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On October 25, 2006, at approximately 0247 … On October 25, 2006, at approximately 0247 hours (EDT), Main Control Room operators observed indications of a 100% load rejection and manually tripped the reactor at 0248 hours (EDT). During the event, Main Control Room operators received an alarm indicating that one or both pressurizer PORVs lifted briefly. The PORV(s) reclosed as designed. The reactor is currently stable in Mode 3. </br>During the event, the steam generator PORVs briefly opened and re-closed, as expected. All controls rods indicated fully inserted following the reactor trip. The normal post-trip electrical lineup is providing power to the plant and the electrical system is stable at this time. Decay heat is currently being removed by use of the normal feedwater system and the condenser steam dumps. </br>The cause of this event is under investigation. Follow-up notifications will be provided if important new information is obtained or plant conditions significantly change.</br>The licensee reported no steam generator tube leakage i.e. no radionuclide release during the brief lifting of the steam generator PORVs.</br> </br>The licensee notified the NRC Resident Inspector.</br>* * * UPDATE ON 10/25/2006 AT 0941 FROM G. SANDERS TO M. ABRAMOVITZ * * *</br>Subsequent to the initial notification, it has been determined that the automatic initiation of the Auxiliary Feedwater (AFW) System is also reportable under 10 CFR 50.72(b)(3)(iv)(A), Specified System Actuation. The AFW System automatically actuated as expected during the event in response to the secondary plant transient.</br>The licensee notified the NRC Resident Inspector.</br>Notified the R2DO (Ernestes).t Inspector.
Notified the R2DO (Ernestes). +
06:48:00, 25 October 2006 +
42,933 +
06:32:00, 25 October 2006 +
06:48:00, 25 October 2006 +
On October 25, 2006, at approximately 0247 … On October 25, 2006, at approximately 0247 hours (EDT), Main Control Room operators observed indications of a 100% load rejection and manually tripped the reactor at 0248 hours (EDT). During the event, Main Control Room operators received an alarm indicating that one or both pressurizer PORVs lifted briefly. The PORV(s) reclosed as designed. The reactor is currently stable in Mode 3. </br>During the event, the steam generator PORVs briefly opened and re-closed, as expected. All controls rods indicated fully inserted following the reactor trip. The normal post-trip electrical lineup is providing power to the plant and the electrical system is stable at this time. Decay heat is currently being removed by use of the normal feedwater system and the condenser steam dumps. </br>The cause of this event is under investigation. Follow-up notifications will be provided if important new information is obtained or plant conditions significantly change.</br>The licensee reported no steam generator tube leakage i.e. no radionuclide release during the brief lifting of the steam generator PORVs.</br> </br>The licensee notified the NRC Resident Inspector.</br>* * * UPDATE ON 10/25/2006 AT 0941 FROM G. SANDERS TO M. ABRAMOVITZ * * *</br>Subsequent to the initial notification, it has been determined that the automatic initiation of the Auxiliary Feedwater (AFW) System is also reportable under 10 CFR 50.72(b)(3)(iv)(A), Specified System Actuation. The AFW System automatically actuated as expected during the event in response to the secondary plant transient.</br>The licensee notified the NRC Resident Inspector.</br>Notified the R2DO (Ernestes).t Inspector.
Notified the R2DO (Ernestes). +
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