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 Entered dateSiteRegionReactor typeEvent description
ENS 5621610 November 2022 10:12:00CookNRC Region 3Westinghouse PWR 4-LoopThe following information was provided by the licensee via email: At 0744 EST on November 10, 2022, DC Cook Unit 2 tripped automatically on high-high level of number 23 steam generator (SG). The reason for the high-high level in SG 23 is under investigation. This notification is being made in accordance with 10 CFR 50.72(b)(2)(iv)(B), Reactor Protection System (RPS) actuation as a four (4) hour report, and under 10 CFR 50.72(b)(3)(iv)(A), specified system actuation of the Auxiliary Feedwater System, as an eight (8) hour report. The DC Cook NRC Resident Inspector has been notified. Unit 2 is being supplied by offsite power. All control rods fully inserted. All Auxiliary Feedwater Pumps started properly. Decay heat is being removed via the Steam Dump System. Preliminary evaluation indicates all plant systems functioned normally following the reactor trip. DC Cook Unit 2 remains stable in Mode 3 while conducting the post trip review. No radioactive release is in progress as a result of this event.
ENS 5617724 October 2022 11:40:00CatawbaNRC Region 2Westinghouse PWR 4-LoopThe following information was provided by the licensee via email: On 10/24/2022 at 0857 EDT, with Unit 2 in Mode 1 at 7 percent power, the reactor was manually tripped due to a 2B train main feedwater pump trip. The trip was not complex, with all systems responding normally post-trip. The auxiliary feedwater (AFW) system started automatically as expected. Operations responded and stabilized the plant. Decay heat is being removed by the steam generators and discharging to the condenser. Unit 1 is not affected. Due to the Reactor Protection System actuation while critical, this event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B). The automatic start of the auxiliary feedwater system is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(iv)(A). There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.
ENS 5617623 October 2022 19:05:00Diablo CanyonNRC Region 4Westinghouse PWR 4-LoopThe following information was provided by the licensee via email: At 0830 PDT on 10/23/2022, during routine outage inspections on Unit 2, it was determined that the RCS Pressure Boundary did not meet ASME Section XI acceptance criteria on a 2-inch vacuum refill connection line. This event is being reported pursuant to 10 CFR 50.72(b)(3)(ii)(A). There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.
ENS 5617220 October 2022 20:24:00CatawbaNRC Region 2Westinghouse PWR 4-LoopThe following information was provided by the licensee via email: At 1446 EDT on October 20, 2022, an individual was transported offsite for treatment at an offsite medical facility. Due to the nature of the medical condition, the individual was not thoroughly surveyed prior to being transported offsite. Follow-up surveys performed by radiation protection technicians identified no contamination of the worker or of the ambulance and response personnel. This is an eight-hour notification, non-emergency for the transportation of a contaminated person offsite. This event is reportable in accordance with 10 CFR 50.72(b)(3)(xii). The NRC Resident Inspector has been notified.
ENS 5616515 October 2022 15:46:00CatawbaNRC Region 2Westinghouse PWR 4-LoopThe following information was provided by the licensee via email: On 10/15/2022 at 1159 (EDT), during the Catawba Nuclear Station Unit 2 refueling outage, it was determined that the results of a planned surface examination Liquid Penetrant test (PT) performed on a previous overlay repair on nozzle number 74 of the reactor vessel closure head (RVCH) did not meet applicable acceptance standards. The examination was being performed to meet the requirements of Relief Request RA-21-0144, 'Proposed Alternative to Use Reactor Vessel Head Penetration Embedded Flaw Repair for Life of Plant'. The penetration required repairs for the discovered indications. The repairs have been completed in accordance with the ASME Code of Record prior to returning the vessel head to service. This event is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(ii)(A). There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified. The original indication that led to the overlay repair was discovered in April 2021, during ultrasonic testing and reported to the NRC and assigned EN55201.
ENS 561537 October 2022 08:35:00BraidwoodNRC Region 3Westinghouse PWR 4-LoopThe following information was provided by the licensee via fax: Control Rod Drive Mechanism (CRDM) penetration 69 degraded. At 0119 (CDT) on October 7, 2022, it was determined that the CRDM penetration 69 was degraded because examination identified unacceptable indications in accordance with ASME Code Case N-729-6. Therefore, this event is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(ii)(A). There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.
ENS 5611719 September 2022 12:49:00South TexasNRC Region 4Westinghouse PWR 4-LoopThe following information was provided by the licensee via email: On September 19, 2022, a non-licensed supervisor violated the station's FFD policy. The employee's unescorted access at South Texas has been terminated. This event was determined to be reportable under 10 CFR 26.719(b)(2)(ii). The NRC resident inspector has been notified.
ENS 5611417 September 2022 13:06:00VogtleNRC Region 2Westinghouse PWR 4-LoopThe following information was provided by Southern Nuclear Company via email: At 2257 EDT on 09/16/2022, it was determined that there was a programmatic vulnerability of the Fleet FFD program. Specifically, it was determined that some individuals were not placed into the follow-up pool for additional screening when required by the program. All identified personnel were in the random FFD pool, and were subject to the behavioral observation program. This is reportable in accordance with 10CFR26.719(b)(4) for all Units and 10CFR26.417(b)(1) for Vogtle Units 3 and 4. The NRC Resident Inspectors have been notified. See EN#s 56112, 56113, and 56115.
