18 mars 2018
La fermeture de la soupape, dont la cause est en cours de recherche, a entrainé une montée en pression de vapeur du réacteur qui était à pleine puissance. Ce problème a entrainé la mise en route du système de protection du réacteur. Les barres de contrôle se sont correctement insérées dans le coeur et tous les sytèmes de protection du réacteur se sont activés normalement. Les vannes de by-pass de la vapeur de la turbine contrôlent la pression du réacteur. Les pompes de circulation de liquide de refroidissement restent actives pour contrôler le niveau d’eau du réacteur.
Type : Fukushima 1 (BWR Mark 1) - Puissance : 3 458 MWth - Première divergence : 8 / 1973 -
Available in english only
Event Number : 53269
Facility : BROWNS FERRY - State : AL
Unit : [1] - RX Type : [1]
Event Date : 03/18/2018 - Event Time : 11:58 [CDT]
Emergency Class : NON EMERGENCY 10 CFR Section : 50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION Person (Organization) : REBECCA NEASE (R2DO)
Initial PWR : 100 % Current PWR : 0 %
Event Text
AUTOMATIC REACTOR SCRAM DUE TO TURBINE CONTROL VALVE CLOSURE
"At 1158 CDT on March 18, 2018, the Unit 1 reactor automatically scrammed due to a Reactor Protection System (RPS) signal generated from High Reactor Steam Dome Pressure in response to Turbine Control Valve Closure. The reactor had been operating at 100 percent power. Investigation is in progress.
"All control rods fully inserted into the core. Main Steam Isolation Valves remained open with Main Steam Relief Valves (MSRVs) operating on the initial transient as expected. Main Turbine Bypass Valves are currently controlling reactor pressure. Reactor Feedwater pumps remained in service to control reactor water level.
"Primary Containment Isolation Signals Groups 2, 3, 6, and 8 containment isolation and initiation signals were received. Upon receipt of these signals all required components actuated as required. All safety system operated as expected. At no time was public health and safety at risk.
"This event is reportable within 4 hours per 10 CFR 50.72(b)(2)(iv)(B) ’any event or condition that results in actuation of the Reactor Protection System (RPS) when the reactor is critical except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation.’ It is also reportable within 8 hours per 10 CFR 50.72(b)(3)(iv)(A) ’any event or condition that results in valid actuation of any of the systems listed in paragraph (b)(3)(iv)(B) of this section, except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation’ and requires an LER within 60 days per 10 CFR 50.73(a)(2)(iv)(A)."
The NRC Resident Inspector has been notified.
https://www.nrc.gov/reading-rm/doc-collections/event-status/event/2018/20180319en.html
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