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 Entered dateSiteRegionReactor typeEvent description
ENS 5722512 July 2024 19:37:00McGuireNRC Region 2Westinghouse PWR 4-LoopThe following information was provided by the licensee via email and phone: On July 12, 2024, at 1337 EDT, operations discovered that the technical support center (TSC) ventilation system was non-functional, which resulted in an unplanned loss of the TSC that could not be restored within 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 loss of the TSC ventilation system 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. The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance: The TSC ventilation system remains out-of-service at the time of the notification. In the event of an emergency, the licensee will use the alternate TSC facility per applicable site procedures until the ventilation system is restored. Repair of the ventilation system is being worked around-the-clock.
ENS 5680218 October 2023 15:18:00McGuireNRC Region 2Westinghouse PWR 4-LoopThe following information was provided by the licensee via email: On October 18, 2023, at 1116 (EDT), with Unit 1 in Mode 5, an automatic actuation of the 1A auxiliary feedwater motor driven pump occurred when an incorrect action resulted in an automatic start signal. 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. Feedwater is not needed for plant conditions, and the 1A auxiliary feedwater pump did not feed the steam generators. There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.
ENS 567145 September 2023 17:05:00McGuireNRC Region 2Westinghouse PWR 4-LoopThe following information was provided by the licensee via email: A non-licensed contract supervisor had a confirmed positive for illegal drugs during a random fitness-for-duty test. The contract supervisor's access to the plant has been terminated.
ENS 564512 April 2023 11:29:00McGuireNRC Region 2Westinghouse PWR 4-LoopThe following information was provided by the licensee via email: On April 2, 2023, at 0341 EDT, with Unit 2 in Mode 3 and the 2B main feedwater pump feeding the steam generators, the 2A main feedwater pump recirculation valve, 2CF-76, failed. Further, observation of the operating 2B main feedwater pump recirculation valve, 2CF-81, called into question its functionality. At 0352 EDT, operations manually started the auxiliary feedwater motor driven pumps to feed the stream generators to allow maintenance on the main feedwater system. The auxiliary feedwater motor driven pumps started as designed. Flow to the steam generator was not adversely impacted during this sequence. 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. There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.
ENS 5636616 February 2023 11:33:00McGuireNRC Region 2Westinghouse PWR 4-LoopThe following information was provided by the licensee via email: On February 16, 2023 at 0859 EST, a contract worker at McGuire was transported off-site for treatment at an off-site medical facility. Upon arrival at the off-site medical facility, medical personnel declared the individual deceased at 0915 EST. The fatality was not work-related and the individual was inside the Radiologically Controlled Area. An on-site survey confirmed that neither the individual nor the individual's clothing were contaminated. A notification will be made to the Occupational Safety and Health Administration. This is a four-hour notification, non-emergency for an on-site fatality and notification of other government agency. This event is reportable in accordance with 10 CFR 50.72(b)(2)(xi). The NRC Resident Inspector has been notified.
ENS 563459 February 2023 14:53:00McGuireNRC Region 2Westinghouse PWR 4-LoopThe following information was provided by the licensee via email: This 60-day optional telephone notification is being made in lieu of a Licensee Event Report as allowed by 10 CFR 50.73(a)(1). This notification is made pursuant to 10 CFR 50.73(a)(2)(iv)(A) for an invalid system actuation. On January 1, 2023, at approximately 0604 EST, static inverter KXA failed causing a loss of power to shared 120-VAC auxiliary control panel board KXA. Operations entered the appropriate procedures to assist in diagnosing and responding to the event. As expected, the solenoid valves in the instrument lines to steam supply valves 1SA-48ABC and 1SA-49AB deenergized, causing 1SA-48ABC and 1SA-49AB to open and admit steam to the unit 1 turbine driven auxiliary feedwater pump (TDAFWP). Operations reduced turbine load to maintain reactor power less than 100 percent. At approximately 0641 EST, power was restored to the KXA panelboard and the TDAFWP was secured. All systems functioned as required. Actuation of the TDAFWP was not initiated in response to actual plant conditions or parameters satisfying the requirements for initiation of the system nor was the actuation due to an intentional manual initiation. Therefore, this actuation is considered an invalid actuation. The NRC Resident Inspector has been notified.
ENS 5631619 January 2023 13:20:00McGuireNRC Region 2Westinghouse PWR 4-LoopThe following information was provided by the licensee via email: On 01/19/23 at approximately 1000 EST, the emergency sirens in Catawba County, Gaston County, Iredell County, Lincoln County, and Mecklenburg County were inadvertently activated by an offsite agency during a planned silent test. The sirens are in the McGuire Emergency Planning Zone (EPZ). Duke Energy notified the state and all counties within the EPZ. Mecklenburg County has issued a press release. 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). The NRC Resident Inspector has been notified.
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 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 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 5476910 July 2020 07:45:00McGuireNRC Region 2At 0900 EDT hours on 7/10/2020 Duke Energy will undertake planned maintenance activities on the common Emergency Operations Facility (EOF) for Brunswick, Catawba, Harris, McGuire, Oconee, and Robinson nuclear sites. The work includes performance of upgrades to the emergency AC power system and requires the removal of both normal and emergency power to the facility. The work duration is approximately ten (10) days. If a declared emergency were to occur at McGuire, the Alternate EOF would be set up in the Catawba Alternate Technical Support Center (TSC) location as described in implementing procedures. The Emergency Response Organization has been notified that the primary EOF will be unavailable during the upgrade project and to report to the alternate location, if activated. 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 work activity affects the functionality of an emergency response facility. The NRC Resident Inspector has been notified.
ENS 547353 June 2020 17:10:00McGuireNRC Region 2A non-licensed employee supervisor had a confirmed positive for drugs during a random fitness-for-duty test. The employee's access to the plant has been terminated.
ENS 5461426 March 2020 10:45:00McGuireNRC Region 2

