Event Notification Report for June 23, 2009
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
06/22/2009 - 06/23/2009
EVENT NUMBERS
4514845151451524515345154
Power Reactor
Event Number: 45148
Facility: HATCH
Region: 2 State: GA
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: STEVE BURTON
HQ OPS Officer: HOWIE CROUCH
Region: 2 State: GA
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: STEVE BURTON
HQ OPS Officer: HOWIE CROUCH
Notification Date: 06/23/2009
Notification Time: 05:08 [ET]
Event Date: 06/23/2009
Event Time: 03:51 [EDT]
Last Update Date: 06/23/2009
Notification Time: 05:08 [ET]
Event Date: 06/23/2009
Event Time: 03:51 [EDT]
Last Update Date: 06/23/2009
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):
JONATHAN BARTLEY (R2DO)
JONATHAN BARTLEY (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | A/R | Y | 61 | Power Operation | 0 | Hot Shutdown |
AUTOMATIC REACTOR SCRAM DUE TO HIGH REACTOR WATER LEVEL
"[The reactor automatically scrammed] on a Main Turbine Trip >27.6% rated thermal power. The main turbine trip was due to reactor high level. Post scram, reactor level decreased to approximately -26 inches. Reactor water level was restored with the condensate system.
"Both reactor recirc pumps tripped as required on EOC RPT Logic when the main turbine tripped. Both pumps have been restarted.
"A Group 2 isolation was received at +3 inches reactor water level with all valves closing as required.
"Investigation as to the cause of the transient is underway."
All rods inserted during the scram. No relief valves actuated during the transient. Decay heat is being removed via turbine bypass valves to the main condenser. The plant is within normal shutdown temperature and pressure limits. The electrical grid is stable and the plant is in a normal shutdown electrical lineup. The Group 2 has been reset. There was no effect on Unit 1.
The licensee has notified the NRC Resident Inspector.
"[The reactor automatically scrammed] on a Main Turbine Trip >27.6% rated thermal power. The main turbine trip was due to reactor high level. Post scram, reactor level decreased to approximately -26 inches. Reactor water level was restored with the condensate system.
"Both reactor recirc pumps tripped as required on EOC RPT Logic when the main turbine tripped. Both pumps have been restarted.
"A Group 2 isolation was received at +3 inches reactor water level with all valves closing as required.
"Investigation as to the cause of the transient is underway."
All rods inserted during the scram. No relief valves actuated during the transient. Decay heat is being removed via turbine bypass valves to the main condenser. The plant is within normal shutdown temperature and pressure limits. The electrical grid is stable and the plant is in a normal shutdown electrical lineup. The Group 2 has been reset. There was no effect on Unit 1.
The licensee has notified the NRC Resident Inspector.
Power Reactor
Event Number: 45151
Facility: LASALLE
Region: 3 State: IL
Unit: [1] [2] []
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: JOHN KEENAN
HQ OPS Officer: VINCE KLCO
Region: 3 State: IL
Unit: [1] [2] []
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: JOHN KEENAN
HQ OPS Officer: VINCE KLCO
Notification Date: 06/23/2009
Notification Time: 15:16 [ET]
Event Date: 06/23/2009
Event Time: 12:49 [CDT]
Last Update Date: 06/23/2009
Notification Time: 15:16 [ET]
Event Date: 06/23/2009
Event Time: 12:49 [CDT]
Last Update Date: 06/23/2009
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):
ANN MARIE STONE (R3DO)
ANN MARIE STONE (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
OFFSITE NOTIFICATION DUE TO FISH KILL
"At 1249 CDT on 06/23/09, it was discovered that a fish kill took place in LaSalle County Nuclear Station's cooling lake, due to increased temperature. As summer air temperatures increased, the cooling lake temperature increased above 93?F, the threshold at which species susceptible to increased temperature begin to perish. It was communicated to the Illinois Department of Natural Resources (IDNR), that a fish kill has occurred. Efforts are under way to contact the IDNR district fish biologist to quantify the mortality.
"This notification is made in accordance with Exelon Reportability manual SAF 1.9, ENV 3.26, LaSalle County Station Facility Operating License Appendix B Section 4.1 'Unusual or Important Environmental Events', and 10CFR50.72(b)(2)(xi)."
The licensee notified the NRC Resident Inspector.
