Event Notification Report for August 17, 2016
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
08/16/2016 - 08/17/2016
Fuel Cycle Facility
Event Number: 52190
Facility: NUCLEAR FUEL SERVICES INC.
Region: 2 State: TN
Unit: [] [] []
RX Type: URANIUM FUEL FABRICATION
Comments: HEU CONVERSION & SCRAP RECOVERY
NAVAL REACTOR FUEL CYCLE
LEU SCRAP RECOVERY
NRC Notified By: RANDY SHACKELFORD
HQ OPS Officer: MARK ABRAMOVITZ
Region: 2 State: TN
Unit: [] [] []
RX Type: URANIUM FUEL FABRICATION
Comments: HEU CONVERSION & SCRAP RECOVERY
NAVAL REACTOR FUEL CYCLE
LEU SCRAP RECOVERY
NRC Notified By: RANDY SHACKELFORD
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 08/18/2016
Notification Time: 16:32 [ET]
Event Date: 08/17/2016
Event Time: 17:39 [EDT]
Last Update Date: 08/18/2016
Notification Time: 16:32 [ET]
Event Date: 08/17/2016
Event Time: 17:39 [EDT]
Last Update Date: 08/18/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
70.50(b)(2) - SAFETY EQUIPMENT FAILURE
10 CFR Section:
70.50(b)(2) - SAFETY EQUIPMENT FAILURE
Person (Organization):
SHANE SANDAL (R2DO)
NMSS_EVENTS_NOTIFIC (EMAI)
FUELS GROUP (EMAI)
SHANE SANDAL (R2DO)
NMSS_EVENTS_NOTIFIC (EMAI)
FUELS GROUP (EMAI)
FAILURE OF A SPEAKER IN AN AREA POTENTIALLY REQUIRING PERSONNEL EVACUATION
"On August 17, 2016 at approximately 1739 hours (EDT), one speaker in Building 120 was identified as non-operational while performing a functional test of the system. This speaker is designed to annunciate alarms generated from the Criticality Accident Alarm System (CAAS) required by 10CFR70.24, alarms generated from the Fire Alarm Control Panel, and Public Address System announcements. Additional functional testing identified that no redundant speaker could adequately provide speaker coverage for all affected areas of this building. Special Nuclear Materials are not processed, handled, or stored within the area where the speaker failed; however, this area requires evacuation in the unlikely event of a nuclear criticality accident as described in the NFS Emergency Plan. There were no actual radiological or other nuclear safety consequences. The potential consequence was that in the event of a nuclear criticality accident, evacuation could have been delayed for those personnel within Building 120 with a resultant increase of postulated doses. A series of compensatory actions were taken to restore compliance including installation of a temporary speaker and limiting equipment operation to limit background noise. On August 18, 2016, at approximately 1100 hours (EDT), full compliance was restored as demonstrated by successfully performing a speaker test in the affected area.
"The licensee notified the NRC Resident Inspector on August 18, 2016."
"On August 17, 2016 at approximately 1739 hours (EDT), one speaker in Building 120 was identified as non-operational while performing a functional test of the system. This speaker is designed to annunciate alarms generated from the Criticality Accident Alarm System (CAAS) required by 10CFR70.24, alarms generated from the Fire Alarm Control Panel, and Public Address System announcements. Additional functional testing identified that no redundant speaker could adequately provide speaker coverage for all affected areas of this building. Special Nuclear Materials are not processed, handled, or stored within the area where the speaker failed; however, this area requires evacuation in the unlikely event of a nuclear criticality accident as described in the NFS Emergency Plan. There were no actual radiological or other nuclear safety consequences. The potential consequence was that in the event of a nuclear criticality accident, evacuation could have been delayed for those personnel within Building 120 with a resultant increase of postulated doses. A series of compensatory actions were taken to restore compliance including installation of a temporary speaker and limiting equipment operation to limit background noise. On August 18, 2016, at approximately 1100 hours (EDT), full compliance was restored as demonstrated by successfully performing a speaker test in the affected area.
"The licensee notified the NRC Resident Inspector on August 18, 2016."
Power Reactor
Event Number: 52187
Facility: SEQUOYAH
Region: 2 State: TN
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ROBERT URBANSKI
HQ OPS Officer: VINCE KLCO
Region: 2 State: TN
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ROBERT URBANSKI
HQ OPS Officer: VINCE KLCO
Notification Date: 08/17/2016
Notification Time: 17:46 [ET]
Event Date: 08/17/2016
Event Time: 17:22 [EDT]
Last Update Date: 08/17/2016
Notification Time: 17:46 [ET]
Event Date: 08/17/2016
Event Time: 17:22 [EDT]
Last Update Date: 08/17/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
SHANE SANDAL (R2DO)
SHANE SANDAL (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 |
UNANALYZED CONDITION DUE TO NOT MEETING SINGLE FAILURE CRITERIA
"At 1722 [EDT] on 8/17/16, a Past Operability Evaluation (POE) determined the configuration of the Emergency Gas Treatment System (EGTS) flow controllers that existed prior to 0420 on 8/6/16 constituted an Unanalyzed Condition due to not meeting single failure criteria. This POE examined the condition where EGTS may auto-swap from the flow control path in A-Auto to the Standby flow control path upon the start of a Design Basis Event (DBE). The intended design of the EGTS swap over flow control path in Auto to Standby was to detect and respond to an actual failure of the A-Auto flow control path. The unnecessary auto-swap to Standby could prevent the EGTS train configured in Auto from performing its required safety function during a DBE. The POE performed a detailed calculation to determine the release effects due to the failure of the redundant trains of EGTS controllers. These calculations concluded that failure of both trains of EGTS controllers would not result in exceeding the 10CFR100 limits, however this condition was unanalyzed and failed to meet single failure criteria.
