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On August 1, 2016 at 0342 EDT St. Lucie Unit 1 commenced a unit shutdown required by Technical Specifications due to Reactor Coolant System Pressure Boundary Leakage in excess of the allowable limit of zero leakage. The leak was initially identified on July 31, 2016 at 2115 EDT as not Pressure Boundary leakage. After further analysis, the leak was determined to be Reactor Coolant System Pressure Boundary leakage at 0123 on August 1, 2016. The leakage is estimated as less than one tenth of a gallon per minute and is not impacting the ability to shut down the unit. Additional impact of the leak is under evaluation. This report is submitted in accordance with 10CFR50.72(b)(2)(i) as 'The initiation of any nuclear plant shutdown required by the plant's Technical Specifications.' The location of the leak is on the Instrumentation piping welded connection at Flow Element FE-3311 attached to (the) Emergency Core Cooling System Injection header to Reactor Coolant System Loop 1A2. The leak activity is 0.167 microCuries per ml. The NRC Resident Inspector has been notified.

• * * RETRACTION AT 1335 EDT ON 09/23/16 FROM RICHARD SCISCENTE TO JEFF HERRERA * * *

The purpose of this notification is to retract a previous report made on EN 52138. NRC notification was initially made as a result of a plant shutdown required by technical specifications (TS) for Reactor Coolant System (RCS) pressure boundary leakage. Subsequent to the initial report, St. Lucie has determined that the RCS leakage was from a seal weld on a threaded connection that was not pressure boundary leakage. However, the leak was non-isolable and required RCS depressurization to allow immediate investigation to ensure there were no faults in a RCS component body or pipe wall. The leakage was estimated to be less than one tenth of a gallon per minute and did not impact the ability to shut down the unit. No TS limits were exceeded during this event. Therefore, the plant shutdown to investigate and correct leakage past the seal weld of a threaded connection does not meet the reporting requirements of 10 CFR 50.72 or 10 CFR 50.73. The NRC Resident Inspector has been notified. Notified the R2DO (Blamey).

On July 25th, 2014 at 1129 EDT, during investigation of a small leak inside Saint Lucie Unit 2 containment, a defect was identified on a valve (V3811, Safety Injection Tank 281 Outlet Vent Valve). This valve is within the Q-Group A (ASME Class 1 equivalent) boundary of the safety injection line. The leak is currently isolated from the reactor coolant system by a Technical Specification credited isolation check valve. The affected Safety Injection Tank has been declared inoperable and the unit has entered 24 hour shutdown (Technical Specification) action statement 3.5.1.b. Unit shutdown is currently being planned for repair of the flaw. This condition is being reported pursuant to 10 CFR 50.72(b)(3)(ii)(A). The licensee has notified the NRC Resident Inspector.

• * * UPDATE FROM JOHN REXRODE TO VINCE KLCO AT 0053 EDT ON 7/26/14 * * *

On July 26, 2014 at 0002 EDT, Saint Lucie Unit 2 commenced shutdown to repair the identified leak. This condition is being reported pursuant to 10 CFR 50.72(b)(3)(ii)(A) and 10 CFR 50.72(b)(2)(i). The NRC Resident Inspector has been notified. Unit 2 current power is 88% at 0105 EDT and expect to trip the unit at approximately 0400 EDT. Notified the R2DO (Musser).

At 0347 on 12/28/07, during plant start up from a refueling outage while In Mode 2, one control element assembly (CEA) dropped to the bottom of the core from the upper electrical limit. The reactor was not critical at the time. Technical Specification LCO 3.1.3.1 action (e) was initiated to proceed to Mode 3 at 0450 while actions are taken to repair and retrieve the CEA. This four hour non-emergency report is being made pursuant to 10 CFR 50.72(b)(2)(i), the 'Initiation of any nuclear plant shutdown required by Technical Specifications'. The licensee notified the NRC Resident Inspector.

• * * RETRACTED ON 03/26/2008 AT 1433 EDT BY JACK BREEN TO DAN LIVERMORE * * *

The licensee is retracting this report based on the following: At 03:47 on 12/28/07, during plant start up from a refueling outage while in Mode 2, one control element assembly (CEA) dropped to the bottom of the core from the upper electrical limit. The reactor was not critical at the time. Technical Specification LCO 3.1.3.1 (Action E) was initiated to proceed to Mode 3 at 0450 while actions were taken to repair and retrieve the CEA. This event was reported as a four hour non-emergency report pursuant to 10CFR 50.72(b)(2)(i), 'The initiation of any nuclear plant shutdown required by Technical Specifications.' Upon further review of the event, and since the Unit was not critical in mode 2 at the time of the event, this event is not considered reportable in accordance with the guidance provide in NUREG-1022, Rev. 2, 'Event Reporting Guidelines 10CFR50.72 and 50.73,' in which 'The initiation of any plant shutdown' does not include mode changes required by TS if initiated after the plant is already in a shutdown condition. As such this notification is being retracted. The Site Resident has been notified of this retraction.