Event Notification Report for September 16, 2015
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
09/15/2015 - 09/16/2015
EVENT NUMBERS
51400514015140251403514045139751398
Agreement State
Event Number: 51400
Rep Org: FLORIDA BUREAU OF RADIATION CONTROL
Licensee: GEORGIA PACIFIC CORPORATION
Region: 1
City: PALATKA State: FL
County:
License #: 1391-1
Agreement: Y
Docket:
NRC Notified By: KELLIE ANDERSON
HQ OPS Officer: JEFF ROTTON
Licensee: GEORGIA PACIFIC CORPORATION
Region: 1
City: PALATKA State: FL
County:
License #: 1391-1
Agreement: Y
Docket:
NRC Notified By: KELLIE ANDERSON
HQ OPS Officer: JEFF ROTTON
Notification Date: 09/16/2015
Notification Time: 14:34 [ET]
Event Date: 09/16/2015
Event Time: 00:00 [EDT]
Last Update Date: 09/16/2015
Notification Time: 14:34 [ET]
Event Date: 09/16/2015
Event Time: 00:00 [EDT]
Last Update Date: 09/16/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
SILAS KENNEDY (R1DO)
NMSS_EVENTS_NOTIFIC (EMAI)
SILAS KENNEDY (R1DO)
NMSS_EVENTS_NOTIFIC (EMAI)
FLORIDA AGREEMENT STATE REPORT - FIXED NUCLEAR GAUGE WITH STUCK OPEN SHUTTER
The following information was received from the State of Florida via email:
"The RSO [Radiation Safety Officer] at Georgia Pacific Corporation in Palatka, Florida called to report [to the State of Florida that] a fixed Cesium-137 source installed on the top half of a tank has the shutter stuck open. Device originally had 2,000 mCi, but now is estimated to have 892 mCi of Cs-137. This same equipment was reported with the same defect on April 9, 2015 (FL15-025). There is no report of any over exposure of personnel and no leaks (confirmed by leak test). The location of the device prohibits the access of personnel and the shutter is only closed when maintenance or repair is performed. The RSO has put in a work order for repair and will provide a copy of a report confirming the equipment was serviced/repaired back in April. Initial NRC Event Notification #50971."
The fixed gauge manufacturer is Kay-Ray, Model number - 7063P, serial number 10682F.
FL Incident Number: FL 15-094
The following information was received from the State of Florida via email:
"The RSO [Radiation Safety Officer] at Georgia Pacific Corporation in Palatka, Florida called to report [to the State of Florida that] a fixed Cesium-137 source installed on the top half of a tank has the shutter stuck open. Device originally had 2,000 mCi, but now is estimated to have 892 mCi of Cs-137. This same equipment was reported with the same defect on April 9, 2015 (FL15-025). There is no report of any over exposure of personnel and no leaks (confirmed by leak test). The location of the device prohibits the access of personnel and the shutter is only closed when maintenance or repair is performed. The RSO has put in a work order for repair and will provide a copy of a report confirming the equipment was serviced/repaired back in April. Initial NRC Event Notification #50971."
The fixed gauge manufacturer is Kay-Ray, Model number - 7063P, serial number 10682F.
FL Incident Number: FL 15-094
Power Reactor
Event Number: 51401
Facility: BYRON
Region: 3 State: IL
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: SHANE HARVEY
HQ OPS Officer: JEFF ROTTON
Region: 3 State: IL
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: SHANE HARVEY
HQ OPS Officer: JEFF ROTTON
Notification Date: 09/16/2015
Notification Time: 21:17 [ET]
Event Date: 09/16/2015
Event Time: 22:00 [CDT]
Last Update Date: 09/16/2015
Notification Time: 21:17 [ET]
Event Date: 09/16/2015
Event Time: 22:00 [CDT]
Last Update Date: 09/16/2015
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):
KENNETH RIEMER (R3DO)
KENNETH RIEMER (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
LOSS OF SEISMIC MONITORING INSTRUMENTATION DURING PLANNED MAINTENANCE
"At 2200 CDT on September 16, 2015, Byron Station's Seismic Instrumentation will be removed from service to support an electrical bus outage. During this time, the seismic instrumentation will not be able to generate Main Control Room annunciation or provide ground acceleration information necessary for Emergency Action Level (EAL) threshold determination until the seismic instrumentation is restored, which is scheduled for 1700 CDT on September 19, 2015. Since the duration of maintenance activity may last greater than 72 hours, with viable compensatory measures in place and communicated to applicable Emergency Response Decision Makers, this condition will result in a Loss of Emergency Assessment Capability while the Seismic Instrumentation is out of service and results in a reportable condition in accordance with 10 CFR 50.72(b)(xiii).