ENS 560947 September 2022 15:06:00South TexasNRC Region 4Westinghouse PWR 4-LoopThe following information was provided by the licensee via fax: Auxiliary Feedwater Pump #12 actuation and isolation of the Steam Generator Blowdown for 'A', 'B' and 'C' Steam Generators. Per 10 CFR 50.73(a)(1), the telephone notification is made under 10 CFR 50.73(a)(2)(iv)(A) for an invalid actuation. On 7/28/2022 at 1705 CDT, the Unit 1 Control Room received alarm SPQD0183 'SG LO-LO LVL TRN B ACT' and actuation of the Auxiliary Feedwater Pump #12 and isolation of the Steam Generator Blowdown for 'A', 'B' and 'D' Steam Generators. This event was classified as an unplanned entry into Technical Specification Shutdown LCO equal to or less than 24 hours 'Simple Restoration', due to the availability of CRMP. This alarm occurred several times and with each occurrence the alarm was short lived (1 second or less). Operations placed Auxiliary Feedwater Pump #12 in the Pull-To-Lock position to prevent starting of the pump with each alarm occurrence. During troubleshooting it was determined that SSPS Logic 'R' train was generating the intermittent alarm condition. A Logic board and a Safeguard Driver board were replaced which was identified as the possible cause. Operations performed applicable sections of the Logic test to ensure SSPS 'R' train operable. The event had no effects/consequences on the unit. The Logic board and Safeguard Driver board in SSPS 'R' train were both replaced as the possible causes, and therefore both boards were sent to Westinghouse to determine which board was at fault. The NRC Resident Inspector has been notified.
ENS 560916 September 2022 03:00:00Comanche PeakNRC Region 4Westinghouse PWR 4-LoopThe following information was provided by the licensee via email: At 2345 CDT, Unit 1 Reactor tripped due to a turbine trip. All auxiliary feedwater pumps started due to steam generator Lo Lo levels. Unit 1 is being maintained in Hot Standby (Mode 3) in accordance with Integrated Plant Operating Procedure IPO-007A. The Emergency Response Guideline procedure has been exited. Decay heat is being rejected to the main condenser via steam dump valves. The cause of the Turbine Trip is currently under investigation. The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance: NRC Resident Inspector has been notified. Unit 2 is unaffected by this event.
ENS 5607628 August 2022 15:41:00CookNRC Region 3Westinghouse PWR 4-LoopThe following information was provided by the licensee via fax or email: On August 28, 2022 at 1348 EDT, DC Cook Unit 1 reactor automatically tripped due to a trip of the #13 Reactor Coolant Pump. This notification is being made in accordance with 10 CFR 50.72(b)(2)(iv)(B), Reactor Protection System (RPS) actuation as a four (4) hour report, and under 10 CFR 50.72(b)(3)(iv)(A), specified system actuation of the Auxiliary Feedwater System, as an eight (8) hour report. The DC Cook Resident NRC Inspector has been notified. Unit 1 is being supplied by offsite power. All control rods fully inserted. All Auxiliary Feedwater Pumps started properly. Decay heat is being removed via the Steam Dump System. Preliminary evaluation indicates all plant systems functioned normally following the Reactor Trip. DC Cook Unit 1 remains stable in Mode 3 while conducting the Post Trip Review. No radioactive release is in progress as a result of this event. Unit 2 remains stable at 100% power / Mode 1.
ENS 5606020 August 2022 12:33:00BraidwoodNRC Region 3Westinghouse PWR 4-LoopA non-licensed, non-supervisory employee had a confirmed positive for alcohol during a for-cause fitness-for-duty test. Subsequent investigation revealed the presence of alcohol within the Protected Area. The employee's access to the plant has been terminated.
ENS 5604716 August 2022 14:09:00Wolf CreekNRC Region 4Westinghouse PWR 4-LoopThe following information was provided by the licensee via email: This 60-day telephone notification is being made under 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 the auxiliary feedwater system. At 1949 Central Daylight Time (CDT), on 7/22/22, an invalid actuation of the auxiliary feedwater system occurred due to human error. At the time of the event, Wolf Creek Generating Station was coming out of a forced outage. Plant conditions were 47 percent power with operators increasing power approximately 10 percent per hour. At this power level there was one main feedwater pump in service and Operations was performing the procedure to place the second main feedwater pump into service. A control room operator was verifying that the control oil switches were not tripped for the main feedwater pumps by verifying the bulbs for both the 'A' and 'B' trains were not lit. To verify the unlit bulbs were not burnt out, the operator was pushing the lamp test buttons. The operator successfully verified the 'A' train, but on the 'B' train the operator mistakenly pushed the bi-stable which is located directly above the bulb rather than the lamp test button. This bi-stable is the low oil pressure switch for the 'A' main feedwater pump. Because the second feedwater pump was not running yet, this caused a 'two out of two' signal for low oil pressure and caused an auxiliary feedwater system actuation. The auxiliary feedwater system responded correctly and was returned to standby condition. The Senior Resident Inspector has been notified.
ENS 5604616 August 2022 12:33:00CookNRC Region 3Westinghouse PWR 4-LoopA licensed employee had a confirmed positive for alcohol during a random fitness-for-duty test. The employee's access to the plant has been terminated.
ENS 5601323 July 2022 02:52:00Wolf CreekNRC Region 4Westinghouse PWR 4-Loop

