Event Notification Report for March 28, 2010
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
03/27/2010 - 03/28/2010
Power Reactor
Event Number: 45798
Facility: PERRY
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: DAVID DUESING
HQ OPS Officer: PETE SNYDER
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: DAVID DUESING
HQ OPS Officer: PETE SNYDER
Notification Date: 03/28/2010
Notification Time: 22:13 [ET]
Event Date: 03/28/2010
Event Time: 00:00 [EDT]
Last Update Date: 03/29/2010
Notification Time: 22:13 [ET]
Event Date: 03/28/2010
Event Time: 00:00 [EDT]
Last Update Date: 03/29/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
LAURA KOZAK (R3DO)
LAURA KOZAK (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 68 | Power Operation |
PRESS RELEASE DUE TO LUBE OIL FIRE AFFECTING REACTOR FEED PUMP
"At 1818 , the control room was notified of a lube oil fire on Reactor Feed Pump Turbine B. The fire brigade was toned out, and the Perry Township Fire Department was notified for assistance. Reactor Feed Pump Turbine B was manually tripped to allow removing the turbine lube oil system from service. The Motor Feed Pump started as expected, and the Reactor Recirculation system lowered reactor power as designed. Currently the reactor is at 68% reactor power following rod line adjustments after the transient was complete.
"The fire was reported to be out by the fire brigade leader at 2122. Damage assessment is currently in progress. Two fire brigade members were transported by ambulance to Tri-Point Medical Center with signs of heat exhaustion. Both individuals were verified to be free of contamination prior to transport.
"A news release will be made due to local media interest for this event. The NRC Resident Inspector has been notified."
* * * UPDATE FROM CHARLES ELBERFELD TO DONALD NORWOOD AT 1636 EDT ON 3/29/2010 * * *
"The purpose of this call is to update Event Number 45798. In the notification made on 3/28/10, it was stated that a news release would be made due to local media interest for this event. After further review, it was determined that discussions with the media adequately addressed the interest and that a new release will not be made. The NRC Resident Inspector has been notified."
Notified R3DO (Duncan).
"At 1818 , the control room was notified of a lube oil fire on Reactor Feed Pump Turbine B. The fire brigade was toned out, and the Perry Township Fire Department was notified for assistance. Reactor Feed Pump Turbine B was manually tripped to allow removing the turbine lube oil system from service. The Motor Feed Pump started as expected, and the Reactor Recirculation system lowered reactor power as designed. Currently the reactor is at 68% reactor power following rod line adjustments after the transient was complete.
"The fire was reported to be out by the fire brigade leader at 2122. Damage assessment is currently in progress. Two fire brigade members were transported by ambulance to Tri-Point Medical Center with signs of heat exhaustion. Both individuals were verified to be free of contamination prior to transport.
"A news release will be made due to local media interest for this event. The NRC Resident Inspector has been notified."
* * * UPDATE FROM CHARLES ELBERFELD TO DONALD NORWOOD AT 1636 EDT ON 3/29/2010 * * *
"The purpose of this call is to update Event Number 45798. In the notification made on 3/28/10, it was stated that a news release would be made due to local media interest for this event. After further review, it was determined that discussions with the media adequately addressed the interest and that a new release will not be made. The NRC Resident Inspector has been notified."
Notified R3DO (Duncan).
