ENS 47767: Difference between revisions
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| event date = 03/24/2012 18:55 EDT | | event date = 03/24/2012 18:55 EDT | ||
| last update date = 03/25/2012 | | last update date = 03/25/2012 | ||
| title = Degradation | | title = Degradation of Steam Generator Nozzle Weld Areas | ||
| event text = On March 24, 2012, at 1855 [EDT] during the performance of work activities to support Alloy 600 dissimilar metal weld overlay work on the 'B' Reactor Coolant loop hot leg to the 'B' Steam Generator nozzle weld, two through-wall defects were identified. The workers noted a small amount of water seeping from the indications in the nozzle weld area. The indications are in the area of excavation that was being performed for the weld overlay project. Approximately 1 [inch] of weld material had been removed prior to the seepage being identified. | | event text = On March 24, 2012, at 1855 [EDT] during the performance of work activities to support Alloy 600 dissimilar metal weld overlay work on the 'B' Reactor Coolant loop hot leg to the 'B' Steam Generator nozzle weld, two through-wall defects were identified. The workers noted a small amount of water seeping from the indications in the nozzle weld area. The indications are in the area of excavation that was being performed for the weld overlay project. Approximately 1 [inch] of weld material had been removed prior to the seepage being identified. | ||
Entered Technical Requirement 3.4 .6, 'ASME Code Class 1, 2 and 3 Components' and immediately initiated actions to isolate the 'B' Reactor Coolant loop. The 'B' Reactor Coolant loop stop valves were closed at 2312 hours on March 24, 2012, which isolated the defects from the reactor coolant system . An engineering evaluation of the defects will be performed and corrective actions implemented. | Entered Technical Requirement 3.4 .6, 'ASME Code Class 1, 2 and 3 Components' and immediately initiated actions to isolate the 'B' Reactor Coolant loop. The 'B' Reactor Coolant loop stop valves were closed at 2312 hours on March 24, 2012, which isolated the defects from the reactor coolant system . An engineering evaluation of the defects will be performed and corrective actions implemented. |
Latest revision as of 22:04, 1 March 2018
Where | |
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North Anna ![]() Virginia (NRC Region 2) | |
Reporting | |
10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
Time - Person (Reporting Time:+2.82 h0.118 days <br />0.0168 weeks <br />0.00386 months <br />) | |
Opened: | Page Kemp 01:44 Mar 25, 2012 |
NRC Officer: | Vince Klco |
Last Updated: | Mar 25, 2012 |
47767 - NRC Website
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