ENS 41448
ENS Event | |
|---|---|
20:00 Feb 27, 2005 | |
| Title | Degraded Condition of Reactor Coolant Boundary Weld |
| Event Description | The licensee provided the following information, via facsimile, about its ongoing Alloy 600 inspection:
IRE-003-574 has identified an axial flaw on line 2-LD-2004-1, 22A cold leg letdown nozzle. Engineering has evaluated the flaws using the procedures of ASME Code Section XI, IWB-3600. The calculated growth rates of the postulated axial flaws are large and do not meet the ASME Section XI Code requirements. This is reportable per NUREG-1022, Rev. 2, Sect. 3.2.4 (degraded or unanalyzed condition). 'Any event or condition resulting in the condition of the nuclear power plant, including its principal safety barriers, being serious degraded.' Unit two is in Mode 6 for refueling and a repair plan is currently being developed. The discovery of this flaw will likely result in the expansion of the inspection scope. Generic concerns for both units have not yet been fully developed by the licensee. The licensee has notified the NRC Resident Inspector. See similar event #41445 |
| Where | |
|---|---|
Calvert Cliffs  Maryland (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| Time - Person (Reporting Time:+0.38 h0.0158 days <br />0.00226 weeks <br />5.20524e-4 months <br />) | |
| Opened: | Robert Pace 20:23 Feb 27, 2005 |
| NRC Officer: | Bill Huffman |
| Last Updated: | Feb 27, 2005 |
| 41448 - NRC Website | |
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 | |