ENS 51747
From kanterella
Jump to navigation
Jump to search
ENS Event | |
---|---|
08:30 Feb 20, 2016 | |
Title | Degraded Condition Discovered on Pressurizer Safety Relief Valve Weld |
Event Description | During the CCNPP [Calvert Cliff Nuclear Power Plant] Unit 1 Refueling, [an ultrasonic test] examination of the Unit 1 dissimilar metal weld (DMW) of the pressurizer safety relief valve RV-201 safe end weld found an indication that is approximately 80 percent though-wall, inside diameter connected axial flaw in weld #4-SR-1006-1.
This is an ASME Class 1 component and Unit 1 has entered the requirements of Technical Requirements Manual (TRM) 15.4.3.A. CCNPP Event #4254. The licensee has notified the NRC Resident Inspector. |
Where | |
---|---|
Calvert Cliffs Maryland (NRC Region 1) | |
Reporting | |
10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
LER: | 05000317/LER-2016-002 |
Time - Person (Reporting Time:+0.7 h0.0292 days <br />0.00417 weeks <br />9.5886e-4 months <br />) | |
Opened: | Ervin Lyson 09:12 Feb 20, 2016 |
NRC Officer: | Howie Crouch |
Last Updated: | Feb 20, 2016 |
51747 - 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 51747\u003C/a\u003E - \u003Ca href=\"/Calvert_Cliffs\" title=\"Calvert Cliffs\"\u003ECalvert Cliffs\u003C/a\u003E\n\u003C/p\u003E\u003C/div\u003E\u003C/b\u003E\u003Cdiv class=\"mw-parser-output\"\u003E\u003Cp\u003EDegraded Condition Discovered on Pressurizer Safety Relief Valve Weld\n\u003C/p\u003E\u003C/div\u003E","title":"ENS 51747 - Calvert Cliffs\n","link":"","lat":38.434263888888886,"lon":-76.44219722222222,"icon":"/w/images/b/be/Constellation_icon.png"}],"imageoverlays":null} | |
WEEKMONTHYEARENS 551222021-03-04T08:23:0004 March 2021 08:23:00
[Table view]10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Notification of Degraded Condition ENS 517472016-02-20T08:30:00020 February 2016 08:30:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition Discovered on Pressurizer Safety Relief Valve Weld ENS 503072014-07-25T03:15:00025 July 2014 03:15:00 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 Reactor Coolant System Pressure Boundary Leakage ENS 487632013-02-17T18:45:00017 February 2013 18:45:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Pressure Boundary Leakage Discovered During Containment Walkdown ENS 481242012-07-21T16:10:00021 July 2012 16:10:00 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 Rcs Pressure Boundary Instrument Line Leakage ENS 481162012-07-17T04:00:00017 July 2012 04:00:00 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 Small Rcs Pressure Boundary Instrument Line Leak ENS 473162011-10-03T14:35:0003 October 2011 14:35:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Technical Specification (Ts) Required Shutdown Due to Both 'A' Train Edg'S Inoperable ENS 466232011-02-18T05:51:00018 February 2011 05:51:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Inactive Leak Identified on Presurizer Heater Well ENS 457372010-03-02T12:30:0002 March 2010 12:30:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Pressurizer Safety Nozzle Weld Degradation ENS 457192010-02-23T20:12:00023 February 2010 20:12:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition - Weld Leak Due to Vibrating Valve Attachment Wire ENS 440062008-02-25T06:40:00025 February 2008 06:40:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition Due to Leakage on a Pressurizer Heater Sleeve ENS 414482005-02-27T20:00:00027 February 2005 20:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition of Reactor Coolant Boundary Weld ENS 414452005-02-26T20:30:00026 February 2005 20:30:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition of Reactor Coolant Boundary Weld 2021-03-04T08:23:00 | |
Retrieved from "https://kanterella.com/w/index.php?title=ENS_51747&oldid=421164"