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St Lucie Plant, Unit 2, manually tripped the reactor at 0531 hrs. EST, as part of a controlled reactor plant shutdown, in response to an RCS leak rate of 0.28 gpm, indicated to be associated with the 2B1 Reactor Coolant Pump seal package. All systems functioned as expected, satisfactorily. All CEAs fully inserted. Decay Heat removal is with Steam Generators and Main Feedwater. This report is made pursuant to 10 CFR 50.72(b)(2)(iv)(B). Unit 2 will cooldown to Mode 5 for repairs. The licensee informed the NRC Resident Inspector.

• * * UPDATE FROM ALAN HALL TO HOWIE CROUCH @ 1218 EST ON 1/28/08 * * *

St. Lucie Plant, Unit 2, reported their manual reactor trip of 0531 hrs. EST, at 0630 hrs. EST, for an unidentified leak associated with the 2B1 RCP seal package (EN 43941). Subsequent investigation, reported to the STA (Shift Technical Advisor) at 1015 hrs. EST, determined that this leak constitutes an RCS Pressure Boundary Leak. This leak is at a pipe-to-flange weld on the outboard side of the first flanged coupling of the 2B1 RCP Upper Cavity Seal pressure sensing line. Investigation is in progress to determine the detailed configuration at the leak and root cause. There were NO ESFAS signals or actuations. Decay Heat Removal continues on Steam Generators, with MFW (Main Feedwater) and SBCS (Steam Bypass Control System); Off-Site power continues (to be) available and stable; Unit 1 at 100% power with operations and conditions normal. This report is made pursuant to 10 CFR 50.72(b)(3)(ii)(A). The licensee informed the NRC Resident Inspector of this update. Notified R2DO (Bonser).

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.