ENS 54707
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ENS Event | |
|---|---|
02:20 May 13, 2020 | |
| Title | Reactor Coolant System Pressure Boundary Degraded |
| Event Description | During the performance of reactor vessel closure head (RVCH) inspections, at 2220 EDT on May 12, 2020, it was determined that the Unit 1 RVCH penetration nozzle number 18 did not meet ASME code case N-729-4 requirements. A surface examination (penetrant test) identified a linear indication on nozzle number 18. The indication was not through-wall as determined by ultrasonic testing. The condition of the Unit 1 reactor vessel head penetration nozzle number 18 will be resolved prior to re-installation of the Unit 1 reactor vessel head. 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. |
| Where | |
|---|---|
Catawba  South Carolina (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| Time - Person (Reporting Time:+-1.1 h-0.0458 days <br />-0.00655 weeks <br />-0.00151 months <br />) | |
| Opened: | Walter Hunnicutt 01:14 May 13, 2020 |
| NRC Officer: | Brian P. Smith |
| Last Updated: | May 13, 2020 |
| 54707 - 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 | |
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