EN Revision Imported Date : 3/30/2020 DEGRADED CONDITION On March 26, 2020, while McGuire Unit 2 was shut down for a scheduled refueling outage, the reactor vessel head penetrations were being examined in accordance with the in-service Inspection Program. Ultrasonic examinations identified a relevant indication in the Control Rod Drive Mechanism nozzle number 35 that did not meet the acceptance criteria under ASME, Section XI IWB-3600, 'Analytic Evaluation of Flaws.' Actions to address the relevant indication will be taken in accordance with the applicable codes, standards, and regulations. This event is being reported as an eight-hour non-emergency notification per 10 CFR 50.72(b)(3)(ii)(A). The relevant indication has no impact on the health and safety of the public or station employees. The NRC Resident Inspector has been notified.

  • * * RETRACTION ON 3/29/2020 AT 1700 EDT FROM TOM BERNARD TO BRIAN P. SMITH * * *

McGuire is retracting the eight hour non-emergency notification made on March 26, 2020, at 10:45 ET (EN#54614). A subsequent evaluation determined that the suspect indication identified during ultrasonic examination of Control Rod Drive Mechanism nozzle number 35 is not service induced nor representative of primary water stress corrosion cracking (PWSCC). The indication has been classified as "non-relevant" and is not reportable as a degraded condition. The senior NRC Resident Inspection has been notified. Notified R2DO (Miller).

ENS 5447213 January 2020 09:17:00McGuireNRC Region 2This 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 work activity affects the functionality of an emergency response facility. A planned modification to the Technical Support Center (TSC) power supplies started on January 13, 2020. The work activity includes installation of a permanent back-up diesel generator and rewiring of automatic and manual power transfer switches. The work duration is approximately three weeks. If an emergency is declared requiring TSC activation during this period, the Emergency Coordinator and the TSC staff will assemble and staff the alternate location in accordance with applicable site procedures. The Emergency Response Organization team has been notified of the TSC modification and the need to assemble and staff the alternate location during an emergency. There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.
ENS 540473 May 2019 19:00:00McGuireNRC Region 2At 1554 EDT on 5/3/19, with Unit 1 in Mode 1 at approximately 100 percent power, the reactor automatically tripped on Over Temperature Delta Temperature following a pressure transient in the Reactor Coolant System. The trip was uncomplicated with all systems responding normally post trip. Operations manually started the motor driven auxiliary feedwater pumps and has stabilized the plant. Decay heat is being removed by the condenser. Unit 2 is not affected. Due to Reactor Protection System actuation while critical and actuation of the motor driven auxiliary feedwater pumps, this event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B) and an 8-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. Unit 1 is in a normal electrical lineup. Prior to the automatic trip, the backup pressurizer heaters were in service as is normal during power ascension. The pressure transient started when the backup heaters were in the process of being removed from service. The licensee notified the NRC Resident Inspector.
ENS 534989 July 2018 18:23:00McGuireNRC Region 2On July 9, 2018, at 1155 hours (EDT), while testing the TSC Ventilation System, an equipment malfunction occurred that resulted in an unplanned loss of TSC ventilation functionality/habitability 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. The TSC ventilation system has been placed in an interim configuration that restored functionality and habitability. Additional maintenance is planned to promptly resolve the malfunctioning equipment. 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. The equipment malfunction (a failed solenoid valve) resulted in the loss of the ability to pressurize and filter the air in the TSC.
ENS 533072 April 2018 11:20:00McGuireNRC Region 2Westinghouse PWR 4-LoopThis 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 work activity affects the functionality of an emergency response facility. A planned modification to the Technical Support Center (TSC) ventilation system started on April 2, 2018. The work activity includes replacement of the air conditioning system. The work duration is approximately three weeks. If an emergency is declared requiring TSC activation during this period, the TSC will be staffed and activated using existing emergency planning procedures unless the TSC becomes uninhabitable due to ambient temperature, radiological, or other conditions. If relocation of the TSC becomes necessary, the Emergency Coordinator will relocate the TSC staff to an alternate location in accordance with applicable site procedures. The Emergency Response Organization team has been notified of the TSC modifications and the possible need to relocate during an emergency. There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.
ENS 532401 March 2018 20:34:00McGuireNRC Region 2Westinghouse PWR 4-LoopThis 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 discovered condition affects the functionality of an emergency response facility. Due to the discovery of a breaker coordination issue during an NRC Inspection, the power supply breakers to the Technical Support Center (TSC), including the ventilation system, has been opened to address the condition. This will make the TSC non-functional. If an emergency is declared requiring TSC activation during this period, the Alternate TSC will be staffed and activated using existing emergency planning procedures. The Emergency Response Organization team has been notified to respond to the Alternate TSC in the event of an ERO (Emergency Response Organization) activation. There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.
ENS 5321716 February 2018 13:58:00McGuireNRC Region 2Westinghouse PWR 4-LoopAt 1014 (EST) hours on 2/16/18, with Unit 1 in Mode 1 at approximately 100 percent power, the reactor automatically tripped when the Reactor Trip Breakers opened during Train B Solid State Protection System (SSPS) testing. The trip was uncomplicated with all systems responding normally post-trip. Operations manually started the motor driven auxiliary feedwater pumps. The turbine driven auxiliary feedwater pump (TDCAP) auto-started on low steam generator level. A Feedwater Isolation occurred as designed due to the Reactor Trip and Lo Tave condition. Operations stabilized the plant. Decay heat is being removed by the condenser. Unit 2 is not affected. Due to the Reactor Protection System actuation while critical, actuation of the TDCAP and motor driven auxiliary feedwater pumps along with the Feedwater Isolation, this event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B) and an 8 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 5316010 January 2018 02:13:00McGuireNRC Region 2Westinghouse PWR 4-Loop