"The Licensee has notified the NRC Resident Inspector and informed the State of Illinois Resident Engineer ."
"At 2200 CDT on September 16, 2015, Byron Station's Seismic Instrumentation will be removed from service to support an electrical bus outage. During this time, the seismic instrumentation will not be able to generate Main Control Room annunciation or provide ground acceleration information necessary for Emergency Action Level (EAL) threshold determination until the seismic instrumentation is restored, which is scheduled for 1700 CDT on September 19, 2015. Since the duration of maintenance activity may last greater than 72 hours, with viable compensatory measures in place and communicated to applicable Emergency Response Decision Makers, this condition will result in a Loss of Emergency Assessment Capability while the Seismic Instrumentation is out of service and results in a reportable condition in accordance with 10 CFR 50.72(b)(xiii).
"The Licensee has notified the NRC Resident Inspector and informed the State of Illinois Resident Engineer ."
Power Reactor
Event Number: 51402
Facility: SURRY
Region: 2 State: VA
Unit: [] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: GEOFFREY HILL
HQ OPS Officer: HOWIE CROUCH
Region: 2 State: VA
Unit: [] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: GEOFFREY HILL
HQ OPS Officer: HOWIE CROUCH
Notification Date: 09/17/2015
Notification Time: 00:36 [ET]
Event Date: 09/16/2015
Event Time: 20:14 [EDT]
Last Update Date: 09/17/2015
Notification Time: 00:36 [ET]
Event Date: 09/16/2015
Event Time: 20:14 [EDT]
Last Update Date: 09/17/2015
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):
BINOY DESAI (R2DO)
BINOY DESAI (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
AUTOMATIC START AND LOADING OF THE #2 EMERGENCY DIESEL GENERATOR
"While performing degraded voltage/under voltage Instrumentation & Control testing with both Units at 100%, the Unit 2 'H' Emergency Bus was lost when an inadvertent under voltage matrix was satisfied. The #2 Emergency Diesel Generator auto-started and assumed the 2H Emergency Bus as designed. The cause of the under voltage matrix coincidence is currently being investigated by station personnel. All testing activities have been terminated and recovery efforts are in progress in accordance with station procedures. Current status is both Units stable at 100% with the #2 Emergency Diesel Generator carrying the 2H Emergency Bus."
The loss of the bus places the Unit in a 7-day action statement for the loss of offsite power to the 2H bus and a 14-day action statement for the auxiliary feed cross tie to Unit 1.
The licensee has notified the NRC Resident Inspector.
"While performing degraded voltage/under voltage Instrumentation & Control testing with both Units at 100%, the Unit 2 'H' Emergency Bus was lost when an inadvertent under voltage matrix was satisfied. The #2 Emergency Diesel Generator auto-started and assumed the 2H Emergency Bus as designed. The cause of the under voltage matrix coincidence is currently being investigated by station personnel. All testing activities have been terminated and recovery efforts are in progress in accordance with station procedures. Current status is both Units stable at 100% with the #2 Emergency Diesel Generator carrying the 2H Emergency Bus."
The loss of the bus places the Unit in a 7-day action statement for the loss of offsite power to the 2H bus and a 14-day action statement for the auxiliary feed cross tie to Unit 1.
The licensee has notified the NRC Resident Inspector.
