Event Notification Report for January 27, 2007
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
01/26/2007 - 01/27/2007
Power Reactor
Event Number: 43127
Facility: ROBINSON
Region: 2 State: SC
Unit: [2] [] []
RX Type: [2] W-3-LP
NRC Notified By: LEONARD WIEGAND
HQ OPS Officer: JEFF ROTTON
Region: 2 State: SC
Unit: [2] [] []
RX Type: [2] W-3-LP
NRC Notified By: LEONARD WIEGAND
HQ OPS Officer: JEFF ROTTON
Notification Date: 01/27/2007
Notification Time: 09:10 [ET]
Event Date: 01/27/2007
Event Time: 09:05 [EST]
Last Update Date: 01/27/2007
Notification Time: 09:10 [ET]
Event Date: 01/27/2007
Event Time: 09:05 [EST]
Last Update Date: 01/27/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
BRIAN BONSER (R2)
BRIAN BONSER (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
ERFIS REMOVED FROM SERVICE FOR PLANNED MODIFICATION
"At 0905 hours EST, on January 27, 2007, the Emergency Response Facility Information System (ERFIS) computer system was removed from service to complete a planned modification of the ERFIS power supply system. The expected duration of ERFIS inoperability is approximately 2 hours. The ERFIS computer system provides monitoring and communications capability for plant data systems including the Emergency Response Data System (ERDS), Safety Parameter Display System (SPDS), Meteorological Data link system, and the Inadequate Core Cooling Monitor (ICCM). The loss of ERFIS requires alternate methods, as described in plant procedures, to be used for the above described functions. Therefore, it is expected that appropriate assessment or plant conditions, notifications, and communications could still be made, if required, during the time that the ERFIS computer system is inoperable. This report is being made in accordance with 10 CFR 50.72(b)(3)(xiii), which is any event that results in a major loss of emergency assessment capability, offsite response capability, or offsite communications capability. As previously stated, alternate means remain available to assess plant conditions, make notifications, and accomplish required communications, as necessary. An update to this message will be provided when the ERFIS is restored.
"This message is similar to the January 6, 2007 event notification number 43081. At that time the ERFIS was being placed on an alternate power supply to allow modification of the normal power supply. This interruption of the ERFIS is due to the completion of that planned modification, which allows restoration of the ERFIS to the normal power supply."
The licensee notified the NRC Resident Inspector.
* * * UPDATE ON 01/27/07 AT 1347 EST FROM LEONARD WIEGAND TO MACKINNON * * *
Emergency Response Facility Information System (ERFIS) returned to service at 1150 EST.
The NRC Resident Inspector will be informed of this update by the licensee.
R2DO (Brian Bonser) notified
"At 0905 hours EST, on January 27, 2007, the Emergency Response Facility Information System (ERFIS) computer system was removed from service to complete a planned modification of the ERFIS power supply system. The expected duration of ERFIS inoperability is approximately 2 hours. The ERFIS computer system provides monitoring and communications capability for plant data systems including the Emergency Response Data System (ERDS), Safety Parameter Display System (SPDS), Meteorological Data link system, and the Inadequate Core Cooling Monitor (ICCM). The loss of ERFIS requires alternate methods, as described in plant procedures, to be used for the above described functions. Therefore, it is expected that appropriate assessment or plant conditions, notifications, and communications could still be made, if required, during the time that the ERFIS computer system is inoperable. This report is being made in accordance with 10 CFR 50.72(b)(3)(xiii), which is any event that results in a major loss of emergency assessment capability, offsite response capability, or offsite communications capability. As previously stated, alternate means remain available to assess plant conditions, make notifications, and accomplish required communications, as necessary. An update to this message will be provided when the ERFIS is restored.
"This message is similar to the January 6, 2007 event notification number 43081. At that time the ERFIS was being placed on an alternate power supply to allow modification of the normal power supply. This interruption of the ERFIS is due to the completion of that planned modification, which allows restoration of the ERFIS to the normal power supply."
The licensee notified the NRC Resident Inspector.
* * * UPDATE ON 01/27/07 AT 1347 EST FROM LEONARD WIEGAND TO MACKINNON * * *
Emergency Response Facility Information System (ERFIS) returned to service at 1150 EST.
The NRC Resident Inspector will be informed of this update by the licensee.
R2DO (Brian Bonser) notified
Power Reactor
Event Number: 43128
Facility: GINNA
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] W-2-LP
NRC Notified By: KEVIN McLAUGHLIN
HQ OPS Officer: STEVE SANDIN
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] W-2-LP
NRC Notified By: KEVIN McLAUGHLIN
HQ OPS Officer: STEVE SANDIN
Notification Date: 01/28/2007
Notification Time: 00:02 [ET]
Event Date: 01/27/2007
Event Time: 20:40 [EST]
Last Update Date: 01/28/2007
Notification Time: 00:02 [ET]
Event Date: 01/27/2007
Event Time: 20:40 [EST]
Last Update Date: 01/28/2007
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):
NEIL PERRY (R1)
NEIL PERRY (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
AUTOMATIC REACTOR TRIP DUE TO LOSS OF LOAD TRANSIENT CAUSED BY EHC PROBLEM
"On January 27, 2007 at approximately 2040 hours an automatic reactor trip occurred. The cause of the trip was Over Temperature Delta T (2/4). All systems functioned as designed. All control rods inserted on the trip. Decay heat removal is via condenser steam dump and Auxiliary Feedwater.
"The initial cause of the trip appears to be from a loss of load due to a turbine electro-hydraulic system issue. This is still under investigation.
"RCS Temperature is 547 Degrees F and stable
"RCS Pressure is 2235 psig and stable
"Both pressurizer PORVs momentarily opened and then closed during the transient.
"For 8Hr Non Emergency 10 CFR 50.72(b)(3)
"RPS actuation occurred.
"Auxiliary Feed Water actuation occurred."
There was no testing or maintenance in progress at the time of the transient.
The licensee informed the NRC Resident Inspector.
"On January 27, 2007 at approximately 2040 hours an automatic reactor trip occurred. The cause of the trip was Over Temperature Delta T (2/4). All systems functioned as designed. All control rods inserted on the trip. Decay heat removal is via condenser steam dump and Auxiliary Feedwater.
"The initial cause of the trip appears to be from a loss of load due to a turbine electro-hydraulic system issue. This is still under investigation.
"RCS Temperature is 547 Degrees F and stable
"RCS Pressure is 2235 psig and stable
"Both pressurizer PORVs momentarily opened and then closed during the transient.
"For 8Hr Non Emergency 10 CFR 50.72(b)(3)
"RPS actuation occurred.
"Auxiliary Feed Water actuation occurred."
There was no testing or maintenance in progress at the time of the transient.
The licensee informed the NRC Resident Inspector.