Event Notification Report for July 02, 2012
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
07/01/2012 - 07/02/2012
EVENT NUMBERS
48063480644806048061
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 48063
Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: JOHN KEMPKES
HQ OPS Officer: DONG HWA PARK
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: JOHN KEMPKES
HQ OPS Officer: DONG HWA PARK
Notification Date: 07/02/2012
Notification Time: 18:42 [ET]
Event Date: 07/02/2012
Event Time: 15:51 [CDT]
Last Update Date: 08/28/2012
Notification Time: 18:42 [ET]
Event Date: 07/02/2012
Event Time: 15:51 [CDT]
Last Update Date: 08/28/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
Person (Organization):
ROBERT DALEY (R3DO)
ROBERT DALEY (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
BOTH DIESEL GENERATORS DECLARED INOPERABLE
"D1 and D2 Diesel Generators (DG) were declared inoperable at 1551 CDT due to exceeding the maximum outside air temperature limit of 97 degree F. This limit was based on heatup analysis for a HELB [High Energy Line Break] in the turbine building. The temperature is measured using the 15 min average of air temperature at the 10 meter meteorological tower, which approximates the intake height for room ventilation.
"LCO 3.8.1 Condition B was entered for both DGs and LCO 3.8.1 Condition E was entered for two DGs inoperable on the same unit. The DGs could start and run if required at the time of entry.
"This condition is reportable per 10 CFR 50.72(b)(3)(v) as an event or condition that could have prevented the fulfillment of a safety function.
"During review of the analysis, two pressure switches on D2 and one on D1 were identified as being limiting and a modification was approved to replace them. Upon replacement, the limiting outside temperature would increase to 100.5 degree F. Replacement of components had been completed for D2 diesel generator prior to LCO entry; however, the temperature limit of 100.5 degree F had not yet been approved.
"Shortly after D1 was declared inoperable, it was isolated to complete the component replacement which is expected to take less than four hours. D1 will return to operable once the component replacement and PMT is completed.
"At 1630 [CDT] D2 was declared operable based on approval of a revised operability recommendation that raised the outside temperature limit to 100.5 degree F.
"Outside air temperature peaked at 97.1 degree F and is slowly decreasing."
The licensee has notified the NRC Resident Inspector.
* * * RETRACTION FROM GENE DAMMANN TO DONALD NORWOOD AT 1555 EDT ON 8/28/12 * * *
"Event Notification 48063 reported that D1 and D2 Diesel Generators (DG) were inoperable due to exceeding the maximum outside air temperature limit of 97 degree F.
"An additional approved evaluation determined that the D2 lube oil pressure switches were replaced prior to exceeding the outside ambient air temperature limit. The new lube oil pressure switches have a higher temperature rating that supports a higher outside ambient air temperature, therefore, D2 was able to fulfill its safety function and Event Notification 48063 is retracted.
"The NRC Resident Inspector has been informed."
Notified R3DO (Cameron).
"D1 and D2 Diesel Generators (DG) were declared inoperable at 1551 CDT due to exceeding the maximum outside air temperature limit of 97 degree F. This limit was based on heatup analysis for a HELB [High Energy Line Break] in the turbine building. The temperature is measured using the 15 min average of air temperature at the 10 meter meteorological tower, which approximates the intake height for room ventilation.
"LCO 3.8.1 Condition B was entered for both DGs and LCO 3.8.1 Condition E was entered for two DGs inoperable on the same unit. The DGs could start and run if required at the time of entry.
"This condition is reportable per 10 CFR 50.72(b)(3)(v) as an event or condition that could have prevented the fulfillment of a safety function.
"During review of the analysis, two pressure switches on D2 and one on D1 were identified as being limiting and a modification was approved to replace them. Upon replacement, the limiting outside temperature would increase to 100.5 degree F. Replacement of components had been completed for D2 diesel generator prior to LCO entry; however, the temperature limit of 100.5 degree F had not yet been approved.
"Shortly after D1 was declared inoperable, it was isolated to complete the component replacement which is expected to take less than four hours. D1 will return to operable once the component replacement and PMT is completed.
"At 1630 [CDT] D2 was declared operable based on approval of a revised operability recommendation that raised the outside temperature limit to 100.5 degree F.
"Outside air temperature peaked at 97.1 degree F and is slowly decreasing."
The licensee has notified the NRC Resident Inspector.
* * * RETRACTION FROM GENE DAMMANN TO DONALD NORWOOD AT 1555 EDT ON 8/28/12 * * *
"Event Notification 48063 reported that D1 and D2 Diesel Generators (DG) were inoperable due to exceeding the maximum outside air temperature limit of 97 degree F.
"An additional approved evaluation determined that the D2 lube oil pressure switches were replaced prior to exceeding the outside ambient air temperature limit. The new lube oil pressure switches have a higher temperature rating that supports a higher outside ambient air temperature, therefore, D2 was able to fulfill its safety function and Event Notification 48063 is retracted.
"The NRC Resident Inspector has been informed."
Notified R3DO (Cameron).
