitor Computer System is expected to be restored to available status at approximately 2000 EDT on August 7, 2014. This notification is being made in accordance with 10CFR50.72(b)(3)(xiii), as an event that results in a major loss of emergency assessment capability, offsite response capability, or offsite communications capability. An update will be provided once the Radiation Monitoring Computer System has been restored to normal operation. The NRC Resident Inspector has been notified.

  • * * UPDATE AT 1925 EDT ON 8/7/14 FROM JOHN REXRODE TO S. SANDIN * * *

The Unit 2 Radiation Monitoring Computer System has been restored to an operable status as of August 7, 2014 at 1733 EDT. The NRC Resident Inspector has been notified. Notified R2DO (Nease).

ENS 5031025 July 2014 14:02:00Saint LucieNRC Region 2CE

On July 25th, 2014 at 1129 EDT, during investigation of a small leak inside Saint Lucie Unit 2 containment, a defect was identified on a valve (V3811, Safety Injection Tank 281 Outlet Vent Valve). This valve is within the Q-Group A (ASME Class 1 equivalent) boundary of the safety injection line. The leak is currently isolated from the reactor coolant system by a Technical Specification credited isolation check valve. The affected Safety Injection Tank has been declared inoperable and the unit has entered 24 hour shutdown (Technical Specification) action statement 3.5.1.b. Unit shutdown is currently being planned for repair of the flaw. This condition is being reported pursuant to 10 CFR 50.72(b)(3)(ii)(A). The licensee has notified the NRC Resident Inspector.

  • * * UPDATE FROM JOHN REXRODE TO VINCE KLCO AT 0053 EDT ON 7/26/14 * * *

On July 26, 2014 at 0002 EDT, Saint Lucie Unit 2 commenced shutdown to repair the identified leak. This condition is being reported pursuant to 10 CFR 50.72(b)(3)(ii)(A) and 10 CFR 50.72(b)(2)(i). The NRC Resident Inspector has been notified. Unit 2 current power is 88% at 0105 EDT and expect to trip the unit at approximately 0400 EDT. Notified the R2DO (Musser).

ENS 5030324 July 2014 07:44:00Saint LucieNRC Region 2CE

On July 24, 2014 at 0800 EDT, the Unit 2 Radiation Monitoring Computer System will be inoperable and unavailable due to pre-planned maintenance to implement an upgrade to the system. Alternate methods for monitoring are being utilized. The Radiation Monitor Computer System is expected to be restored to available status at approximately 1700 EDT on July 24, 2014. This notification is being made in accordance with 10CFR 50.72 (b)(3)(xiii), as an event that results in a major loss of emergency assessment capability, offsite response capability, or offsite communications capability. An update will be provided once the Radiation Monitoring Computer System has been restored to normal operation. The NRC Resident Inspector has been notified.

  • * * UPDATED PROVIDED BY TIM KUDO TO JEFF ROTTON AT 1708 EDT ON 7/24/2014 * * *

The Unit 2 Radiation Monitoring Computer System has been restored to an operable status as of July 24, 2014 at 1650 EDT. The NRC Resident Inspector has been notified. Notified R2DO(Musser)

ENS 5029021 July 2014 08:09:00Saint LucieNRC Region 2CE

On July 21, 2014 at 0800 EDT, the Unit 2 Radiation Monitoring Computer System will be inoperable and unavailable due to pre-planned maintenance to implement an upgrade to the system. Alternate methods for monitoring are being utilized. The Radiation Monitor Computer System is expected to be restored to available status at approximately 1900 EDT on July 21, 2014. This notification is being made in accordance with 10CFR 50.72 (b)(3)(xiii), as any event that results in a major loss of emergency assessment capability, offsite response capability, or offsite communications capability. An update will be provided once the Radiation Monitoring Computer System has been restored to normal operation. The NRC Resident Inspector has been notified.

  • * * UPDATE FROM CARLOS SANTOS TO DONALD NORWOOD AT 2038 EDT ON 7/21/2014 * * *

The Unit 2 Radiation Monitoring Computer System is restored to an available status as of July 21, 2014 at 1955 EDT. The NRC Resident Inspector has been notified. Notified R2DO (McCoy).

