Event Notification Report for January 15, 2005
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
01/14/2005 - 01/15/2005
Power Reactor
Event Number: 41339
Facility: RIVER BEND
Region: 4 State: LA
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: DAN PIPKIN
HQ OPS Officer: CHAUNCEY GOULD
Region: 4 State: LA
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: DAN PIPKIN
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 01/15/2005
Notification Time: 05:08 [ET]
Event Date: 01/15/2005
Event Time: 02:12 [CST]
Last Update Date: 01/15/2005
Notification Time: 05:08 [ET]
Event Date: 01/15/2005
Event Time: 02:12 [CST]
Last Update Date: 01/15/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
RUSSELL BYWATER (R4)
RUSSELL BYWATER (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | M/R | Y | 100 | Power Operation | 0 | Hot Shutdown |
MANUAL REACTOR SCRAM DUE TO RECEIVING A MAIN GENERATOR ALARM
At 0212 plant operators inserted a manual reactor scram and tripped the main turbine while at 100% power due to indications and alarms of a generator field ground fault. All rods fully inserted and there were no indications of any relief valves lifting. The reactor water level is being controlled within the normal band with feed pump "C" and reactor pressure is being controlled with bypass valves at 800-1090 psig. Also the "A" heater drain pump tripped during the reactor scram due to the water level in the third port heater. The licensee is investigating the cause.
The NRC Resident Inspector was notified.
At 0212 plant operators inserted a manual reactor scram and tripped the main turbine while at 100% power due to indications and alarms of a generator field ground fault. All rods fully inserted and there were no indications of any relief valves lifting. The reactor water level is being controlled within the normal band with feed pump "C" and reactor pressure is being controlled with bypass valves at 800-1090 psig. Also the "A" heater drain pump tripped during the reactor scram due to the water level in the third port heater. The licensee is investigating the cause.
The NRC Resident Inspector was notified.
Power Reactor
Event Number: 41340
Facility: SEABROOK
Region: 1 State: NH
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: RON STRICKLAND
HQ OPS Officer: BILL GOTT
Region: 1 State: NH
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: RON STRICKLAND
HQ OPS Officer: BILL GOTT
Notification Date: 01/15/2005
Notification Time: 14:11 [ET]
Event Date: 01/15/2005
Event Time: 00:00 [EST]
Last Update Date: 01/15/2005
Notification Time: 14:11 [ET]
Event Date: 01/15/2005
Event Time: 00:00 [EST]
Last Update Date: 01/15/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
JOHN KINNEMAN (R1)
JOHN KINNEMAN (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
UNSPECIFIED REQUIREMENT
The following information was provided by the licensee via facsimile
"On January 15, 2005 at 0750, it was determined that Containment Isolation Valve CC-V-1095 was inoperable due to a post maintenance retest not being performed. The valve was declared inoperable and Technical Specification 3.6.3, Action a. was entered. The valve was satisfactorily retested and restored to OPERABLE status at 1042 on January 15, 2005. A routine preventive maintenance activity was performed on the valve's power supply on January 13, 2005. However, the valve was not stroke tested in accordance with the requirements of Technical Specification Surveillance Requirement 4.6.3.1. This report is made pursuant to the requirements of Section 2.G. of the Seabrook Station Operating License for the violation of the requirements of the Technical Specifications."
The licensee notified the NRC Resident Inspector.
The following information was provided by the licensee via facsimile
"On January 15, 2005 at 0750, it was determined that Containment Isolation Valve CC-V-1095 was inoperable due to a post maintenance retest not being performed. The valve was declared inoperable and Technical Specification 3.6.3, Action a. was entered. The valve was satisfactorily retested and restored to OPERABLE status at 1042 on January 15, 2005. A routine preventive maintenance activity was performed on the valve's power supply on January 13, 2005. However, the valve was not stroke tested in accordance with the requirements of Technical Specification Surveillance Requirement 4.6.3.1. This report is made pursuant to the requirements of Section 2.G. of the Seabrook Station Operating License for the violation of the requirements of the Technical Specifications."
The licensee notified the NRC Resident Inspector.