Event Notification Report for October 19, 2013
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
10/18/2013 - 10/19/2013
Power Reactor
Event Number: 49453
Facility: VOGTLE
Region: 2 State: GA
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DAN MONAHON
HQ OPS Officer: HOWIE CROUCH
Region: 2 State: GA
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DAN MONAHON
HQ OPS Officer: HOWIE CROUCH
Notification Date: 10/19/2013
Notification Time: 09:36 [ET]
Event Date: 10/19/2013
Event Time: 06:43 [EDT]
Last Update Date: 10/19/2013
Notification Time: 09:36 [ET]
Event Date: 10/19/2013
Event Time: 06:43 [EDT]
Last Update Date: 10/19/2013
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):
MIKE ERNSTES (R2DO)
MIKE ERNSTES (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
AUTOMATIC REACTOR TRIP DUE TO TURBINE TRIP
"VEGP [Vogtle Electric Generating Plant] unit two was at 100% power, normal activities, when the unit two turbine tripped causing an automatic reactor trip. All control rods fully inserted and nothing unusual was noted. Auxiliary feed water and feedwater isolation actuated as expected. The unit is currently stable in Mode 3 at normal operating temperature and pressure. A forced outage response team has been formed to determine the cause of the turbine trip and determine restart criteria and time of restart."
During the transient, no relief valves lifted. The electrical grid is stable and supplying plant safety loads. Decay heat is being removed via steam dumps to the condenser.
The licensee has notified the NRC Resident Inspector.
"VEGP [Vogtle Electric Generating Plant] unit two was at 100% power, normal activities, when the unit two turbine tripped causing an automatic reactor trip. All control rods fully inserted and nothing unusual was noted. Auxiliary feed water and feedwater isolation actuated as expected. The unit is currently stable in Mode 3 at normal operating temperature and pressure. A forced outage response team has been formed to determine the cause of the turbine trip and determine restart criteria and time of restart."
During the transient, no relief valves lifted. The electrical grid is stable and supplying plant safety loads. Decay heat is being removed via steam dumps to the condenser.
The licensee has notified the NRC Resident Inspector.
Power Reactor
Event Number: 49454
Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: KEN GOODALL
HQ OPS Officer: CHARLES TEAL
Region: 1 State: MA
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: KEN GOODALL
HQ OPS Officer: CHARLES TEAL
Notification Date: 10/19/2013
Notification Time: 09:57 [ET]
Event Date: 10/19/2013
Event Time: 03:31 [EDT]
Last Update Date: 10/19/2013
Notification Time: 09:57 [ET]
Event Date: 10/19/2013
Event Time: 03:31 [EDT]
Last Update Date: 10/19/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
PAUL KROHN (R1DO)
PAUL KROHN (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 1 | Startup | 0 | Hot Shutdown |
GROUP 1 ISOLATION DUE TO HIGH REACTOR WATER LEVEL
"On Saturday, October 19, 2013 at 0331 hours, with the reactor critical at approximately 1% core thermal power and the mode switch in start-up, a high reactor water level condition resulted in a main turbine trip and a valid Group 1 isolation signal. As a result, the Main Steam Isolation Valves (MSIVs) closed.
"The plant was in start-up from a forced outage. The initial plant conditions were reactor pressure at approximately 280 psig with a corresponding reactor coolant temperature for that pressure. Currently reactor pressure and water level are being maintained with the MSIVs closed in normal bands. The reactor is being cooled down in preparation for operation in shutdown cooling. Off-site power is supplying station power from the Start-up Transformer (normal power supply for shutdown operations). All plant systems responded as designed.
"The cause of the increase in reactor water level is currently under investigation.
"This event had no impact on the health and/or safety of the public.
"The USNRC Senior Resident Inspector has been notified."
"On Saturday, October 19, 2013 at 0331 hours, with the reactor critical at approximately 1% core thermal power and the mode switch in start-up, a high reactor water level condition resulted in a main turbine trip and a valid Group 1 isolation signal. As a result, the Main Steam Isolation Valves (MSIVs) closed.
"The plant was in start-up from a forced outage. The initial plant conditions were reactor pressure at approximately 280 psig with a corresponding reactor coolant temperature for that pressure. Currently reactor pressure and water level are being maintained with the MSIVs closed in normal bands. The reactor is being cooled down in preparation for operation in shutdown cooling. Off-site power is supplying station power from the Start-up Transformer (normal power supply for shutdown operations). All plant systems responded as designed.
"The cause of the increase in reactor water level is currently under investigation.
"This event had no impact on the health and/or safety of the public.
"The USNRC Senior Resident Inspector has been notified."
Power Reactor
Event Number: 49455
Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [1] [2] [3]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: MARK MOEBES
HQ OPS Officer: DONG HWA PARK
Region: 2 State: AL
Unit: [1] [2] [3]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: MARK MOEBES
HQ OPS Officer: DONG HWA PARK
Notification Date: 10/19/2013
Notification Time: 23:00 [ET]
Event Date: 10/19/2013
Event Time: 17:05 [CDT]
Last Update Date: 10/19/2013
Notification Time: 23:00 [ET]
Event Date: 10/19/2013
Event Time: 17:05 [CDT]
Last Update Date: 10/19/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
STEVEN RUDISAIL (R2DO)
STEVEN RUDISAIL (R2DO)
| 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 |
| 3 | N | Y | 100 | Power Operation | 100 | Power Operation |
PARTIAL LOSS OF OFFSITE COMMUNICATIONS DUE TO A BLOWN FUSE
"On 10/19/2013 at 1705 CDT, Browns Ferry Nuclear Plant (BFN) experienced a partial loss of offsite communications, which included the NRC Emergency Notification System, the Emergency Plan Paging System and normal phone communication to offsite. Main control room indications and assessment capability were not affected. The Nextel cellular phone system and the satellite phones in the control rooms were unaffected. The plant radio system was also unaffected. The Emergency Response Data System is currently out of service due to planned maintenance on the associated offsite power supply. Operation of BFN Unit 1, Unit 2, and Unit 3 was not affected by the event.
