ENS Event | |
|---|---|
21:05 Nov 12, 2021 | |
| Title | Reactor Coolant System Pressure Boundary Degraded |
| Event Description | At 1605 EST on 11/12/21, it was determined that the RCS Pressure Boundary does not meet ASME Section XI, Table IWB-341 0-1, 'Acceptable Standards' due to a through wall leak of the Core Exit Thermocouple Nozzle Assembly.
Measures have been taken to establish Mode 5 for corrective actions. This event is being reported pursuant to 10 CFR 50.72(b)(3)(ii)(A). The NRC Resident Inspector has been notified.
The following information was provided by the licensee via email: On 11/12/2021 EN 55574 reported possible evidence of pressure boundary through-wall leakage observed on a Core Exit Thermocouple (CET) tube. On 3/10/2022, based on laboratory analysis of the affected CET tube section, FPL Engineering determined that there was no pressure boundary through-wall leakage associated with this event. Analysis identified that the leakage likely originated from an adjacent threaded compression fitting on a tubing joint. This condition complies with ASME Section XI requirements and is therefore not reportable. This follow-up NRCOC notification is a retraction of EN 55574. The NRC Resident Inspector has been notified. Notified R2DO (Miller). |
| Where | |
|---|---|
Turkey Point  Florida (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| LER: | 05000250/LER-2021-004 Cancelation of LER 2021-004 Through-Wall Leakage from Core Exit Thermocouple Tubing |
| Time - Person (Reporting Time:+-0.3 h-0.0125 days <br />-0.00179 weeks <br />-4.1094e-4 months <br />) | |
| Opened: | Humberto Benitez 20:47 Nov 12, 2021 |
| NRC Officer: | Donald Norwood |
| Last Updated: | Mar 28, 2022 |
| 55574 - NRC Website
Loading map... | |
Unit 3 | |
|---|---|
| Reactor critical | Not Critical |
| Scram | No |
| Before | Hot Standby (0 %) |
| After | Hot Standby (0 %) |
WEEKMONTHYEARENS 575832025-03-03T23:03:0003 March 2025 23:03:00
[Table view]10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition ENS 564742023-04-15T15:12:00015 April 2023 15:12:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded RCS Pressure Boundary Degraded ENS 555742021-11-12T21:05:00012 November 2021 21:05:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Coolant System Pressure Boundary Degraded ENS 499332014-03-20T02:02:00020 March 2014 02:02:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Potential Leak Discovered Around Pressurizer Heater Bank ENS 463622010-10-26T02:00:00026 October 2010 02:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Containment Liner Corrosion Degradation ENS 443992008-08-07T16:30:0007 August 2008 16:30:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Principal Safety Barrier ENS 436412007-09-14T03:04:00014 September 2007 03:04:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Potential Reactor Pressure Boundary Leakage ENS 436272007-09-08T16:28:0008 September 2007 16:28:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Pressure Boundary Leakage 2025-03-03T23:03:00 | |