ENS 47767
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ENS Event | |
|---|---|
22:55 Mar 24, 2012 | |
| Title | Degradation Of Steam Generator Nozzle Weld Areas |
| Event Description | 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 hours0.0268 days <br />0.642 hours <br />0.00382 weeks <br />8.79716e-4 months <br /> 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. This event is reportable in accordance to 10CFR50.72(b)(3)(ii)(A) for 'any event or condition that results in the condition of the nuclear power plant, including its principle safety barriers, being seriously degraded'. The licensee notified the NRC Resident Inspector and will notify Louisa County. |
| Where | |
|---|---|
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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WEEKMONTHYEARENS 567742023-10-03T15:54:0003 October 2023 15:54:00
[Table view]10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition ENS 554572021-09-12T21:28:00012 September 2021 21:28:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition Identified While Unit Shutdown ENS 521372016-07-30T15:52:00030 July 2016 15:52:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Technical Specification Required Shutdown Due to Unisolable Reactor Coolant System Boundary Leakage ENS 507002014-12-23T03:30:00023 December 2014 03:30:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Unit 1 Technical Specification Shutdown Due to Rcs Pressure Boundary Leakage ENS 504572014-09-15T13:00:00015 September 2014 13:00:00 10 CFR 20.2201(a)(1)(ii), 10 CFR 74.11(a), 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Failed Fuel Assembly Identified During Core Off-Load ENS 489402013-04-17T20:00:00017 April 2013 20:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition Due to Suspected Valve Body Leakage ENS 477672012-03-24T22:55:00024 March 2012 22:55:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degradation of Steam Generator Nozzle Weld Areas 2023-10-03T15:54:00 | |
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