Event Notification Report for April 07, 2008
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
04/06/2008 - 04/07/2008
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 44122
Facility: COOK
Region: 3 State: MI
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JAMES SHAW
HQ OPS Officer: HOWIE CROUCH
Region: 3 State: MI
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JAMES SHAW
HQ OPS Officer: HOWIE CROUCH
Notification Date: 04/07/2008
Notification Time: 05:11 [ET]
Event Date: 04/07/2008
Event Time: 04:30 [EDT]
Last Update Date: 04/07/2008
Notification Time: 05:11 [ET]
Event Date: 04/07/2008
Event Time: 04:30 [EDT]
Last Update Date: 04/07/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
RICHARD SKOKOWSKI (R3)
RICHARD SKOKOWSKI (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 | 100 | Power Operation | 100 | Power Operation |
TECHNICAL SUPPORT CENTER MAY BECOME UNINHABITABLE DUE TO SCHEDULED MAINTENANCE
"At 04:30 hours on Monday, April 7, 2008, the Cook Nuclear Plant (CNP) removed the Technical Support Center [TSC] Heating Ventilation Air Conditioning [HVAC] System from service for planned maintenance. The TSC HVAC system will remain out of service for a period of approximately three days.
"Compensatory measures exist to relocate TSC personnel to the unaffected unit's control room if necessary based upon results of procedurally required monitoring of TSC radiological conditions.
"This notification is being made in accordance with NUREG 1022 as a potential unavailability of an emergency response facility in accordance with 10 CFR 50.72 (b)(3)(xiii).
"The licensee notified the NRC Resident Inspector. The licensee will supplement this notification upon returning the TSC HVAC system to normal operational status."
* * * UPDATE PROVIDED AT 1329 ON 04/07/08 BY RICHARD HACKMAN TO JEFF ROTTON * * *
The following information was provided by the licensee to RETRACT the event:
"Upon additional evaluation CNP determined that the planned maintenance reported above was limited in scope and did not remove the entire TSC HVAC system from service. The planned maintenance resulted in two of three fully redundant air chillers (air conditioners) being removed from service for maintenance. The third chiller and the TSC HVAC system is operable and remains in service. Therefore, the CNP TSC has been maintained in a configuration that ensures habitability.
"The NRC Resident Inspector has been notified of the retraction."
Notified R3DO (Skokowski).
"At 04:30 hours on Monday, April 7, 2008, the Cook Nuclear Plant (CNP) removed the Technical Support Center [TSC] Heating Ventilation Air Conditioning [HVAC] System from service for planned maintenance. The TSC HVAC system will remain out of service for a period of approximately three days.
"Compensatory measures exist to relocate TSC personnel to the unaffected unit's control room if necessary based upon results of procedurally required monitoring of TSC radiological conditions.
"This notification is being made in accordance with NUREG 1022 as a potential unavailability of an emergency response facility in accordance with 10 CFR 50.72 (b)(3)(xiii).
"The licensee notified the NRC Resident Inspector. The licensee will supplement this notification upon returning the TSC HVAC system to normal operational status."
* * * UPDATE PROVIDED AT 1329 ON 04/07/08 BY RICHARD HACKMAN TO JEFF ROTTON * * *
The following information was provided by the licensee to RETRACT the event:
"Upon additional evaluation CNP determined that the planned maintenance reported above was limited in scope and did not remove the entire TSC HVAC system from service. The planned maintenance resulted in two of three fully redundant air chillers (air conditioners) being removed from service for maintenance. The third chiller and the TSC HVAC system is operable and remains in service. Therefore, the CNP TSC has been maintained in a configuration that ensures habitability.
"The NRC Resident Inspector has been notified of the retraction."
Notified R3DO (Skokowski).
Power Reactor
Event Number: 44123
Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: JEFF ISCH
HQ OPS Officer: JOHN KNOKE
Region: 4 State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: JEFF ISCH
HQ OPS Officer: JOHN KNOKE
Notification Date: 04/07/2008
Notification Time: 12:06 [ET]
Event Date: 04/07/2008
Event Time: 10:33 [CDT]
Last Update Date: 04/07/2008
Notification Time: 12:06 [ET]
Event Date: 04/07/2008
Event Time: 10:33 [CDT]
Last Update Date: 04/07/2008
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
RYAN LANTZ (R4)
ELMO COLLINS (RA)
JIM WIGGINS (NRR)
JEFF CRUZ (IRD)
MJ ROSS-LEE (NRR)
RYAN LANTZ (R4)
ELMO COLLINS (RA)
JIM WIGGINS (NRR)
JEFF CRUZ (IRD)
MJ ROSS-LEE (NRR)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
UNUSUAL EVENT - LOSS OF OFF-SITE POWER WHILE DEFUELED
At 1020 CDT on 4/7/08 a loss of off-site power was experienced due to maintenance work in the switch yard. At 1033 CDT the licensee declared an Unusual Event. Presently, off-site power is in the process of being restored . The "B" Emergency Diesel Generator is running and loaded, while the "A" Emergency Diesel Generator and "A" bus is tagged out of service for maintenance. The Essential Service Water system developed a leak in the end bell of a cooling unit, which in turn caused licensee to secure control room cooling. This put the licensee in LCO 3.7. The plant is currently defueled. Spent fuel pool cooling has been reestablished.
