05000456/LER-2013-002
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Braidwood Station, Unit 1 | |
Event date: | 09-14-2013 |
---|---|
Report date: | 11-13-2013 |
Reporting criterion: | 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded |
Initial Reporting | |
ENS 49343 | 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded |
4562013002R00 - NRC Website | |
A. Plant Operating Conditions Before the Event:
Event Date: September 14, 2013 Unit: 1 MODE: 6 Reactor Power: 000 percent Unit 1 Reactor Coolant System [A]]: Shutdown for refueling outage, no fuel movement in progress No structures, systems or components were inoperable at the start of this event that contributed to the event.
B. Description of Event:
On September 14, 2013 at 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />, indications exceeding ASME Section III acceptance criteria were discovered in the embedded flaw repair weld of Control Rod Drive Mechanism (CRDM) Penetration 69. The Al R17 examination of the embedded flaw repair in Penetration 69 was performed in accordance with Braidwood Third Interval Relief Request