Event Notification Report for February 10, 2013
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
02/09/2013 - 02/10/2013
Power Reactor
Event Number: 48738
Facility: HATCH
Region: 2 State: GA
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: KENNETH HUNTER
HQ OPS Officer: JOHN SHOEMAKER
Region: 2 State: GA
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: KENNETH HUNTER
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 02/10/2013
Notification Time: 09:11 [ET]
Event Date: 02/10/2013
Event Time: 07:00 [EST]
Last Update Date: 02/10/2013
Notification Time: 09:11 [ET]
Event Date: 02/10/2013
Event Time: 07:00 [EST]
Last Update Date: 02/10/2013
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):
GEORGE HOPPER (R2DO)
GEORGE HOPPER (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | M/R | Y | 47 | Power Operation | 0 | Hot Shutdown |
MANUAL REACTOR SCRAM INSERTED DUE TO DEGRADING REACTOR WATER CHEMISTRY
"During normal power operations, the crew observed condensate/feedwater conductivity begin to increase at approximately 0530 EST on 02/10/13. The crew responded to the associated alarm response procedures and entered abnormal operating procedure 34AB-N61-001-1 due to degrading reactor water chemistry parameters. A power reduction [from 100%] was initiated at 0555 EST in accordance with station procedures for responding to a suspected condenser tube leak. At 0700 EST, a manual reactor SCRAM [from approximately 47%] was inserted due to the elevated reactor water conductivity in accordance with station abnormal operating procedures. All rods inserted completely and no complications were encountered following the reactor SCRAM, normal feedwater injection remained available. Following the SCRAM, a Group 2 Primary Containment Isolation Signal (PCIS} was received as a result of reactor water level lowering below +3 inches. The lowest reactor water level observed was [minus] 2 inches and was restored to normal operating levels utilizing normal feedwater injection. Following restoration of reactor water level to the normal operating level, the Group 2 PCIS signal was reset. No ECCS injection systems actuated as a result of the reactor SCRAM."
The SCRAM was uncomplicated and the plant is stable. Decay heat removal is to the main condenser via the turbine bypass valves. The plant is in a normal offsite electrical power shutdown alignment. Efforts are in progress to isolate the condenser in-leakage. There was no impact on Unit 2.
The licensee has notified the NRC Resident Inspector.
"During normal power operations, the crew observed condensate/feedwater conductivity begin to increase at approximately 0530 EST on 02/10/13. The crew responded to the associated alarm response procedures and entered abnormal operating procedure 34AB-N61-001-1 due to degrading reactor water chemistry parameters. A power reduction [from 100%] was initiated at 0555 EST in accordance with station procedures for responding to a suspected condenser tube leak. At 0700 EST, a manual reactor SCRAM [from approximately 47%] was inserted due to the elevated reactor water conductivity in accordance with station abnormal operating procedures. All rods inserted completely and no complications were encountered following the reactor SCRAM, normal feedwater injection remained available. Following the SCRAM, a Group 2 Primary Containment Isolation Signal (PCIS} was received as a result of reactor water level lowering below +3 inches. The lowest reactor water level observed was [minus] 2 inches and was restored to normal operating levels utilizing normal feedwater injection. Following restoration of reactor water level to the normal operating level, the Group 2 PCIS signal was reset. No ECCS injection systems actuated as a result of the reactor SCRAM."
The SCRAM was uncomplicated and the plant is stable. Decay heat removal is to the main condenser via the turbine bypass valves. The plant is in a normal offsite electrical power shutdown alignment. Efforts are in progress to isolate the condenser in-leakage. There was no impact on Unit 2.
The licensee has notified the NRC Resident Inspector.
Power Reactor
Event Number: 48739
Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: RICHARD PROBASCO
HQ OPS Officer: BILL HUFFMAN
Region: 1 State: MA
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: RICHARD PROBASCO
HQ OPS Officer: BILL HUFFMAN
Notification Date: 02/10/2013
Notification Time: 20:20 [ET]
Event Date: 02/10/2013
Event Time: 14:05 [EST]
Last Update Date: 02/10/2013
Notification Time: 20:20 [ET]
Event Date: 02/10/2013
Event Time: 14:05 [EST]
Last Update Date: 02/10/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION 50.72(b)(3)(v)(B) - POT RHR INOP
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION 50.72(b)(3)(v)(B) - POT RHR INOP
Person (Organization):
RAY POWELL (R1DO)
RON BELLAMY (R1)
MICHELE EVANS (NRR)
RAY POWELL (R1DO)
RON BELLAMY (R1)
MICHELE EVANS (NRR)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
LOSS OF OFFSITE POWER AND SUBSEQUENT PRESS RELEASE
"On Sunday, February 10, 2013 at 1405 [EST], with the reactor at 0% core thermal power, all control rods fully inserted, and in cold shutdown conditions, the plant experienced a loss of off-site power. With Pilgrim Station aligned to off-site power via the start-up transformer (SUT), a fault on the 'B' phase of the SUT was experienced due to suspected falling ice striking the phase's insulator. This resulted in the tripping of the feeder breaker, ACB-102, and the loss of power to 4160 KV buses A1 through A4. Emergency Diesel Generators (EDGs) 'A' and 'B' auto-started as designed and are powering emergency buses.
"The loss of off-site power resulted in de-energization of both Reactor Protection System (RPS) channels resulting in a reactor scram signal and isolation of shutdown cooling. At 1418, shutdown cooling was returned to service. All other plant systems responded as designed. Station personnel are in the process of establishing back-up power in accordance with plant procedures.
"The following press release was made at 1715 hours: 'Offsite power to Pilgrim station was interrupted this afternoon. The plant is in a cold shutdown condition and Pilgrim's diesel generators are providing power to the site. There is no worker or public safety concern. Plant personnel are troubleshooting the cause of the interruption.'
"This event had no impact on the health and/or safety of the public.
"The NRC Senior Resident Inspector has been notified."
"On Sunday, February 10, 2013 at 1405 [EST], with the reactor at 0% core thermal power, all control rods fully inserted, and in cold shutdown conditions, the plant experienced a loss of off-site power. With Pilgrim Station aligned to off-site power via the start-up transformer (SUT), a fault on the 'B' phase of the SUT was experienced due to suspected falling ice striking the phase's insulator. This resulted in the tripping of the feeder breaker, ACB-102, and the loss of power to 4160 KV buses A1 through A4. Emergency Diesel Generators (EDGs) 'A' and 'B' auto-started as designed and are powering emergency buses.
"The loss of off-site power resulted in de-energization of both Reactor Protection System (RPS) channels resulting in a reactor scram signal and isolation of shutdown cooling. At 1418, shutdown cooling was returned to service. All other plant systems responded as designed. Station personnel are in the process of establishing back-up power in accordance with plant procedures.
"The following press release was made at 1715 hours: 'Offsite power to Pilgrim station was interrupted this afternoon. The plant is in a cold shutdown condition and Pilgrim's diesel generators are providing power to the site. There is no worker or public safety concern. Plant personnel are troubleshooting the cause of the interruption.'
"This event had no impact on the health and/or safety of the public.
"The NRC Senior Resident Inspector has been notified."