Event Notification Report for November 20, 2004
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
11/19/2004 - 11/20/2004
EVENT NUMBERS
41213
Power Reactor
Event Number: 41213
Facility: VOGTLE
Region: 2 State: GA
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ROBERT DORMAN
HQ OPS Officer: STEVE SANDIN
Region: 2 State: GA
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ROBERT DORMAN
HQ OPS Officer: STEVE SANDIN
Notification Date: 11/20/2004
Notification Time: 14:56 [ET]
Event Date: 11/20/2004
Event Time: 11:40 [EST]
Last Update Date: 11/20/2004
Notification Time: 14:56 [ET]
Event Date: 11/20/2004
Event Time: 11:40 [EST]
Last Update Date: 11/20/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(2)(iv)(A) - ECCS INJECTION 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)(2)(iv)(A) - ECCS INJECTION 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
THOMAS DECKER (R2)
GENE IMBRO (NRR)
RICHARD WESSMAN (IRD)
THOMAS DECKER (R2)
GENE IMBRO (NRR)
RICHARD WESSMAN (IRD)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
UNEXPECTED AUTOMATIC REACTOR TRIP DURING SURVEILLANCE TESTING WITH SI INJECTION
"On 11/20/2004 at 1140 EST during the performance of 14421-2 'Solid State Protection System And Reactor Trip Breaker Train B Operability Test' an automatic Reactor Trip occurred and a Safety Injection occurred a short time thereafter. The Reactor Trip was caused by an error made in the performance of the 14421-2 procedure. The operator working with a peer checker mistakenly placed the 'A' train multiplexer test switch in the 'A + B' position instead of the 'B' train one. The 'B' train multiplexer test switch was still in the inhibit position. When the 'A' Train multiplexer switch went through the inhibit position, it caused the second general warning which tripped the reactor. The Safety Injection is believed to have been caused by a failure of the loop 2 Reactor Coolant Average Temperature which impacted the Steam Dump control system. The Steam Dumps did not close as expected during the Reactor Trip response and Pressurizer pressure lowered below the Safety Injection System setpoint and a Safety Injection was actuated.
"All systems operated as expected during the Safety Injection and Reactor Trip. All the Control Rods fully inserted on the Reactor Trip. The Main Steam Lines were isolated by the operator due to the lower than expected decrease of the Reactor Coolant System Average Temperature. Both Motor Driven AFW pumps started as expected as did the Turbine Driven AFW pump. All ECCS pumps started as expected on the Safety Injection. The Containment Coolers all started in low speed on the Safety Injection as expected. Both Diesel Generators started on the Safety Injection actuation. The Containment Isolation systems isolated containment as expected. During the recovery from the Safety Injection pressurizer level did reach 100%, but the Pressurizer PORVs were not required to open to control Pressurizer pressure."
Unit 2 is currently stable in mode 3 removing decay heat via the Atmospheric Steam Dumps.
The licensee informed the NRC Resident Inspector.
"On 11/20/2004 at 1140 EST during the performance of 14421-2 'Solid State Protection System And Reactor Trip Breaker Train B Operability Test' an automatic Reactor Trip occurred and a Safety Injection occurred a short time thereafter. The Reactor Trip was caused by an error made in the performance of the 14421-2 procedure. The operator working with a peer checker mistakenly placed the 'A' train multiplexer test switch in the 'A + B' position instead of the 'B' train one. The 'B' train multiplexer test switch was still in the inhibit position. When the 'A' Train multiplexer switch went through the inhibit position, it caused the second general warning which tripped the reactor. The Safety Injection is believed to have been caused by a failure of the loop 2 Reactor Coolant Average Temperature which impacted the Steam Dump control system. The Steam Dumps did not close as expected during the Reactor Trip response and Pressurizer pressure lowered below the Safety Injection System setpoint and a Safety Injection was actuated.
"All systems operated as expected during the Safety Injection and Reactor Trip. All the Control Rods fully inserted on the Reactor Trip. The Main Steam Lines were isolated by the operator due to the lower than expected decrease of the Reactor Coolant System Average Temperature. Both Motor Driven AFW pumps started as expected as did the Turbine Driven AFW pump. All ECCS pumps started as expected on the Safety Injection. The Containment Coolers all started in low speed on the Safety Injection as expected. Both Diesel Generators started on the Safety Injection actuation. The Containment Isolation systems isolated containment as expected. During the recovery from the Safety Injection pressurizer level did reach 100%, but the Pressurizer PORVs were not required to open to control Pressurizer pressure."
Unit 2 is currently stable in mode 3 removing decay heat via the Atmospheric Steam Dumps.
The licensee informed the NRC Resident Inspector.