The following information was provided by the licensee via email: At 1949 CDT, while operating in Mode 1 at 46 percent power, an Auxiliary Feedwater actuation signal resulted from a human performance error while performing SYS AE-121 to place a second main feedwater pump in service. All systems responded correctly and were restored to standby condition. The Unit remained in Mode 1, at 47 percent power following the actuation. This event is being reported in accordance with 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of the Auxiliary Feedwater System. The Senior NRC Resident Inspector has been informed.

  • * * RETRACTION ON 8/16/22 AT 1406 EDT FROM JASON KNUST TO BRIAN P. SMITH * * *

Wolf Creek is retracting the original notification (EN# 56013) of a valid actuation and has recategorized this as a 60-day optional (see EN #56047). Notified R4DO (Werner)

ENS 5600518 July 2022 21:17:00Wolf CreekNRC Region 4Westinghouse PWR 4-Loop

The following information was provided by the licensee via email: While operating at 100 percent reactor power, the Control Room received indications of a feedwater transient, and indications of decreasing level on Steam Generator `B.' Reactor Trip occurred approximately 30 seconds after initial indications of transient at 1803 CDT on 7/18/22. All Safety Related Equipment responded as expected, including actuation of Auxiliary Feedwater. Control Room responded properly and progressed through Emergency Operating Procedures. The Unit is Stable in Mode 3. The NRC Senior Resident Inspector has been notified. The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance: The plant is in a normal post-trip electrical line-up. Wolf Creek intends to make a press release.

  • * * UPDATE FROM JOSHUA TURNER TO DONALD NORWOOD AT 1538 EDT ON 7/19/2022 * * *

The original event notification inadvertently indicated that a media / press release would be provided. However, no media / press release is planned. Notified R4DO (Gaddy).

