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The query [[Category:ENS Notification]] [[Site::Beaver Valley]] [[Scram::+]] was answered by the SMWSQLStore3 in 0.4801 seconds.


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 Entered dateSiteRegionScramReactor typeEvent description
ENS 530567 November 2017 08:29:00Beaver ValleyNRC Region 1Automatic ScramWestinghouse PWR 3-LoopOn 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 5098515 April 2015 07:32:00Beaver ValleyNRC Region 1Manual ScramWestinghouse PWR 3-LoopAt 0411 EDT on April 15, 2015, Beaver Valley Power Station (BVPS) Unit 1 manually tripped the reactor from approximately 85% power due to the trip of a condensate pump. The unit was performing an emergent power reduction due to a degraded condensate pump prior to the manual reactor trip. An end of cycle Tave coastdown was in progress at the time of the event. All control rods fully inserted into the core. All three auxiliary feed water pumps started as expected and were subsequently secured in accordance (with) station procedures. The main feedwater system remains available and in service. The unit is currently stable in Mode 3. Unit 2 was unaffected and remains at full power. Decay heat removal is via main feedwater system with steam discharge to the main condenser via the steam bypass valves. Unit 1 is in a normal shutdown electrical lineup. No primary or secondary reliefs or safeties lifted during the transient. The licensee informed the NRC Resident Inspector.
ENS 5012420 May 2014 10:52:00Beaver ValleyNRC Region 1Manual ScramWestinghouse PWR 3-LoopOn 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 496976 January 2014 19:09:00Beaver ValleyNRC Region 1Automatic ScramWestinghouse 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 495055 November 2013 19:27:00Beaver ValleyNRC Region 1Automatic Scram
Manual 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.

  • * * UPDATE FROM J. A. DAUGHERTY TO JOHN SHOEMAKER AT 2005 EST ON 11/05/13 * * *

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 4674410 April 2011 06:40:00Beaver ValleyNRC Region 1Manual ScramWestinghouse PWR 3-LoopOn 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 428347 September 2006 23:23:00Beaver ValleyNRC Region 1Automatic ScramWestinghouse PWR 3-LoopOn 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 424672 April 2006 15:46:00Beaver ValleyNRC Region 1Automatic ScramWestinghouse PWR 3-LoopAt 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 4032013 November 2003 13:48:00Beaver ValleyNRC Region 1Automatic ScramWestinghouse PWR 3-LoopUnit 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 4024715 October 2003 01:56:00Beaver ValleyNRC Region 1Automatic ScramWestinghouse PWR 3-LoopAutomatic 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.