ENS 4971210 January 2014 13:27:00Saint LucieNRC Region 2CEOn January 10, 2014, Florida Power and Light reported to the Florida Department of Environmental Protection that the St. Lucie Nuclear Plant temporarily bypassed the normal storm collection outfall path at 17:45 EST on January 9, 2014. The bypassed flow of water was a result of severe rainfall at the station and a blockage in the normal outfall path. This non-emergency notification is being made pursuant to 10CFR50.72(b)(2)(xi) due to the notification of the Florida Department of Environmental Protection. The licensee originally made the offsite notification to the State of Florida agency associated with the emergency declaration and severe weather event on January 9, 2014 (see Event Notification 49707). The licensee has notified the NRC Resident Inspector.
ENS 497079 January 2014 18:56:00Saint LucieNRC Region 2CE

On January 9, 2014 St. Lucie Unit 1 declared an Unusual Event based on a severe rain storm, a natural occurrence affecting the Protected Area. Specifically, visual sightings by station personnel that water levels are approaching storm drain system capacity. Countermeasures are being deployed and are currently operating satisfactorily. Both units continue to operate at full power. All safety systems remain available. The licensee has notified the NRC Resident Inspector, state, and other local authorities. Notified R2DO (Hopper), NRR EO (Lubinski) and IRD. Notified DHS SWO, DOE Ops Center, FEMA Ops Center, HHS Ops Center, NICC Watch Officer, and Nuclear SSA via email.

  • * * UPDATE FROM RACHEL SMITH TO GEROND GEORGE ON 01/10/2014 AT 0043 EST * * *

On January 10, 2014 at 0001 EST, St. Lucie Unit 1 terminated an Unusual Event. Site storm drain system functioning as required. Severe weather has passed, site water levels have returned to normal. Notified R2DO (Hopper), NRR EO (Lubinski) and IRD. Notified DHS SWO, DOE Ops Center, FEMA Ops Center, HHS Ops Center, NICC Watch Officer, and Nuclear SSA via email.

ENS 496882 January 2014 12:14:00Saint LucieNRC Region 2CEThis report is being made under 10 CFR 50.73(a)(2)(iv)(A) as an invalid actuation of Emergency Diesel Generator (EDG) 1A in lieu of a 60-day LER. Per NUREG-1022, the following information is provided: The specific train and system that were actuated: At 0323 hours (EST) on November 3, 2013, the St. Lucie Unit 1 train 'A' EDG automatically started. Troubleshooting revealed that the ESF-A group 7 actuation relay (K507A) failed, providing an invalid Engineered Safety Feature (ESF) 'start' signal to EDG 1A, and the EDG started and operated in the standby mode. The failed relay was replaced, and the post maintenance test was successful. Was train actuation complete or partial? This was a partial actuation of the 'A' train emergency power system as the 1A EDG output breaker did not close, by design, with power on the emergency busses. Did the system start and function correctly? The failed 7A actuation relay provided an invalid start signal to EDG 1A that properly responded to the start signal. The EDG output breaker closing logic prevented closure because the 4160 VAC emergency bus was energized at the time the actuation relay failed. The system started and functioned as would be expected for the existing plant conditions. The licensee informed the NRC Resident Inspector. Notified R2DO (Haag).
ENS 4966219 December 2013 16:04:00Saint LucieNRC Region 2CEAt 1320 ET on December 19, 2013, Florida Power and Light identified that atmospheric conditions that had sustained high winds exceeding approximately 50 miles per hour from the ENE direction could result in inadequate heat removal to support continuous operation of the Unit 2 emergency diesel generators. Upon identification of this condition, an adverse condition monitoring plan was issued requiring implementation of compensatory measures to assure adequate emergency diesel generator cooling to support continuous operation of the U2 emergency diesel generators, should weather forecasts identify conditions that would likely result in this condition. This condition is reportable pursuant to 10 CFR 50.72(b)(3)(ii)(B). The NRC Resident Inspector has been notified of this condition.
ENS 4953614 November 2013 14:57:00Saint LucieNRC Region 2CEOn November 14, 2013 at 1218 EST, Unit 2 was manually tripped due to a lowering 2B Steam Generator level caused by the spurious closure of 2B Main Feedwater Isolation Valve HCV-09-2A. All CEAs (Control Element Assemblies) fully inserted into the core. All safety systems responded as expected with the 2B Train Auxiliary Feedwater Actuation System Channel 2 (AFAS 2) actuating on low 2B Steam Generator level. Decay Heat Removal is from Main Feedwater to the 2A Steam Generator and Auxiliary Feedwater to the 2B Steam Generator with Steam Bypass to the Main Condenser. This event is reportable pursuant to 10CFR 50.72(b)(2)(iv)(B) for the Reactor Trip and 10CFR 50.72(b)(3)(iv)(A) for the AFAS 2 actuation. The plant is in its normal shutdown electrical lineup. No safeties or relief valves lifted during this event. The NRC Resident Inspector has been notified by the licensee.
ENS 4952812 November 2013 01:23:00Saint LucieNRC Region 2CEAt 0002 EST, Unit 1 Manually tripped the Reactor from 90% power due to an unisolable leak in the Digital Electro-Hydraulic (DEH) System. All CEAs fully inserted into the Reactor Core. All systems responded as expected on the trip. Decay Heat removal currently using Main Feedwater and Steam Bypass Control System. After the trip, DEH pumps were secured to stop the transfer of fluid from the DEH system to the Turbine Building. Investigation ongoing to determine exact location of the leak. This condition is reportable pursuant to 10CFR50.72(b)(2)(iv)(B). The was no impact on Unit 2. The NRC Resident Inspector has been notified.
ENS 491788 July 2013 10:57:00Saint LucieNRC Region 2CEOn July 8, 2013, at 0830 EDT, the National Response Center and the State Watch office were notified of a leak greater than the limit of 109 gal of 11% Sodium Hypochlorite onto the ground. Total amount spilled is approximately 200 gallons. While the leak is currently active, the leak has being routed to an approved injection point. This notification is being made in accordance with 10CFR 50.72 (b)(2)(xi) due to notification of off-site agencies. The NRC Resident Inspector has been notified.
ENS 4914223 June 2013 20:39:00Saint LucieNRC Region 2CE