ENS 5599615 July 2022 17:34:00BraidwoodNRC Region 3Westinghouse PWR 4-LoopThe following information was provided by the licensee via email: At 1035 CDT on 7/15/2022, it was determined that a non-licensed supervisor tested positive in accordance with the fitness-for-duty testing program. The individual's authorization for site access has been terminated. The NRC Resident Inspector has been notified.
ENS 5598912 July 2022 13:22:00SeabrookNRC Region 1Westinghouse PWR 4-LoopThe following information was provided by the licensee via fax or email: At 1051 EDT on July 12, 2022, Seabrook Station received report of inadvertent siren activation. Local authorities have been contacted to apprise them of inadvertent activation of sirens. No press release is planned at this time. This event is being reported pursuant to 10 CFR 50.72(b)(2)(xi). The NRC Resident Inspector has been notified. The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance: The inadvertent activation involved one group of nine (9) sirens in the Seabrook Beach area. The cause of the activation is under investigation.
ENS 5597230 June 2022 14:21:00CallawayNRC Region 4Westinghouse PWR 4-LoopThe following information was provided by the licensee via phone and email: This non-emergency notification is being made pursuant to the provisions of 10 CFR 50.73(a)(1) to report the occurrence of an invalid automatic actuation satisfying the reporting criterion of 10 CFR 50.73(a)(2)(iv)(A), specifically for the actuation of one train of the Essential Service Water (ESW) system that occurred on May 1, 2022. On May 1, 2022, with the plant shut down and the core offloaded, control room personnel were performing a fast power transfer from Engineered Safety Feature (ESF) transformer XNB02 to ESF transformer XNB01. In anticipation of this activity, the `B' load shedder and emergency load sequencer (LSELS) had been removed from service. Also, at the time, a portion of the `A' ESW train was isolated to support performance of a local leak rate test (LLRT) of a containment isolation valve in the affected portion of `A' ESW train piping. Service Water was supplying cooling water flow to `A' train loads (in lieu of ESW cooling water). When the power transfer was performed, an unexpected automatic start of the `A' ESW pump, along with some associated, automatic valve repositioning, occurred. The actuation occurred due to inadvertent satisfaction of automatic start logic for the ESW pump. The logic is intended to detect loss of ESW flow when the opposite train LSELS isolates Service Water during an undervoltage condition on a safety bus. The flow transmitter involved in the actuation is situated in a portion of the ESW piping that was isolated for the LLRT. The low-flow signal from the transmitter was consequently not reflective of low cooling water flow to plant loads in light of the fact that cooling water flow was being supplied to plant loads and the transmitter was locally isolated. In regard to the ESW train actuation, therefore, although the undervoltage signal was considered a valid signal due to the voltage drop caused by the fast transfer activity, the low-flow signal from the noted transmitter was considered to be invalid. For this invalid actuation, it was concluded that the actuation was not part of a pre-planned sequence, that the affected system was not properly removed from service during the occurrence, and that the safety function had not already been performed relative to the occurrence. (The) NRC Resident Inspector has been notified and an email of this report has been sent to hoo.hoc@nrc.gov.
ENS 5595522 June 2022 02:26:00McGuireNRC Region 2Westinghouse PWR 4-LoopThe following information was provided by the licensee via email: At 2240 on 06/21/2022, it was discovered that both required trains of Control Room Ventilation and Control Area Chilled Water System were simultaneously inoperable; therefore, this condition is being reported as an eight-hour, nonemergency notification per 10 CFR 50.72(b)(3)(v)(d). There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified. The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance: The 'B' train was restored at 2315.
ENS 5591827 May 2022 22:53:00South TexasNRC Region 4Westinghouse PWR 4-LoopThe following information was provided by the licensee via email: On 5/25/2022 at 1354 (CDT), during the replacement of two detectors, a halon actuation occurred which resulted in an unintentional release of approximately 384 pounds of halon gas into an enclosed room in the Unit 1 Electrical Auxiliary Building. There was no impact to plant operations or plant personnel. The room was verified by station Safety Personnel to be safe for normal access. On 5/27/2022 at 2038 (CDT), Region 12 (Houston) of the Texas Commission of Environmental Quality (TCEQ) was notified of an event which met the requirements of "Emission Event" for the TCEQ of a halon release that exceeded the reportable quantity threshold of 100 pounds in a 24 hour period. The halon discharge was contained within the site protected area. Therefore, this event is not significant with respect to the health and safety of the public. The licensee has notified the NRC Resident Inspector.
ENS 5591024 May 2022 06:49:00CookNRC Region 3Westinghouse PWR 4-LoopThe following information was provided by the licensee via email: On May 24, 2022, at 0414 EDT, while rolling the Unit 1 main turbine during the Unit 1 Cycle 31 refueling outage, the Unit 1 main turbine experienced high vibrations and the main turbine was manually tripped with reactor power at 12 percent. Main turbine vibrations persisted and the reactor was manually tripped, Main Steam Stop Valves were closed, and main condenser vacuum was broken. This notification is being made in accordance with 10 CFR 50.72(b)(2)(iv)(B), Reactor Protection System (RPS) actuation as a four (4) hour report, and under 10 CFR 50.72(b)(3)(iv)(A), specified system actuation of the Auxiliary Feedwater System, as an eight (8) hour report. The DC Cook Resident NRC Inspector has been notified. Unit 1 is being supplied by offsite power. All control rods fully inserted. Both Motor Driven Auxiliary Feedwater Pumps started properly. Decay heat is being removed via Steam Generator Power Operated Relief Valves. Preliminary evaluation indicates all plant systems functioned normally following the Reactor Trip. DC Cook Unit 1 remains stable in Mode 3 while conducting the Post Trip Review. No radioactive release is in progress as a result of this event.
ENS 5589311 May 2022 18:12:00MillstoneNRC Region 1Westinghouse PWR 4-LoopThe following information was provided by the licensee via email: A licensed operator had a confirmed positive for alcohol during a follow-up fitness-for-duty test. The employee's access to the plant is on hold in accordance with the licensee's fitness-for-duty policy. The licensee notified the NRC Resident Inspector.
ENS 558753 May 2022 18:44:00VogtleNRC Region 2Westinghouse PWR 4-LoopThe following information was provided by the licensee via email: At 1541 EDT on May 3, 2022, with Unit 1 in Mode 1 at 100 power, the reactor was manually tripped due to the loss of one of the main feed pumps. The trip was not complex, with all systems responding normally post-trip. No equipment was inoperable prior to the event that contributed to the event or adversely impacted plant response to the scram. Operations responded and stabilized the plant. Decay heat is being removed by Auxiliary Feedwater through the steam dumps to the condenser. Unit 2 is not affected. An automatic actuation of the Auxiliary Feedwater System (AFW) also occurred. The AFW auto-start is an expected response from the reactor trip. Due to the Reactor Protection System actuation while critical, this event is being reported as a four-hour, nonemergency notification per 10 CFR 50.72(b)(2)(iv)(B). This event is also being reported as an eight-hour, nonemergency notification per 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of the Auxiliary Feedwater System. There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.
ENS 5586729 April 2022 07:04:00SequoyahNRC Region 2Westinghouse PWR 4-LoopThe following information was provided by the licensee via fax: On 4/28/2022, at 2338 EDT, Sequoyah received an unexpected alarm for seismological recording initiated. At 2341 EDT, unexpected alarm 1/2 Safe Shutdown Earthquake response spectra exceeded was received. The National Earthquake Information Center was contacted to confirm there was no seismic activity, and this was also confirmed on the U.S. Geological Survey website. The alarms were determined to be invalid, and they occurred due to a failure in the seismic monitoring system. This failure results in loss of ability to assess the Emergency Action Level for Initiating Condition HU2 `Seismic event greater than Operating Basis Earthquake (OBE) levels' per procedure EPIP-1, `Emergency Plan Classification Matrix.' If an actual seismic event had occurred, HU2 could not be assessed. However, compensatory measures have been implemented and include assessing OBE criteria based on alternative criteria contained in procedure AOP-N.05, `Earthquake,' which provides conservative guidance when seismic instruments are unavailable. This is an eight-hour, non-emergency notification for an event resulting in a major loss of Emergency Assessment Capability. This event is reportable in accordance with 10 CFR 50.72(b)(3)(xiii). There is no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified." The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance: The faulty detector was removed from service, so the remaining detector provides conservative detection as the only source to make-up the logic for a seismological alarm.
ENS 5586629 April 2022 00:19:00SequoyahNRC Region 2Westinghouse PWR 4-Loop

