Event Notification Report for July 04, 2008
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
07/03/2008 - 07/04/2008
EVENT NUMBERS
44337
Power Reactor
Event Number: 44337
Facility: HATCH
Region: 2 State: GA
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: JIM ANDERSON
HQ OPS Officer: STEVE SANDIN
Region: 2 State: GA
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: JIM ANDERSON
HQ OPS Officer: STEVE SANDIN
Notification Date: 07/04/2008
Notification Time: 10:04 [ET]
Event Date: 07/04/2008
Event Time: 08:39 [EDT]
Last Update Date: 07/04/2008
Notification Time: 10:04 [ET]
Event Date: 07/04/2008
Event Time: 08:39 [EDT]
Last Update Date: 07/04/2008
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):
MARVIN SYKES (R2)
MARVIN SYKES (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 100 | Power Operation | 0 | Hot Shutdown |
AUTOMATIC REACTOR SCRAM ON TURBINE TRIP
"A Turbine Trip greater than 30% power caused a Reactor Trip (Scram), both Recirculation Pumps tripped. A low level [Reactor Vessel Water Level] of approximately 2 inches caused a Group 2 containment valve isolation signal, all valves closed as required.
"The cause of the Turbine Trip is under investigation"
All control rods fully inserted with no ECCS actuations. Unit 1 is currently stable in mode 3 (Hot Shutdown) with decay heat being removed via the bypass. Following the scram, one SRV lifted and reseated. At the time of the transient, an EHC pump autostart was in progress, however, there is no indication that this was the cause of the turbine trip. Unit 1 is in a normal shutdown electrical lineup.
The licensee informed the NRC Resident Inspector.
"A Turbine Trip greater than 30% power caused a Reactor Trip (Scram), both Recirculation Pumps tripped. A low level [Reactor Vessel Water Level] of approximately 2 inches caused a Group 2 containment valve isolation signal, all valves closed as required.
"The cause of the Turbine Trip is under investigation"
All control rods fully inserted with no ECCS actuations. Unit 1 is currently stable in mode 3 (Hot Shutdown) with decay heat being removed via the bypass. Following the scram, one SRV lifted and reseated. At the time of the transient, an EHC pump autostart was in progress, however, there is no indication that this was the cause of the turbine trip. Unit 1 is in a normal shutdown electrical lineup.
The licensee informed the NRC Resident Inspector.