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| Entered date | Site | Region | Scram | Reactor type | Event description | |
|---|---|---|---|---|---|---|
| ENS 55943 | 15 June 2022 09:47:00 | Beaver Valley | NRC Region 1 | Manual Scram | Westinghouse PWR 3-Loop | The following information was provided by the licensee via email: At 0724 EDT on 6/15/2022, with Unit 1 in Mode 1 at 100 percent power, the reactor was manually tripped due to lowering Steam Generator levels due to a secondary plant perturbation in the Heater Drain System. All control rods fully inserted into the core and the Auxiliary Feedwater System automatically started as designed in response to the full power reactor trip. The trip was not complex, with all systems responding normally post-trip. There was no equipment inoperable prior to the event that contributed to the reactor trip or adversely impacted plant response. Operations responded and stabilized the plant. Decay heat is being removed by discharging steam to the main condenser using the condenser steam dump valves. Unit 2 is not affected and remains at 100 percent power and stable. 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). Additionally, 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 55586 | 17 November 2021 16:24:00 | Beaver Valley | NRC Region 1 | Manual Scram | Westinghouse PWR 3-Loop | At 1313 hours on November 17, 2021, with Unit 2 in Mode 1 at 100 percent power, the reactor was manually tripped due to a loss of the 21B Main Feedwater Pump (due to low suction pressure). The Auxiliary Feedwater System automatically started as designed in response to the full power reactor trip. Additionally, the Main Steam Isolation Valves were manually closed to prevent excessive reactor coolant system cooldown. The trip was not complex, with all systems responding normally post-trip. There was no equipment inoperable prior to the event that contributed to the reactor trip or adversely impacted plant response. Operations responded and stabilized the plant. Decay heat is being removed by discharging steam to the atmosphere using the Atmospheric Dump Valves. Beaver Valley Power Station Unit 1 is unaffected and remains at 100 percent power in Mode 1. 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). Additionally, the automatic actuation of the Auxiliary Feedwater System is being reported as an eight-hour, non-emergency Specific System Actuation per 10 CFR 50.72(b)(3)(vi)(A). There was no impact on the health and safety of the public or plant personnel. The NRC Resident has been notified. |
| ENS 55572 | 12 November 2021 13:52:00 | Beaver Valley | NRC Region 1 | Manual Scram | Westinghouse PWR 3-Loop | At 1007 EST on November 12, 2021, with Unit 2 in Mode 1 at approximately 17 percent power following a refueling outage, the reactor was manually tripped due to increasing steam generator water levels due to an oscillating Main Feedwater Pump Recirculation Valve. Additionally, the Main Steam Isolation Valves were manually closed to prevent excessive reactor coolant system cooldown. Decay heat is being removed by discharging steam to the atmosphere using the Atmospheric Dump Valves. The trip was not complex, with all systems responding normally post-trip. There was no equipment inoperable prior to the event that contributed to the reactor trip or adversely impacted plant response. Operations responded and stabilized the plant. Beaver Valley Power Station Unit 1 is unaffected and remains at 100 percent power in Mode 1. 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). There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified. |
| ENS 55507 | 5 October 2021 10:07:00 | Beaver Valley | NRC Region 1 | Automatic Scram | Westinghouse PWR 3-Loop | At 0632 EDT on October 5, 2021, with Unit 2 in Mode 1 at approximately 90 percent power for an end of cycle coastdown, the reactor automatically tripped due to an unexpected unblocking of the low power trip logic. The trip was not complex, with all systems responding normally post-trip. There was no equipment inoperable prior to the event that contributed to the reactor trip or adversely impacted plant response. The Auxiliary Feedwater System automatically started as designed in response to the reactor trip. Operations responded and stabilized the plant. Decay heat is being removed by discharging steam to the main condenser using the condenser steam dump valves. Beaver Valley Power Station Unit 1 is unaffected and remains at 100 percent power in Mode 1. 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). Additionally, the automatic actuation of the Auxiliary Feedwater System is being reported as an eight hour, non-emergency Specific System Actuation 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 54369 | 4 November 2019 09:06:00 | Beaver Valley | NRC Region 1 | Manual Scram | At 0535 (EST) on November 4, 2019, with Unit 1 in mode 1 at 15 (percent) power, the reactor was manually tripped due to the lifting of an 'A' Main Steamline Safety Valve following a Condenser Steam Dump transient. The trip response was not complex, with all systems responding normally post-trip, and all control rods fully inserted into the core. Operations responded and stabilized the plant. Decay heat is being removed by discharging steam to the Main Condenser by using the Condenser Steam Dump Valves. Offsite power is available and is currently supplying Normal and Emergency busses. The plant is currently stable in mode 3. Unit 2 is unaffected by this event and remains at 100 (percent) power in mode 1. 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). There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified. | |