The following is a summary of information provided by the licensee via telephone: On 04/28/22, at 2355 EDT, with both Sequoyah Unit 1 and 2 in Mode-1, 100 percent, a Notice of Unusual Event was declared due to receiving two seismic alarms and security feeling ground movement. Additionally, security in a tower heard an explosion. Both units remain in Mode-1, 100 percent and they are investigating the validity of the seismic alarms before proceeding with the Abnormal Operating Procedure required shutdown. The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance: The licensee will notify the NRC Resident Inspector. The state of Tennessee and the Tennessee Valley Authority were notified. Notified DHS SWO, FEMA Operations Center, CISA Central, FEMA NWC (email), DHS NRCC THD Desk(email), and DHS Nuclear SSA (email).

  • * * UPDATE ON 04/29/2022 AT 0410 EDT FROM BRIAN KLEIN TO OSSY FONT * * *

The following is a summary of information provided by the licensee via telephone: On 4/29/22, at 0406 EDT, Sequoyah Unit 1 and Unit 2 terminated the Notice of Unusual Event. The Civil Engineers determined that the alarms were due to a failed seismic indicator channel. Through interviews, only one security officer felt ground movement for a couple of seconds and heard a faint rumbling sound. The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance: The licensee will notify the NRC Resident Inspector. The state of Tennessee and the Tennessee Valley Authority were notified. Notified R2DO (Miller), NRR EO (Miller), and IR MOC (Gott) via email. Additionally, notified DHS SWO, FEMA Operations Center, CISA Central, FEMA NWC (email), DHS NRCC THD Desk(email), and DHS Nuclear SSA (email).

  • * * RETRACTION ON 05/02/2022 AT 2118 EDT FROM SCOTT SEAL TO LLOYD DESOTELL * * *

The following information was provided by the licensee via email: SQN (Sequoyah Nuclear Plant) is retracting the previous NOUE (Notice of Unusual Event) declaration made on 4/28/22 at 2355 (EDT) based on Emergency Action Level HU2 for a seismic event greater than Operating Basis Earthquake levels. Following the declaration of the NOUE, the station reviewed all available indications and determined that a seismic event had not occurred. The instrumentation failure was documented under Event Notification #55867. Notified R2DO (Miller), and IR MOC (Gott), NRR EO (Miller) via email.

ENS 5585723 April 2022 16:27:00ByronNRC Region 3Westinghouse PWR 4-Loop

The following information was provided by the licensee via email: At 0854 (CDT) on April 23, 2022, while performing volumetric inspections required by ASME Code Case N-729-6, a rejectable indication on Reactor Vessel Head Penetration 75 Core Exit Thermocouple (CETC) was identified. The indication is located inboard of the J-groove weld and is OD-initiated (outer diameter - initiated). This event is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(ii)(A). There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified. The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance: The repair is scheduled during the refueling outage.

  • * * UPDATE ON 04/29/22 AT 1112 EDT FROM BRYAN LYKKEBAK TO OSSY FONT * * *

The following information was provided by the licensee via telephone and email: The rejectable indication on Reactor Vessel Head Penetration 75 Core Exit Thermocouple (CETC) initiated on the outside diameter (OD) of the nozzle in an area that was not surface stress mitigated (peened). The indication was found to be acceptable for continued operation under CFR and ASME requirements and will not be repaired during this outage. The licensee notified the NRC Resident Inspector. Notified R3DO (Ziolkowski).

