ENS 52309
ENS Event | |
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01:30 Oct 20, 2016 | |
Title | Safety Injection Piping Weld Flaw |
Event Description | While performing a scheduled inservice inspection on a section of safety injection system piping, a flaw was identified in a circumferential weld on the 14 inch safety injection line from the 2A safety injection tank to the 2A reactor coolant loop. Examination results indicate that the flaw constitutes a welding defect that cannot be found acceptable under ASME Section XI, IWB-3600, or Table IWB-3410-1. Further analysis is being conducted.
The unit had been shutdown for its 19th refueling outage (3R19) on October 8, 2016, at 0000. The NRC Resident Inspectors have been informed of this condition. This piping is required to be operable in modes one through four.
Subsequent engineering examination of the weld on the 14" safety injection line from the 2A safety injection tank to the 2A reactor coolant loop using enhanced examination techniques concluded the indication in the circumferential weld does not represent a flaw constituting a weld defect. The indication was the result of a metallurgical weld interface in the area of a previously documented weld repair. Therefore, the indication is acceptable under ASME Section XI with no further analysis required. Based on the above information, PVNGS has determined the indication does not represent a degraded condition of a principal safety barrier as defined by 10CFR 50.72(b)(3)(ii)(A) and event notification#52309 is retracted. The NRC Resident Inspectors have been notified. Notified R4DO (Campbell). |
Where | |
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Palo Verde ![]() Arizona (NRC Region 4) | |
Reporting | |
10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
Time - Person (Reporting Time:+-1.35 h-0.0563 days <br />-0.00804 weeks <br />-0.00185 months <br />) | |
Opened: | Armando Aviles 00:09 Oct 20, 2016 |
NRC Officer: | Mark Abramovitz |
Last Updated: | Nov 10, 2016 |
52309 - NRC Website
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WEEKMONTHYEARENS 567852023-10-09T22:07:0009 October 2023 22:07:00
[Table view]10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Coolant System Pressure Boundary Degraded ENS 523092016-10-20T01:30:00020 October 2016 01:30:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Safety Injection Piping Weld Flaw ENS 519102016-05-05T12:00:0005 May 2016 12:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded High Pressure Safety Injection Valve Bonnet Leakage Identified During Refueling Outage ENS 518612016-04-11T12:35:00011 April 2016 12:35:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Pressure Bounday Leakage ENS 509682015-04-08T10:30:0008 April 2015 10:30:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Coolant System Pressure Boundary Leakage Identified ENS 494162013-10-07T09:19:0007 October 2013 09:19:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Potential Reactor Coolant System Pressure Boundary Leakage Identified ENS 428862006-10-07T18:40:0007 October 2006 18:40:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Axial Indications Identified on Pressure Boundry ENS 417832005-06-17T18:00:00017 June 2005 18:00:00 10 CFR 21.21, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Potential Degraded Condition Due to Pressurizer Heater Element Non-Conformance ENS 416292005-04-23T07:00:00023 April 2005 07:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Discovered Two Axial Indications on Inside Diameter of Reactor Vessel Head Penetration ENS 405562004-02-29T07:00:00029 February 2004 07:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Boric Acid Residue Found on Pressurizer Heater Sleeve ENS 405032004-02-03T22:35:0003 February 2004 22:35:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Technical Specification Required Shutdown Due to Rcs Pressure Boundary Leakage ENS 397142003-03-29T11:00:00029 March 2003 11:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded 2023-10-09T22:07:00 | |