Power Reactor
Event Number: 45799
Facility: ROBINSON
Region: 2 State: SC
Unit: [2] [] []
RX Type: [2] W-3-LP
NRC Notified By: CURTIS CASTELL
HQ OPS Officer: PETE SNYDER
Region: 2 State: SC
Unit: [2] [] []
RX Type: [2] W-3-LP
NRC Notified By: CURTIS CASTELL
HQ OPS Officer: PETE SNYDER
Notification Date: 03/28/2010
Notification Time: 22:47 [ET]
Event Date: 03/28/2010
Event Time: 18:52 [EDT]
Last Update Date: 03/28/2010
Notification Time: 22:47 [ET]
Event Date: 03/28/2010
Event Time: 18:52 [EDT]
Last Update Date: 03/28/2010
Emergency Class: ALERT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED 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(a) (1) (i) - EMERGENCY DECLARED 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):
EUGENE GUTHRIE (R2DO)
EUGENE GUTHRIE (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | A/R | Y | 99 | Power Operation | 0 | Hot Standby |
ALERT DECLARED DUE TO FIRE AFFECTING SAFETY RELATED EQUIPMENT
"At approximately 1852 hours Eastern Daylight Time [EDT], on March 28, 2010, with the unit operating at approximately 99.5% power, the H. B. Robinson Steam Electric Plant, Unit No. 2, reactor protection system actuated resulting in an automatic trip of the reactor. At about the time of the reactor trip, there was indication of a loss of the power to the Train 'B' emergency bus. The Train 'B' Emergency Diesel Generator started and provided power to the Train 'B' emergency bus. The Reactor Coolant System pressure response after the reactor trip resulted in the actuation of the Safety Injection System. The reduction in Reactor Coolant System pressure allowed the safety injection system to provide flow to the reactor coolant system, although, there was no indication of conditions that would require the safety injection system to provide flow to the reactor coolant system. Specifically, diagnosis of the event determined that a loss of coolant event, steam generator tube rupture, or secondary system break were not occurring. The safety systems that actuated for this event included the Reactor Protection System, the Safety Injection System, both Emergency Diesel Generators started and the 'B' Emergency Diesel Generator provided power to the 'B' Train Emergency Bus, the Auxiliary Feedwater System actuated, and the three main steam isolation valves closed. The Steam Generator Power Operated Relief Valves are being used for decay heat removal because of the closure of the main steam isolation valves. The Startup Transformer is energized and providing power to the 'A' Train Emergency Bus. Investigation of the cause of the reactor trip and associated emergency system actuations is in progress. At the time of the event, it was noted that there was evidence of a fire condition at 4KV bus number 5 located in the Turbine Building. It is currently believed that this is the cause of the transient condition that resulted in the reactor trip and other emergency system actuations. The reactor is currently being maintained in MODE 3, Hot Standby, conditions."
"This event is being reported in accordance with 10 CFR 50.72(b)(2)(iv)(A) for ECCS discharge into the RCS and (B) for RPS actuation, and 10 CFR 50.72(b)(3)(iv)(A) for specified system actuation as described.
"Additionally, based on an inquiry from the local news media reporter, information regarding this event was discussed with the local media. This contact with the local news media is being reported in accordance with 10 CFR 50.72(b)(2)(xi)."
All control rods fully inserted on the trip. Volume Control Tank [VCT] level was not dropping consistent with no reactor coolant system leakage. Pressurizer level and pressure drop was indicative of shrink associated with the Reactor Coolant Pump stoppage and cooldown in one loop. The licensee observed no indication of reactor coolant system leakage from the containment sump water level monitors.
The licensee informed the NRC Resident Inspector.
* * * UPDATE AT 2340 EDT ON 03/28/10 FROM MIKE DONITHAN TO PETE SNYDER * * *
The original Non-Emergency classification was reclassified as an ALERT based on the following:
"A fire on 4kV Bus 5 affected 4kV Bus 4 which caused a loss of 'B' Reactor Coolant Pump which caused a Reactor trip and Turbine Trip.
"That fire was extinguished without a required event declaration, but a subsequent fire on 4kV Bus 4 required declaration of an ALERT at 2300 [EDT] based on the fire affecting the safety-related 'A' and 'B' DC Buses. The fire was out at 2301 [EDT].
"The primary systems are available and control of the Reactor Coolant System has been maintained. The Safety Injection termination Emergency Operating Procedure has been performed and the general procedure for post-trip stabilization is being performed."
The licensee informed state/local agencies and the NRC Resident Inspector. Notified R2DO(Guthrie), IRD(Gott), EO(Blount), ET(Leeds), and R2RA(Reyes).
* * * UPDATE AT 0134 EDT ON 03/29/10 FROM BRYAN C. WALDSMITH TO CHARLES TEAL * * *
"Event Termination Notice for Event 45799. ALERT declaration is no longer required.
"Event Termination Notice: Current plant Conditions are stable and the conditions that required declaration of the ALERT are no longer present. The fire causing the ALERT classification was extinguished at 2301 [EDT]. There was no explosion or steam line break. The last safety-related DC bus ground was identified and cleared at 0001 [EDT]."
The licensee informed state/local agencies and the NRC Resident Inspector. Notified R2DO(Guthrie), IRD(Gott), EO(Blount), DHS(Moore), FEMA(Casto), DOE(Moorone), USDA(Hovey), and HHS(Nunn).
