27 mars 2013
Découverte d’une fuite sur le circuit primaire au niveau de la soudure d’un tuyau. La cause de la fuite ainsi que la résolution du problème sont en cours d’étude.
1ère divergence : octobre 1971 - Type : BWR Mark 1 – P : 882 MWe
Available in english only.
Facility : QUAD CITIES - State : IL - Unit : [1] RX Type : [1] GE-3
Event Date : 03/27/2013 - Event Time : 02:45
Emergency Class : NON EMERGENCY 10 CFR Section : 50.72(b)(3)(ii)(A) - DEGRADED CONDITION Person (Organization) : GREG PICK (R4DO)
Initial PWR : 0 % Current PWR : 0 %
Event Text
REACTOR PRESSURE BOUNDARY LEAKAGE
"On March 26, 2013, at 1635 [CDT], with Unit 1 shutdown for refueling, leakage was identified from the 2-inch reactor head vent line during a Reactor Pressure Vessel (RPV) pressure test. The leakage was approximately 20 drops per minute. The RPV pressure test was stopped and the reactor vessel depressurized to facilitate examination of the piping and associated flange connections. At 0245 hours on March 27, 2013, the leak was confirmed to be through-wall originating from a socket weld (i.e., pipe elbow). The cause and resolution are under evaluation. The condition is being reported under 50.72(b)(3)(ii)(A) given the defect was associated with the primary coolant system pressure boundary."
The licensee notified the NRC Resident Inspector
https://www.nrc.gov/reading-rm/doc-collections/event-status/event/2013/20130328en.html
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