During normal power operations at 100 percent power on Unit 2, both trains of Containment Air Return Fans (CARF) were declared inoperable at 19:28 (EST) on January 9, 2018 due to a common issue with control power fuses. The fuses potentially could not handle the in-rush current upon re-energizing the circuits. This condition resulted in a loss of a reasonable expectation that the Unit 2 Containment Air Return Fans would meet their design safety function and mitigate an accident. This loss of safety function is reportable under 10CFR50.72(b)(3)(v)(D), 8 hour report. The site entered T.S. 3.0.3 at 19:28 and exited at 20:54 when repairs to 2B CARF were completed. 2A CARF repairs are complete. There was no impact on the health and safety of the public or plant personnel. The senior NRC Resident Inspector has been notified. The licensee verified this problem does not affect unit-1.

  • * * RETRACTION AT 0939 EST ON 03/08/2018 FROM JUSTIN BLACK TO TOM KENDZIA * * *

A subsequent evaluation determined that the fuses for the Containment Air Return Fans (CARFs) would be able to perform their safety function and were operable at the time of discovery. The limiting safety condition for the fuses is the return to power following a Loss of Offsite Power (LOOP). The evaluation determined that the fuses would satisfy their safety function upon re-energizing the circuits if a LOOP occurred and would not impact the ability of the CARFs to perform their safety function. The subject fuses were replaced on January 9, 2018." The Licensee notified the NRC Senior Resident Inspector. Notified the R2DO (Musser).

