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| Start date | Reporting criterion | Title | Event description | System | LER | |
|---|---|---|---|---|---|---|
| ENS 56474 | 15 April 2023 15:12:00 | 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | RCS Pressure Boundary Degraded | The following information was provided by the licensee via email: At 1112 EDT on 4/15/23, it was determined that the (reactor coolant system) RCS pressure boundary does not meet ASME Section XI, Table IWB-341 0-1, `Acceptable Standards,' due to through wall leak of the flux mapper seal table guide tube H-6. Corrective actions have been scheduled. `This event is being reported pursuant to 10 CFR 50.72(b)(3)(ii)(A). A follow-up review of the condition revealed that 10 CFR 50.72 notification was applicable within 8 hours of the time of discovery on 04/15/23. The NRC Resident Inspector has been notified. | ||
| ENS 55574 | 12 November 2021 21:05:00 | 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | Reactor Coolant System Pressure Boundary Degraded | 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). | Reactor Coolant System | 05000250/LER-2021-004, Cancelation of LER 2021-004, Through-Wall Leakage from Core Exit Thermocouple Tubing Cancelation of LER 2021-004 Through-Wall Leakage from Core Exit Thermocouple Tubing |
| ENS 49933 | 20 March 2014 02:02:00 | 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | Potential Leak Discovered Around Pressurizer Heater Bank | This report is in accordance with 10 CFR 50.72(b)(3)(ii)(A). During an inspection, a small amount of boric acid residue was noted in the vicinity of the Pressurizer heater components. Subsequent examination revealed a small flaw in Pressurizer Backup heater Bank B element 11. This component is part of the primary system boundary. Repair options are being evaluated. Currently, Unit 3 is in Mode 5 in preparation for refueling. The repair will be performed prior to restart. The NRC Resident Inspector has been informed. | 05000250/LER-2014-002 | |
| ENS 46362 | 26 October 2010 02:00:00 | 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | Containment Liner Corrosion Degradation | This report is made in accordance with 10 CFR 50.72(b)(3)(ii) as a condition resulting in a serious degradation of the Containment liner. During a visual inspection on 10/22/10, corrosion was found in the containment sump liner on Unit 3, A more detailed inspection was performed on 10/24/10 after the corroded area was cleaned. Evaluation of the inspection results has determined that the corrosion is greater than allowed by the ASME Code, including through wall areas, and requires repair. At this time, it is not known whether any leakage caused by the through-wall condition would have resulted in exceeding the containment allowed leakage limit. Unit 3 is currently in Mode 5 preparing to return to service following refueling. The corroded areas will be repaired prior to entering Mode 4. The licensee notified the NRC Resident Inspector | 05000250/LER-2010-005 | |
| ENS 44399 | 7 August 2008 16:30:00 | 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | Degraded Principal Safety Barrier | This is a late non-emergency notification to the NRC Operations Center in accordance with 10 CFR 50.72(b)(3)(ii)(A) due to the degradation of a principal safety barrier. A flaw in a weld in a 3/4 inch test connection off the seal water injection line for the 4B reactor coolant pump was identified at approximately 1230 during a containment entry on August 7, 2008. The flaw is leaking at the rate of approximately 0.14 gpm (current total), it (the leak) is isolable, and the leakage is currently considered as unidentified leakage from the reactor coolant system. The Technical Specification limit for unidentified leakage is 1.0 gpm. Currently, the leak is being monitored while repair options are evaluated. The licensee notified the NRC Resident Inspector. | Reactor Coolant System | |
| ENS 43641 | 14 September 2007 03:04:00 | 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | Potential Reactor Pressure Boundary Leakage | During an investigation in response to a low megger reading, a small amount of water was discovered in the environmental qualification boundary of the 22B RCS Thot thermowell (TE-3-422B2). Analysis of the water on 9/13/07 at 2304 showed Cesium 137 and 134, and Magnesium 54 indicating that the source of water intrusion into the thermowell was likely reactor coolant system (RCS) fluid. We are continuing the investigation for potential causes of water intrusion other than the Reactor Coolant System. This report is being made based on the previous indication of RCS leakage into 23A, RCS Tcold thermowell (TE-3-420) (see EN #43627 from 09/10/07) and similar discovery in our preliminary investigation. PTN Unit 3 Technical Specifications (TS) Limiting Condition for Operation (LCO) 3.4.6.2.a permits no reactor coolant pressure boundary leakage in Modes 1-4. This report to the NRC is pursuant to the requirements of 10 CFR 50.72 (b)(3)(ii)(A) as a degraded condition. Turkey Point Unit 3 is presently defueled. The licensee will notify the NRC Resident Inspector. | Reactor Coolant System | |
| ENS 43627 | 8 September 2007 16:28:00 | 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | Reactor Pressure Boundary Leakage | On September 7, 2007, a small amount of water was discovered in the environmental qualification boundary of the 3B RCS Tcold thermowell (TE-3-420) during inspection of the thermowell. Subsequent mass spectroscopy analysis conducted at 1228, on September 8, 2007, indicated small levels of lithium, boron, strontium, and bromine indicating that the source of the water intrusion into the thermowell was likely reactor coolant system (RCS) fluid. Turkey Point Unit 3 Technical Specification (TS) Limiting Condition for Operation (LCO) 3.4.6.2.a permits no reactor coolant system pressure boundary leakage. As a result of the chemical analysis and indication of fluid in the thermowell, this condition is being reported to the NRC pursuant to the requirements of 10 CFR 50.72(b)(3)(ii)(A) as a degraded condition. An investigation of the source of the water intrusion into the thermowell is ongoing. Leakage into the TE-3-420 was previously noted during the last refueling outage for Unit 3 in March 2006 and a Short Notice Outage (SNO) conducted in June 2007. Previous inspections and sampling did not indicate the presence of boron or activity levels that were consistent with RCS water. At the time of discovery, Turkey Point Unit 3 was in Operational Mode 6 (Refueling). Turkey Point Unit 3 is presently defueled. This is a late prompt notification. The NRC Resident inspector will be notified. | Reactor Coolant System |