31 janvier 2019
A 3 h 01 du matin, le réacteur n°2, à 100 % de sa puissance, a été arrêté suite au gel de l’eau d’alimentation des 4 pompes de son refroidissement. Le système de refroidissement par ventilateur du confinement n’a pu être activé car il était en maintenance... mais cela n’aurait pas eu de conséquence néfaste. Le système d’alimentation auxiliaire en eau a été activé suite à l’atteinte d’un niveau bas dans un générateur de vapeur. Là aussi il n’y aurait eu aucun problème et le retrait de la chaleur du cœur est effectué par les décharges de vapeur principales et le système de refroidissement auxiliaire.
Type : PWR - Puissance : 3 459 MWth - Première divergence : 08 / 1980
Available in english only
Event Number : 53852
Facility : SALEM - State : NJ
Unit : [2] - RX Type : [2] W-4-LP
Event Date : 01/31/2019 - Event Time : 03:01 [EST]
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 : 0 %
Event Text
MANUAL REACTOR TRIP - CIRCULATING WATER ICING CONDITIONS
"At 0301 [EST] on 1/31/19, with Unit 2 in Mode 1 at 100% power, the reactor was manually tripped due to icing conditions requiring the removal of 4 Circulating Water Pumps from service. The trip was not complex, with all systems responding normally post-trip. 21 CFCU [Containment Fan Cooler Unit] was inoperable prior to the event for a planned maintenance window and did not contribute to the cause of the event and did not adversely impact the plant response to the trip. An actuation of the Auxiliary Feedwater System occurred following the manual reactor trip. The reason for the Auxiliary Feed Water System auto-start was due to low level in a steam generator. Operations responded and stabilized the plant. Decay heat is being removed by the Main Steam Dumps and Auxiliary Feedwater System.
"Due to the Reactor Protection System actuation while critical, this event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B). This event is also being reported as an eight hour non-emergency notification in accordance with 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of the Auxiliary Feed Water System. There was no impact on the health and safety of the public or plant personnel.
"The NRC Resident Inspector has been notified."
The icing condition was described as frazil ice.
Unit-1 reduced power to 88% because one circulating water pump was shutdown.
https://www.nrc.gov/reading-rm/doc-collections/event-status/event/2019/20190201en.html
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