Event Notification Report for August 12, 2010
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
08/11/2010 - 08/12/2010
Power Reactor
Event Number: 46171
Facility: LASALLE
Region: 3 State: IL
Unit: [1] [2] []
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: MICHAEL FITZPATRICK
HQ OPS Officer: BILL HUFFMAN
Region: 3 State: IL
Unit: [1] [2] []
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: MICHAEL FITZPATRICK
HQ OPS Officer: BILL HUFFMAN
Notification Date: 08/12/2010
Notification Time: 23:50 [ET]
Event Date: 08/12/2010
Event Time: 19:52 [CDT]
Last Update Date: 08/12/2010
Notification Time: 23:50 [ET]
Event Date: 08/12/2010
Event Time: 19:52 [CDT]
Last Update Date: 08/12/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
JAMNES CAMERON (R3DO)
JAMNES CAMERON (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 76 | Power Operation | 76 | Power Operation |
| 2 | N | Y | 82 | Power Operation | 82 | Power Operation |
TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO ENVIRONMENTAL CONDITIONS RESULTING IN ELEVATED ULTIMATE HEAT SINK TEMPERATURE
"At 2050 [CDT] on 8/12/10, LaSalle Unit 1 and Unit 2 commenced a Plant Shutdown. At 1952 [CDT] on 8/12/10, LaSalle Ultimate Heat Sink exceeded the 101.25?F limit per Technical Specification LCO 3.7.3, Condition B. Per Technical Specification LCO 3.7.3, Required Action B.1, both Unit 1 and Unit 2 are to be in Mode 3 (Hot Shutdown) in 12 hours. Per Technical Specification LCO 3.7.3 Required Action B.2, both Unit 1 and Unit 2 are to be in Mode 4 (Cold Shutdown) in 36 hours. Technical Specification LCO 3.7.3, Ultimate Heat Sink requires that both Unit 1 and Unit 2 to be in MODE 3 by 8/13/10 at 0752 [CDT] and MODE 4 by 8/14/10 at 0752 [CDT].
"Unit 1 was initially at 76% Power due to a response to elevated Main Condenser In-Leakage, not related to the Ultimate Heat Sink High Temperature. Unit 2 was initially at 82% Power due to elevated Condensate Temperature and in response to worsening Main Condenser Backpressure. For Unit 2, both of these parameters were related to the elevated Ultimate Heat Sink Temperature.
"The Ultimate Heat Sink Temperature is currently 101.33?F. All Systems are responding as expected."
This condition is a result of the hot environmental conditions and is not due to any equipment problems or other operating issues at the site.
The licensee has notified the NRC Resident Inspector.
"At 2050 [CDT] on 8/12/10, LaSalle Unit 1 and Unit 2 commenced a Plant Shutdown. At 1952 [CDT] on 8/12/10, LaSalle Ultimate Heat Sink exceeded the 101.25?F limit per Technical Specification LCO 3.7.3, Condition B. Per Technical Specification LCO 3.7.3, Required Action B.1, both Unit 1 and Unit 2 are to be in Mode 3 (Hot Shutdown) in 12 hours. Per Technical Specification LCO 3.7.3 Required Action B.2, both Unit 1 and Unit 2 are to be in Mode 4 (Cold Shutdown) in 36 hours. Technical Specification LCO 3.7.3, Ultimate Heat Sink requires that both Unit 1 and Unit 2 to be in MODE 3 by 8/13/10 at 0752 [CDT] and MODE 4 by 8/14/10 at 0752 [CDT].
"Unit 1 was initially at 76% Power due to a response to elevated Main Condenser In-Leakage, not related to the Ultimate Heat Sink High Temperature. Unit 2 was initially at 82% Power due to elevated Condensate Temperature and in response to worsening Main Condenser Backpressure. For Unit 2, both of these parameters were related to the elevated Ultimate Heat Sink Temperature.
"The Ultimate Heat Sink Temperature is currently 101.33?F. All Systems are responding as expected."
This condition is a result of the hot environmental conditions and is not due to any equipment problems or other operating issues at the site.
The licensee has notified the NRC Resident Inspector.
Power Reactor
Event Number: 46169
Facility: QUAD CITIES
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: C. STEFFES
HQ OPS Officer: BILL HUFFMAN
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: C. STEFFES
HQ OPS Officer: BILL HUFFMAN
Notification Date: 08/12/2010
Notification Time: 08:04 [ET]
Event Date: 08/12/2010
Event Time: 03:58 [CDT]
Last Update Date: 08/12/2010
Notification Time: 08:04 [ET]
Event Date: 08/12/2010
Event Time: 03:58 [CDT]
Last Update Date: 08/12/2010
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):
JAMNES CAMERON (R3DO)
JAMNES CAMERON (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 |
UNIT 1 REACTOR AUTOMATIC SCRAM DUE TO TURBINE TRIP
"While performing a main condenser flow reversal at 0358 [CDT] on August 12, 2010 the Unit 1 reactor received an automatic scram on turbine stop valve closure. Turbine stop valve closure was initiated from a turbine trip on low vacuum. Reactor water level decreased to approximately -3 [inches], which resulted in automatic Group II and III isolations as expected. All systems responded properly to the event. Unit One remains in Mode 3, maintaining reactor pressure with reactor water level in the normal level band. The cause of the event is still under investigation.
"Unit 2 was unaffected by the event and remains at 100% power.
"This report is being made in accordance with 10CFR50.72(b)(2)(iv)(B) and 10CFR50.72(b)(3)(iv)(A)."
All rods fully inserted. Normal feedwater is supplying the reactor with decay heat removal via the turbine bypass valves. No safety relief valves lifted during the transient. The transient was initiated during the condenser flow reversal when one of the flow reversal valves failed to fully reverse the flow. This resulted in inadequate heat transfer to circ water at full power operation causing the condenser vacuum to increase. In addition, the condenser vacuum trip of the turbine appears to have initiated before it was actually required. Overall, the scram was characterized as uncomplicated and all systems functioned as required.
"While performing a main condenser flow reversal at 0358 [CDT] on August 12, 2010 the Unit 1 reactor received an automatic scram on turbine stop valve closure. Turbine stop valve closure was initiated from a turbine trip on low vacuum. Reactor water level decreased to approximately -3 [inches], which resulted in automatic Group II and III isolations as expected. All systems responded properly to the event. Unit One remains in Mode 3, maintaining reactor pressure with reactor water level in the normal level band. The cause of the event is still under investigation.
"Unit 2 was unaffected by the event and remains at 100% power.
"This report is being made in accordance with 10CFR50.72(b)(2)(iv)(B) and 10CFR50.72(b)(3)(iv)(A)."
All rods fully inserted. Normal feedwater is supplying the reactor with decay heat removal via the turbine bypass valves. No safety relief valves lifted during the transient. The transient was initiated during the condenser flow reversal when one of the flow reversal valves failed to fully reverse the flow. This resulted in inadequate heat transfer to circ water at full power operation causing the condenser vacuum to increase. In addition, the condenser vacuum trip of the turbine appears to have initiated before it was actually required. Overall, the scram was characterized as uncomplicated and all systems functioned as required.