ENS 530618 November 2017 11:52:00McGuireNRC Region 2Westinghouse PWR 4-LoopAt 0824 EST on 11/8/17, a Switchyard Autotransformer began to burn due to an equipment failure. The autotransformer supports interconnectivity between each side of the switchyard and is not required for switchyard operation. There was no work in progress on the associated autotransformer at the time of the event. The autotransformer and the switchyard are outside the protected area approximately one mile away. The fire was contained to the autotransformer only. The fault has been electrically isolated and there was no effect on either MNS (McGuire Nuclear Site) Unit 1 or Unit 2 operations. No personnel were injured as a result of the fire. Local Fire Department responded and has contained the fire. MNS fire brigade leader along with switchyard maintenance have confirmed no effects to the MNS bus lines, power availability, or the ability for the site to generate power. Environmental personnel have made a notification to the National Response Center due to the oil and foam mixture occurring as a result of the fire response. McGuire hazmat personnel are currently working to contain this oil and foam mixture. Environmental personnel are also submitting a report to the NC (North Carolina) Department of Environmental Water Quality within 24 hours. There is no impact to the public. The NRC Resident Inspector has been informed.
ENS 5257323 February 2017 22:01:00McGuireNRC Region 2Westinghouse PWR 4-LoopOn February 23, 2017, a containment visual inspection was performed to identify the source of elevated RCS (Reactor Coolant System) leakage. A leak was identified at the nozzle connection of the boron injection line to 2D RCS cold leg at 1922 (EST). It was determined that the leak cannot be isolated and is considered RCS pressure boundary leakage. Unit 2 entered TS LCO 3.4.13, RCS Operational Leakage, Condition B, for the existence of pressure boundary leakage. This event is reportable in accordance with 10CFR50.72(b)(2)(i) (4 hours) for 'initiation of plant shutdown required by Technical Specifications' and 10CFR50.72(b)(3)(ii)(A) (8 hours) for 'any event or condition that results in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded.' The unit will shutdown and repairs will be performed in Mode 5. This condition has no impact on public health and safety. The licensee has informed the NRC Resident Inspector. At the time of the event notification, Unit 2 was at 33 percent power. Unidentified RCS leakage is estimated at 0.28 gpm. Unit 2 is expected to be in Mode 3 by 0122 EST on 02/24/2017. Unit 1 is not affected by this event.
ENS 5224819 September 2016 12:21:00McGuireNRC Region 2Westinghouse PWR 4-LoopThis is a non-emergency facsimile notification required by 10 CPR 21.21(d)(3)(i). A written notification in accordance with 10 CFR 21.21(d)(3)(ii) will be provided within 30 days. Duke Energy McGuire Nuclear Station (McGuire) has determined there is evidence of a departure from technical requirements, a Deviation, associated with Joslyn Clark overload heater element Part Number (PIN) 2455. This part was procured in accordance with the Duke Energy Commercial Grade Program (CGP) and dedicated for use in safety related applications. Three of 18 overload heater elements, purchased as a lot, had insufficient top weld material. One failed in-service during a post maintenance test, the second and third failed during a visual and mechanical inspection. An extent of condition review inspected over 500 similar Joslyn Clark overload heater elements. No other inventory was found with a top weld issue. These overload heater elements are used in motor starters for the Emergency Diesel Generator (EDG) ventilation fans. This condition was discovered during post maintenance testing of the 2A EDG on July 27, 2016. None of the suspect overload heater elements were installed in Operable EDG ventilation fan motor starters. The dedicated overload heater elements, from this lot, were not transferred or sold to any third party customers. Specialty Product Technologies, manufacturer of the Joslyn Clark overload heater elements, has been notified of the deviation and is investigating their welding process. The Evaluation of the deviation determined that a Substantial Safety Hazard would have been created if the overload heater elements were installed and left uncorrected. The NRC Senior Resident Inspector has been notified.
ENS 522192 September 2016 23:33:00McGuireNRC Region 2Westinghouse PWR 4-Loop

Unit 1 Spent Fuel Pool Area Radiation Monitor (1EMF17) lost signal resulting in off scale high indications. Subject EMF provides alarm functions and indication which are used for assessment of EAL classifications. Failure response conducted per applicable Alarm Response Procedures and subsequent actions performed per applicable license commitment required actions. Temporary dose rate monitor has been set up for area monitoring with alarm setpoint commensurate with subject EMF. Issue entered into corrective action program and prioritized to restore subject EMF to functional status within required 30 days. The licensee notified the NRC Resident Inspector.

  • * * RETRACTION FROM PHILIP BALES TO STEVEN VITTO AT 2323 EDT ON 9/4/2016 * * *

This notification is being made to retract event EN 52219, which was reported on September 2, 2016. Upon further investigation, the loss of radiation monitor 1EMF17 did not prevent the evaluation of all EALs (Emergency Action Level) for the associated emergency initiating conditions. Additionally, it has been determined 1EMF17 is not utilized for performing radiological assessments. Therefore, no actual or potential major loss of emergency assessment capability existed per 10 CFR 50.72(b)(3)(xiii). This is consistent with NUREG 1022, Rev. 3, Supplement 1 and NEI 13-01, Rev. 0. The NRC Resident Inspector will be notified of the retraction. Notified R2DO (Bartley).

ENS 5218015 August 2016 15:32:00McGuireNRC Region 2Westinghouse PWR 4-LoopThis is a non-emergency eight hour notification for a loss of Emergency Assessment Capability. The Technical Support Center (TSC) was removed from service on 08/15/2016 at 1030 (EDT) for a scheduled facility upgrade project, which will improve the overall functionality of the facility. The duration of the upgrade is expected to be 26 days. This event is reportable in accordance with 10 CFR 50.72(b)(3)(xiii), as the TSC will be unavailable for greater than 72 hours. In the event of an emergency, McGuire's alternate TSC will be used while the TSC is upgraded. During this period, the alternate TSC will be staffed and activated using existing emergency planning procedures. The Emergency Response Organization team has been notified that the TSC will be unavailable during the upgrade and to report to the alternate TSC in the event of an emergency. This upgrade does not affect the health and safety of the public or station employees. The NRC Resident Inspector has been notified.
ENS 521452 August 2016 14:22:00McGuireNRC Region 2Westinghouse PWR 4-LoopThis is a non-emergency eight-hour notification for a loss of Emergency Assessment Capability. This event is reportable in accordance with 10 CFR 50.72(b)(3)(xiii) as the discovered condition affects the functionality of an emergency response facility. A condition impacting functionality due to a loss of cooling of the TSC (Technical Support Center) Ventilation system was discovered on 8/2/16 at 0630 EDT. Repairs are complete at 1030 EDT on 08/02/16. If an emergency would have been declared requiring TSC activation during this period, the TSC would have been staffed and activated using existing emergency planning procedures unless the TSC had become uninhabitable. 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 emergency plan implementing procedures. The Emergency Response Organization team was notified of the condition and the possible need to relocate during an emergency. This condition does not affect the health and safety of the public or station employees. The NRC Resident Inspector has been notified.
ENS 5182829 March 2016 16:31:00McGuireNRC Region 2Westinghouse PWR 4-Loop

