Event Notification Report for December 08, 2007
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
12/07/2007 - 12/08/2007
EVENT NUMBERS
43830
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 43830
Facility: CALVERT CLIFFS
Region: 1 State: MD
Unit: [] [2] []
RX Type: [1] CE,[2] CE
NRC Notified By: KENT MILLS
HQ OPS Officer: JEFF ROTTON
Region: 1 State: MD
Unit: [] [2] []
RX Type: [1] CE,[2] CE
NRC Notified By: KENT MILLS
HQ OPS Officer: JEFF ROTTON
Notification Date: 12/08/2007
Notification Time: 07:54 [ET]
Event Date: 12/08/2007
Event Time: 00:50 [EST]
Last Update Date: 12/27/2007
Notification Time: 07:54 [ET]
Event Date: 12/08/2007
Event Time: 00:50 [EST]
Last Update Date: 12/27/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
RICHARD BARKLEY (R1)
RICHARD BARKLEY (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
REACTOR POWER INADVERTENTLY INCREASED ABOVE ACCIDENT ANALYSIS LIMIT
"On December 8, 2007 at 0050, during plant maneuvers to return Unit Two from 84% to 100% reactor power following main turbine control valve testing, the two-minute instantaneous thermal power was inadvertently increased above the accident analysis thermal power limit of 2735.1 thermal megawatts while adjusting main turbine load to maintain Reactor Coolant temperature on program. The maximum power level attained was 2741 thermal megawatts. This is a potentially unanalyzed condition. Prompt operator action was taken to restore reactor power to within limits. Reactor thermal power was restored to within limits [below 2735.1 thermal megawatts] eight minutes later at 0058."
The two-minute instantaneous thermal power was restored to below 2700 thermal megawatts (100% rated thermal power) at 0105.
The licensee notified the NRC Resident Inspector.
* * * RETRACTION FROM DAVID SUPANICH TO HOWIE CROUCH ON 12/27/07 @ 1243 EST VIA EMAIL * * *
"Based on the results of an evaluation of the event, the licensee concluded that Unit 2 operated at a maximum power level of 2741 MWth [101.5 percent rated thermal power (RTP)]. The maximum analyzed steady-state reactor core power levels, including uncertainties, are 102 percent of RTP or 2754 MWth. The unit was not in an unanalyzed condition. Therefore, this event is not reportable.
"Based on this evaluation, the associated non-emergency notification made on December 8, 2007, is retracted."
Licensee has notified the NRC Resident Inspector. Notified R1DO (Perry).
"On December 8, 2007 at 0050, during plant maneuvers to return Unit Two from 84% to 100% reactor power following main turbine control valve testing, the two-minute instantaneous thermal power was inadvertently increased above the accident analysis thermal power limit of 2735.1 thermal megawatts while adjusting main turbine load to maintain Reactor Coolant temperature on program. The maximum power level attained was 2741 thermal megawatts. This is a potentially unanalyzed condition. Prompt operator action was taken to restore reactor power to within limits. Reactor thermal power was restored to within limits [below 2735.1 thermal megawatts] eight minutes later at 0058."
The two-minute instantaneous thermal power was restored to below 2700 thermal megawatts (100% rated thermal power) at 0105.
The licensee notified the NRC Resident Inspector.
* * * RETRACTION FROM DAVID SUPANICH TO HOWIE CROUCH ON 12/27/07 @ 1243 EST VIA EMAIL * * *
"Based on the results of an evaluation of the event, the licensee concluded that Unit 2 operated at a maximum power level of 2741 MWth [101.5 percent rated thermal power (RTP)]. The maximum analyzed steady-state reactor core power levels, including uncertainties, are 102 percent of RTP or 2754 MWth. The unit was not in an unanalyzed condition. Therefore, this event is not reportable.
"Based on this evaluation, the associated non-emergency notification made on December 8, 2007, is retracted."
Licensee has notified the NRC Resident Inspector. Notified R1DO (Perry).