Power Reactor
Event Number: 51403
Facility: PALO VERDE
Region: 4 State: AZ
Unit: [] [2] []
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: ROBERT PIERCE
HQ OPS Officer: JEFF HERRERA
Region: 4 State: AZ
Unit: [] [2] []
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: ROBERT PIERCE
HQ OPS Officer: JEFF HERRERA
Notification Date: 09/17/2015
Notification Time: 02:53 [ET]
Event Date: 09/16/2015
Event Time: 23:01 [MST]
Last Update Date: 09/17/2015
Notification Time: 02:53 [ET]
Event Date: 09/16/2015
Event Time: 23:01 [MST]
Last Update Date: 09/17/2015
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
THOMAS FARNHOLTZ (R4DO)
WILLIAM GOTT (IRD)
MARC DAPAS (RA)
SCOTT MORRIS (NRR)
WILLIAM DEAN (NRR)
THOMAS FARNHOLTZ (R4DO)
WILLIAM GOTT (IRD)
MARC DAPAS (RA)
SCOTT MORRIS (NRR)
WILLIAM DEAN (NRR)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
NOTIFICATION OF UNUSUAL EVENT DUE TO RAPID COMBUSTION OF A LOAD CENTER BREAKER
"The following event description is based on information currently available. If through subsequent reviews of this event, additional information is identified that is pertinent to this event, or alters the information being provided at this time a follow-up notification will be made via the ENS or under the reporting requirements of 10CFR50.73.
"Non Class Load Center Breaker, 2ENGN-L04 failed, resulting an a visible observation of rapid combustion and resultant charring (burned area) of the breaker enclosure and housing. No physical deformation to the breaker housing or surrounding area has been identified. The rapid combustion self-extinguished immediately following the audible and visible combustion event. As a result, an Emergency Classification of HU2.2, EXPLOSION was declared due to the Load Center breaker failure and noise and visible indication observed in the field.
"The plant was, and continues to operate at 100% full power operations on normal power alignment. The 2ENGN-L04 Non-Class Load Center breaker supplies power to non-essential service loads and has no immediate impact to plant operation or safety mitigating systems. The plant remains stable and the event did not adversely affect the safe operation of the plant or health and safety of the public.
"The NRC Resident Inspector has been notified."
Notified DHS SWO, DHS NICC, FEMA, and Nuclear SSA via email.
* * * UPDATE FROM ROBERT PIERCE TO HOWIE CROUCH AT 0702 EDT ON 9/17/15 * * *
"PVNGS Unit 2 terminated the Unusual Event HU2.2 on 9/17/15 at 04:04 MST. Non-Class load center 2ENGN-L04 has been isolated and de-energized. There was no reflash or fire at the breaker and no hazard to plant personnel exists. Damage appears to be limited to the NGN-L04D3 breaker cubicle and a spare breaker cubicle below NGN-L04D3. There was no damage to any safety related equipment."
The licensee will be notifying the state of Arizona, Maricopa County authorities and the NRC Resident Inspector. Notified R4DO (Farnholtz), NRR EO (Morris), IRD MOC (Gott), DHS SWO, FEMA Ops, DHS NICC and NuclearSSA (email).
"The following event description is based on information currently available. If through subsequent reviews of this event, additional information is identified that is pertinent to this event, or alters the information being provided at this time a follow-up notification will be made via the ENS or under the reporting requirements of 10CFR50.73.
"Non Class Load Center Breaker, 2ENGN-L04 failed, resulting an a visible observation of rapid combustion and resultant charring (burned area) of the breaker enclosure and housing. No physical deformation to the breaker housing or surrounding area has been identified. The rapid combustion self-extinguished immediately following the audible and visible combustion event. As a result, an Emergency Classification of HU2.2, EXPLOSION was declared due to the Load Center breaker failure and noise and visible indication observed in the field.
"The plant was, and continues to operate at 100% full power operations on normal power alignment. The 2ENGN-L04 Non-Class Load Center breaker supplies power to non-essential service loads and has no immediate impact to plant operation or safety mitigating systems. The plant remains stable and the event did not adversely affect the safe operation of the plant or health and safety of the public.
"The NRC Resident Inspector has been notified."
Notified DHS SWO, DHS NICC, FEMA, and Nuclear SSA via email.
* * * UPDATE FROM ROBERT PIERCE TO HOWIE CROUCH AT 0702 EDT ON 9/17/15 * * *
"PVNGS Unit 2 terminated the Unusual Event HU2.2 on 9/17/15 at 04:04 MST. Non-Class load center 2ENGN-L04 has been isolated and de-energized. There was no reflash or fire at the breaker and no hazard to plant personnel exists. Damage appears to be limited to the NGN-L04D3 breaker cubicle and a spare breaker cubicle below NGN-L04D3. There was no damage to any safety related equipment."