"At approximately 1852 hours Eastern Daylight Time [EDT], on March 28, 2010, with the unit operating at approximately 99.5% power, the H. B. Robinson Steam Electric Plant, Unit No. 2, reactor protection system actuated resulting in an automatic trip of the reactor. At about the time of the reactor trip, there was indication of a loss of the power to the Train 'B' emergency bus. The Train 'B' Emergency Diesel Generator started and provided power to the Train 'B' emergency bus. The Reactor Coolant System pressure response after the reactor trip resulted in the actuation of the Safety Injection System. The reduction in Reactor Coolant System pressure allowed the safety injection system to provide flow to the reactor coolant system, although, there was no indication of conditions that would require the safety injection system to provide flow to the reactor coolant system. Specifically, diagnosis of the event determined that a loss of coolant event, steam generator tube rupture, or secondary system break were not occurring. The safety systems that actuated for this event included the Reactor Protection System, the Safety Injection System, both Emergency Diesel Generators started and the 'B' Emergency Diesel Generator provided power to the 'B' Train Emergency Bus, the Auxiliary Feedwater System actuated, and the three main steam isolation valves closed. The Steam Generator Power Operated Relief Valves are being used for decay heat removal because of the closure of the main steam isolation valves. The Startup Transformer is energized and providing power to the 'A' Train Emergency Bus. Investigation of the cause of the reactor trip and associated emergency system actuations is in progress. At the time of the event, it was noted that there was evidence of a fire condition at 4KV bus number 5 located in the Turbine Building. It is currently believed that this is the cause of the transient condition that resulted in the reactor trip and other emergency system actuations. The reactor is currently being maintained in MODE 3, Hot Standby, conditions."
"This event is being reported in accordance with 10 CFR 50.72(b)(2)(iv)(A) for ECCS discharge into the RCS and (B) for RPS actuation, and 10 CFR 50.72(b)(3)(iv)(A) for specified system actuation as described.
"Additionally, based on an inquiry from the local news media reporter, information regarding this event was discussed with the local media. This contact with the local news media is being reported in accordance with 10 CFR 50.72(b)(2)(xi)."
All control rods fully inserted on the trip. Volume Control Tank [VCT] level was not dropping consistent with no reactor coolant system leakage. Pressurizer level and pressure drop was indicative of shrink associated with the Reactor Coolant Pump stoppage and cooldown in one loop. The licensee observed no indication of reactor coolant system leakage from the containment sump water level monitors.
The licensee informed the NRC Resident Inspector.
* * * UPDATE AT 2340 EDT ON 03/28/10 FROM MIKE DONITHAN TO PETE SNYDER * * *
The original Non-Emergency classification was reclassified as an ALERT based on the following:
"A fire on 4kV Bus 5 affected 4kV Bus 4 which caused a loss of 'B' Reactor Coolant Pump which caused a Reactor trip and Turbine Trip.
"That fire was extinguished without a required event declaration, but a subsequent fire on 4kV Bus 4 required declaration of an ALERT at 2300 [EDT] based on the fire affecting the safety-related 'A' and 'B' DC Buses. The fire was out at 2301 [EDT].
"The primary systems are available and control of the Reactor Coolant System has been maintained. The Safety Injection termination Emergency Operating Procedure has been performed and the general procedure for post-trip stabilization is being performed."
The licensee informed state/local agencies and the NRC Resident Inspector. Notified R2DO(Guthrie), IRD(Gott), EO(Blount), ET(Leeds), and R2RA(Reyes).
* * * UPDATE AT 0134 EDT ON 03/29/10 FROM BRYAN C. WALDSMITH TO CHARLES TEAL * * *
"Event Termination Notice for Event 45799. ALERT declaration is no longer required.
"Event Termination Notice: Current plant Conditions are stable and the conditions that required declaration of the ALERT are no longer present. The fire causing the ALERT classification was extinguished at 2301 [EDT]. There was no explosion or steam line break. The last safety-related DC bus ground was identified and cleared at 0001 [EDT]."
The licensee informed state/local agencies and the NRC Resident Inspector. Notified R2DO(Guthrie), IRD(Gott), EO(Blount), DHS(Moore), FEMA(Casto), DOE(Moorone), USDA(Hovey), and HHS(Nunn).