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 Entered dateSiteRegionScramReactor typeEvent description
ENS 5585623 April 2022 06:04:00CatawbaNRC Region 2Manual ScramWestinghouse 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 552291 May 2021 15:39:00CatawbaNRC Region 2Automatic ScramWestinghouse PWR 4-LoopAt 0755 EDT, on May 1, 2021, with Unit 2 in Mode 3 at 0 percent (not critical) power, the reactor trip breakers opened during heat-up activities. The trip was not complex, with all systems responding normally post-trip. At 1013 EDT, on May 1, 2021, with Unit 2 in Mode 3 at 0 percent power, an actuation of the Auxiliary Feedwater (AFW) System occurred. The loss of both main feedwater pump turbines caused an AFW auto-start. The 2A and 2B motor driven auxiliary feedwater (MDAFW) pumps automatically started as designed when the loss of both main feedwater pumps signal was received. The cause of the actuation is still being evaluated. Operations responded and stabilized the plant. Decay heat is being removed by the steam generators and discharging steam to the condenser. Unit 1 is not affected. Due to the Reactor Protection System (RPS) actuation while not critical and the actuation of the AFW system, this event 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 548888 September 2020 13:13:00CatawbaNRC Region 2Automatic ScramAt 0925 EDT, on September 8, 2020, with Unit 1 in Mode 1 at 100 percent power, the reactor automatically tripped on Overpower Delta Temperature. Unit 1 Channel 1 Overpower Delta Temperature was tripped as a planned evolution when an inadvertent Unit 1 Channel 2 Overpower Delta Temperature signal was received. This resulted in an automatic reactor trip. The trip was not complex, with all systems responding normally. Because of the reactor trip, the Auxiliary Feedwater (AFW) System actuated as expected due to on ATWS Mitigation System Actuation Circuitry (AMSAC) signal. Unit 2 is not affected. Operations responded and stabilized the plant. Decay heat is being removed by discharging steam to the main condenser using the condenser steam dump valves. Due to the Reactor Protection System (RPS) actuation while critical, this event is being reported as a 4-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B). This event is also being reported as an 8-hour non-emergency notification per 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of the AFW system. There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.
ENS 5452312 February 2020 21:51:00CatawbaNRC Region 2Automatic ScramAt 1800 EST, on February 12, 2020, with Unit 1 in Mode 1 at 100 percent power, the reactor automatically tripped due to a turbine trip. The trip was not complex, with all systems responding normally post trip. Because of the reactor trip, the Auxiliary Feedwater (AFW) System actuated as expected due to on ATWS Mitigation System Actuation Circuitry (AMSAC) signal. The AFW pumps started as designed when the valid system actuation was received. Operations responded and stabilized the plant. Decay heat is being removed by discharging steam to the main condenser using the condenser steam dump valves. Due to the Reactor Protection System (RPS) actuation while critical, this event is being reported as an 4-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B). This event is also being reported as an 8-hour non-emergency notification per 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of the AFW system. There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified. The site remains in a normal electrical lineup. The cause of the turbine trip is under investigation.
ENS 4115428 October 2004 03:29:00CatawbaNRC Region 2Manual ScramWestinghouse PWR 4-LoopAt 0052 on 10/28/04 the Unit 2 reactor was manually tripped after an electrical fault caused Shutdown Bank D control rods to drop into the core. An automatic start of the Auxiliary Feedwater system occurred when water levels in all four Steam Generators reduced to the Lo-Lo level setpoint. A letdown isolation occurred on Lo Pressurizer level resulting from the cooldown of the primary system after the Auxiliary Feedwater system start. Reactor Coolant system temperature has been recovered and the plant has been stabilized at Hot Shutdown conditions. The licensee stated that there were no complications during the trip. All systems functioned as required. No significant safety systems were out of service when the trip occurred. No primary or secondary relief valves lifted during the transient. Decay heat is currently being removed using aux feedwater to the steam generators steaming to the main condenser. Tave dropped to a low point of 540 degrees F during the transient. The reactor was manually tripped in approximately 18 seconds after the shutdown bank dropped. The licensee plans to remain in mode 3. The licensee will notify the NRC Resident Inspector. The licensee will also notify state and local authorities in North and South Carolina.
ENS 4053822 February 2004 19:02:00CatawbaNRC Region 2Manual ScramWestinghouse PWR 4-LoopThe 1CF-42B (1B Steam Generator Feedwater Isolation Valve) failed closed with Unit 1 at 100% power. Operators performed a manual reactor trip as required by 'Loss of Normal Steam Generator Feedwater Supply', AP-06. Emergency procedures were utilized to respond and stabilize Unit 1 in mode 3. The plant is currently stable in mode 3 at normal operating pressure and temperature. Currently, steam generator levels are being maintained using the auxiliary feedwater system. Other than the failure of 1CF-42B (Initiating Event), all plant safety systems operated as required. No primary or secondary safeties or reliefs lifted during the transient. All control rods fully inserted. The main condenser is in-service to remove decay heat. The licensee had identified a problem with the hydraulic motor associated with 1CF-42B and was in the process of developing corrective actions before the failure. The licensee will inform both state/local agencies (courtesy notification) and has informed the NRC resident inspector.
ENS 4011429 August 2003 10:27:00CatawbaNRC Region 2Automatic ScramWestinghouse PWR 4-LoopUnit 1 tripped on Over Temperature - Delta Temperature (OTDT) protection. Channel 1 OTDT was in a trip condition due to a reactor coolant hot leg temperature problem. Per Technical Specifications, this required Channel 1 OTDT to be placed in the tripped condition. Channel 2 Pressurizer pressure failed low at 0203 EDT. This input (Channel 2 Pressurizer Low Pressure) caused Channel 2 OTDT to enter a trip condition. With 2 of 4 OTDT Channels in the trip condition, a reactor trip signal was generated by the reactor protection system resulting in an automatic reactor trip. After the reactor trip occurred, RCS (Reactor Coolant System) letdown was lost on the chemical and volume control system due to low Pressurizer level. 1NV-1A (Reactor Coolant Letdown Isolation Valve) did not close as required. This necessitated the alignment of the excess letdown flowpath to maintain the desired Pressurizer level. ESF (Engineered Safety Features) operated as designed. Auxiliary feedwater automatically started and main feedwater isolated as designed. All control rods fully inserted on the reactor trip. Station service electrical systems, emergency diesel generators, and ESF equipment are available. Catawba Unit 2 was unaffected by the trip of Unit 1. The licensee has notified the NRC Resident Inspector and will be notifying state and local officials.