On June 24, 2013, at 0000 EDT, the Technical Support Center (TSC) will be unavailable due to a pre-planned facility upgrade project. The TSC is expected to be restored to operational status on July 1, 2013. If an emergency is declared requiring TSC activation during this period, the TSC will be staffed and activated using existing emergency planning procedures, and the TSC staff will be located at a preplanned alternate location in accordance with applicable site procedures. This notification is being made in accordance with 10CFR 50.72 (b)(3)(xiii) due to the loss of an emergency response facility (ERF). An update will be provided once the TSC has been restored to operational status. The NRC Resident Inspector has been notified. The upgrades will require structural changes to the TSC.

  • * * UPDATE ON 6/30/13 AT 2020 EDT FROM FRED POLLAK TO HUFFMAN * * *

The Technical Support Center functionality has been restored as of 1953 EDT on 6/30/13. The NRC Resident Inspector has been notified. R2DO (Franke) notified.

ENS 4908231 May 2013 10:26:00Saint LucieNRC Region 2CEOn May 31, 2013 at 0712 (EDT), Unit 2 (reactor) was manually tripped due to high differential pressure on the debris filter for the 2A1 Condenser Waterbox which required a trip of the 2A1 Circulating Water Pump. The 2A2 Condenser Waterbox and the 2A2 Circulating Water Pump were already removed from service due to a suspected condenser tube leak. All CEAs (Control Element Assembly) fully inserted into the core. Decay heat removal is from main feedwater and steam bypass to the main condenser. The cause of the rising differential pressure on the 2A1 debris filter was potentially due to an influx of algae. This event is reportable pursuant to 10CFR 50.72(b)(2)(iv)(B) for the reactor trip. The reactor trip response is considered uncomplicated and the unit is stable in Mode 3 at normal temperature and pressure. Unit 2 is in a normal shutdown electrical lineup. There was no impact on Unit 1. The licensee has notified the NRC Resident Inspector.
ENS 488823 April 2013 14:13:00Saint LucieNRC Region 2CEA licensed employee was arrested for possession of a controlled substance while off-duty. The employee's access to the plant has been terminated. The licensee notified the NRC Resident Inspector.
ENS 4881812 March 2013 18:01:00Saint LucieNRC Region 2CEOn 3/12/13 at 1451 EDT, during normal full power operations, Unit 1 automatically tripped due to the Thermal Margin/ Low Pressure trip setpoint being exceeded. The trip was uncomplicated and all CEAs (control element assembly) fully inserted when the reactor was tripped. Main Steam Safety valves lifted momentarily post trip and reseated. No automatic safety system actuations were required and none occurred. The cause and details of the automatic trip are under investigation. The plant is stable in Mode 3 at normal operating temperature and pressure. RCS Heat Removal is being maintained with Main Feedwater and Atmospheric Dump Valves in operation. The operation of the Steam Bypass Control System is under review by Engineering. The Offsite power grid is available and stable. The licensee has notified the NRC Resident Inspector and there was no impact on Unit 2.
ENS 483888 October 2012 02:37:00Saint LucieNRC Region 2CEOn October 7, 2012, with Unit 2 in a defueled condition, a differential current lockout occurred on the 2B3 4.16kV essential bus, causing a deenergization of the 2B3 4.16kV essential bus. At the time of the event, the 2B Emergency Diesel Generator (EDG) was loaded to the essential bus. Due to the differential current lockout, all bus loads were lost and the 2B EDG output breaker feeding the essential bus opened and the 2B EDG transferred to emergency mode. The 2A EDG is operable and in standby. All equipment responded as expected. The plant is currently being maintained in a defueled condition. Decay heat removal is being supplied by the 2A Fuel Pool Cooling train. The cause of the differential current lockout of the 2B3 4.16kv bus is under investigation. This event is reportable pursuant to 10CFR 50.72(b)(3)(iv)(A). The licensee notified the NRC Resident Inspector.
ENS 483693 October 2012 12:15:00Saint LucieNRC Region 2CEOn October 3, 2012, with Unit 2 in a defueled condition, a failure occurred on the 2B Startup Transformer, causing an undervoltage condition on an essential bus and resulted in the automatic start and loading of the 2B Emergency Diesel Generator (EDG). Prior to the event, the 2B EDG was available and not required by Technical Specifications; however, the 2B EDG was inoperable. Additionally, the 2A EDG is available. All equipment responded as expected. Currently maintaining the plant in a defueled condition. Decay heat removal is being supplied by the 2A Fuel Pool Cooling train and was never interrupted. There was no impact on the Shutdown Safety Assessment. This event is reportable pursuant to 10CFR50.72(b)(3)(iv)(A). Due to common high side feed, the loss of the 2B Startup Transformer resulted in the loss of the 1B Startup Transformer. Prior to the event, the 1A EDG was out of service for maintenance. As a result, Unit 1 entered Technical Specification 3.8.1.1 Action C. due to the loss of one offsite AC circuit and one diesel generator inoperable. The licensee has notified the NRC Resident Inspector.
ENS 4830614 September 2012 11:20:00Saint LucieNRC Region 2CEA non-licensed contract employee supervisor had a confirmed positive for alcohol during a random fitness-for-duty test. The employee's access to the plant has been terminated. Contact the Headquarters Operations Officer for additional details. The licensee has notified the NRC Resident Inspector.
