Event Notification Report for June 21, 2009
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
06/20/2009 - 06/21/2009
Power Reactor
Event Number: 45146
Facility: QUAD CITIES
Region: 3 State: IL
Unit: [] [2] []
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: RANDALL DEWEERDT
HQ OPS Officer: HOWIE CROUCH
Region: 3 State: IL
Unit: [] [2] []
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: RANDALL DEWEERDT
HQ OPS Officer: HOWIE CROUCH
Notification Date: 06/21/2009
Notification Time: 07:42 [ET]
Event Date: 06/21/2009
Event Time: 03:08 [CDT]
Last Update Date: 06/21/2009
Notification Time: 07:42 [ET]
Event Date: 06/21/2009
Event Time: 03:08 [CDT]
Last Update Date: 06/21/2009
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):
CHRISTINE LIPA (R3DO)
CHRISTINE LIPA (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
LOSS OF UNIT 2 EMERGENCY RESPONSE DATA SYSTEM (ERDS) DUE TO A PLANT PROCESS COMPUTER ISSUE
"On June 21, 2009, it was identified that Unit 2 ERDS was unavailable for approximately 3 hours and 1 minute (0208-0509 hours CDT). This was due to the loss of the Unit 2 Plant Process Computer (PPC) interface with ERDS. Unit 2 ERDS was restored when the Unit 2 PPC interface with ERDS was restored. The cause of the Unit 2 PPC interface interruption is under investigation.
"This event is reportable under 10 CFR 50.72(b)(3)(xiii) as a major loss of communications capability.
"The Duty NRC Resident Inspector has been notified."
"On June 21, 2009, it was identified that Unit 2 ERDS was unavailable for approximately 3 hours and 1 minute (0208-0509 hours CDT). This was due to the loss of the Unit 2 Plant Process Computer (PPC) interface with ERDS. Unit 2 ERDS was restored when the Unit 2 PPC interface with ERDS was restored. The cause of the Unit 2 PPC interface interruption is under investigation.
"This event is reportable under 10 CFR 50.72(b)(3)(xiii) as a major loss of communications capability.
"The Duty NRC Resident Inspector has been notified."
Power Reactor
Event Number: 45147
Facility: PERRY
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: DAVID O'DONNELL
HQ OPS Officer: VINCE KLCO
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: DAVID O'DONNELL
HQ OPS Officer: VINCE KLCO
Notification Date: 06/21/2009
Notification Time: 20:58 [ET]
Event Date: 06/21/2009
Event Time: 17:50 [EDT]
Last Update Date: 06/21/2009
Notification Time: 20:58 [ET]
Event Date: 06/21/2009
Event Time: 17:50 [EDT]
Last Update Date: 06/21/2009
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):
CHRISTINE LIPA (R3DO)
CHRISTINE LIPA (R3DO)
| 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 RELATED TO A MAIN TURBINE TRIP
"On June 21, 2009, at approximately 1750 hours, an automatic Reactor Protection System (RPS) actuation occurred at the Perry Nuclear Power Plant, Unit 1. At the time of the event, the plant was in Mode 1 at 100% power. All control rods are inserted into the core and the plant is currently stable, in Mode 3 (Hot Shutdown) with reactor pressure at approximately 930 psig. No Emergency Core Cooling Systems were required or utilized to
respond to the event and there were no other reportable actuations. Reactor coolant level is being maintained in its normal band by the feedwater system and decay heat is being removed by the condenser. The plant is in a normal electrical line-up with all three Emergency Diesel Generators operable and available if needed.
"The cause of the reactor scram is currently under investigation. Preliminary indications are that the cause of the RPS actuation is related to a main turbine trip. The NRC Resident Inspector has been notified."
No safety relief valves lifted during the event and a reactor cooldown is in progress.
"On June 21, 2009, at approximately 1750 hours, an automatic Reactor Protection System (RPS) actuation occurred at the Perry Nuclear Power Plant, Unit 1. At the time of the event, the plant was in Mode 1 at 100% power. All control rods are inserted into the core and the plant is currently stable, in Mode 3 (Hot Shutdown) with reactor pressure at approximately 930 psig. No Emergency Core Cooling Systems were required or utilized to
respond to the event and there were no other reportable actuations. Reactor coolant level is being maintained in its normal band by the feedwater system and decay heat is being removed by the condenser. The plant is in a normal electrical line-up with all three Emergency Diesel Generators operable and available if needed.
"The cause of the reactor scram is currently under investigation. Preliminary indications are that the cause of the RPS actuation is related to a main turbine trip. The NRC Resident Inspector has been notified."
No safety relief valves lifted during the event and a reactor cooldown is in progress.