ENS 5585623 April 2022 06:04:00CatawbaNRC Region 2Westinghouse PWR 4-LoopThe following information was provided by the licensee via fax or email: On April 23, 2022, at 0224 (EDT) hours, with Unit 2 in Mode 1 at 100 percent power, two control rods dropped during control rod testing resulting in misalignment, which required a manual reactor trip in accordance with plant procedure. All safety systems functioned as expected. The Auxiliary Feedwater system actuated as designed to provide makeup flow to the steam generators. Operations responded and stabilized the plant. Decay heat is being removed by the steam generator power operated relief valves. Due to the Reactor Protection System actuation while critical, this event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B). The automatic start of the Auxiliary Feedwater system is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(iv)(A). The cause of the dropped rods is being investigated. Unit 1 is not affected. There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified." The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance: Electrical power is in normal off-site arrangement. All emergency electrical supplies are available.
ENS 5584819 April 2022 18:02:00CallawayNRC Region 4Westinghouse PWR 4-LoopThe following information was provided by the licensee via email: A contract employee supervisor had a confirmed positive for illegal drugs during a random fitness-for-duty test. The employee's access to the plant has been terminated. The licensee notified the NRC Resident Inspector.
ENS 5580428 March 2022 14:55:00SeabrookNRC Region 1Westinghouse PWR 4-LoopA non-licensed employee possessed a prohibited substance (alcohol) within the Protected Area. The employee's access to the plant has been placed on hold pending results of an investigation. The NRC Resident Inspector has been notified.
ENS 557696 March 2022 00:55:00ByronNRC Region 3Westinghouse PWR 4-LoopThe following information was provided by the licensee: At 2115 CST on March 5, 2022 Byron Station Technical Support Center (TSC) emergency ventilation system supply fan belt failed. This failure affected the ability of the TSC ventilation system to maintain adequate radiological habitability in the event of an emergency with an airborne radiological release. All other capabilities of the TSC are unaffected by this condition. If an emergency was declared requiring TSC activation during this period, the TSC would be staffed and activated using existing emergency planning procedures. If the TSC becomes uninhabitable, the Station Emergency Director would relocate the TSC staff to an alternate TSC location in accordance with applicable procedures. This event is reportable in accordance with 10 CFR 50.72(b)(3)(xiii) because the discovered condition affected the functionality of an emergency response facility. The licensee notified the NRC resident inspector.
ENS 5575825 February 2022 16:10:00McGuireNRC Region 2Westinghouse PWR 4-LoopThe following information was provided by the licensee: On 2/25/22, at 1133 EDT, the Technical Support Center (TSC) high temperature alarm annunciated in the Control Room due to an equipment malfunction that resulted in an unplanned loss of the TSC for greater than seventy-five minutes. If an emergency had been declared requiring TSC activation during this period, the TSC would have been staffed and activated using existing emergency planning procedures. If relocation of the TSC had been necessary, the Emergency Coordinator would have relocated the TSC staff to an alternate location in accordance with applicable site procedures. This is an eight-hour, non-emergency notification for a loss of Emergency Assessment Capability. This event is reportable in accordance with 10 CFR 50.72(b)(3)(xiii) because the equipment malfunction affected the functionality of an emergency response facility. There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.
ENS 5574818 February 2022 08:35:00McGuireNRC Region 2Westinghouse PWR 4-LoopThe following information was provided by the licensee via telephone and email: On 2/18/2022, McGuire Nuclear Station Unit 2 experienced a turbine runback to 55 percent power. Based on concerns with unit stability, the reactor was manually tripped at 0459 (EST). All Auxiliary Feedwater pumps started on low steam generator level as required. The reactor trip was uncomplicated with all systems responding normally post trip. A feedwater isolation occurred as designed. Unit 1 was not affected. Due to the Reactor Protection System actuation while critical, actuation of the Turbine Driven Auxiliary Feedwater Pump and Motor Driven Auxiliary Feedwater pumps along with the Feedwater Isolation, this event is being reported as a four hour, nonemergency notification per 10 CFR 50.72(b)(2)(iv)(B) and an 8 hour nonemergency notification per 10 CFR 50.72(b)(3)(iv)(A). There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance: All control rods fully inserted. Decay heat is being removed via the condenser and normal feedwater. Unit 2 is in a normal shutdown electrical lineup.
ENS 5574216 February 2022 17:01:00SequoyahNRC Region 2Westinghouse PWR 4-LoopThe following information was provided by the licensee via fax or email: At 1128 EST on 2/16/2022, the SQN (Sequoyah Nuclear) Shift Manager was notified that TVA (Tennessee Valley Authority) attempted to notify Tennessee Emergency Management Agency (TEMA) regarding routine siren testing at 0750. TVA was unable to reach TEMA via telephone land line or the Emergency Communication and Notification System (ECNS). TEMA Watch Point staff were located at their back-up facility. TVA subsequently notified TEMA via cell phone that there were communication issues with the primary and backup notification methods. It was determined that the TEMA back-up facility was not able to receive incoming calls. At 0820, TEMA positioned personnel at their primary facility in order to respond to notifications. This restored primary and backup means of notifying the state because the primary facility was not affected by the communication issues. This event is reportable in accordance with 10 CFR 50.72(b)(3)(xiii) as a Major Loss of Offsite Communications Capability because it affected TVA's ability to notify the State of TN. The licensee has notified the NRC Resident Inspector.