ENS 479872 June 2012 21:52:00Saint LucieNRC Region 2CEAt 1935 during normal full power operations, Unit 1 automatically tripped due to a loss of load caused by an instantaneous failure of the turbine control system. The trip was uncomplicated and all CEAs (control rods) fully inserted when the reactor was tripped. No automatic safety system actuations were required and none occurred. The cause and details of the turbine control system failure are under investigation. The plant is stable in Mode 3 at normal operating temperature and pressure. RCS Heat Removal is being maintained with Main Feedwater and Steam Bypass Control Systems with condenser vacuum. The offsite power grid is available and stable. This non-emergency notification is being made pursuant to 10 CFR 50.72(b)(2)(iv)(B) due to RPS actuation with the reactor critical. The licensee notified the NRC Resident Inspector.
ENS 4791511 May 2012 07:07:00Saint LucieNRC Region 2CEOn May 11, 2012, a failure of the High Power Feed Regulating Valve FCV-9011 resulted in '2A' S/G water level lowering. Manual operator control of the Main Feed Regulating system was unsuccessful in stabilizing S/G water level. '2A' S/G level lowered to the procedurally required manual reactor trip criteria. The crew inserted a manual trip. All CEAs fully inserted into the core. Following the trip, Auxiliary Feedwater actuated as designed and decay heat removal was via Auxiliary Feedwater and Steam Bypass to the Main Condenser. All equipment operated as expected. Currently, Unit 2 is maintaining pressurizer pressure at 2250 psia, temperature at 532 degrees F on Main Feedwater (using Low Power Feed Regulating Valves LCV-9005/9006) and Steam Bypass Control. 'Unit 1 was unaffected and remains in Mode 1 at 29% power. This event is reportable pursuant to 10CFR50.72(b)(2)(iv)(B) for the Reactor Trip, as well as 10CFR50.72(b)(3)(iv)(A) for specified system actuation (Auxiliary Feedwater). The licensee has notified the NRC Resident Inspector.
ENS 4779331 March 2012 03:42:00Saint LucieNRC Region 2CEAt 0022 (EDT) on 03/31/12 while maintaining power stable at 10% for Steam Bypass Control System testing, Unit 1 was manually tripped due to an uncontrolled cooldown caused by PCV-8802 (Steam Bypass Control Valve) unexpectedly opening. Following the trip, PCV-8802 closed and the secondary was isolated by closing the Main Steam Isolation Valves per Standard Post Trip Actions. Following isolation of the steam demand, the trip was uncomplicated with all CEAs fully inserted. No automatic safety system actuations were required and none occurred. The cause of the unexpected opening of the Steam Bypass Control System valve is under investigation. The plant is stable in Mode 3 at normal operating temperature and pressure. RCS Heat Removal is being maintained with Auxiliary Feedwater and Atmospheric Dump Valves. The Offsite power grid is available and stable. This non-emergency notification is being made pursuant to 10 CFR 50.72(b)(2)(iv)(B) due to manual RPS actuation with the reactor at power. The RCS cooled down from 532 degree to 515 degrees over a period of approximately 2 minutes and 40 seconds. The reactor was manually tripped when RCS temperature reached 515 degrees and the lowest RCS temperature observed after the trip was 505 degrees. The licensee has notified the NRC Resident Inspector.
ENS 4775219 March 2012 02:24:00Saint LucieNRC Region 2CEAt 2336 EDT, during performance at Low Power Physics Testing, Unit 1 was manually tripped while the reactor was critical at less than 1% power due to Control Element Assembly (CEA) Regulating Group #3 exhibiting anomalous behavior (continued to insert with no operator action). The trip was uncomplicated and all CEAs fully inserted when the reactor was tripped. No automatic safety system actuations were required and none occurred. The cause for the abnormal CEA performance is under investigation. The plant is stable in Mode 3 at normal operating temperature and pressure. RCS Heat Removal is being maintained with Auxiliary Feedwater and Atmospheric Dump Valves. The offsite power grid is available and stable. This non-emergency notification is being made pursuant to 10 CFR 50.72(b)(2)(iv)(B) due to manual RPS actuation with the reactor critical The NRC Resident Inspector has been informed.
ENS 4765710 February 2012 07:31:00Saint LucieNRC Region 2CEOn February 10, 2012, with Unit 1 in Mode 5, while performing scheduled maintenance, a technician inadvertently made contact with a component that caused an undervoltage condition on an essential bus, resulting in the automatic start and loading of the 1B Emergency Diesel Generator (EDG). Prior to the event the 1B EDG was inoperable and not required by Technical Specifications; however, the 1B EDG was available. All equipment responded as expected. Currently maintaining the plant in Mode 5. Decay heat removal is being supplied by the 1A Shutdown Cooling train and was never interrupted. There was no impact on the Shutdown Safety Assessment. Unit 2 was unaffected and remains in Mode 1 at 100% power. This event is reportable pursuant to 10CFR 50.72(b)(3)(iv(A). The licensee notified the NRC Resident Inspector.
ENS 4758310 January 2012 14:44:00Saint LucieNRC Region 2CEFlorida Department of Environmental Protection was notified at 1130 EST on 01/10/12 that Stormwater Basin Discharge for the month of December exceeded the total monthly allowable limit for Total Suspended Solids (TSS). The Monthly Average for TSS limit is 34 mg/l. The limit per the St. Lucie Plant DEP Discharge Permit is 30 mg/l for the month. This limit was exceeded due to rainfall and required pumping prior to an additional sample point. While the basin was pumped, the Daily Maximum Limit of 100 ppm was not exceeded. The FDEP representative concurred that there was no threat to the public as a result of this discharge. This non-emergency notification is being made pursuant to 10 CFR 50.72(b)(2)(xi) due to the Offsite Notification to the Florida Department of Environmental Protection. The licensee informed the NRC Resident Inspector.
ENS 4754622 December 2011 09:56:00Saint LucieNRC Region 2CE