At approximately 1900 EDT on March 28, 2016, an unplanned loss of retail power to the McGuire Meteorological tower occurred. This loss of power impacted communication between the Meteorological tower and the control room, which resulted in a major loss of emergency assessment capability. Compensatory measures existed within the site's emergency planning procedures to obtain meteorological data from the National Weather Service. Meteorological information could have been provided via the emergency notification system to the NRC operations center. Power was restored at 2245 EDT on March 28, 2016. The NRC Resident Inspector has been notified. There was no impact to the public.

  • * * RETRACTION AT 1423 EDT ON 4/19/2016 FROM SCOTT SLIETER TO MARK ABRAMOVITZ * * *

This notification is being made to retract event EN 51828 that was reported March 29, 2016. Based on further investigation, Emergency Plan Implementing Procedures provide acceptable alternative methods to perform emergency assessment that are in addition to the control room indications from the meteorological tower. Furthermore, it was determined that the meteorological tower data was valid and available in the control room during the applicable period. It was therefore determined that no actual or potential major loss of emergency assessment capability existed per 10CFR50.72(b)(3)(xiii). This is consistent with NUREG 1022, rev 3, supplement 1 and NEI 13-01, rev 0. The NRC Resident Inspector has been notified of the retraction. Notified the R2DO (McCoy).