"The BFN facilities personnel found a blown fuse in one of the temporary Diesel Generators (DGs) supplying the node associated with the outside phone communications. The fuse was replaced and the DG has been in-service with no issues. Normal communications and access have been restored.
"The NRC Senior Resident Inspector has been notified.
"This event is reportable under 10CFR50.72(b)(3)(xiii), 'Any event that results in a major loss of emergency assessment capability, offsite response capability, or offsite communications capability' (e.g., significant portion of control room indication, emergency notification system, or offsite notification system)."
"On 10/19/2013 at 1705 CDT, Browns Ferry Nuclear Plant (BFN) experienced a partial loss of offsite communications, which included the NRC Emergency Notification System, the Emergency Plan Paging System and normal phone communication to offsite. Main control room indications and assessment capability were not affected. The Nextel cellular phone system and the satellite phones in the control rooms were unaffected. The plant radio system was also unaffected. The Emergency Response Data System is currently out of service due to planned maintenance on the associated offsite power supply. Operation of BFN Unit 1, Unit 2, and Unit 3 was not affected by the event.
"The BFN facilities personnel found a blown fuse in one of the temporary Diesel Generators (DGs) supplying the node associated with the outside phone communications. The fuse was replaced and the DG has been in-service with no issues. Normal communications and access have been restored.
"The NRC Senior Resident Inspector has been notified.
"This event is reportable under 10CFR50.72(b)(3)(xiii), 'Any event that results in a major loss of emergency assessment capability, offsite response capability, or offsite communications capability' (e.g., significant portion of control room indication, emergency notification system, or offsite notification system)."
Power Reactor
Event Number: 49456
Facility: SURRY
Region: 2 State: VA
Unit: [1] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: JONATHAN FORD
HQ OPS Officer: HOWIE CROUCH
Region: 2 State: VA
Unit: [1] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: JONATHAN FORD
HQ OPS Officer: HOWIE CROUCH
Notification Date: 10/20/2013
Notification Time: 11:07 [ET]
Event Date: 10/19/2013
Event Time: 23:20 [EDT]
Last Update Date: 10/20/2013
Notification Time: 11:07 [ET]
Event Date: 10/19/2013
Event Time: 23:20 [EDT]
Last Update Date: 10/20/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
STEVEN RUDISAIL (R2DO)
STEVEN RUDISAIL (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 90 | Power Operation | 90 | Power Operation |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
LICENSED OPERATOR TESTED POSITIVE FOR ALCOHOL ON A FOR-CAUSE FITNESS FOR DUTY TEST
A licensed operator had a confirmed positive for alcohol during a for-cause fitness for duty test. The employee's access to the plant has been placed on hold.
The licensee has notified the NRC Resident Inspector.
A licensed operator had a confirmed positive for alcohol during a for-cause fitness for duty test. The employee's access to the plant has been placed on hold.
The licensee has notified the NRC Resident Inspector.
Power Reactor
Event Number: 49457
Facility: CATAWBA
Region: 2 State: SC
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: RODGER ELLINGWOOD
HQ OPS Officer: DONALD NORWOOD
Region: 2 State: SC
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: RODGER ELLINGWOOD
HQ OPS Officer: DONALD NORWOOD
Notification Date: 10/21/2013
Notification Time: 15:02 [ET]
Event Date: 10/19/2013
Event Time: 23:30 [EDT]
Last Update Date: 10/21/2013
Notification Time: 15:02 [ET]
Event Date: 10/19/2013
Event Time: 23:30 [EDT]
Last Update Date: 10/21/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
MIKE ERNSTES (R2DO)
MIKE ERNSTES (R2DO)
| 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 | 19 | Power Operation | 19 | Power Operation |
OFFSITE NOTIFICATION DUE TO SPILL OF WATER CONTAINING LOW-LEVEL TRITIUM CONCENTRATION
"A spill of greater than 100 gallons of water, containing a low-level tritium concentration with the potential to reach groundwater has occurred on the Catawba site. The tritium levels in this water were 8,314 picocuries per liter, less than one-half of the US Environmental Protection Agency drinking water standard for tritium of 20,000 picocuries per liter.
"While conducting planned Unit 2 maintenance activities, water from the main condenser was being pumped to a site collection pond and overflowed due to exceeding capacity. The source of the spill was stopped. Based upon the on-site spill location and low tritium levels, there is no health or safety risk to the public or employees.
"In accordance with the industry voluntary Groundwater Protection Initiative, the NRC Resident Inspector, states, and counties will be notified."
"A spill of greater than 100 gallons of water, containing a low-level tritium concentration with the potential to reach groundwater has occurred on the Catawba site. The tritium levels in this water were 8,314 picocuries per liter, less than one-half of the US Environmental Protection Agency drinking water standard for tritium of 20,000 picocuries per liter.
"While conducting planned Unit 2 maintenance activities, water from the main condenser was being pumped to a site collection pond and overflowed due to exceeding capacity. The source of the spill was stopped. Based upon the on-site spill location and low tritium levels, there is no health or safety risk to the public or employees.
"In accordance with the industry voluntary Groundwater Protection Initiative, the NRC Resident Inspector, states, and counties will be notified."