Event Notification Report for April 04, 2005
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
04/03/2005 - 04/04/2005
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 41562
Facility: QUAD CITIES
Region: 3 State: IL
Unit: [1] [2] []
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: DUANE HAAS
HQ OPS Officer: HOWIE CROUCH
Region: 3 State: IL
Unit: [1] [2] []
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: DUANE HAAS
HQ OPS Officer: HOWIE CROUCH
Notification Date: 04/04/2005
Notification Time: 19:51 [ET]
Event Date: 04/04/2005
Event Time: 16:07 [CST]
Last Update Date: 04/13/2005
Notification Time: 19:51 [ET]
Event Date: 04/04/2005
Event Time: 16:07 [CST]
Last Update Date: 04/13/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
KENNETH O'BRIEN (R3)
KENNETH O'BRIEN (R3)
| 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 |
MINIMUM SWITCHYARD VOLTAGE REQUIREMENTS NOT MET
The following information was obtained from the licensee via facsimile (licensee text in quotes):
"On April 4, 2005, at 1607 hours [CDT], Quad Cities was notified that the switchyard voltage was below that required to ensure that offsite power would remain available following a design basis accident. Both sources of off site power were declared inoperable. The appropriate Technical Specification required actions were taken for both units. The ability of the Emergency Diesel Generators to perform their design function is not affected by this condition. This event is being reported in accordance with 10 CFR 50.72(b)(3)(v)(D) as a condition that could have prevented the fulfillment of a safety function given the predicted post-LOCA switchyard voltage.
"This notification report is similar to the condition reported on March 24, 2005 (reference EN#41524 for additional information)."
Technical Specification minimum switchyard voltage is 348.4 KV. Switchyard voltage at 1607 hrs. was approximately 343.7 KV. Switchyard voltage at the time of NRC notification was 358 KV which is above the Technical Specification minimum.
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)
The following information was obtained from the licensee via facsimile (licensee text in quotes):
"On April 4, 2005, at 1607 hours [CDT], Quad Cities was notified that the switchyard voltage was below that required to ensure that offsite power would remain available following a design basis accident. Both sources of off site power were declared inoperable. The appropriate Technical Specification required actions were taken for both units. The ability of the Emergency Diesel Generators to perform their design function is not affected by this condition. This event is being reported in accordance with 10 CFR 50.72(b)(3)(v)(D) as a condition that could have prevented the fulfillment of a safety function given the predicted post-LOCA switchyard voltage.
"This notification report is similar to the condition reported on March 24, 2005 (reference EN#41524 for additional information)."
Technical Specification minimum switchyard voltage is 348.4 KV. Switchyard voltage at 1607 hrs. was approximately 343.7 KV. Switchyard voltage at the time of NRC notification was 358 KV which is above the Technical Specification minimum.
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: 41563
Facility: SEABROOK
Region: 1 State: NH
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: PAUL DUNDIN
HQ OPS Officer: HOWIE CROUCH
Region: 1 State: NH
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: PAUL DUNDIN
HQ OPS Officer: HOWIE CROUCH
Notification Date: 04/05/2005
Notification Time: 14:00 [ET]
Event Date: 04/04/2005
Event Time: 20:36 [EST]
Last Update Date: 04/05/2005
Notification Time: 14:00 [ET]
Event Date: 04/04/2005
Event Time: 20:36 [EST]
Last Update Date: 04/05/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
10 CFR Section:
26.73 - FITNESS FOR DUTY
Person (Organization):
JAMES NOGGLE (R1)
JAMES NOGGLE (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
FITNESS FOR DUTY REPORT
A non-licensed contract supervisor was determined to be under the influence of alcohol during for-cause testing. The employee's access to the plant has been terminated. Contact the Headquarters Operations Officer for additional details.
The licensee has notified the NRC Resident Inspector.
A non-licensed contract supervisor was determined to be under the influence of alcohol during for-cause testing. The employee's access to the plant has been terminated. Contact the Headquarters Operations Officer for additional details.
The licensee has notified the NRC Resident Inspector.