Event Notification Report for February 21, 2007
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
02/20/2007 - 02/21/2007
Power Reactor
Event Number: 43178
Facility: FERMI
Region: 3 State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: JEFF GROFF
HQ OPS Officer: JEFF ROTTON
Region: 3 State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: JEFF GROFF
HQ OPS Officer: JEFF ROTTON
Notification Date: 02/21/2007
Notification Time: 20:37 [ET]
Event Date: 02/21/2007
Event Time: 13:30 [EST]
Last Update Date: 02/21/2007
Notification Time: 20:37 [ET]
Event Date: 02/21/2007
Event Time: 13:30 [EST]
Last Update Date: 02/21/2007
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):
BRUCE BURGESS (R3)
BRUCE BURGESS (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
ALTERNATE EOF UNAVAILABLE
"While the normal Emergency Operations Facility (EOF) was unavailable due to modification, the space that is utilized for the Alternate EOF was in a locked condition and it is normally not locked. This condition was discovered during the dayshift and was readily corrected. However, had the facility been required during off hours it would have delayed activation of the Alternate EOF.
"Additionally, activation of the Alternate EOF would have been hampered by key availability to the facility storage room and supply cabinet.
"Access to Alternate EOF and equipment has been restored."
The licensee notified the NRC Resident Inspector.
"While the normal Emergency Operations Facility (EOF) was unavailable due to modification, the space that is utilized for the Alternate EOF was in a locked condition and it is normally not locked. This condition was discovered during the dayshift and was readily corrected. However, had the facility been required during off hours it would have delayed activation of the Alternate EOF.
"Additionally, activation of the Alternate EOF would have been hampered by key availability to the facility storage room and supply cabinet.
"Access to Alternate EOF and equipment has been restored."
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 43179
Facility: CRYSTAL RIVER
Region: 2 State: FL
Unit: [3] [] []
RX Type: [3] B&W-L-LP
NRC Notified By: RICKY E. RAWLS
HQ OPS Officer: STEVE SANDIN
Region: 2 State: FL
Unit: [3] [] []
RX Type: [3] B&W-L-LP
NRC Notified By: RICKY E. RAWLS
HQ OPS Officer: STEVE SANDIN
Notification Date: 02/21/2007
Notification Time: 22:11 [ET]
Event Date: 02/21/2007
Event Time: 19:15 [EST]
Last Update Date: 02/21/2007
Notification Time: 22:11 [ET]
Event Date: 02/21/2007
Event Time: 19:15 [EST]
Last Update Date: 02/21/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
EUGENE GUTHRIE (R2)
EUGENE GUTHRIE (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | A/R | Y | 71 | Power Operation | 0 | Hot Standby |
AUTOMATIC REACTOR TRIP ON HIGH RCS PRESSURE FOLLOWING A FEEDWATER TRANSIENT
"At 1915 on February 21, 2007, Crystal River Unit 3 was at reduced power (71%) for planned maintenance on one of four condenser waterboxes when the Integrated Control System (ICS) for Main Feedwater became erratic causing a feedwater transient that underfed the once thru steam generators. The reactor protection system (RPS) actuated on high Reactor Coolant System pressure causing a reactor trip. CR3 also received an Emergency Feedwater Actuation (EFIC) on low steam generator levels. This event is reportable as a 4-Hour Non-Emergency Notification per 10CFR50.72 (b)(2)(iv)(B) for Reactor Protection System Actuation and as an 8-Hour Non-Emergency Notification per 10CFR50.72 (b)(3)(iv)(A) for Emergency Feedwater Actuation and for Reactor Protection System actuation. All systems responded as designed and the plant remains stable with Emergency Feedwater in MODE 3."
The licensee informed the NRC Resident Inspector.
"At 1915 on February 21, 2007, Crystal River Unit 3 was at reduced power (71%) for planned maintenance on one of four condenser waterboxes when the Integrated Control System (ICS) for Main Feedwater became erratic causing a feedwater transient that underfed the once thru steam generators. The reactor protection system (RPS) actuated on high Reactor Coolant System pressure causing a reactor trip. CR3 also received an Emergency Feedwater Actuation (EFIC) on low steam generator levels. This event is reportable as a 4-Hour Non-Emergency Notification per 10CFR50.72 (b)(2)(iv)(B) for Reactor Protection System Actuation and as an 8-Hour Non-Emergency Notification per 10CFR50.72 (b)(3)(iv)(A) for Emergency Feedwater Actuation and for Reactor Protection System actuation. All systems responded as designed and the plant remains stable with Emergency Feedwater in MODE 3."
The licensee informed the NRC Resident Inspector.