| ENS 53056 | 7 November 2017 08:29:00 | Beaver Valley | NRC Region 1 | Automatic Scram | Westinghouse PWR 3-Loop | On November 7, at 0504 (EST), BVPS (Beaver Valley Power Station) Unit 1 experienced an automatic reactor trip due to Main Unit Generator over current. The Auxiliary Feedwater system activated and remains in service. Offsite power supply is available. Normal and Emergency busses are being supplied by Offsite power. One Source Range channel failed to energize due to its corresponding Intermediate Range instrument being under compensated. It was manually energized and is not indicating as expected. The second Source Range instrument energized but is reading erratically. Both Source Range instruments have been declared inoperable and the appropriate Technical Specification has been complied with by making the Control Rods not capable of withdrawal and isolating all dilution flow paths. Plant trip response was as expected without complications, and all control rods fully inserted in the core. The plant is currently stable in Mode 3. This event is being reported as an actuation of the Reactor Protection system 10 CFR 50.72(b)(2)(iv)(B) and a Specified System Actuation (Auxiliary Feedwater System) 10 CFR 50.72(b)(3)(iv)(A). BVPS Unit 2 is unaffected by this event and remains at 100% power in Mode 1. The NRC Resident Inspector has been notified. |
| ENS 50124 | 20 May 2014 10:52:00 | Beaver Valley | NRC Region 1 | Manual Scram | Westinghouse PWR 3-Loop | On May 20, 2014, at 0835 hours during plant startup, Beaver Valley Power Station Unit 2 Operations personnel manually tripped the reactor due to meeting the pre-briefed trip criteria of 85% narrow range level on the 'A' Steam Generator. This manual trip criterion was reached after the steam generator water level began to oscillate following the start of the 'A' Condensate pump. A manual main steam line isolation was performed in order to limit reactor coolant system cool down. Plant trip response was as expected without complications, and all control rods fully inserted in the core. The plant is currently stable in Mode 3. This event is reportable pursuant to 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A). Beaver Valley Power Station Unit 1 was not affected by this event. The NRC Resident Inspector has been notified. No relief or safety valves lifted during this event. The unit is maintaining primary temperature using the atmospheric steam dumps and main feedwater pumps. There is no primary to secondary leakage. The plant is in its normal shutdown electrical lineup. |
| ENS 49697 | 6 January 2014 19:09:00 | Beaver Valley | NRC Region 1 | Automatic Scram | Westinghouse PWR 3-Loop | At 1659 EST hours on January 6, 2014, Beaver Valley Power Station Unit 1 automatically tripped from 100% power. The cause of the reactor trip was a main transformer differential trip. All rods fully inserted into the core and the plant is stable in Mode 3. All three auxiliary feedwater pumps automatically started as expected. Normal and Emergency Busses are being powered by Offsite Power. The cause of the main transformer differential trip is being investigated. All other equipment functioned as expected. At 1757 EST hours the Emergency Operating Procedures were exited. Resident inspector has been notified. Decay heat is being removed via the turbine bypass valves to the condenser. No primary or secondary safety valves lifted. Unit 2 was unaffected. Licensee notified the States of Pennsylvania, Ohio, and West Virginia and the Counties of Beaver, PA, Hancock, OH, and Columbiana, OH. |
| ENS 49505 | 5 November 2013 19:27:00 | Beaver Valley | NRC Region 1 | Manual Scram Automatic Scram | Westinghouse PWR 3-Loop | On 11/5/13 at 1746 (EST), Beaver Valley Unit 1 Generator tripped on 'C' Transformer differential protection. The Unit was at 47%, so an automatic trip of the reactor was not expected. The reactor was tripped manually. Entered E-0 Reactor Trip Response. The Aux Feedwater Turbine Driven Pump automatically started as required and one motor driven pump was manually started. At 1748, the control room received report of fire in the Turbine building. The deluge system had actuated and extinguished the fire in the Turbine plant mezzanine. Off-site assistance was staged and available. At 1828, an Unusual Event was declared when fire brigade reports indications that an explosion and fire had occurred in a cable tray in the Unit 1 Turbine Mezzanine. The (NRC) Resident Inspector was notified of the events that occurred. At 1836, NRC (Resident Inspector) was notified of the Unusual Event. Cause of the cable tray explosion and fire is being investigated. The reactor trip was uncomplicated and Unit 1 is stable in mode 3 with decay heat being released to the main condenser. Normal offsite power is available. Unit 2 continues to operate at 100% and there is no impact on the health and safety of the public.
