ENS 55122
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ENS Event | |
|---|---|
08:23 Mar 4, 2021 | |
| Title | Notification of Degraded Condition |
| Event Description | At time 0323 [EST] on March 04, 2021, it was determined that the Reactor Coolant System (RCS) pressure boundary did not meet the acceptance criteria under ASME,Section XI IWB-3600, "Analytical Evaluation of Flaws." This condition will be resolved prior to plant start up. This event is being reported as an eight hour non-emergency notification per 10 CFR 50.72(b)(3)(ii)(A).
There was no impact on the health and safety of the public or plant personnel. The NRC Resident has been notified. |
| Where | |
|---|---|
Calvert Cliffs  Maryland (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| Time - Person (Reporting Time:+-4.38 h-0.183 days <br />-0.0261 weeks <br />-0.006 months <br />) | |
| Opened: | Kent Mills 04:00 Mar 4, 2021 |
| NRC Officer: | Kerby Scales |
| Last Updated: | Mar 4, 2021 |
| 55122 - NRC Website
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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 | |
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