ENS 56165
ENS Event | |
|---|---|
15:59 Oct 15, 2022 | |
| Title | Reactor Vessel Head Penetration Repair Degraded |
| Event Description | The following information was provided by the licensee via email:
On 10/15/2022 at 1159 [EDT], during the Catawba Nuclear Station Unit 2 refueling outage, it was determined that the results of a planned surface examination Liquid Penetrant test (PT) performed on a previous overlay repair on nozzle number 74 of the reactor vessel closure head (RVCH) did not meet applicable acceptance standards. The examination was being performed to meet the requirements of Relief Request RA-21-0144, 'Proposed Alternative to Use Reactor Vessel Head Penetration Embedded Flaw Repair for Life of Plant'. The penetration required repairs for the discovered indications. The repairs have been completed in accordance with the ASME Code of Record prior to returning the vessel head to service. 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 Inspector has been notified. The original indication that led to the overlay repair was discovered in April 2021, during ultrasonic testing and reported to the NRC and assigned EN55201. |
| Where | |
|---|---|
Catawba  South Carolina (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| Time - Person (Reporting Time:+-0.22 h-0.00917 days <br />-0.00131 weeks <br />-3.01356e-4 months <br />) | |
| Opened: | Will Fowler 15:46 Oct 15, 2022 |
| NRC Officer: | Karen Cotton-Gross |
| Last Updated: | Oct 15, 2022 |
| 56165 - NRC Website
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WEEKMONTHYEARENS 561652022-10-15T15:59:00015 October 2022 15:59:00
[Table view]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 2022-10-15T15:59:00 | |