On December 22, 2011, at 1000 EST, due to pre-planned refueling outage maintenance, the Control Room Emergency Ventilation system on St. Lucie Unit 1 is inoperable. The Unit 1 Control Room Emergency Ventilation system provides filtered air to the Technical Support Center (TSC) ventilation system, therefore, the TSC ventilation system has been rendered unavailable during the course of the work activities. The Control Room Emergency Ventilation system is expected to be returned to service in 38 hours, and TSC filtered ventilation restored. If an emergency is declared requiring TSC activation during this period, the TSC will be staffed and activated using existing emergency planning procedures. Should the TSC become uninhabitable, the TSC staff will relocate to an alternate TSC location in accordance with applicable site procedures. This notification is being made in accordance with 10CFR 50.72 (b)(3)(xiii) due to the potential loss of an emergency response facility (ERF). An update will be provided once the Control Room Emergency Ventilation system has been restored to normal operation. The NRC Resident Inspector has been notified. Unit 1 is currently de-fueled.

  • * * UPDATE FROM CHUCK MONTANA TO VINCE KLCO AT 0459 EST ON 12/23/2011* * *

Update 12/23/2011, 0418 EST: The U1 Control Room Emergency Ventilation has been restored to operable (status) and the TSC filtered ventilation has been restored (to operable status). The licensee notified the NRC Resident Inspector. Notified the R2DO (McCoy).