Event Notification Report for November 04, 2012
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
11/03/2012 - 11/04/2012
Power Reactor
Event Number: 48478
Facility: PALISADES
Region: 3 State: MI
Unit: [1] [] []
RX Type: [1] CE
NRC Notified By: TODD MULFORD
HQ OPS Officer: JOHN KNOKE
Region: 3 State: MI
Unit: [1] [] []
RX Type: [1] CE
NRC Notified By: TODD MULFORD
HQ OPS Officer: JOHN KNOKE
Notification Date: 11/04/2012
Notification Time: 14:52 [ET]
Event Date: 11/04/2012
Event Time: 12:30 [EDT]
Last Update Date: 11/04/2012
Notification Time: 14:52 [ET]
Event Date: 11/04/2012
Event Time: 12:30 [EDT]
Last Update Date: 11/04/2012
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):
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 | 47 | Power Operation |
TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO SECONDARY SIDE STEAM LEAK
"At 1115 EST on November 4, 2012, primary coolant loop #2 was declared inoperable due to a small un-isolable steam leak on a drain valve of an atmospheric steam dump valve on the secondary side of the 'B' Steam Generator. The valve is ASME Class II high energy piping and the non-conforming condition could not be evaluated with the steam generator pressurized. Based on the condition of the valve and the inability to evaluate, Technical Specification 3.4.4, PCS loops - Modes 1 and 2, Required Action A.1 was entered which requires the plant to be placed in Mode 3 in 6 hours. Repair of the valve may require cooldown to Mode 5.
"At 1230 EST on November, 2012, Palisades initiated a shutdown in accordance with Technical Specification 3.4.4."
The licensee has notified the NRC Resident Inspector.
"At 1115 EST on November 4, 2012, primary coolant loop #2 was declared inoperable due to a small un-isolable steam leak on a drain valve of an atmospheric steam dump valve on the secondary side of the 'B' Steam Generator. The valve is ASME Class II high energy piping and the non-conforming condition could not be evaluated with the steam generator pressurized. Based on the condition of the valve and the inability to evaluate, Technical Specification 3.4.4, PCS loops - Modes 1 and 2, Required Action A.1 was entered which requires the plant to be placed in Mode 3 in 6 hours. Repair of the valve may require cooldown to Mode 5.
"At 1230 EST on November, 2012, Palisades initiated a shutdown in accordance with Technical Specification 3.4.4."
The licensee has notified the NRC Resident Inspector.
Power Reactor
Event Number: 48479
Facility: FITZPATRICK
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: DAVE RICHARDSON
HQ OPS Officer: BILL HUFFMAN
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: DAVE RICHARDSON
HQ OPS Officer: BILL HUFFMAN
Notification Date: 11/05/2012
Notification Time: 00:40 [ET]
Event Date: 11/04/2012
Event Time: 21:53 [EST]
Last Update Date: 11/05/2012
Notification Time: 00:40 [ET]
Event Date: 11/04/2012
Event Time: 21:53 [EST]
Last Update Date: 11/05/2012
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):
JAMES NOGGLE (R1DO)
JAMES NOGGLE (R1DO)
| 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 FROM FULL POWER FOLLOWING TURBINE TRIP
"The reactor was scrammed on a valid reactor protection system activation caused by a main turbine trip. The cause of the main turbine trip is under investigation. All control rods fully inserted. All isolations and initiations occurred as designed. High Pressure Coolant Injection (HPCI) and Reactor Core Isolation Cooling (RCIC) initiated as expected. RCIC injected into the reactor coolant system, HPCI did not, as expected."
This scram was characterized as uncomplicated and the reactor is stable in Mode 3. The plant is in a normal post shutdown electrical lineup. All systems functioned as required.
The NRC Resident Inspector has been notified.
"The reactor was scrammed on a valid reactor protection system activation caused by a main turbine trip. The cause of the main turbine trip is under investigation. All control rods fully inserted. All isolations and initiations occurred as designed. High Pressure Coolant Injection (HPCI) and Reactor Core Isolation Cooling (RCIC) initiated as expected. RCIC injected into the reactor coolant system, HPCI did not, as expected."
This scram was characterized as uncomplicated and the reactor is stable in Mode 3. The plant is in a normal post shutdown electrical lineup. All systems functioned as required.
The NRC Resident Inspector has been notified.