Event Notification Report for December 16, 2012
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
12/15/2012 - 12/16/2012
EVENT NUMBERS
48598
Power Reactor
Event Number: 48598
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: ALEX McLLELLAN
HQ OPS Officer: BILL HUFFMAN
Region: 1 State: PA
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: ALEX McLLELLAN
HQ OPS Officer: BILL HUFFMAN
Notification Date: 12/16/2012
Notification Time: 04:39 [ET]
Event Date: 12/16/2012
Event Time: 01:56 [EST]
Last Update Date: 12/16/2012
Notification Time: 04:39 [ET]
Event Date: 12/16/2012
Event Time: 01:56 [EST]
Last Update Date: 12/16/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(2)(iv)(A) - ECCS INJECTION 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)(2)(iv)(A) - ECCS INJECTION 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
DANIEL HOLODY (R1DO)
DANIEL HOLODY (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | A/R | Y | 98 | Power Operation | 0 | Hot Shutdown |
REACTOR SCRAM FROM 98% POWER DURING TURBINE CONTROL VALVE TESTING
"At approximately 01:56 hours on December 16, 2012, Susquehanna Steam Electric Station Unit 2 reactor automatically scrammed while performing testing of the number 2 control valve per the station surveillance testing program. The number 2 control valve closure initiated a 1/2 scram in the reactor protection system as designed; specifically the 'B1' channel. Evaluation of plant data indicates that an 'A' scram channel signal was activated during the time period the number 2 control valve scram signal was active, thereby causing a full reactor scram. The cause of the 'A' scram channel signal is not understood at this time and is under investigation.
"A second reactor scram signal was received at approximately 02:10 hours due to reactor water level lowering to 13 inches. Reactor water level was restored above the trip setpoint. All control rods inserted and both reactor recirculation pumps tripped at -38 inches. Reactor water level lowered to -48.5 inches causing Level 3 (+13 inches) and level 2 (-38 inches) isolations.
"HPCI and RCIC both automatically initiated and were overridden by control room operators after water level was restored. All isolations and initiations at this level occurred as expected. No steam relief valves opened. Pressure was controlled via turbine bypass valve operation. All safety systems operated as expected.
"This report is being made per 10 CFR 50.72(b)(2)(iv)(A) and 10 CFR 50.72(b)(2)(iv)(B) for 4 hour reports, and 10 CFR 50.72(b)(3)(iv)(A) for an 8 hour report.
"The unit 2 reactor is currently stable in Mode 3. An investigation into the cause of the reactor scram is underway.
"Unit 1 continued power operation.
"The NRC resident inspectors were notified. A press release will occur." The licensee will be notifying the State authorities.
"At approximately 01:56 hours on December 16, 2012, Susquehanna Steam Electric Station Unit 2 reactor automatically scrammed while performing testing of the number 2 control valve per the station surveillance testing program. The number 2 control valve closure initiated a 1/2 scram in the reactor protection system as designed; specifically the 'B1' channel. Evaluation of plant data indicates that an 'A' scram channel signal was activated during the time period the number 2 control valve scram signal was active, thereby causing a full reactor scram. The cause of the 'A' scram channel signal is not understood at this time and is under investigation.
"A second reactor scram signal was received at approximately 02:10 hours due to reactor water level lowering to 13 inches. Reactor water level was restored above the trip setpoint. All control rods inserted and both reactor recirculation pumps tripped at -38 inches. Reactor water level lowered to -48.5 inches causing Level 3 (+13 inches) and level 2 (-38 inches) isolations.
"HPCI and RCIC both automatically initiated and were overridden by control room operators after water level was restored. All isolations and initiations at this level occurred as expected. No steam relief valves opened. Pressure was controlled via turbine bypass valve operation. All safety systems operated as expected.
"This report is being made per 10 CFR 50.72(b)(2)(iv)(A) and 10 CFR 50.72(b)(2)(iv)(B) for 4 hour reports, and 10 CFR 50.72(b)(3)(iv)(A) for an 8 hour report.
"The unit 2 reactor is currently stable in Mode 3. An investigation into the cause of the reactor scram is underway.
"Unit 1 continued power operation.
"The NRC resident inspectors were notified. A press release will occur." The licensee will be notifying the State authorities.