ENS 5181722 March 2016 23:33:00McGuireNRC Region 2Westinghouse PWR 4-LoopOn Tuesday, March 22, 2016, while performing planned inspections of Unit 1 Reactor Coolant System piping welds, a flaw indication was identified on a 3 inch Charging Line connection to the Reactor Coolant System piping. NDE (Non-Destructive Evaluation) results showed a change in the flaw since the previous outage inspection and the condition is now determined as not meeting the acceptance criteria specified in ASME Code Section XI. As such, this indication is reportable under 10 CFR 50.72(b)(3)(ii)(A) as a degraded condition. An action plan is being developed. There is no impact on current Unit 1 refueling operations. This condition and the action plan have no impact to the health and safety of the public or employees. The NRC Resident (Inspector) has been notified.
ENS 5181121 March 2016 17:28:00McGuireNRC Region 2Westinghouse PWR 4-LoopAt 1152 EDT, a contractor employee working in the Containment Building in a potentially contaminated area was found passed out and unresponsive. At 1210 EDT, the individual was transported to Carolinas Medical Center, Charlotte, NC. Radiation Protection had not yet fully determined if the individual was contaminated. At 1300 EDT, Radiation Protection determined the individual was not contaminated. The determination was made after arrival to the hospital. The licensee notified the NRC Resident Inspector.
ENS 5160214 December 2015 12:30:00McGuireNRC Region 2Westinghouse PWR 4-LoopA non-licensed supervisor tested positive for drugs on a random fitness-for-duty test. The individual's access to the facility has been terminated. The licensee has notified the NRC Resident Inspector.
ENS 5147415 October 2015 22:18:00McGuireNRC Region 2Westinghouse PWR 4-LoopOn October 7, 2015, with McGuire Nuclear Station Unit 2 in Mode 4, operators were testing the main turbine and main feedwater pump turbines, 2A safety injection (SI) train trip functions. At the time of the test, the 2A and 2B Auxiliary Feedwater (AFW) pumps were in operation to provide make-up to the steam generators. The main feedwater system was not in service. During realignment activities from the 2A Sl test, the 2A AFW train actuation signal was unblocked when the '2A AFW auto start defeat' switch was returned to 'reset.' This caused the 2A AFW train control valves to fully open, and the associated steam generator sampling and blowdown valves to close. The actuation occurred as designed and there was no adverse impact to the Unit. Public health and safety were not impacted by this event. Based on a review of the Event Reporting Guidelines and the plant licensing basis, this event was initially determined to be an invalid actuation. However, after further review and discussions with the NRC, Duke Energy concluded the event should be reported as an 8-hour non-emergency in accordance with 10 CFR 50.72 (b)(3)(iv)(A) as a valid actuation of the Auxiliary Feedwater System. A Nuclear Condition Report was initiated for the late notification. The NRC Resident Inspector has been notified.
ENS 5140617 September 2015 21:32:00McGuireNRC Region 2Westinghouse PWR 4-LoopA miniature alcohol bottle, containing trace amounts of liquid, was discovered inside the protected area. Site security took possession of the bottle and removed it from the protected area. The licensee notified the NRC Resident Inspector.
ENS 5138510 September 2015 11:35:00McGuireNRC Region 2Westinghouse PWR 4-LoopA contract supervisory employee had a confirmed positive test for alcohol during a random fitness-for-duty test. The employee's access to the plant has been terminated. The licensee has notified the NRC Resident Inspector.
ENS 512078 July 2015 11:13:00McGuireNRC Region 2Westinghouse PWR 4-LoopThis notification is being reported to the NRC in accordance with 10 CFR 50.72(b)(2)(xi) for notification of a fatality of an employee. Station personnel intend to notify OSHA of the individual fatality. At approximately 0629 (EDT) on July 8th, 2015, Control Room personnel received an emergency call requiring station medical first responders. The individual was transported offsite via ambulance. The site has been notified of the individual fatality. The fatality was due to an apparent personal medical issue and not work related. The individual was not contaminated. A press release is not planned at this time. The NRC Resident Inspector has been notified. The individual was inside the Protected Area but not within a Radioactive Control Area.
ENS 5116317 June 2015 16:04:00McGuireNRC Region 2Westinghouse PWR 4-LoopA licensed (non-supervisor) operator was found in violation of the fitness-for-duty policy. The employee's access to the plant has been revoked. The NRC Resident Inspector has been notified.
ENS 507207 January 2015 12:27:00McGuireNRC Region 2Westinghouse PWR 4-LoopThis 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 1A EDG. The 1A EDG start resulted from a degraded component during the testing of the 1A Emergency Load Sequencer. At 2355 (EST) on November 15, 2014, the 1A EDG auto started during performance of the monthly 1A Emergency Load Sequencer test. The test was terminated by personnel prior to a full actuation of the Emergency Load Sequencer due to the unexpected response of the sequencer. The 1A EDG started and functioned normally. Troubleshooting identified a degraded relay downstream of the under voltage sensing circuit which made up the invalid 2/3 logic necessary to start the EDG. There were NO actual plant conditions or parameters (i.e. under voltage, degraded voltage, safety injection or manual initiation) involved in this actuation. The degraded relay would NOT have prevented the 1A Emergency Load Sequencer or the EDG from performing their safety related functions. Following troubleshooting, replacement of the relay and an evaluation for extent of condition, the 1A Emergency Load Sequencer and EDG were returned to service. The health and safety of the public was not affected by this issue. The NRC Resident Inspector has been notified.
ENS 5063120 November 2014 17:29:00McGuireNRC Region 2Westinghouse PWR 4-LoopA supervisory licensed employee had a confirmed positive test 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 5049727 September 2014 20:09:00McGuireNRC Region 2Westinghouse PWR 4-LoopOn Friday, September 26, 2014, while performing planned inspections of Reactor Coolant System piping welds, one flaw indication was identified on each of two 1.5 inch Safety Injection Line connections to the Reactor Coolant System piping. On Saturday, September 27, 2014, after confirmatory inspections and evaluation, both of the flaw indications were determined to not meet the acceptance criteria specified in ASME Code Section XI. As such, these indications are reportable under 10 CFR 50.72(b)(3)(ii) as a Degraded Condition. A repair plan is being developed. There is no impact on current Unit 1 refueling operations while defueled and in No Mode. This condition and repair have no impact to the health and safety of the public or employees. The NRC Resident Inspector was notified.
ENS 5023026 June 2014 15:29:00McGuireNRC Region 2Westinghouse 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 both the McGuire and Oconee plants has been restricted. The NRC Resident Inspectors at both the McGuire and Oconee sites have been notified.
ENS 5014728 May 2014 23:57:00McGuireNRC Region 2Westinghouse PWR 4-LoopOne emergency siren was making noise (siren 27). Huntersville Fire Department was contacted by someone in the area of the siren. No siren was activated. Initial investigation shows power loss to this one siren around the time of occurrence. Local news media contacted Duke Energy representative to question if sirens were set off. Continue to investigate to determine the issue with this one siren. Emergency Planning notified Mecklenburg County of failure of siren #27. The licensee notified the NRC Resident Inspector.
ENS 500958 May 2014 12:17:00McGuireNRC Region 2Westinghouse PWR 4-Loop

At approximately 0429 hours (EDT) on May 8, 2014, McGuire was informed that 34 emergency sirens were incapable of activation from the primary location. The loss of these 34 sirens for more than one hour is reportable pursuant to 10 CFR 50.72(b)(3)(xiii). Until repairs are complete, backup route alerting is in place. Troubleshooting is in progress. During troubleshooting, an inadvertent actuation of emergency sirens occurred at 1030 hours (EDT) on May 8, 2014. Mecklenburg County Emergency Management was notified of this inadvertent actuation which is being reported pursuant to 10 CFR 50.72(b)(2)(xi). Although these sirens were activated there was no incident at McGuire. This event does not impact public health and safety. The NRC Resident Inspector and local agencies were notified.

