Event Notification Report for September 06, 2004
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
09/05/2004 - 09/06/2004
EVENT NUMBERS
41023
Power Reactor
Event Number: 41023
Facility: CRYSTAL RIVER
Region: 2 State: FL
Unit: [3] [] []
RX Type: [3] B&W-L-LP
NRC Notified By: R. SWEENEY
HQ OPS Officer: STEVE SANDIN
Region: 2 State: FL
Unit: [3] [] []
RX Type: [3] B&W-L-LP
NRC Notified By: R. SWEENEY
HQ OPS Officer: STEVE SANDIN
Notification Date: 09/06/2004
Notification Time: 12:44 [ET]
Event Date: 09/06/2004
Event Time: 11:50 [EDT]
Last Update Date: 09/06/2004
Notification Time: 12:44 [ET]
Event Date: 09/06/2004
Event Time: 11:50 [EDT]
Last Update Date: 09/06/2004
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):
BENOIT DESAI (R2)
MICHAEL CASE (NRR)
RICHARD WESSMAN (IRD)
BENOIT DESAI (R2)
MICHAEL CASE (NRR)
RICHARD WESSMAN (IRD)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | A/R | Y | 97 | Power Operation | 0 | Hot Standby |
AUTOMATIC REACTOR TRIP FOLLOWING PARTIAL LOSS OF OFFSITE POWER
"At approximately 1150 [EDT], CR3 Site experienced a 230KV 'B' Buss loss. The resultant loss of power was a loss of both non-vital 4160V busses. All RCPs tripped and a reactor trip occurred. The plant is stable on natural circulation cooling.
"This report is based on the Reactor Protection System Actuation and Specified System Actuation (Emergency Feedwater)."
The "B" ESF 4160KV Bus deenergized resulting in an autostart of the "B" EDG, as expected. Natural Circulation has been confirmed with both Steam Generators [SGs] receiving Emergency Feedwater [EFW] via both the Turbine-Driven and Diesel-Driven EFW Pumps. The SGs are using the Atmospheric Dumps to remove decay heat. There was no known SG tube leakage prior to the transient. The cause for the partial loss of offsite power is under investigation.
The licensee informed the NRC Resident Inspector.
"At approximately 1150 [EDT], CR3 Site experienced a 230KV 'B' Buss loss. The resultant loss of power was a loss of both non-vital 4160V busses. All RCPs tripped and a reactor trip occurred. The plant is stable on natural circulation cooling.
"This report is based on the Reactor Protection System Actuation and Specified System Actuation (Emergency Feedwater)."
The "B" ESF 4160KV Bus deenergized resulting in an autostart of the "B" EDG, as expected. Natural Circulation has been confirmed with both Steam Generators [SGs] receiving Emergency Feedwater [EFW] via both the Turbine-Driven and Diesel-Driven EFW Pumps. The SGs are using the Atmospheric Dumps to remove decay heat. There was no known SG tube leakage prior to the transient. The cause for the partial loss of offsite power is under investigation.
The licensee informed the NRC Resident Inspector.