ENS 47767: Difference between revisions

From kanterella

Latest revision as of 21:04, 1 March 2018

v t e 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.

ENS 47767 +/-
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 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 47767\u003C/a\u003E - \u003Ca href=\"/North_Anna\" title=\"North Anna\"\u003ENorth Anna\u003C/a\u003E\n\u003C/p\u003E\u003C/div\u003E\u003C/b\u003E\u003Cdiv class=\"mw-parser-output\"\u003E\u003Cp\u003EDegradation of Steam Generator Nozzle Weld Areas\n\u003C/p\u003E\u003C/div\u003E","title":"ENS 47767 - North Anna\n","link":"","lat":38.06055555555555,"lon":-77.78944444444444,"icon":"/w/images/b/b0/Dominion_icon.png"}],"imageoverlays":null}
v • d • e

v t e Emergency Notification System
North Anna with 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded
WEEKMONTHYEAR2023-10-03T15:54:00 [Table view]
[ENS list for North Anna]

@@ Line 16: / Line 16: @@
 | event date = 03/24/2012 18:55 EDT
 | last update date = 03/25/2012
-| title = Degradation Of Steam Generator Nozzle Weld Areas
+| 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.
 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.