At 1959 on 11/5/13, the licensee terminated the Unusual Event. The licensee has notified the NRC Resident Inspector. Notified the R1DO (Noggle), NRR EO (Skeen), IRD (Marshall). Notified the DHS SWO, FEMA, DHS NICC, and Nuclear SSA via e-mail. |
| ENS 46744 | 10 April 2011 06:40:00 | Beaver Valley | NRC Region 1 | Manual Scram | Westinghouse PWR 3-Loop | On April 09, 2011, at 2349 (EDT), Beaver Valley Power Station (BVPS) Unit No. 2 was operating at 15% power while preparing to synchronize the main unit generator to the grid. At that time, the 'A' Auxiliary Feedwater Injection Header was declared inoperable due to a water leak identified from a vent valve fillet weld between the inside and outside Containment Isolation Valves (outside of containment) for containment penetration X-79. In accordance with Technical Specification 3.7.5, Auxiliary Feedwater (AFW) System, Condition D, at 0345 (EDT), April 10, 2011, BVPS Unit 2 commenced a Reactor Shutdown to Mode 3. Required action is to be in Mode 3 within 6 hours. This event is being reported as a Technical Specification required shutdown pursuant to 10CFR50.72(b)(2)(i), 4 hour notification. Repairs are in progress. The following additional shutdown actions may be required from the time the Injection Header/Containment Penetration was declared inoperable: Technical Specification 3.7.5, Condition D, Mode 4 in 18 hours and Technical Specification 3.6.1, Condition A, Mode 5 within 37 hours. This event is also being reported as a degraded condition for Containment pursuant to 10CFR50.72(b)(3)(ii)(A), 8 hour notification. Additionally, at 0357 (EDT), during the Reactor Shutdown, at 4.6% Reactor Power, the BVPS Unit 2 Reactor was manually tripped due to reaching a pre-established manual trip criteria of 25% Steam Generator Level for the 21A Steam Generator. This was conservative criteria set above automatic actuation setpoint of 20.5% level. This event is being reported as a RPS Actuation pursuant to 10CFR50.72(b)(2)(iv)(B), 4 hour notification. Control room personnel entered Emergency Operating Procedure E-0, 'Response to Reactor Trip and Safety Injection.' Safety systems and equipment functioned as designed following the manual reactor trip. Due to the cooldown and subsequent shrink of level in the 21A Steam Generator, an automatic start of the Steam Driven Auxiliary Feedwater Pump (2FWE-P22) occurred at 20.5%. This event is being reported as an Auxiliary Feedwater System Actuation pursuant to 10CFR50.72(b)(3)(iv)(A), 8 hour notification. All control rods fully inserted into the core. The plant electrical system is aligned to normal offsite power sources. Decay heat from the reactor coolant pumps is being directed to atmospheric dump valve. There is no primary to secondary leakage. There was no impact on Unit 1. The licensee notified the NRC Resident Inspector. |
| ENS 42834 | 7 September 2006 23:23:00 | Beaver Valley | NRC Region 1 | Automatic Scram | Westinghouse PWR 3-Loop | On September 7, 2006 at 2157 hours, Beaver Valley Power Station Unit No. 1 was operating at 100% when an automatic reactor trip occurred following a spurious opening of the 'B' Reactor Trip Breaker. The first-out indication for the reactor trip was turbine trip due to reactor trip. Control room personnel entered Emergency Operating Procedure E-0, 'Response to Reactor Trip and Safety Injection.' Safety systems and equipment functioned as designed following the automatic reactor trip. Reactor pressure and temperature have been stabilized following the reactor trip without requiring a Safety Injection. The plant was stabilized in Mode 3 utilizing the normal heat sink (main condenser) with steam generator levels restored to post shutdown values by the Auxiliary Feedwater System. All normal and emergency busses are energized from offsite power. The cause of the reactor trip is being investigated. All rods fully inserted, all ESF systems remain operable, and the electrical grid is stable. The licensee notified the NRC Resident Inspector and plans to issue a press release. |