  • * * UPDATE FROM NICHOLAS BARTSCHER TO DANIEL MILLS ON 5/08/2014 AT 1603 EDT * * *

The emergency sirens have been repaired and are functional. The NRC Resident Inspector has been notified. Notified R2DO (Bonser).

ENS 5006227 April 2014 17:44:00McGuireNRC Region 2Westinghouse PWR 4-Loop

The Technical Support Center (TSC) cooling system is not operating properly. The temperature of the TSC is currently 80 degrees F. The TSC is still capable of being pressurized. If needed, facilities in the Admin building are available for use as the back-up TSC. The licensee will notify the NRC Resident Inspector.

  • * * UPDATE AT 1133 EDT ON 04/28/14 FROM SHAUGHN RICE TO S. SANDIN * * *

TSC Ventilation (VH) System is out-of-service. TSC is not capable of being pressurized, filtered or cooled. This is planned maintenance for work to repair leak reported on 04/27/14. The licensee informed the NRC Resident Inspector. Notified R2DO (King).

ENS 499913 April 2014 02:44:00McGuireNRC Region 2Westinghouse PWR 4-LoopOn Tuesday, April 1, 2014, while performing planned inspections of Reactor Coolant System piping welds, two flaw indications were identified on a 1.5 inch Safety Injection Line connection to the Reactor Coolant System piping. On Wednesday, April 2, 2014, after confirmatory inspections and evaluation, one of the two flaw indications was determined to not meet the acceptance criteria specified in ASME Code Section XI. As such, this indication is reportable under 10 CFR 50.72(b)(3)(ii) as a degraded condition. A repair plan is being developed. There is no impact on current Unit 2 refueling operations. This condition and repair have no impact to the health and safety of the public or employees. The NRC Resident Inspector was notified.
ENS 4953814 November 2013 16:03:00McGuireNRC Region 2Westinghouse PWR 4-Loop

On November 14, 2013, at 1313 Eastern Standard Time, Unit 1 was manually tripped from 100% power due to indications of (four) dropped control rods. This manual reactor protection system actuation is reportable per 10 CFR 50.72(b)(2)(iv)(B). The cause of the dropped rods is not confirmed at this time, but may be related to maintenance in a Rod Control Power Cabinet ongoing at the time of the event. The Operations crew entered the reactor trip procedure and stabilized Unit 1 in Mode 3 at normal operating temperature and pressure. All control rods fully inserted into the core following the reactor trip and all plant systems operated as designed. The Auxiliary Feedwater (AFW) system (1A and 1B motor-driven pumps) was manually started for steam generator level control following reactor trip. The start of the AFW system is reportable per 10 CFR 50.72 (b)(3)(iv)(A) for a valid system actuation. Decay heat is being removed via the steam generators (via steam dumps to the main condenser). This event does not impact public health and safety. Unit 2 was not affected by this event. The licensee notified the NRC Resident Inspector.

  • * * UPDATE FROM WARREN MOORE TO DANIEL MILLS ON 11/18/13 AT 0950 EST * * *
A subsequent licensee evaluation determined that there were ten dropped control rods. 

Notified the R1DO (Desai).

ENS 4915729 June 2013 03:12:00McGuireNRC Region 2Westinghouse PWR 4-Loop

Notification is to be made to an offsite agency: North Carolina Department of Environment and Natural Resources (NCDENR). Due to heavy rains on site, a holdup pond overflowed to the Catawba River. Holdup pond overflow included chemicals (Rotenone) used to treat macro fouling in the Standby Nuclear Service Water Pond. Notification to NCDENR will be made by telephone Saturday morning 6/29/13. The licensee notified the NRC Resident Inspector.

  • * * UPDATE ON 7/2/13 AT 1139 EDT FROM BRENT BARE TO DONG PARK * * *

Due to continued rains on site, the holdup pond continues to overflow to the Catawba River. The overflow includes a new chemical, Potassium Permanganate, used to neutralize the Rotenone treatment of the Standby Nuclear Service Water Pond. This new chemical has the potential to initially turn water purple, which is normal when applied. The North Carolina Department of Environment and Natural Resources (NCDENR) has been updated. The licensee notified the NRC Resident Inspector. Notified R2DO (Freeman).

