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The following information was provided by the licensee by email: On 06/18/2024 at 0317 EDT with Unit 2 at 18 percent power, the reactor was manually tripped due to elevated secondary chemistry levels (sodium and chlorides). The trip was uncomplicated with all systems responding normally post trip. Operations stabilized the plant in Mode 3. Decay heat is being removed by auxiliary feedwater and atmospheric dump valves. St. Lucie Unit 1 was unaffected and remains at 100 percent power. This event is being reported pursuant 10CFR 50.72(b)(2)(iv)(B). The NRC Resident Inspector has been notified. The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance: All rods fully inserted. An investigation is underway to determine the root cause of the elevated chemistry levels.

• * * RETRACTION ON 6/24/2024 AT 1315 FROM BOB MURRELL TO ADAM KOZIOL * * *

The following retraction was provided by the licensee via email: The purpose of this notification is to retract a previous report made on 06/18/2024 at 0652 (EDT) (EN# 57177). Notification of the event to the NRC was initially made because of inserting a manual reactor trip due to elevated secondary chemistry levels (sodium and chlorides). After the initial report, Florida Power and Light has concluded that the event did not meet the reporting requirements on 10 CFR 50.72(b)(2)(iv)(B) since it was part of a normal plant shutdown. Therefore, this event is not considered an unplanned scram and is not reportable to the NRC as a Licensee Event Report per 10 CFR 50.73. The NRC Senior Resident Inspector has been notified.

At 1257 EST on January 3, 2024, it was determined that a class 1 system barrier had a through wall flaw with leakage. The leakage renders both trains of high pressure safety injection inoperable. The unit is being cooled down to cold shutdown to comply with technical specifications. This event is being reported pursuant to 10 CFR 50.72(b)(3)(ii)(A) and 10 CFR 50.72(b)(3)(v)(D). The NRC Resident Inspector has been notified. The following additional information was obtained from the licensee in accordance with Headquarters Operations Officer Report Guidance: At the time of the discovery, the unit was shutdown in mode 3. The unit was experiencing signs of reactor coolant system leakage and a shutdown was initiated in order to search for possible sources. The unit is currently cooling down and proceeding to mode 5, where the safety function is not required.

• * *UPDATE AT 1257 EST ON 02/12/24 FROM B. MURRELL TO T. HERRITY***

The purpose of this notification update is to retract a portion of a previous report, made on 1/03/2024 at 1257 EST (EN 56912). Notification of the event to the NRC was initially made as a result of declaring both trains of unit 2 high pressure safety injection system inoperable due to reactor coolant barrier through wall leak on the vent line for the 2A2 safety injection tank. Subsequent to the initial report, Florida Power and Light has concluded that the through wall leak rate was insignificant, and therefore the safety injection system's safety-related function was maintained. Therefore, this portion of the event is not considered a safety system functional failure and is not reportable to the NRC pursuant 10 CFR 50.72(3)(v)(D). This update does not affect the original 10 CFR 50.72(b)(3)(ii)(A) report for the degraded condition related to the reactor coolant barrier through wall leak. The NRC Resident Inspector has been notified. Notified R2DO (Miller).

The following information was provided by the licensee via email: On June 2, 2023, a blind specimen provided to a laboratory did not analyze as expected. The specimen reported a false negative for amphetamines and a false positive for opiates. This event is being reported pursuant to 10 CFR 26.719(c)(2) and 10 CFR 26.719(c)(3). The NRC Resident Inspector has been notified.

• * * RETRACTION AT 0909 EDT ON JUNE 22, 2023 FROM ANDREW CORRETTE TO BRIAN P. SMITH * * *

Follow-up investigation by an independent Health and Human Services laboratory confirmed that the blind specimen in question was analyzed correctly. The error is thought to have occurred during the preparation of the blind specimen, prior to delivery to the site. The NRC Resident Inspector has been notified." Notified R1DO (Eve) and FFD Group (email)

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 1741 EDT on September 26, 2022, it was discovered that both trains of the chemical volume and control system were simultaneously inoperable due to an unisolable piping flaw detected during plant pressurization in preparation for startup following refueling outage. St. Lucie Unit 2 was not affected and remains at 100 percent power. This event is being reported pursuant to 10 CFR 50.72(b)(3)(v)(D). The NRC Resident Inspector has been notified.

• * * RETRACTION FROM RICHARD ROGERS TO DONALD NORWOOD AT 1155 EST ON 11/11/2022 * * *

The following information was provided by the licensee via email: The purpose of this notification is to retract a previous report made on 09/26/2022 at 2239 EDT (EN 56128). Notification of the event to the NRC was initially made as a result of declaring both trains of U1 Chemical and Volume Control System inoperable due to a piping flaw detected during plant pressurization in preparation for startup following a refueling outage. Subsequent to the initial report, FPL (Florida Power and Light) has concluded that the flaw identified in line 2"-CH(1)104 did not exceed (with sufficient margin) the allowable axial flaw size utilizing the ASME Code Case N-869 methodology, and the Chemical and Volume Control System was Operable but degraded for the period of concern. Therefore, this event is not considered a Safety System Functional Failure and is not reportable to the NRC as a Licensee Event Report (LER) per 10 CFR 50.73. The NRC Senior Resident Inspector has been notified. Notified R2DO (Miller).

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.

• * * RETRACTION ON 3/28/2022 AT 0849 EDT FROM DAVID STOIA TO MIKE STAFFORD * * *

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).

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).

A Hurricane Warning is in effect for St. Lucie County including the plant site. A Hurricane Warning was confirmed with the State Watch Office at 1700 EDT. As a mater of procedure, St. Lucie Nuclear Power Plant entered an Unusual Event classification for the Hurricane Warning. State and local officials have been notified by the licensee. The NRC Resident Inspector was notified by the licensee. This report is submitted in accordance with 10 CFR 50.72(a)(1)(i) due to the Notice of Unusual Event and 10 CFR 50.72(b)(2)(xi) due to the Offsite Notification. Notified DHS SWO, FEMA OC, DHS NICC WO, CISA IOCC (email), DHS SWO (email); FEMA NWC (email), FEMA Ops Center (email), FEMA-NRCC-sasc (email), NRCC THD Desk (email), NuclearSSA (email).

• * * UPDATE ON 8/2/20 AT 1456 EDT FROM LOUIS ENGELKE TO BETHANY CECERE * * *

The Hurricane Warning was downgraded to a Tropical Storm Warning by the National Weather Service for St. Lucie County, including the plant site. At time 1445 EDT, on 08/02/20, St. Lucie Nuclear Plant has terminated from the Unusual Event classification. There are no changes in plant status for either unit. Both units are stable at 100% power. The NRC Resident Inspector was notified of this by the licensee. The licensee notified State and County officials of the termination. Notified R2DO (M. Miller), IRD MOC (Kennedy), NRR EO (C. Miller), DHS SWO, FEMA OC, DHS NICC WO, CISA IOCC (email), DHS SWO (email); FEMA NWC (email), FEMA Ops Center (email), FEMA-NRCC-sasc (email), NRCC THD Desk (email), NuclearSSA (email)