17 janvier 2019
Ce problème a été détecté par ultrasons lors d’inspections planifiées pendant l’arrêt du réacteur. Il a été repéré sur le circuit de refroidissement du cœur qui constitue la deuxième barrière de protection.
Type : PWR - Puissance : 3 716 MWth - Première divergence : 03 / 1985 -
Available in english only
Event Number : 53834
Facility : WATERFORD - State : LA
Unit :  - RX Type :  CE
Event Date : 01/17/2019 - Event Time : 00:00 [CST]
Emergency Class : NON EMERGENCY 10 CFR Section : 50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Initial PWR : 0 % Current PWR : 0 %
RELEVANT INDICATION OF DEGRADED CONDITION
"This is a non-emergency notification from Waterford 3.
"On January 17, 2019, a relevant indication was detected in the performance of Phased Array Ultrasonic Examinations of A600 Dissimilar Metal Piping Welds during planned inspections. The indication was observed during the analysis of data recorded of the Reactor Coolant System (RCS) Loop 1A Reactor Coolant Pump Suction Drain Nozzle to Safe-End Butt Weld (07-009). This indication does not meet applicable acceptance criteria under American Society of Mechanical Engineers (ASME) Section Xl.
"The plant was in Mode 6 (Refueling) at 0 percent power for a planned refueling outage at the time of discovery. The condition will be resolved prior to plant startup. This condition has no impact to the health and safety of the public. This report is being made in accordance with 10 CFR 50.72(b)(3)(ii)(A), ’Any event or condition that results in : (A) The condition of the nuclear power plant, including its principal safety barriers, being seriously degraded,’ because an indication was found that did not meet acceptance criteria referenced in ASME Section Xl. IWB-3514-2 and Code Case N-770-2, 3132.
"The NRC Resident Inspector has been notified.
"Reference : CR-WF3-2019-0967"