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At 1402 EST Turkey Point Unit 3, while operating at 100 percent, declared an Unusual Event due to unidentified leakage greater than 10 gallons per minute for more than 15 minutes. The abnormal procedure for Reactor Coolant System leakage was entered. The plant remains at 100 percent power. The cause of the leakage is under investigation. At 1446 EST it was verified that the leak had been isolated. The plant remains at 100 percent power. Unit 4 was unaffected. State and local authorities were notified by the licensee. The NRC Resident Inspector has been notified. Notified DHS SWO, FEMA Operations Center, CISA Central, FEMA NWC (email), DHS NRCC THD Dest (email), and DHS Nuclear SSA (email).

• * * UPDATE ON 12/08/22 AT 1621 (EST) FROM SZEMEI CHOI TO THOMAS HERRITY * * *

Turkey Point Unit 3 has isolated the leak. The Unusual Event was terminated at 1558 EST. The NRC Resident Inspector has been notified. Notified R2DO (Miller), NRR EO (Miller), and IR MOC (Crouch). Notified DHS SWO, FEMA Operations Center, CISA Central, FEMA NWC (email), DHS NRCC THD Dest (email), and DHS Nuclear SSA (email).

• * * RETRACTION FROM BRANDEN NATHE TO DONALD NORWOOD AT 1446 EST ON 1/9/2023 * * *

Turkey Point Nuclear Unit 3 is retracting this notification based on the following additional information not available at the time of the notification, Following the event for unidentified RCS leakage on 12/8/22 at 1403 EST, additional information demonstrated that an RCS leak did not exist. A review of indications showed that the in-service seal water return filter D/P (Differential Pressure) rose from 1 psid to 6 psid with a corresponding rise in VCT (Volume Control Tank) level as would be seen with an increase in excess letdown flowrate. Additionally, the on-contact radiation dose rate from the excess letdown piping in the U3 Pipe and Valve Room was measured by RP (Radiation Personnel) to be significantly higher than normal with no other sources of elevated radiation levels noted. Following the closure of CV-3-387, RCS To Excess Letdown HX (Heat Exchanger) Control Valve, a nominal input/output flow balance was able to be restored. Containment parameters including pressure, temperature, sump level and radiation level did not change during the event. Due to the shared nature of piping between excess letdown and seal water return, a challenge to system integrity would not allow RCP (Reactor Coolant Pump) controlled bleed-off to remain in service with a normal flow balance which it has at all times subsequent to the event. Turkey Point Nuclear reported initially based on the available information at the time and to ensure timeliness with emergency declaration and reporting notification requirements. The NRC Resident Inspector has been notified. Notified R2DO (Miller).

The following information was provided by the licensee via email: At 0050 EST on 3/12/22, while shutting down for entry into a scheduled refueling outage, the station discovered that a single Main Steam Isolation Valve (4A MSIV) did not fully close on demand. All other equipment operated as expected. This condition is being reported pursuant to 10 CFR 50.72(b)(3)(v). The NRC Resident Inspector has been notified.

• * * RETRACTION ON 04/26/22 AT 1422 EDT FROM DAVID STOIA TO BRIAN PARKS * * *

The following information was provided by the licensee via email: On 3/12/2022 at 0656 EDT Turkey Point Unit 4 notified the NRC pursuant to 10 CFR 50.72(b)(3)(v)(D) that a single Main Steam Isolation Valve (MSIV) did not fully close when manually demanded from the control room during shutdown of Unit 4 for a refueling outage. Following disassembly and inspection of the MSIV, Florida Power & Light Engineering identified the cause of the deficiency and determined that the valve would have fully seated under its design accident conditions. This notification is a retraction of EN# 55785. The NRC Resident Inspector has been notified of this retraction. Notified R2DO (Miller).

At 1240 EST on 12/14/20, it was determined that all Unit 4 Charging Pumps and Boration Flowpaths were simultaneously inoperable. This condition is being reported pursuant to 10 CFR 50.72(b)(3)(v). The NRC Resident Inspector has been notified.

• * * RETRACTION ON 2/10/2021 AT 1210 EST FROM DAVID STOIA TO BETHANY CECERE * * *

On 1/21/21 a past operability review was completed that assessed the event reported on 12/14/20. The evaluation concluded that the condition did not render any Unit 4 Charging Pump or all boration flowpaths inoperable, and that the 8-hour notification submitted on 12/14/20 was not required. This notification is a retraction of EN #55036. The NRC Site Resident has been notified of the EN #55036 retraction. Notified R2DO (Miller).

At 0925 (EST) on 1/2/2015, Engineering personnel identified a gas void in each of two Unit 4 cold leg High Head Safety Injection (HHSI) discharge lines which exceeded procedural gas accumulation acceptance criteria. This condition rendered the cold leg HHSI flow path inoperable and required entry into Technical Specification 3.0.3. The voids were vented and Technical Specification (TS) 3.0.3 was exited at 1032. The testing for gas voids conducted on 1/2/2015 was a follow-up to a gas void found in one Unit 4 HHSI line on 12/26/2014. On 12/26/14, TS 3.0.3 was entered at 1020 and exited at 1048 after the gas void was vented. After further review, the 12/26/2014 event was also reportable in accordance with 10 CFR 50.72(b)(3)(v)(D). Engineering evaluation will be performed for both events to determine the specific impact of the gas voids on HHSI system function. Cause evaluation is being conducted to determine the source of the gas and any needed corrective actions. Unit 3 was verified to not have this voiding issue. The licensee notified the NRC Resident Inspector.

• * * RETRACTION FROM SEAN BLOOM TO VINCE KLCO AT 1120 EDT ON 3/11/15 * * *

On 1/2/2015 at 1645 (EST), Event Notification 50714 reported to the NRCOC (Nuclear Regulatory Commission Operations Center) gas voids detected on 12/26/2014 and 1/2/2015 in Unit 4 cold leg High Head Safety Injection (HHSI) piping which exceeded procedural gas accumulation acceptance criteria. Subsequent analysis has determined that if a HHSI pump started with the measured gas voids present, the resulting system conditions would not have impacted the integrity of the Unit 4 HHSI discharge flow path to the reactor coolant system (RCS) and therefore its safety related function would not be impaired. The Unit 4 HHSI system discharge flow path to the RCS had been operable with the voids present, Technical Specification (TS) requirements were met, and entry into TS 3.0.3 was not required. The HHSI system remained capable of fulfilling the safety function to mitigate the consequences of an accident on Unit 4. Therefore, the immediate notification to the NRCOC on 1/2/2015 at 1645 in accordance with 10 CFR 50.72(b)(3)(v)(D) is hereby retracted. The NRC Resident Inspector has been informed. Notified R2DO (Shaeffer).