"At 1249 CDT on 06/23/09, it was discovered that a fish kill took place in LaSalle County Nuclear Station's cooling lake, due to increased temperature. As summer air temperatures increased, the cooling lake temperature increased above 93?F, the threshold at which species susceptible to increased temperature begin to perish. It was communicated to the Illinois Department of Natural Resources (IDNR), that a fish kill has occurred. Efforts are under way to contact the IDNR district fish biologist to quantify the mortality.
"This notification is made in accordance with Exelon Reportability manual SAF 1.9, ENV 3.26, LaSalle County Station Facility Operating License Appendix B Section 4.1 'Unusual or Important Environmental Events', and 10CFR50.72(b)(2)(xi)."
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 45152
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: TIM BUCHAL
HQ OPS Officer: VINCE KLCO
Region: 1 State: NY
Unit: [2] [] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: TIM BUCHAL
HQ OPS Officer: VINCE KLCO
Notification Date: 06/23/2009
Notification Time: 20:35 [ET]
Event Date: 06/23/2009
Event Time: 18:23 [EDT]
Last Update Date: 06/23/2009
Notification Time: 20:35 [ET]
Event Date: 06/23/2009
Event Time: 18:23 [EDT]
Last Update Date: 06/23/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
Person (Organization):
PAMELA HENDERSON (R1DO)
PAMELA HENDERSON (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
POTENTIALLY DEGRADED INVENTORY CONTROL DURING SHUTDOWN
"[At 1823 EDT, the] 23 charging pump, the in-service pump, exhibited degraded capacity resulting in slowly lowering pressurizer level. The 21 charging pump was placed in service and the 23 charging pump was secured. The 23 charging pump is required for fulfillment of the [Reactor Coolant System] RCS inventory control safety function needed to shut down the reactor and maintain it in a safe shutdown condition. Troubleshooting is in progress to determine cause of degraded capacity."
In accordance with Technical Specification 3.3.4, the out of service 23 charging pump places the Indian Point Unit 2 into a 30 day shutdown action statement.
The licensee notified the NRC Resident Inspector and the New York Public Service Commission (PSC) of the event.
"[At 1823 EDT, the] 23 charging pump, the in-service pump, exhibited degraded capacity resulting in slowly lowering pressurizer level. The 21 charging pump was placed in service and the 23 charging pump was secured. The 23 charging pump is required for fulfillment of the [Reactor Coolant System] RCS inventory control safety function needed to shut down the reactor and maintain it in a safe shutdown condition. Troubleshooting is in progress to determine cause of degraded capacity."
In accordance with Technical Specification 3.3.4, the out of service 23 charging pump places the Indian Point Unit 2 into a 30 day shutdown action statement.
The licensee notified the NRC Resident Inspector and the New York Public Service Commission (PSC) of the event.
Power Reactor
Event Number: 45153
Facility: LIMERICK
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: BRANDON SHULTZ
HQ OPS Officer: VINCE KLCO
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: BRANDON SHULTZ
HQ OPS Officer: VINCE KLCO
Notification Date: 06/23/2009
Notification Time: 22:40 [ET]
Event Date: 06/23/2009
Event Time: 20:30 [EDT]
Last Update Date: 06/24/2009
Notification Time: 22:40 [ET]
Event Date: 06/23/2009
Event Time: 20:30 [EDT]
Last Update Date: 06/24/2009
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):
PAMELA HENDERSON (R1DO)
PAMELA HENDERSON (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
PARTIAL LOSS OF THE EMERGENCY RESPONSE DATA SYSTEM (ERDS)
"A partial loss of the ability to send ERDS data to the NRC for greater than 60 minutes occurred. The loss affects transmission of Standby Liquid Control Tank levels, Main Condenser Vacuum levels, and data for North and South Ventilation Stacks and Drywall Post LOCA radiation monitors.
"The [Safety Parameter Display System] SPDS, [Health Physics Network] HPN and [Emergency Notification System] ENS systems are not affected.
"Troubleshooting to identify and correct the data loss to ERDS is in progress."
The licensee notified the NRC Resident Inspector.
* * * UPDATE AT 0029 EDT ON 6/24/09 FROM SHULTZ TO HUFFMAN * * *
"Data for North and South Ventilation Stacks and Drywell Post LOCA radiation monitors was restored to ERDS at 2345 hours on 6/23/09" The licensee will notify the NRC Resident Inspector.
