26 mars 2019
Le réacteur étant à 0 % de sa puissance, le taux de fuite détecté sur la vanne est supérieur aux limites autorisées. Le problème est déclaré suite à une dégradation sérieuse du confinement primaire. La fuite doit être réparée pour pouvoir redémarrer le réacteur.
Type : Fukushima I (BWR Mark 1) - Puissance : 3 458 MWth - Première divergence : n°2 : 7 / 1974 -
Available in english only
Event Number : 53959
Facility : BROWNS FERRY - State : AL
Unit : [2] - RX Type : [2] GE-4
Event Date : 03/26/2019 - Event Time : 10:30 [CDT]
Emergency Class : NON EMERGENCY 10 CFR Section : 50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Initial PWR : 0 % Current PWR : 0 %
Event Text
REPORT OF DEGRADED CONDITION DUE TO LEAKING VALVE
"On 3/26/2019 at 1030 CDT Engineering evaluation determined that Traversing lncore Probe (TIP) System test results related to Leak Rate Testing of 2-CKV-76-653, TIP Purge Header Check Valve, during the Unit 2 Refueling Outage resulted in a reportable condition. On 3/24/2019 at 1558 CDT, Leak Rate Testing identified a [local leak rate test] LLRT failure of 2-CKV-76-653. The gross leakage Leak Rate value exceeded the Technical Specification allowable value for Type C valves of less than 0.6 [allowable leakage] La.
"This constitutes an 8-hour NRC notification in accordance with 10 CFR 50.72(b)(3)(ii)(A) - Any event or condition that results in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded.
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."
The short-term corrective actions include repairing the valve such that it passes the test. The valve needs to be repaired before the unit can change modes.
https://www.nrc.gov/reading-rm/doc-collections/event-status/event/2019/20190327en.html
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