7 novembre 2014
L’injection de liquide haute pression et le système d’isolation du cœur ont été enclenchés. Le réacteur a été rétabli dans les paramètres requis et les systèmes de sécurité mis en route sont passés au repos. Durant l’arrêt d’urgence, toutes les barres de contrôle se sont correctement insérées et toutes les opérations se sont déroulées conformément aux règles, avec également la mise en route d’un générateur diesel d’urgence.
Type : BWR Mark III - Puissance : 3 758 MWth - Première divergence : 06/1986
Available in english only.
Event Number : 50601
Facility : PERRY - Region : 3 State : OH -
Unit : [1] - RX Type : [1] GE-6
Event Date : 11/07/2014 - Event Time : 08:47
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 : 0 %
Event Text
AUTOMATIC REACTOR SCRAM DUE TO LOSS OF FEEDWATER
"The Perry Nuclear Power Plant experienced an automatic reactor scram due to a loss of feedwater, which resulted in receiving valid reactor vessel water Level 3 and Level 2 initiation signals. The High Pressure Core Spray system and the Reactor Core Isolation Cooling system started and injected. Reactor water level and pressure have been stabilized in the required bands. The motor feed pump automatically started and is being used to control reactor vessel water level. The High Pressure Core Spray and Reactor Core Isolation Cooling systems have been returned to the standby mode. As a result of receiving a reactor vessel water Level 2 signal a Balance of Plant containment isolation signal was received. All systems isolated as required and the plant is restoring isolated systems in accordance with plant procedures.
"During the scram, all rods fully inserted into the core. Decay heat is being removed via turbine bypass valves to the main condenser. The electrical grid is stable and is supplying plant loads. An emergency diesel generator [Division 3 High Pressure Core Spray] started, as designed, as a result of the reactor vessel water Level 2 signal. No safety relief valves lifted as a result of the transient.
"The plant is stable with cooldown and depressurization to Mode 4 in progress. The cause of the loss of feedwater is under investigation.
"The NRC Resident Inspector has been notified. The State of Ohio and local officials will be notified."
https://www.nrc.gov/reading-rm/doc-collections/event-status/event/2014/20141110en.html#en50601
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