ENS Event | |
|---|---|
02:30 Apr 21, 2021 | |
| Title | Reactor Coolant System (Rcs) Pressure Boundary Degraded |
| Event Description | During the performance of reactor vessel closure head (RVCH) examinations, at 2230 EDT on April 20, 2021, it was determined that the Unit 2 RVCH penetration nozzle number 74 did not meet the requirements of 10CFR50.55a(g)(6)(ii)(D) and ASME code case N-729-6 . All other RVCH penetration examinations have been completed per 10CFR50.55a(g)(6)(ii)(D) and ASME code case N-729-6 with no other relevant indications identified. The condition of the Unit 2 reactor vessel head penetration nozzle number 74 will be resolved prior to re-installation of the Unit 2 RVCH. This event is being reported as an eight-hour, non-emergency notification per 10CFR50.72(b)(3)(ii)(A).
There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified. |
| Where | |
|---|---|
Catawba  South Carolina (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| Time - Person (Reporting Time:+0.12 h0.005 days <br />7.142857e-4 weeks <br />1.64376e-4 months <br />) | |
| Opened: | Terry Odoms 02:37 Apr 21, 2021 |
| NRC Officer: | Brian Lin |
| Last Updated: | Apr 21, 2021 |
| 55201 - NRC Website
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WEEKMONTHYEARENS 579062025-09-05T13:09:0005 September 2025 13:09:00
[Table view]10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition ENS 561652022-10-15T15:59:00015 October 2022 15:59:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Vessel Head Penetration Repair Degraded ENS 552752021-05-25T21:51:00025 May 2021 21:51:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Unit 2 Containment Local Leak Rate and As-Found Integrated Overall Leakage Rate Exceeded Acceptance Criteria ENS 552012021-04-21T02:30:00021 April 2021 02:30:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Coolant System (Rcs) Pressure Boundary Degraded ENS 547072020-05-13T02:20:00013 May 2020 02:20:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Coolant System Pressure Boundary Degraded ENS 457102010-02-19T00:15:00019 February 2010 00:15:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Rcs Pressure Boundary Leakage Identified on Rtd Weld ENS 410482004-09-17T14:00:00017 September 2004 14:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Apparent Pressure Boundary Leakage Identified on Steam Generator Bowl Drains ENS 403722003-12-03T20:00:0003 December 2003 20:00:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded, 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Backward Installation of Containment Loop Seal Penetration Vacuum Breakers 2025-09-05T13:09:00 | |