Event Notification Report for January 25, 2011
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
01/24/2011 - 01/25/2011
Power Reactor
Event Number: 46569
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: GORDON ROBINSON
HQ OPS Officer: JOHN SHOEMAKER
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: GORDON ROBINSON
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 01/25/2011
Notification Time: 08:12 [ET]
Event Date: 01/25/2011
Event Time: 06:10 [EST]
Last Update Date: 01/25/2011
Notification Time: 08:12 [ET]
Event Date: 01/25/2011
Event Time: 06:10 [EST]
Last Update Date: 01/25/2011
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):
CHRISTOPHER NEWPORT (R1DO)
CHRISTOPHER NEWPORT (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | M/R | Y | 65 | Power Operation | 0 | Hot Shutdown |
MANUAL REACTOR SCRAM DUE TO AN UNISOLABLE EXTRACTION STEAM SYSTEM LEAK
"At 0610 EST hours on January 25, 2011, Susquehanna Steam Electric Station Unit 1 reactor was manually scrammed due to an unisolable extraction steam system leak in the 1C Feed Water Heater Bay area.
"At 0517 EST reactor operators commenced lowering reactor power from 98.4% to 65%. Attempts to isolate the source of the leakage were unsuccessful. Based on continued indications of unisolated steam leakage, operations decided to shut down the plant. The reactor operator placed the mode switch in shutdown. All control rods inserted. Reactor water level lowered to -31 inches causing Level 3 (+ 13 inches) isolation and RCIC initiation. The operations crew subsequently maintained reactor water level at the normal operating band using FW [feedwater]. No steam relief valves opened. All safety systems operated as expected. RCIC automatically initiated on a -30 inch level signal and was manually secured.
"The reactor is currently stable in Mode 3. Investigation into the cause of the extraction steam system leakage is underway.
"The NRC Resident Inspector was notified. A voluntary notification to PEMA and press release will occur."
The steam leak was isolated after the turbine was tripped. The plant is stable at normal temperature and pressure. Decay heat is being removed via the condenser steam dumps to the main condenser. The electrical lineup is in a normal configuration. Estimated time to restart is not known.
"At 0610 EST hours on January 25, 2011, Susquehanna Steam Electric Station Unit 1 reactor was manually scrammed due to an unisolable extraction steam system leak in the 1C Feed Water Heater Bay area.
"At 0517 EST reactor operators commenced lowering reactor power from 98.4% to 65%. Attempts to isolate the source of the leakage were unsuccessful. Based on continued indications of unisolated steam leakage, operations decided to shut down the plant. The reactor operator placed the mode switch in shutdown. All control rods inserted. Reactor water level lowered to -31 inches causing Level 3 (+ 13 inches) isolation and RCIC initiation. The operations crew subsequently maintained reactor water level at the normal operating band using FW [feedwater]. No steam relief valves opened. All safety systems operated as expected. RCIC automatically initiated on a -30 inch level signal and was manually secured.
"The reactor is currently stable in Mode 3. Investigation into the cause of the extraction steam system leakage is underway.
"The NRC Resident Inspector was notified. A voluntary notification to PEMA and press release will occur."
The steam leak was isolated after the turbine was tripped. The plant is stable at normal temperature and pressure. Decay heat is being removed via the condenser steam dumps to the main condenser. The electrical lineup is in a normal configuration. Estimated time to restart is not known.
Power Reactor
Event Number: 46573
Facility: ARKANSAS NUCLEAR
Region: 4 State: AR
Unit: [1] [2] []
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: DUSTIN HILL
HQ OPS Officer: VINCE KLCO
Region: 4 State: AR
Unit: [1] [2] []
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: DUSTIN HILL
HQ OPS Officer: VINCE KLCO
Notification Date: 01/26/2011
Notification Time: 17:08 [ET]
Event Date: 01/25/2011
Event Time: 20:43 [CST]
Last Update Date: 01/26/2011
Notification Time: 17:08 [ET]
Event Date: 01/25/2011
Event Time: 20:43 [CST]
Last Update Date: 01/26/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
GEOFFREY MILLER (R4DO)
GEOFFREY MILLER (R4DO)
| 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 |
FITNESS FOR DUTY REPORT INVOLVING A NON-LICENSED CONTRACT SUPERVISOR
A non-licensed contract employee supervisor had a confirmed positive for a controlled substance during a random fitness-for-duty test. The subject individual has been terminated. Contact the Headquarters Operations Officer for additional details.
The licensee has notified the NRC Resident Inspectors.
A non-licensed contract employee supervisor had a confirmed positive for a controlled substance during a random fitness-for-duty test. The subject individual has been terminated. Contact the Headquarters Operations Officer for additional details.
The licensee has notified the NRC Resident Inspectors.