ENS 4877521 February 2013 12:49:00McGuireNRC Region 2Westinghouse PWR 4-LoopAt 0957 EST on 02/21/13, Unit 1 Reactor automatically tripped from 100% power, due to a turbine trip. The turbine trip was caused by a loss of both main feedwater (MFW) pumps. The 1A motor driven auxiliary feedwater (AFW) pump auto started to feed the "A" and "B" Steam Generators (S/G). The 1B motor driven AFW pump was unavailable due to planned maintenance, so the turbine driven AFW pump was manually started to feed the "C" and "D" S/Gs. The reactor trip was uncomplicated. All control rods fully inserted. Decay heat removal is to the main condenser via the turbine bypass valves. There was no primary to secondary leakage. Electrical buses are being supplied via offsite power. Steam generator levels are being returned to normal and MFW has been reset and is available. All other plant systems functioned as designed during and after the reactor trip. There is no impact on Unit 2. There is no impact on the health and safety of the public. The loss of the MFW pumps is still under investigation. The licensee has informed the NRC Resident Inspector.
ENS 4870328 January 2013 17:38:00McGuireNRC Region 2Westinghouse PWR 4-LoopA fire was reported within the Owner Controlled Area but outside the Protected Area. The fire was located in an air conditioning unit for a small building. The fire was extinguished within 15 minutes by the offsite fire department. The plant did not sustain any damage. The NRC Resident Inspector has been informed.
ENS 4867917 January 2013 16:27:00McGuireNRC Region 2Westinghouse PWR 4-LoopFailure of Unit 2 McGuire switchyard Power Circuit Breaker (PCB) 55 resulted in a fire and damage to the PCB. PCB 55 and the McGuire switchyard are located outside of the protected area. The fire was confined to the PCB only and extinguished by offsite municipal fire department in 33 minutes. This breaker affects the offsite transmission supply to Rock Springs and South Mountain. The Unit 2 plant breakers connecting offsite to onsite power were not affected and remain in service. The failure of PCB 55 did not damage any plant equipment nor did this event cause a plant transient. An estimated 50 gallons of oil has spilled from the damaged equipment which is contained to the immediate area. The spilled oil cleanup efforts are underway at this time. The NRC Resident Inspector will be informed.
ENS 485502 December 2012 14:06:00McGuireNRC Region 2Westinghouse PWR 4-Loop

The Unit-2 AMSAC (Anticipated Transient Without Scram Mitigation Actuation Circuitry) actuation generated a Unit-2 turbine trip signal. The Unit-2 turbine was already tripped, but the 2A and 2B Auxiliary Feedwater and 2B Nuclear Service Water pump started. AMSAC actuation occurred during calibration of AMSAC actuation pressure switches. The licensee notified the NRC Resident Inspector.

  • * * UPDATE FROM TIM JOHNSON TO VINCE KLCO ON 12/11/12 AT 1550 EST * * *

This notification retracts an eight (8) hour notification per 10CFR50.72(b)(3)(iv)(A) which was made December 2, 2012 and documented as NRC Event Notification (EN) # 48550. The December 2, 2012 actuation of the Auxiliary Feedwater System was initially reported under 10CFR 50.72(b)(3)(iv)(A), valid actuation of the Auxiliary Feedwater system as listed in paragraph 10CFR50.72(b)(3)(iv)(B)(6). McGuire Nuclear Station (MNS) has subsequently determined that the actuation signal, which was caused by a test signal during calibration of the AMSAC (Anticipated Transient Without Scram Mitigation Actuation Circuitry) actuation pressure switches, constitutes an invalid actuation as described in Revision 2 of NUREG-1022 (Event Reporting Guidelines 10CFR50.72 and 50.73). Specifically, valid actuations result from signals initiated in response to actual plant conditions or parameters satisfying the requirements for initiation of the safety function of the system. A test signal is not representative of an actual plant condition and was therefore an invalid actuation signal and does not meet the NRC 8-hour reporting criteria under paragraph 10 CFR50.72(b)(3)(iv)(B)(6). In addition to retracting the 10CFR50.72(b)(3)(iv)(B)(6) notification, MNS is notifying the NRC Operations Center that the December 2, 2012 event met the reporting criteria specified in 10CFR50.73(a)(2)(iv)(A). Specifically, an invalid actuation of the auxiliary feed water system occurred while the systems was in service. The event did not involve an actuation of the reactor protection system (RPS) when the reactor was critical; therefore, MNS is opting to notify the NRC Operations Center within 60 days in lieu of a 60 day written licensee Event Report (LER), as allowed by 10CFR 50.73(a)(1) and 10CFR50.73(a)(2)(iv)(A). This notification satisfies 10CFR50.73(a)(2)(iv)(A) reporting requirements in lieu of a written LER. The 2A and 2B trains of the auxiliary feed water were actuated by an invalid signal. Each train's actuation was complete and systems operated as designed. The licensee notified the NRC Resident Inspector. Notified the R2DO (Sykes).