ENS 51742
From kanterella
Revision as of 17:16, 24 September 2017 by StriderTol (talk | contribs) (Created page by program invented by Mark Hawes)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
ENS Event | |
---|---|
11:31 Feb 16, 2016 | |
Title | Weld Overlay Flaw Did Not Meet Acceptance Criteria |
Event Description | As part of the upgrade to the full structural weld overlays (FSWOL) per NRC-approved ISI [In-service Inspection] Alternative HNP-ISI-ALT-15-01, the surface of the existing weld overlay for the 1E Recirculation weld (1B31-1RC-12BR-E-5) was ground to prepare the surface for receipt of a new Alloy 52M overlay. Upon performance of the subsequent liquid penetrant testing examination, it was discovered that the as-found condition of the flaw did not meet acceptance criteria. It was determined that the flaw constituted a defect in the primary coolant system that could not be found acceptable per ASME Section XI. Therefore, this event notification is being made in accordance with 10 CFR 50.72(b)(3)(ii)(A).
Evaluation of the flaw found in the weld overlay suggests that the non-satisfactory liquid penetrant surface examination is a result of the propagation of the original flaw that was found on the 1E Recirculation Loop Piping. The flaw is axial in nature and therefore there is no impact on structure integrity degradation. No leakage is currently present or was seen during the previous operating cycle from this flaw. There is also reasonable assurance that there was not a breach in the credited RCS [Reactor Coolant System] boundary during the previous operating cycle. As part of the corrective action to fix the flaw, the 1E Recirculation weld will be upgraded to full structural weld overlay per the NRC-approved ISI Alternative. The Licensee notified the NRC Resident Inspector. |
Where | |
---|---|
Hatch Georgia (NRC Region 2) | |
Reporting | |
10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
Time - Person (Reporting Time:+52.28 h2.178 days <br />0.311 weeks <br />0.0716 months <br />) | |
Opened: | Guy Griffis 15:48 Feb 18, 2016 |
NRC Officer: | Steven Vitto |
Last Updated: | Feb 18, 2016 |
51742 - NRC Website
Loading map... {"minzoom":false,"maxzoom":false,"mappingservice":"leaflet","width":"350px","height":"250px","centre":false,"title":"","label":"","icon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"zoom":6,"defzoom":14,"layers":["OpenStreetMap"],"image layers":[],"overlays":[],"resizable":false,"fullscreen":false,"scrollwheelzoom":true,"cluster":false,"clustermaxzoom":20,"clusterzoomonclick":true,"clustermaxradius":80,"clusterspiderfy":true,"geojson":"","clicktarget":"","imageLayers":[],"locations":[{"text":"\u003Cb\u003E\u003Cdiv class=\"mw-parser-output\"\u003E\u003Cp\u003E\u003Ca class=\"mw-selflink selflink\"\u003EENS 51742\u003C/a\u003E - \u003Ca href=\"/Hatch\" title=\"Hatch\"\u003EHatch\u003C/a\u003E\n\u003C/p\u003E\u003C/div\u003E\u003C/b\u003E\u003Cdiv class=\"mw-parser-output\"\u003E\u003Cp\u003EWeld Overlay Flaw Did Not Meet Acceptance Criteria\n\u003C/p\u003E\u003C/div\u003E","title":"ENS 51742 - Hatch\n","link":"","lat":31.93298888888889,"lon":-82.34381666666667,"icon":"/w/images/1/14/Southern_Nuclear_icon.png"}],"imageoverlays":null} | |
WEEKMONTHYEARENS 569592024-02-11T15:11:00011 February 2024 15:11:00
[Table view]10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Primary Containment Degraded ENS 563422023-02-07T22:38:0007 February 2023 22:38:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Primary Containment Degraded ENS 544632020-01-04T16:09:0004 January 2020 16:09:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Primary Containment Degraded ENS 525672017-02-20T04:23:00020 February 2017 04:23:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Containment Penetration Exceeded Allowable Leakage ENS 517422016-02-16T11:31:00016 February 2016 11:31:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Weld Overlay Flaw Did Not Meet Acceptance Criteria ENS 487952013-02-28T16:55:00028 February 2013 16:55:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Closed Cooling Water Isolation Valve Fails Local Leak Rate Test ENS 487722013-02-20T10:28:00020 February 2013 10:28:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition - Containment Penetration Fails Local Leak-Rate Testing ENS 440382008-03-06T09:00:0006 March 2008 09:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Pin Hole Leak Discovered in 1 Inch Instrument Line During Rpv Pressure Test ENS 440052008-02-23T21:00:00023 February 2008 21:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Unacceptable Flaw in Rpv Cap-To-Pipe Weld ENS 432242007-03-09T05:30:0009 March 2007 05:30:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Main Steam Line Flow Instrument Line Pressure Boundary Leakage ENS 423722006-02-23T23:50:00023 February 2006 23:50:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition of Shroud Tie Rods 2024-02-11T15:11:00 | |
Retrieved from "https://kanterella.com/w/index.php?title=ENS_51742&oldid=82920"