20 octobre 2014
Les alarmes ont été déclenchées suite à une baisse effective du niveau d’eau du circuit primaire. Le système d’injection d’eau de refroidissement haute pression avec l’isolation du cœur se sont enclenchés. Le refroidissement du cœur aurait été correctement obtenu avec injection des barres de contrôle dans le cœur. Des investigations sont en cours pour déterminer l’origine de la perte d’eau de refroidissement.
Type : BWR Mark III - Puissance : 3 758 MWth - Première divergence : 06/1986
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Event Number : 50551
Facility : PERRY - State : OH
Unit : [1] - RX Type : [1] GE-6
Event Date : 10/20/2014 - Event Time : 02:18
Emergency Class : NON EMERGENCY 10 CFR Section : 50.72(b)(2)(iv)(A) - ECCS INJECTION 50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Initial PWR : 100% Current PWR : 100%
Event text
AUTOMATIC REACTOR SCRAM ON LOSS OF FEEDWATER
"The Perry Power Plant experienced a reactor scram during a shift of non-essential vital power supply to the alternate source. Feedwater was lost resulting in receiving a valid level 3 and level 2 signal. High Pressure Core Spray and Reactor Core Isolation Cooling started and injected. Reactor level and pressure have been stabilized to required bands. The motor feed pump has been started and is controlling level. High Pressure Core Spray and Reactor Core Isolation Cooling have been returned to standby."
During the scram, all rods fully inserted into the core. Decay heat is being removed via the steam dumps to the condenser. The electrical grid is stable and supplying plant loads. An emergency diesel generator started, as designed, as a result of the level 2 signal but did not load. No safety valves lifted as a result of the transient. The cause of the loss of feedwater is under investigation.
The licensee will be notifying the State of Ohio and Perry Township and has notified the NRC Resident Inspector.
* * * UPDATE FROM DOUG SHORTER TO HOWIE CROUCH AT 0933 EDT ON 10/20/14 * * *
"The plant is currently in Mode 3, stable with cooldown and depressurization to Mode 4 in progress. Level control is being provided by the motor feedwater pump. Troubleshooting of the cause of the scram and loss of feed water is on-going.
"The initial notification identified 10CFR50.72(b)(3)(iv)(A), ’Specified System Actuation’, as a reporting criteria. The specific system that actuated was not provided. As a result of receiving a reactor vessel water level 2 signal a containment/BOP isolation signal was received. All systems isolated as required and the plant is restoring isolated systems in accordance with procedure."
The licensee will be notifying the State of Ohio and Perry Township and has notified the NRC Resident Inspector.
Notified R3DO (Pelke).
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