*Power Reactor Event Number: 49353 Facility: BRAIDWOOD Region: 3 State: IL Unit: [1] Degraded Condition/Defueled BOROSCOPIC INSPECTION OF REACTOR VESSEL HEAD DETERMINED EVIDENCE OF BOUNDARY LEAKAGE "Boroscopic inspection of the reactor head assembly during refuel outage A1R17 has determined that white powder residue observed at reactor head penetrations 41, 49, 61, 65, and 73 is evidence of past Reactor Coolant System pressure boundary leakage at one or more of these locations. This determination was made today at 0510 [CDT] after completion of boroscopic inspections and consultation with the reactor head vendor. These reactor head penetrations are control rod drive mechanism (CRDM) penetrations. The location of the identified leakage is suspected to be the omega seal welded threaded connection on one or more of these CRDM penetrations. Further inspections must be performed to confirm the exact leakage location. This condition will be repaired before U-1 returns to mode 4." The licensee has notified the NRC Resident Inspector *Power Reactor Event Number: 49355 Facility: VERMONT YANKEE Region: 1 State: VT Unit: 1 HIGH PRESSURE COOLANT INJECTION SYSTEM DECLARED INOPERABLE DUE TO STEAM LEAK "On 9/18/13, during performance of the High Pressure Coolant Injection (HPCI) pump operability surveillance, a minor steam leak was discovered on the governor valve inspection cover flange. Due to the leak, HPCI was declared inoperable. "Actions taken: A 14-day LCO per TS 3.5.E.2 has been entered and corrective actions are in progress." The licensee has notified the NRC Resident Inspector. *Power Reactor Event Number: 49356 Facility: MONTICELLO Region: 3 State: MN Unit: [1] BOTH SECONDARY CONTAINMENT ACCESS DOORS BRIEFLY OPENED SIMULTANEOUSLY "While performing the secondary containment airlock door interlock surveillance, the interlock to the main plenum room did not prevent the opening of both doors to the plenum room airlock (DOOR-85 and DOOR-86). The plenum room airlock doors were immediately closed. The time both doors were opened is estimated to be approximately one (1) second. "When both doors open, Technical Specification surveillance requirement SR 3.6.4.1.3 was not met and secondary containment was declared inoperable. Secondary containment was declared operable after independently verifying at least one secondary containment access door was closed. "There were no radiological releases associated with this event. The NRC resident inspector has been notified."
Posted on: Thu, 19 Sep 2013 11:25:51 +0000
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