Skip to main content

Event Notification Report for April 11, 2005

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
04/10/2005 - 04/11/2005

EVENT NUMBERS
41586415874158841589

Power Reactor
Event Number: 41586
Facility: OCONEE
Region: 2     State: SC
Unit: [1] [] []
RX Type: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP
NRC Notified By: DAN HALL
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 04/11/2005
Notification Time: 11:03 [ET]
Event Date: 04/11/2005
Event Time: 09:49 [EST]
Last Update Date: 04/11/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xii) - OFFSITE MEDICAL
Person (Organization):
WALTER ROGERS (R2)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Cold Shutdown 0 Cold Shutdown
Event Text
POSSIBLE CONTAMINATED INJURED PERSONNEL TRANSPORTED TO HOSPITAL

"Individual received laceration to right leg while working in Unit 1 Reactor Building. Individual transported to Oconee Hospital at 0949 with potential contamination. Radiation Protection conducted survey at 1046 in hospital and found no indication of contamination in wounded of individual."

The licensee notified the NRC Resident Inspector


!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 41587
Facility: QUAD CITIES
Region: 3     State: IL
Unit: [1] [2] []
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: DAVE BOWMAN
HQ OPS Officer: BILL HUFFMAN
Notification Date: 04/11/2005
Notification Time: 15:39 [ET]
Event Date: 04/11/2005
Event Time: 12:40 [CST]
Last Update Date: 04/13/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
JOHN MADERA (R3)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Refueling 0 Refueling
2 N Y 85 Power Operation 85 Power Operation
Event Text
MINIMUM SWITCHYARD VOLTAGE REQUIREMENTS NOT MET

"At 1240 on April 11, 2005 Quad Cities Station was notified calculated post-LOCA switchyard voltage is below the minimum acceptable value required to ensure offsite power will remain available following a design basis accident. The appropriate Technical Specification Actions have been taken for both Units. The ability of the Emergency Diesel Generators to fulfill their design function is not affected by this condition. This event is being reported in accordance with 10CFR50.72(b)(3)(v)(D) as a condition that could have prevented the fulfillment of a safety function given the predicted post-LOCA switchyard voltage.

"Actual Switchyard voltage at the time of this notification is 361 Kv. The required minimum post-accident switchyard voltage is 348.4 Kv, while the projected post-accident voltage which prompted this notification is 346.3 Kv.

"This notification is similar to the condition reported on March 24, 2005 (EN #41524) and April 4, 2005 (EN #41562)."

The licensee has notified the NRC Resident Inspector.

* * * RETRACTION FROM C. STEFFES TO M. RIPLEY 1556 EDT 04/13/05 * * *

"The purpose of this report is to retract the following ENS reports: 1) ENS # 41524 on March 24, 2005; 2) ENS # 41562 on April 4, 2005; and 3) ENS # 41587 on April 11, 2005.

"These reports were made following notification to Quad Cities that the switchyard voltage was below the required value necessary to ensure that offsite power would remain available following a design basis accident. For each event, both sources of offsite power were declared inoperable, the appropriate Technical Specification required actions were taken for both units, and an ENS notification was made for a condition that could have prevented fulfillment of a safety function.

"The events occurred when Unit 1 was in a refueling outage and Unit 2 was operating at 85% power. Subsequent Engineering analysis has determined that with a unit shutdown, and the large 4 Kv loads on that unit not running, the required minimum post-accident switchyard voltage is reduced to 339.3 kV (for the shutdown unit). Given the new minimum post-accident switchyard voltage, it was confirmed that there was a source of off-site power available to the Station. Specifically for all three events, the projected post-accident switchyard voltage (which ranged between 343 kV to 347.5 kV) was higher than the required minimum post-accident switchyard voltage (339.3 kV) for the shutdown unit. As a result, there was no condition present that could have prevented fulfillment of a safety function, and thus these events are not reportable."

The licensee notified the NRC Resident Inspector. Notified R3 DO (J. Madera)


Power Reactor
Event Number: 41588
Facility: COOPER
Region: 4     State: NE
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: ANDREW OHRABLO
HQ OPS Officer: BILL HUFFMAN
Notification Date: 04/11/2005
Notification Time: 19:11 [ET]
Event Date: 04/11/2005
Event Time: 16:04 [CST]
Last Update Date: 04/12/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
REBECCA NEASE (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
LOSS OF PUBLIC PROMPT NOTIFICATION CAPABILITY

"At approximately 1604 CDT on 4/11/05, Cooper Nuclear Station (CNS) was informed by Emergency Preparedness officials of Atchison County that the radio transmission tower that provides signals to activate tone alert radios within the 10-mile Emergency Planning Zone (EPZ) was not functioning. Tone alert radio is relied on by approximately 650 households in the EPZ who are not in audible range of sirens for notification of an emergency at CNS. Based on a total EPZ population currently estimated at 4600 persons (who are alerted principally by sirens and the tone alert radio), this is considered to be a major loss of the Public Prompt Notification system capability, and is reportable under 10CFR50.72(b)(3)(xiii).

"Investigations are ongoing, a repair technician has been dispatched to the tower. During the interim, compensatory measures have been verified to be in place via state and local emergency planning officials for backup route alerting for personnel within the 10-mile EPZ."

NRC Resident Inspector was notified.

* * * UPDATED PROVIDED BY LICENSEE (JOBE) TO NRC (HELD) AT 1632 ON 4/12/05 * * *

"22:53 on 4/11/05- CNS was notified by the NWS [National Weather Service] that the transmitter had been returned to high power service at 19:35. The cause of the high power transmitter loss was a lightning strike to the transmitter. The strike did not result in any equipment damage, however the transmitter had to be manually reset.

"22:55 on 4/11/05- CNS contacted Nemaha and Richardson County Sheriff's Departments and the Atchison County 911 center to notify them that the transmitter/tower had been returned to service.

"Operation of equipment was verified. Transmitter tower and tone alert radios have been returned to service."

NRC Resident Inspector was notified by the licensee.

R4DO (Nease) was notified.


Power Reactor
Event Number: 41589
Facility: GRAND GULF
Region: 4     State: MS
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: FRANK WEAVER
HQ OPS Officer: JEFF ROTTON
Notification Date: 04/11/2005
Notification Time: 19:59 [ET]
Event Date: 04/11/2005
Event Time: 16:38 [CST]
Last Update Date: 04/11/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
REBECCA NEASE (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 INADVERTENT SINGLE EMERGENCY SIREN ACTIVATION

"A single Alert Notification System siren inadvertently sounded. The Clairborne Count Civil Defense Department is issuing a notification to local media advising the public of the inadvertent sounding and that no emergency exists. The siren has been secured. There were no effects on plant operations."

The inadvertent siren actuation may have been due to bad weather in the area.

The licensee has notified the NRC Resident Inspector.