The licensee notified the NRC Resident Inspector. Licensee will be contacting other state, local, and government agencies, and will be issuing a press release.
* * * UPDATE PROVIDED AT 1406 EDT ON 04/07/08 FROM JEFF ISCH TO JEFF ROTTON * * *
At 1250 CDT, normal off-site power was restored to NB02 and the Unusual Event was terminated. The "B" Emergency Diesel Generator was secured and placed in standby. The licensee has notified the state and local emergency response organizations and will be notifying the NRC Resident Inspector.
Notified R4DO(Lantz), NRREO (Ross-Lee), IRD (Cruz), DHS (Akers), and FEMA (Biscoe).
At 1020 CDT on 4/7/08 a loss of off-site power was experienced due to maintenance work in the switch yard. At 1033 CDT the licensee declared an Unusual Event. Presently, off-site power is in the process of being restored . The "B" Emergency Diesel Generator is running and loaded, while the "A" Emergency Diesel Generator and "A" bus is tagged out of service for maintenance. The Essential Service Water system developed a leak in the end bell of a cooling unit, which in turn caused licensee to secure control room cooling. This put the licensee in LCO 3.7. The plant is currently defueled. Spent fuel pool cooling has been reestablished.
The licensee notified the NRC Resident Inspector. Licensee will be contacting other state, local, and government agencies, and will be issuing a press release.
* * * UPDATE PROVIDED AT 1406 EDT ON 04/07/08 FROM JEFF ISCH TO JEFF ROTTON * * *
At 1250 CDT, normal off-site power was restored to NB02 and the Unusual Event was terminated. The "B" Emergency Diesel Generator was secured and placed in standby. The licensee has notified the state and local emergency response organizations and will be notifying the NRC Resident Inspector.
Notified R4DO(Lantz), NRREO (Ross-Lee), IRD (Cruz), DHS (Akers), and FEMA (Biscoe).
Power Reactor
Event Number: 44125
Facility: ARKANSAS NUCLEAR
Region: 4 State: AR
Unit: [] [2] []
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: CHUCK OLSON
HQ OPS Officer: JOHN KNOKE
Region: 4 State: AR
Unit: [] [2] []
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: CHUCK OLSON
HQ OPS Officer: JOHN KNOKE
Notification Date: 04/07/2008
Notification Time: 20:44 [ET]
Event Date: 04/07/2008
Event Time: 13:45 [CDT]
Last Update Date: 04/07/2008
Notification Time: 20:44 [ET]
Event Date: 04/07/2008
Event Time: 13:45 [CDT]
Last Update Date: 04/07/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
RYAN LANTZ (R4)
RYAN LANTZ (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | N | 0 | Hot Standby | 0 | Hot Standby |
CORE ELEMENT ASSEMBLY CALCULATORS DECLARED INOPERABLE
"On 4/7/2008, at approximately 1345 CDT, with ANO-2 in Mode 3 (Hot Shutdown) at normal operating temperature and pressure, and with all control element assemblies (CEAs) withdrawn approximately 2 stops, the Control Room was notified by the Computer Support Group (CSG) that the software verification for CEAC1 and CEAC2 (Core Element Assembly Calculators) had not been verified. Both CEAC's were declared inoperable. The Reed Switch Position Indicators (CEA positions) are considered inoperable if the CEAC's are inoperable. Tech Spec 3.1.3.3 requires at least one of these position indicators be operable in Modes 3 through 5 for each CEA not fully inserted. All CEAs were approximately 2 steps withdrawn from fully inserted during plant heatup to clear the rod bottom indications in preparations for CEA Drop Time Testing. At 1350 the reactor trip breakers were opened and CEA's were verified to be fully inserted to meet the Action Statement for Tech Spec 3.1.3.3. Note that no actual position indication was lost, nor did the CEAC show any signs of malfunction. The software verifications have been completed by the CSG."
The licensee notified the NRC Resident Inspector. The licensee also notified the state.
"On 4/7/2008, at approximately 1345 CDT, with ANO-2 in Mode 3 (Hot Shutdown) at normal operating temperature and pressure, and with all control element assemblies (CEAs) withdrawn approximately 2 stops, the Control Room was notified by the Computer Support Group (CSG) that the software verification for CEAC1 and CEAC2 (Core Element Assembly Calculators) had not been verified. Both CEAC's were declared inoperable. The Reed Switch Position Indicators (CEA positions) are considered inoperable if the CEAC's are inoperable. Tech Spec 3.1.3.3 requires at least one of these position indicators be operable in Modes 3 through 5 for each CEA not fully inserted. All CEAs were approximately 2 steps withdrawn from fully inserted during plant heatup to clear the rod bottom indications in preparations for CEA Drop Time Testing. At 1350 the reactor trip breakers were opened and CEA's were verified to be fully inserted to meet the Action Statement for Tech Spec 3.1.3.3. Note that no actual position indication was lost, nor did the CEAC show any signs of malfunction. The software verifications have been completed by the CSG."
The licensee notified the NRC Resident Inspector. The licensee also notified the state.