| ENS 42467 | 2 April 2006 15:46:00 | Beaver Valley | NRC Region 1 | Automatic Scram | Westinghouse PWR 3-Loop | At 1402 Beaver Valley Unit 2 experienced a reactor trip due to a Main Generator trip. Unit 2 was operating at 100% power at the time of the trip (control rods inserted fully). All systems functioned as expected. Emergency busses (are) being supplied by offsite power. Auxiliary Feedwater started as expected. Both Emergency Diesel Generators started on momentary undervoltage and remained operating unloaded. The Control Room Crew entered Emergency Operating procedure E-0, 'Response to Reactor Trip and Safety Injection' and have transitioned as expected to ES-0.1 'Reactor Trip Response.' The plant is stable in Mode 3 with steam generator levels and Reactor Coolant System temperature restored to normal values with Auxiliary Feed System operation. The cause of the Generator / Reactor trip is being investigated. No radiological releases ongoing or caused by this event. Beaver Valley Unit 1 is in Mode 5 for a Steam Generator Replacement outage and was unaffected. The licensee notified the NRC Resident Inspector. |
| ENS 40320 | 13 November 2003 13:48:00 | Beaver Valley | NRC Region 1 | Automatic Scram | Westinghouse PWR 3-Loop | Unit 1 was at 100% power when an automatic reactor trip occurred. The Auxiliary Feedwater systems automatically started due to low post trip steam generator levels. This includes the steam driven Auxiliary feedwater pump. The steam discharge of this pump is considered to (be) a gaseous release due to trace amounts of tritium in the secondary system. These trace amounts are well below limits. The pump was shutdown after 31 minutes of operation, terminating the discharge. The Rad Waste & Effluents Section will assess the impact during the event response review. The plant is currently stable in mode 3 with steam generator levels restored to post shutdown values. The steam dumps and main unit condenser are available for heat removal. All normal and emergency busses are energized from offsite power. All rods fully inserted, no ECCS actuation and no primary or secondary relief valves lifted. The NRC Resident Inspector was notified. |
| ENS 40247 | 15 October 2003 01:56:00 | Beaver Valley | NRC Region 1 | Automatic Scram | Westinghouse PWR 3-Loop | Automatic Trip due to low (21%) B Steam Generator Level (all rods fully inserted into the core). While decreasing power for heater drain pump repairs, the B main feedwater regulating valve did not respond properly. Manual attempts to restore level were not effective. Steam generator level decreased to the low level trip setpoint. Auxiliary feedwater systems automatically started due to low post trip steam generator levels. This includes the Steam Driven Auxiliary Feedwater Pump. The steam discharge of this pump is considered to a gaseous release due to trace amounts of tritium in the secondary system. These trace amounts are well below limits. The pump was shutdown after 16 minutes of operation, terminating the discharge. The Rad Waste & Effluents Section will assess the impact during the event response review. Plant is currently stable in Mode 3 with steam generator levels restored to post shutdown values. The steam dumps and main unit condenser are available for heat removal. All normal and emergency busses are energized from offsite power. The NRC Resident Inspector was notified of the event by the licensee. |