Power Reactor
Event Number: 48064
Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: ERIC ROBEN
HQ OPS Officer: DONG HWA PARK
Region: 3 State: IA
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: ERIC ROBEN
HQ OPS Officer: DONG HWA PARK
Notification Date: 07/02/2012
Notification Time: 18:50 [ET]
Event Date: 07/02/2012
Event Time: 15:05 [CDT]
Last Update Date: 07/02/2012
Notification Time: 18:50 [ET]
Event Date: 07/02/2012
Event Time: 15:05 [CDT]
Last Update Date: 07/02/2012
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):
ROBERT DALEY (R3DO)
ROBERT DALEY (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
HPCI DECLARED INOPERABLE
"A spurious isolation of the High Pressure Coolant Injection (HPCI) Outboard Steam Supply Valve and Outboard Torus Suction Valve occurred. Initial verifications indicate that the signal was not valid and investigations in the vicinity of the piping revealed no evidence of leaks. Troubleshooting is in progress.
"HPCI declared inoperable per TS 3.5.1 Condition F which allows 14 days to restore to operable status.
"All remaining ECCS and RCIC are operable and available. Grid stability has been verified."
The licensee has notified the NRC Resident Inspector.
"A spurious isolation of the High Pressure Coolant Injection (HPCI) Outboard Steam Supply Valve and Outboard Torus Suction Valve occurred. Initial verifications indicate that the signal was not valid and investigations in the vicinity of the piping revealed no evidence of leaks. Troubleshooting is in progress.
"HPCI declared inoperable per TS 3.5.1 Condition F which allows 14 days to restore to operable status.
"All remaining ECCS and RCIC are operable and available. Grid stability has been verified."
The licensee has notified the NRC Resident Inspector.
Power Reactor
Event Number: 48060
Facility: COOK
Region: 3 State: MI
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BUD HINCKLEY
HQ OPS Officer: BILL HUFFMAN
Region: 3 State: MI
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BUD HINCKLEY
HQ OPS Officer: BILL HUFFMAN
Notification Date: 07/02/2012
Notification Time: 01:49 [ET]
Event Date: 07/02/2012
Event Time: 02:00 [EDT]
Last Update Date: 07/02/2012
Notification Time: 01:49 [ET]
Event Date: 07/02/2012
Event Time: 02:00 [EDT]
Last Update Date: 07/02/2012
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):
NICK VALOS (R3DO)
NICK VALOS (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
UNAVAILABILITY OF TSC VENTILATION SYSTEM DUE TO SCHEDULED MAINTENANCE
"At 02:00 EDT on Monday, July 2, 2012, the Cook Nuclear Plant (CNP) Technical Support Center (TSC) air conditioning and charcoal filtration systems will be removed from service for scheduled maintenance.
"Under certain accident conditions the TSC may become unavailable due to the inability of the air conditioning and charcoal filtration systems to maintain a habitable atmosphere. Compensatory measures exist to relocate TSC personnel to the unaffected unit's control room if necessary.
"TSC ventilation system maintenance and post maintenance testing is scheduled to be completed by 15:00 EDT on Monday, July 2, 2012.
"The licensee has notified the NRC Resident Inspector.
"This notification is being made in accordance with 10 CFR 50.72 (b)(3)(xiii) due to the loss of an emergency response facility."
* * * UPDATE FROM BEN HUFFMAN TO DONG PARK AT 1727 EDT ON 7/2/12 * * *
"The TSC ventilation system maintenance was completed satisfactorily and the system was restored to service at 1725 EDT on 7/2/12."
The licensee will notify the NRC Resident Inspector.
Notified R3DO (Daley).
"At 02:00 EDT on Monday, July 2, 2012, the Cook Nuclear Plant (CNP) Technical Support Center (TSC) air conditioning and charcoal filtration systems will be removed from service for scheduled maintenance.
"Under certain accident conditions the TSC may become unavailable due to the inability of the air conditioning and charcoal filtration systems to maintain a habitable atmosphere. Compensatory measures exist to relocate TSC personnel to the unaffected unit's control room if necessary.
"TSC ventilation system maintenance and post maintenance testing is scheduled to be completed by 15:00 EDT on Monday, July 2, 2012.
"The licensee has notified the NRC Resident Inspector.
"This notification is being made in accordance with 10 CFR 50.72 (b)(3)(xiii) due to the loss of an emergency response facility."
* * * UPDATE FROM BEN HUFFMAN TO DONG PARK AT 1727 EDT ON 7/2/12 * * *
"The TSC ventilation system maintenance was completed satisfactorily and the system was restored to service at 1725 EDT on 7/2/12."
The licensee will notify the NRC Resident Inspector.
Notified R3DO (Daley).
