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Event Notification Report for September 28, 2003

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
09/27/2003 - 09/28/2003

EVENT NUMBERS
4020440205

Power Reactor
Event Number: 40204
Facility: ARKANSAS NUCLEAR
Region: 4     State: AR
Unit: [1] [] []
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: BLAKE HOQUE
HQ OPS Officer: MIKE RIPLEY
Notification Date: 09/28/2003
Notification Time: 03:02 [ET]
Event Date: 09/28/2003
Event Time: 00:13 [CDT]
Last Update Date: 09/28/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
GREG PICK (R4)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 100 Power Operation
Event Text
OFFSITE NOTIFICATION DUE TO REPORT OF EMERGENCY SIREN ACTUATION

"At 00:13 on 9/28/03, the Unit 1 Control Room received an offsite call from the Pope County 911 office stating that two local individuals had reported the actuation of emergency sirens in the Russellville area. The Arkansas Department of Health, who controls the actuation of the sirens, was contacted; but they had no indication of the sirens alarming at the time that they were notified. The actuation of the sirens has not been confirmed.

"This report is being made in accordance with SAF 4.1 'News Release or Government Agency Notification' and
10CFR50.72(b)(2)(xi) since there was a notification of state/county agencies of inadvertent actuation of part of the public notification system."

The licensee will inform the state and has informed the NRC Resident Inspector.


Power Reactor
Event Number: 40205
Facility: COOPER
Region: 4     State: NE
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: WILLIAM GILBERT
HQ OPS Officer: ERIC THOMAS
Notification Date: 09/29/2003
Notification Time: 15:22 [ET]
Event Date: 09/28/2003
Event Time: 23:45 [CDT]
Last Update Date: 09/29/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
CHUCK CAIN (R4)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 65 Power Operation 22 Power Operation
Event Text
50.72 NON-EMERGENCY - ACCIDENT MITIGATION

"This report is being made in accordance with 10CFR50.72 section (b)(3)(v)(D).

"At 2345 [CDT] on 9/28/03, while performing Turbine Trip Testing, the required sequence of events failed to occur, and it was determined that a turbine trip would not occur when required by Technical Specification 3.3.2.2, Feedwater and Main Turbine High Water Level Trip. Condition B of Specification 3.3.2.2 was entered, requiring restoration [of] highwater level trip capability in two hours, and Condition C requiring that thermal power be reduced to less than 25% in four hours.

"The feedwater and main turbine high water level trip instrumentation is assumed to be capable of providing a turbine trip in the design basis transient analysis for a feedwater controller failure, maximum demand event. The Level 8 trip indirectly initiates a reactor scram from the main turbine trip (above 30% RTP) and trips the feedwater pumps, thereby terminating the event. The reactor scram mitigates the reduction in MCPR [Minimum Critical Power Ratio].

"Since the Turbine trip would not have occurred, the reactor scram would not have occurred. At 0530 on 9/29/03 reactor power was lowered to below 25%.

"This event was determined to be reportable on 9/29/2003 at 1230 [CDT]."

The licensee notified the NRC Resident Inspector.