The licensee will be notifying the state of Arizona, Maricopa County authorities and the NRC Resident Inspector. Notified R4DO (Farnholtz), NRR EO (Morris), IRD MOC (Gott), DHS SWO, FEMA Ops, DHS NICC and NuclearSSA (email).
Non-Agreement State
Event Number: 51404
Rep Org: JANX
Licensee: JANX
Region: 3
City: PARMA State: MI
County:
License #: 21-16560-01
Agreement: N
Docket:
NRC Notified By: WILLIAM REEVE
HQ OPS Officer: HOWIE CROUCH
Licensee: JANX
Region: 3
City: PARMA State: MI
County:
License #: 21-16560-01
Agreement: N
Docket:
NRC Notified By: WILLIAM REEVE
HQ OPS Officer: HOWIE CROUCH
Notification Date: 09/17/2015
Notification Time: 11:36 [ET]
Event Date: 09/16/2015
Event Time: 12:15 [EDT]
Last Update Date: 09/17/2015
Notification Time: 11:36 [ET]
Event Date: 09/16/2015
Event Time: 12:15 [EDT]
Last Update Date: 09/17/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
Person (Organization):
KENNETH RIEMER (R3DO)
SILAS KENNEDY (R1DO)
NMSS_EVENTS_NOTIFICA (EMAI)
KENNETH RIEMER (R3DO)
SILAS KENNEDY (R1DO)
NMSS_EVENTS_NOTIFICA (EMAI)
RADIOGRAPHY CAMERA SOURCE DISCONNECT
While the licensee was performing radiography work in Twilight, West Virginia, a radiography camera (SPEC-150; Ir-192; 72 Ci; S/N: WH0603) source became disconnected and did not return to the shielded position. The West Virginia site called the corporate RSO at 0200 on 9/17/2015, who then called a qualified Pennsylvania RSO in order to supervise source retraction. The qualified RSO verified boundaries at the 2mR level. The source was retrieved and placed in the shielded position. The camera was secured and is out of service. There was no indication of excessive dose.
While the licensee was performing radiography work in Twilight, West Virginia, a radiography camera (SPEC-150; Ir-192; 72 Ci; S/N: WH0603) source became disconnected and did not return to the shielded position. The West Virginia site called the corporate RSO at 0200 on 9/17/2015, who then called a qualified Pennsylvania RSO in order to supervise source retraction. The qualified RSO verified boundaries at the 2mR level. The source was retrieved and placed in the shielded position. The camera was secured and is out of service. There was no indication of excessive dose.
Power Reactor
Event Number: 51397
Facility: PALISADES
Region: 3 State: MI
Unit: [1] [] []
RX Type: [1] CE
NRC Notified By: KRIS RUETZ
HQ OPS Officer: HOWIE CROUCH
Region: 3 State: MI
Unit: [1] [] []
RX Type: [1] CE
NRC Notified By: KRIS RUETZ
HQ OPS Officer: HOWIE CROUCH
Notification Date: 09/16/2015
Notification Time: 03:59 [ET]
Event Date: 09/16/2015
Event Time: 01:17 [EDT]
Last Update Date: 09/16/2015
Notification Time: 03:59 [ET]
Event Date: 09/16/2015
Event Time: 01:17 [EDT]
Last Update Date: 09/16/2015
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):
KENNETH RIEMER (R3DO)
KENNETH RIEMER (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 85 | Power Operation | 0 | Hot Standby |
AUTOMATIC REACTOR TRIP DUE TO TURBINE TRIP
"At 0117 [EDT] on 9/16/2015 a reactor trip occurred (4-hr non-emergency). The plant was at approximately 85% power performing a coastdown in preparation for a refueling outage when a Digital Electro-Hydraulic (DEH) alarm was received in the control room. Shortly following receipt of the alarm the turbine tripped. This resulted in an RPS actuation and a reactor trip on Loss of Load. The crew entered EOP-1 Standard Post Trip Actions and completed all required actions. The crew subsequently entered EOP-2 Reactor Trip Recovery.
"All full-length control rods inserted fully. Auxiliary Feedwater System actuated in response to low steam generator water levels (8-hr non-emergency). Steam generator water levels are in progress of being returned to normal operating levels. No known primary to secondary leakage. Atmospheric Steam Dump Valves lifted after the trip and subsequently reseated.