* * * UPDATE AT 1310 EDT ON 06/24/09 FROM MARK CHRISTOPHER TO S. SANDIN * * *
"Data gathered from Standby Liquid Control and Main Condenser Vacuum is not plant data that is transmitted to ERDS. ERDS was fully restored with the required input data at 2345 hours on 6/23/2009."
The licensee informed the NRC Resident Inspector. Notified R1DO (Henderson).
"A partial loss of the ability to send ERDS data to the NRC for greater than 60 minutes occurred. The loss affects transmission of Standby Liquid Control Tank levels, Main Condenser Vacuum levels, and data for North and South Ventilation Stacks and Drywall Post LOCA radiation monitors.
"The [Safety Parameter Display System] SPDS, [Health Physics Network] HPN and [Emergency Notification System] ENS systems are not affected.
"Troubleshooting to identify and correct the data loss to ERDS is in progress."
The licensee notified the NRC Resident Inspector.
* * * UPDATE AT 0029 EDT ON 6/24/09 FROM SHULTZ TO HUFFMAN * * *
"Data for North and South Ventilation Stacks and Drywell Post LOCA radiation monitors was restored to ERDS at 2345 hours on 6/23/09" The licensee will notify the NRC Resident Inspector.
* * * UPDATE AT 1310 EDT ON 06/24/09 FROM MARK CHRISTOPHER TO S. SANDIN * * *
"Data gathered from Standby Liquid Control and Main Condenser Vacuum is not plant data that is transmitted to ERDS. ERDS was fully restored with the required input data at 2345 hours on 6/23/2009."
The licensee informed the NRC Resident Inspector. Notified R1DO (Henderson).
Power Reactor
Event Number: 45154
Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: ELLIS VANN
HQ OPS Officer: BILL HUFFMAN
Region: 3 State: IA
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: ELLIS VANN
HQ OPS Officer: BILL HUFFMAN
Notification Date: 06/23/2009
Notification Time: 23:37 [ET]
Event Date: 06/23/2009
Event Time: 17:04 [CDT]
Last Update Date: 06/24/2009
Notification Time: 23:37 [ET]
Event Date: 06/23/2009
Event Time: 17:04 [CDT]
Last Update Date: 06/24/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
ANN MARIE STONE (R3DO)
ANN MARIE STONE (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
AUTO START OF EMERGENCY DIESEL GENERATORS DUE TO OFFSITE VOLTAGE TRANSIENT
"This report is being made under 10CFR50.72(b)(3)(iv)(A), 'Any event or condition that results in valid actuation of any of the systems listed in paragraph (b)(3)(iv)(A) of this section' due to the auto start of the 'A' and 'B' Standby Diesel Generators.
"The auto start of the 'A' and 'B' Standby Diesel Generators occurred on a valid bus undervoltage condition caused by a transient on the 161 kV Fairfax line while there were severe thunderstorms in the DAEC area. The Standby Diesel Generator supply breakers did not close onto their respective essential buses. The essential buses were not required to load onto either diesel as they remained powered from their normal power supply, 1X003 Start-up Transformer, during and after the event. Offsite power remained fully operable during and following the event. The Standby Diesel Generators have been returned to the standby/readiness condition.
"As designed, both Emergency Service Water systems auto started when the SBDGs started. The Emergency Service Water systems have been returned to the standby/readiness condition.
"All ECCS systems were available before the event and have remained available following the event.
"The NRC Resident Inspector has been informed of the automatic SBDG start."
"This report is being made under 10CFR50.72(b)(3)(iv)(A), 'Any event or condition that results in valid actuation of any of the systems listed in paragraph (b)(3)(iv)(A) of this section' due to the auto start of the 'A' and 'B' Standby Diesel Generators.
"The auto start of the 'A' and 'B' Standby Diesel Generators occurred on a valid bus undervoltage condition caused by a transient on the 161 kV Fairfax line while there were severe thunderstorms in the DAEC area. The Standby Diesel Generator supply breakers did not close onto their respective essential buses. The essential buses were not required to load onto either diesel as they remained powered from their normal power supply, 1X003 Start-up Transformer, during and after the event. Offsite power remained fully operable during and following the event. The Standby Diesel Generators have been returned to the standby/readiness condition.
"As designed, both Emergency Service Water systems auto started when the SBDGs started. The Emergency Service Water systems have been returned to the standby/readiness condition.
"All ECCS systems were available before the event and have remained available following the event.
"The NRC Resident Inspector has been informed of the automatic SBDG start."