ENS 5574116 February 2022 16:42:00Watts BarNRC Region 2Westinghouse PWR 4-LoopThe following information was provided by the licensee via fax or email: At 1159 EST, on 2/16/2022, the Watts Bar Nuclear, Shift Manager was notified that Tennessee Valley Authority (TVA) attempted to notify Tennessee Emergency Management Agency (TEMA) regarding routine siren testing at 0750 EST. TVA was unable to reach TEMA via telephone land line or the Emergency Communication and Notification System (ECNS). TEMA Watch Point staff were located at their back-up facility. TVA subsequently notified TEMA via cell phone that there were communication issues with the primary and backup notification methods. It was determined that the TEMA back-up facility was not able to receive incoming calls. At 0820 EST, TEMA positioned personnel at their primary facility in order to respond to notifications. This restored primary and backup means of notifying the state because the primary facility was not affected by the communication issues. This event is reportable in accordance with 10 CFR 50.72(b)(3)(xiii) as a Major Loss of Offsite Communications Capability because it affected TVA's ability to notify the State of TN. The licensee has notified the NRC Resident Inspector.
ENS 557221 February 2022 15:20:00BraidwoodNRC Region 3Westinghouse PWR 4-LoopThe following information was provided by the licensee via fax or email: At approximately 1025 CST on 2/1/22, the Braidwood Station Main Control Room was notified of a public notification of multiple inadvertent siren actuation affecting Braidwood Station in Will County, Illinois while testing sirens. This event is reportable per 10 CFR 50.72(b)(2)(xi), News release or notification of other Government Agencies. Braidwood NRC Resident has been notified.
ENS 557201 February 2022 11:42:00Diablo CanyonNRC Region 4Westinghouse PWR 4-LoopThe following information was provided by the licensee via fax or email: At 1350 PST on 01/31/2022, Pacific Gas and Electric determined that a non-licensed employee supervisor violated Diablo Canyon FFD policy and had a confirmed positive on a direct observed test. The employee's access to the plant has been terminated and permanent denial has been entered into PADS. The NRC Senior Resident Inspector has been notified.
ENS 556987 January 2022 16:29:00CallawayNRC Region 4Westinghouse PWR 4-LoopThe following information was provided by the licensee via email: At 1223 CST on January 7, 2022, Callaway Plant was in Mode 1 at approximately 100 percent power when a turbine trip / reactor trip occurred. All safety systems responded as expected with the exception of an indication issue with the 'B' Feedwater Isolation Valve, which was confirmed closed. A valid Feedwater Isolation Signal and Auxiliary Feedwater Actuation Signal were also received as a result of the reactor trip. The plant is being maintained stable in Mode 3. All control rods fully inserted from the reactor trip signal, and decay heat is being removed via the Auxiliary Feedwater and Steam Dump Systems. The NRC Senior Resident Inspector was notified. The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance: The plant is in a normal shutdown electrical lineup.
ENS 556947 January 2022 09:32:00Comanche PeakNRC Region 4Westinghouse PWR 4-LoopThe following information was provided by the licensee via fax or email: At 0120 (CST) on 01/07/2022, a partial loss of the 25KV Power Distribution System caused a loss of both the Primary and Backup Meteorological Towers at the Comanche Peak Nuclear Power Plant. This resulted in a loss of emergency assessment capability with regard to meteorological conditions. A backup diesel generator for the primary Meteorological Tower did not start due to a dead battery. After the battery issue was resolved, the diesel generator started but it subsequently tripped due to a loose fuse. The 25 KV Plant Support Power Loop feeds certain non-safety-related equipment and does not affect plant operation. Power was restored to both Meteorological Towers at 0305 (CST) on 01/07/2022 and proper operation was verified. The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance: The NRC Resident Inspector was notified.
ENS 556926 January 2022 12:29:00South TexasNRC Region 4Westinghouse PWR 4-LoopAt 0603 CST on 1/6/2022, with Unit 2 in Mode 1 at 100 percent power, the South Texas Project (STP) south switchyard electrical bus was de-energized momentarily and re-energized approximately 40 seconds later. Emergency Diesel Generators (EDG) 22 automatically started in response to loss of offsite power on Train B Engineered Safety Feature (ESF) Bus. This event is reportable under 10 CFR 50.72(b)(3)(iv)(A) as an event that resulted in the valid actuation of an emergency AC electrical power system (50.72(b)(3)(iv)(B)(8)). There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified. The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance: Unit 2 is in a 72 hour LCO per TS 3.8.1.1.A for the loss of one offsite power supply. The plant is in a normal electrical lineup. There was no impact on Unit 1.
ENS 556916 January 2022 11:06:00CookNRC Region 3Westinghouse PWR 4-Loop