"The plant is currently stable in Mode 3 at NOP/NOT being maintained by the Turbine Bypass Valve.
"Initial investigation into the cause of the turbine trip appears to be from a DEH power supply failure.
"The NRC Resident Inspector was notified of the reactor trip at 0139 on 9/16/2015."
"At 0117 [EDT] on 9/16/2015 a reactor trip occurred (4-hr non-emergency). The plant was at approximately 85% power performing a coastdown in preparation for a refueling outage when a Digital Electro-Hydraulic (DEH) alarm was received in the control room. Shortly following receipt of the alarm the turbine tripped. This resulted in an RPS actuation and a reactor trip on Loss of Load. The crew entered EOP-1 Standard Post Trip Actions and completed all required actions. The crew subsequently entered EOP-2 Reactor Trip Recovery.
"All full-length control rods inserted fully. Auxiliary Feedwater System actuated in response to low steam generator water levels (8-hr non-emergency). Steam generator water levels are in progress of being returned to normal operating levels. No known primary to secondary leakage. Atmospheric Steam Dump Valves lifted after the trip and subsequently reseated.
"The plant is currently stable in Mode 3 at NOP/NOT being maintained by the Turbine Bypass Valve.
"Initial investigation into the cause of the turbine trip appears to be from a DEH power supply failure.
"The NRC Resident Inspector was notified of the reactor trip at 0139 on 9/16/2015."
Power Reactor
Event Number: 51398
Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: TODD CHRISTENSEN
HQ OPS Officer: HOWIE CROUCH
Region: 2 State: AL
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: TODD CHRISTENSEN
HQ OPS Officer: HOWIE CROUCH
Notification Date: 09/16/2015
Notification Time: 10:10 [ET]
Event Date: 09/16/2015
Event Time: 02:00 [CDT]
Last Update Date: 09/16/2015
Notification Time: 10:10 [ET]
Event Date: 09/16/2015
Event Time: 02:00 [CDT]
Last Update Date: 09/16/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
BINOY DESAI (R2DO)
BINOY DESAI (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
HIGH PRESSURE COOLANT INJECTION SYSTEM DECLARED INOPERABLE DUE TO VALVE STEM PACKING STEAM LEAK
"At 0200 CDT on 9/16/2015, the High Pressure Coolant Injection (HPCI) System was manually isolated to stop a steam leak from the stem packing of the HPCI Steam Supply Valve 2-FCV-073-0016. The leak occurred following performance of 2-SR-3.6.1.3.5 (HPCI) HPCI System Motor Operated Valve Operability, which cycled 2-FCV-073-0016. No Area Radiation Monitoring (ARM) or PCIS Area High Temperature alarms were received and no automatic isolation setpoints were reached. HPCI was declared inoperable per Technical Specification (TS) Limiting Condition for Operation (LCO) 3.5.1 Emergency Core Cooling Systems (ECCS)- Operating, Condition C.
"This constitutes an unplanned HPCI system inoperability and requires an 8-hour ENS notification in accordance with 10 CFR 50.72(b)(3)(v)(D), due to the failure of a single train system affecting accident mitigation, and a 60-day written report in accordance with 10 CFR 50.73(a)(2)(v)(D).
"The NRC resident inspector has been notified."
"At 0200 CDT on 9/16/2015, the High Pressure Coolant Injection (HPCI) System was manually isolated to stop a steam leak from the stem packing of the HPCI Steam Supply Valve 2-FCV-073-0016. The leak occurred following performance of 2-SR-3.6.1.3.5 (HPCI) HPCI System Motor Operated Valve Operability, which cycled 2-FCV-073-0016. No Area Radiation Monitoring (ARM) or PCIS Area High Temperature alarms were received and no automatic isolation setpoints were reached. HPCI was declared inoperable per Technical Specification (TS) Limiting Condition for Operation (LCO) 3.5.1 Emergency Core Cooling Systems (ECCS)- Operating, Condition C.
"This constitutes an unplanned HPCI system inoperability and requires an 8-hour ENS notification in accordance with 10 CFR 50.72(b)(3)(v)(D), due to the failure of a single train system affecting accident mitigation, and a 60-day written report in accordance with 10 CFR 50.73(a)(2)(v)(D).
"The NRC resident inspector has been notified."