"This condition is reportable under 10CFR50.72(b)(3)(ii)(B), Unanalyzed Condition due to a system required to meet the single failure criterion does not do so.
"This condition had no impact to the health and safety of the public.
"The NRC Resident Inspector has been notified."
"At 1722 [EDT] on 8/17/16, a Past Operability Evaluation (POE) determined the configuration of the Emergency Gas Treatment System (EGTS) flow controllers that existed prior to 0420 on 8/6/16 constituted an Unanalyzed Condition due to not meeting single failure criteria. This POE examined the condition where EGTS may auto-swap from the flow control path in A-Auto to the Standby flow control path upon the start of a Design Basis Event (DBE). The intended design of the EGTS swap over flow control path in Auto to Standby was to detect and respond to an actual failure of the A-Auto flow control path. The unnecessary auto-swap to Standby could prevent the EGTS train configured in Auto from performing its required safety function during a DBE. The POE performed a detailed calculation to determine the release effects due to the failure of the redundant trains of EGTS controllers. These calculations concluded that failure of both trains of EGTS controllers would not result in exceeding the 10CFR100 limits, however this condition was unanalyzed and failed to meet single failure criteria.
"This condition is reportable under 10CFR50.72(b)(3)(ii)(B), Unanalyzed Condition due to a system required to meet the single failure criterion does not do so.
"This condition had no impact to the health and safety of the public.
"The NRC Resident Inspector has been notified."
Power Reactor
Event Number: 52188
Facility: FORT CALHOUN
Region: 4 State: NE
Unit: [1] [] []
RX Type: (1) CE
NRC Notified By: CHARLES SMITH
HQ OPS Officer: VINCE KLCO
Region: 4 State: NE
Unit: [1] [] []
RX Type: (1) CE
NRC Notified By: CHARLES SMITH
HQ OPS Officer: VINCE KLCO
Notification Date: 08/17/2016
Notification Time: 21:30 [ET]
Event Date: 08/17/2016
Event Time: 18:26 [CDT]
Last Update Date: 08/17/2016
Notification Time: 21:30 [ET]
Event Date: 08/17/2016
Event Time: 18:26 [CDT]
Last Update Date: 08/17/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
DAVID PROULX (R4DO)
DAVID PROULX (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 |
OFFSITE POWER SOURCE BELOW THE OPERABILITY LIMIT
"At 1826 [CDT], Operators identified that off-site 161 kV power source predicted post-trip voltage was below the operability limit of 161.3 kV. [Operators] entered AOP-31, 161 kV Grid Malfunctions, Section 1, 161 kV Grid Instability, and declared House Service Transformers T1A-3 and T1A-4 inoperable. [Operators] entered Technical Specification 2.7(2)c. Per Technical Specification 2.7(2)c, 'Both house service transformers T1A-3 and T1A-4 (4.16kV) may be inoperable for up to 72 hours. The loss of the 161kV incoming line renders both transformers inoperable. The NRC Operations Center shall be notified by telephone within 4 hours after inoperability of both transformers.'
"Per OPPD [Omaha Public Power District] Transmission, grid conditions are currently stable. OPPD Transmission has successfully raised predicted post-trip 161 kV voltage with all predicted voltages meeting or exceeding operability requirement of 161.3 kV as of 1834. Current post-trip predicted voltage is 162.2 kV as of 2029.
"Lowest observed actual voltage was 163.7 kV. The 161 kV line and transformers T1A-3 and T1A-4 remained available at all times."
The licensee notified the NRC Resident Inspector.
"At 1826 [CDT], Operators identified that off-site 161 kV power source predicted post-trip voltage was below the operability limit of 161.3 kV. [Operators] entered AOP-31, 161 kV Grid Malfunctions, Section 1, 161 kV Grid Instability, and declared House Service Transformers T1A-3 and T1A-4 inoperable. [Operators] entered Technical Specification 2.7(2)c. Per Technical Specification 2.7(2)c, 'Both house service transformers T1A-3 and T1A-4 (4.16kV) may be inoperable for up to 72 hours. The loss of the 161kV incoming line renders both transformers inoperable. The NRC Operations Center shall be notified by telephone within 4 hours after inoperability of both transformers.'
"Per OPPD [Omaha Public Power District] Transmission, grid conditions are currently stable. OPPD Transmission has successfully raised predicted post-trip 161 kV voltage with all predicted voltages meeting or exceeding operability requirement of 161.3 kV as of 1834. Current post-trip predicted voltage is 162.2 kV as of 2029.
"Lowest observed actual voltage was 163.7 kV. The 161 kV line and transformers T1A-3 and T1A-4 remained available at all times."
The licensee notified the NRC Resident Inspector.