The following information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance: On 01/06/22 at 1044 (EST), an Unusual Event was declared due to a Fire Detection Actuation in the Unit 1, auxiliary cable vault (EAL H.U 4.1). No fire was detected. Unit 1 and Unit 2 remain at 100 percent power. The Llcensee notified the NRC Resident Inspector, the state, and local authorities. Notified DHS SWO, FEMA Operations Center, CISA Central, FEMA NWC (email), and DHS Nuclear SSA (email).

  • * * UPDATE FROM DAN WALTER TO TOM KENDZIA AT 1452 (EST) ON 01/06/2022 * * *

At 1441 (EST), DC Cook Unit 1 terminated their notification of unusual event. The basis for termination was that the inspection identified no damage to cables or cable trays. The fire protection system is out of service for the auxiliary cable vault with compensatory measures in effect. The licensee has notified the state and local authorities and will notify the NRC Resident Inspector. Notified R3DO (Skokowski), IRD MOC (Grant), NRR EO (Felts), IR (Kennedy)(email), NRR (Veil)(email), R3 DRA (Shuaibi)(email), DHS SWO, FEMA Operations Center, CISA Central, FEMA NWC (email), DHS Nuclear SSA (email), and FEMA NRCC SASC (email).

ENS 5561024 November 2021 21:42:00Comanche PeakNRC Region 4Westinghouse PWR 4-LoopA violation occurred concerning Comanche's Peak's Fitness-For-Duty Program. Two empty mini-bottles of alcohol were discovered in a trash can within the protected area. The event has been documented in the corrective action program. The resident inspector has been notified.
ENS 5559018 November 2021 02:21:00Watts BarNRC Region 2Westinghouse PWR 4-LoopAt 2238 Eastern Standard Time (EST), on 11/17/2021, a Watts Bar Nuclear Plant contractor was transported offsite for treatment at an offsite medical facility. The offsite medical facility notified Watts Barr Nuclear Plant at 2310 EST that the individual had been declared deceased. The fatality was not work-related and the individual was inside of the Unit 1 Radiological Controlled Area. The individual was confirmed not to be contaminated. This is a four-hour notification, non-emergency for a notification of other government agency. This event is reportable in accordance with 10 CFR 50.72(b)(2)(xi). There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified. The licensee will notify OSHA.
ENS 5555028 October 2021 14:19:00Watts BarNRC Region 2Westinghouse PWR 4-LoopAt 1340 EDT on October 28, 2021, Watts Bar Nuclear Plant (WBN) Units 1 and 2 initiated voluntary communication to the State of Tennessee and local officials as part of the Nuclear Energy Institute (NEI) Groundwater Protection Initiative (GPI), after receiving analysis results for two on-site monitoring wells that indicated tritium activity above the GPI voluntary communication threshold. The suspected source, a permitted release line, has been isolated, and additional corrective actions are in progress. This condition did not exceed any NRC regulations or reporting criteria. This notification is being made solely as a four-hour, non-emergency notification for a Notification of Other Government Agency. This event is reportable in accordance with 10 CFR 50.72(b)(2)(xi). There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.
ENS 5554927 October 2021 20:39:00CatawbaNRC Region 2Westinghouse PWR 4-LoopAt 1429 EDT on October 27, 2021 with Unit 1 in Mode 6 at 0 percent power, the 1B Emergency Diesel Generator (EDG) Load Sequencer was actuated by a valid undervoltage condition on the 1B 4160V Essential Bus that occurred during 1B Sequencer calibration activities. Valid signals were sent to both the 1B EDG and Unit 1 Auxiliary Feedwater (CA) systems. Neither system automatically started as they were both removed from service for maintenance activities at the time. This event is being reported in accordance with 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of the 1B EDG and Unit 1 CA systems. There was no impact to the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.
ENS 5553921 October 2021 19:01:00Wolf CreekNRC Region 4Westinghouse PWR 4-LoopPlant cafeteria workers discovered that four gallons of cooking wine were included in a delivery to their inventory within the plant protected area. Security took possession of the sealed unopened containers and removed the alcohol from the protected area. The NRC Senior Resident Inspector has been informed.
ENS 5553821 October 2021 18:46:00CallawayNRC Region 4Westinghouse PWR 4-LoopA non-licensed 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. The NRC Resident Inspector has been notified.
ENS 5552615 October 2021 23:28:00Diablo CanyonNRC Region 4Westinghouse PWR 4-LoopOn October 15, 2021, at 1749 PDT with Diablo Canyon Power Plant Unit 2 operating at approximately 90 percent power, the reactor was manually tripped in accordance with plant procedures due to increasing water level in feedwater heater 2-5B. The reactor trip was uncomplicated and the Auxiliary Feedwater system started as expected. The plant is stable in Mode 3. This notification is being made in accordance the requirements of 10 CFR 50.72(b)(2)(iv)(B) as a manual actuation of the reactor protection system and 10 CFR 50.72(b)(3)(iv)(A) as an automatic actuation of a specified safety system. The cause of the increased feedwater level is under investigation. There was no impact to the health and safety of the public or plant personnel. The Resident Inspector has been notified.
ENS 5545813 September 2021 05:53:00McGuireNRC Region 2Westinghouse PWR 4-LoopAt 0011 EDT, with Unit 2 in Mode 5 (Cold Shutdown), actuations of the 2B Diesel Generator (DG) and the 2B Motor Driven Auxiliary Feedwater (AFW) Pump occurred during Engineered Safety Features Actuation Periodic Testing while resetting the 2B DG Load Sequencer. The 2B DG was running unloaded following test actuation, and during realignment from the test, a blackout condition was experienced when the breaker opened supplying the 4160 Volt Essential Power System 2ETB from the Standby Auxiliary Power Transformer SATB. Sequencer actuation closed the emergency breaker to 2ETB and loaded the 2B Motor Driven AFW Pump onto the bus. Steam supply valves to the Turbine Driven AFW Pump were open from the previous test configuration. This event is being reported in accordance with 10CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of the 2B DG and the 2B Motor Driven AFW Pump. There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.
ENS 5544031 August 2021 16:00:00South TexasNRC Region 4Westinghouse PWR 4-LoopOn August 4, 2021 a Licensed Reactor Operator violated the station's FFD policy. The employee's unescorted access to South Texas has been terminated. The event was determined to be reportable under 10 CFR 26.719(b)(2)(ii). The NRC Resident Inspector will be been notified.