6 janvier 2014
Ce défaut est lié à la défaillance d’une vanne principale de régulation. Les opérateurs ont engagé les procédures d’urgence. Le cœur étant critique, les systèmes de protection du réacteur se sont enclenchés.
Type : PWR - Puissance : 3 216 MWTh - Première divergence : 04/1976
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Event Number : 49698 Facility : INDIAN POINT - State : NY - Unit [3] - W-4-LP -
Event Date : 01/06/2014 - Event Time : 21:15 -
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
Initial PWR : 100 % Current PWR : 100 %
Event Text
AUTOMATIC REACTOR TRIP ON LOW STEAM GENERATOR WATER LEVEL DUE TO A FAILED MAIN FEEDWATER REG VALVE
"On January 6th, 2014 at 2115 EST Indian Point Unit 3 experienced an Automatic Reactor Trip due to ’33 Steam Generator Steam flow/Feed flow Mismatch.’ Operators entered emergency procedure E-0, Reactor Trip or Safety Injection. All control rods fully inserted, all safety systems responded as expected, and off-site power remained in-service. No primary or secondary safety valves actuated due to the trip. This is reportable under 10CFR50.72(b)(2)(iv)(B). The main condenser is being used for heat sink. Unit 2 remains stable at 100% power.
The Auxiliary Feedwater System actuated following the automatic trip as expected. This is reportable under 10CFR50.72(b)(3)(iv)(A).
"Investigation is underway to determine the cause of the 33 Steam Generator Mismatch condition."
The licensee will inform local and other government agencies and issue a press release. The licensee has informed the State of New York and the NRC Resident Inspector.
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