Power Reactor
Event Number: 48061
Facility: FERMI
Region: 3 State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: DEREK ETUE
HQ OPS Officer: CHARLES TEAL
Region: 3 State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: DEREK ETUE
HQ OPS Officer: CHARLES TEAL
Notification Date: 07/02/2012
Notification Time: 08:25 [ET]
Event Date: 07/02/2012
Event Time: 08:00 [EDT]
Last Update Date: 07/03/2012
Notification Time: 08:25 [ET]
Event Date: 07/02/2012
Event Time: 08:00 [EDT]
Last Update Date: 07/03/2012
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):
NICK VALOS (R3DO)
NICK VALOS (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
SPDS AND ERDS OUT OF SERVICE FOR MAINTENANCE
"Beginning July 2, 2012, at approximately 0800, the Fermi 2 Integrated Plant Computer System (IPCS) will be removed from service to support installation of a Cyber Security Modification. The Safety Parameters Display System (SPDS) and Emergency Response Data System (ERDS) reside on the IPCS platform and will be out of service when the IPCS is removed from service. These systems will be unavailable to the Control Room and all other Emergency Response Facilities (ERFs) for approximately 20 hours. By 0300 on July 3, 2012, it is planned to restore IPCS, including SPDS and ERDS, to the Control Room, Operational Support Center, the Technical Support Center, and alternate facilities. During this time dose assessment capability will only be available in the manual data input mode. The majority of the Control Room indications remain available to the plant staff, and will be used for emergency response, if needed. Information will be communicated to the NRC using other available communication systems as needed. A follow-up notification will be submitted when the IPCS is completely restored. This notification is being made per the requirements of 8 Hour Non-Emergency Notification 10 CFR 50.72(b)(3)(xiii), any event that results in a major loss of emergency assessment capability."
The licensee has notified the NRC Resident Inspector.
* * * UPDATE ON 7/03/12 AT 0113 EDT FROM GROFF TO HUFFMAN * * *
"On July 3, 2012, at 01:00, the Fermi 2 Integrated Plant Computer System (IPCS) has been returned to service. Emergency assessment capabilities have been restored to all onsite emergency response facilities. Due to equipment problems, the Cyber Security Modification was not installed and the original IPCS configuration was restored."
The licensee has notified the NRC Resident Inspector. R3DO (Daley) notified.
* * * UPDATE ON 7/03/12 AT 0556 EDT FROM GROFF TO HUFFMAN * * *
"At approximately 02:04 on July 3, the Fermi 2 Integrated Plant Computer System (IPCS) failed. The Safety Parameters Display System (SPDS) and Emergency Response Data System (ERDS) reside on the IPCS platform. IPCS had previously been removed from service on 7/2/12 for a Cyber Security Modification and restored at 0100 on 7/3/12.
"At 0354, plant personnel were able to reboot IPCS and restore the system to normal with a Prime and Backup CPUs. Emergency assessment capabilities have been restored to all onsite emergency response facilities.
"This notification is being made per the requirements of 8 Hour Non-Emergency Notification 10 CFR 50.72(b)(3)(xiii), any event that results in a major loss of emergency assessment capability."
The licensee has notified the NRC Resident Inspector. R3DO (Daley) notified.
"Beginning July 2, 2012, at approximately 0800, the Fermi 2 Integrated Plant Computer System (IPCS) will be removed from service to support installation of a Cyber Security Modification. The Safety Parameters Display System (SPDS) and Emergency Response Data System (ERDS) reside on the IPCS platform and will be out of service when the IPCS is removed from service. These systems will be unavailable to the Control Room and all other Emergency Response Facilities (ERFs) for approximately 20 hours. By 0300 on July 3, 2012, it is planned to restore IPCS, including SPDS and ERDS, to the Control Room, Operational Support Center, the Technical Support Center, and alternate facilities. During this time dose assessment capability will only be available in the manual data input mode. The majority of the Control Room indications remain available to the plant staff, and will be used for emergency response, if needed. Information will be communicated to the NRC using other available communication systems as needed. A follow-up notification will be submitted when the IPCS is completely restored. This notification is being made per the requirements of 8 Hour Non-Emergency Notification 10 CFR 50.72(b)(3)(xiii), any event that results in a major loss of emergency assessment capability."
The licensee has notified the NRC Resident Inspector.
* * * UPDATE ON 7/03/12 AT 0113 EDT FROM GROFF TO HUFFMAN * * *
"On July 3, 2012, at 01:00, the Fermi 2 Integrated Plant Computer System (IPCS) has been returned to service. Emergency assessment capabilities have been restored to all onsite emergency response facilities. Due to equipment problems, the Cyber Security Modification was not installed and the original IPCS configuration was restored."
The licensee has notified the NRC Resident Inspector. R3DO (Daley) notified.
* * * UPDATE ON 7/03/12 AT 0556 EDT FROM GROFF TO HUFFMAN * * *
"At approximately 02:04 on July 3, the Fermi 2 Integrated Plant Computer System (IPCS) failed. The Safety Parameters Display System (SPDS) and Emergency Response Data System (ERDS) reside on the IPCS platform. IPCS had previously been removed from service on 7/2/12 for a Cyber Security Modification and restored at 0100 on 7/3/12.
"At 0354, plant personnel were able to reboot IPCS and restore the system to normal with a Prime and Backup CPUs. Emergency assessment capabilities have been restored to all onsite emergency response facilities.
"This notification is being made per the requirements of 8 Hour Non-Emergency Notification 10 CFR 50.72(b)(3)(xiii), any event that results in a major loss of emergency assessment capability."
The licensee has notified the NRC Resident Inspector. R3DO (Daley) notified.