| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
9/25/2018 - 9/26/2018 ** EVENT NUMBERS ** |
| !!!!! THIS EVENT HAS BEEN RETRACTED.THIS EVENT HAS BEEN RETRACTED !!!!! | | Fuel Cycle Facility | Event Number: 53612 | Facility: BWX TECHNOLOGIES, INC.
RX Type: URANIUM FUEL FABRICATION
Comments: HEU FABRICATION & SCRAP
Region: 2
City: LYNCHBURG State: VA
County: CAMPBELL
License #: SNM-42
Docket: 070-27
NRC Notified By: CHRIS TERRY
HQ OPS Officer: ANDREW WAUGH
| Notification Date: 09/18/2018
Notification Time: 14:15 [ET]
Event Date: 09/17/2018
Event Time: 00:00 [EDT]
Last Update Date: 09/20/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
PART 70 APP A (b)(1) - UNANALYZED CONDITION | Person (Organization):
EUGENE GUTHRIE (R2DO)
FUELS GROUP (EMAIL)
NMSS_EVENTS_NOTIFICATION (EMAIL) | Event Text UNANALYZED CONDITION
"On September 17, 2018, a notification was made by [Specialty Fuel Facility] (SFF) Operations that during dissolution of depleted uranium in the Conversion Area, the Recovery scrubber system was shut down for maintenance. During the shutdown, a reduction in vacuum to the box ventilation was experienced and a small amount of NOx [Nitrous Oxide] was released into the room. As the result of BWXT's review of this event, it cannot be determined within the 24 hour notification period that documentation is available to demonstrate that the condition has been analyzed in the [Integrated Safety Analysis] (ISA). BWXT is making this report per 10 CFR 70.61, Appendix A(b)(1), 'Any event or condition that results in the facility being in a state that was not analyzed, was improperly analyzed, or is different from that analyzed in the ISA, and which results in a failure to meet the performance requirements of 10 CFR 70.61 (i.e. high consequence events are highly unlikely and intermediate consequences are unlikely)'.
"The area is currently shutdown and in preparation for inventory. No material has been processed within the system since the event. BWXT is continuing to review the ISA documentation and will provide further updates as appropriate."
The licensee notified the NRC Resident Inspector.
* * * RETRACTION AT 1315 EDT ON 9/20/18 FROM CHRIS TERRY TO JEFF HERRERA * * *
"BWXT is retracting Event Notification #53612 that was reported on September 18, 2018. The notification was made due to the fact that it could not be determined within the 24 hour notification period that documentation was available to demonstrate that a NOx release from the Conversion Area dissolver had been analyzed in the ISA. Subsequently, BWXT located the documentation that the condition was analyzed and meets the performance requirements of 10 CFR 70.61. Additionally, new calculations of the current process were run and the results confirmed the original analysis."
The licensee notified the NRC Resident Inspector.
Notified the R2DO (Guthrie), NMSS Events and Fuels group (via email). |
| Power Reactor | Event Number: 53622 | Facility: RIVER BEND
Region: 4 State: LA
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: JASON BUSH
HQ OPS Officer: OSSY FONT | Notification Date: 09/25/2018
Notification Time: 20:25 [ET]
Event Date: 09/25/2018
Event Time: 00:00 [CDT]
Last Update Date: 09/25/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
RYAN ALEXANDER (R4DO) | | Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 90 | Power Operation | 90 | Power Operation | Event Text CONTROL BUILDING CHILLERS IN UNANALYZED CONDITION
"At 1200 CDT on September 25, 2018, while the plant was in MODE 1 at 90 percent power, it was identified that an additional condition existed which had not previously been considered in developing the compensatory measures implemented for design flaws and single point vulnerabilities associated with the Control Building Chilled Water System. Specifically, a 20 minute 'quick restart timer' on Control Building Chillers that have analog control systems (HVK-CHL1A & 1B) would prevent the chillers from starting in specific scenarios.
"The recommended compensatory actions to address the new condition were implemented at 1235 CDT on September 25, 2018.
"Currently the Chilled Water System is otherwise operating as designed. Operator actions are in place to ensure the plant meets all required design safety system functions. Work is currently underway to identify and correct all design vulnerabilities.
"The [NRC] Senior Resident Inspector has been notified."
This was identified by engineering during an extended condition search. |
| Power Reactor | Event Number: 53623 | Facility: CLINTON
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: PATRICK SELZER
HQ OPS Officer: VINCE KLCO | Notification Date: 09/26/2018
Notification Time: 15:10 [ET]
Event Date: 09/26/2018
Event Time: 00:00 [CDT]
Last Update Date: 09/26/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
LAURA KOZAK (R3DO) | | Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 98 | Power Operation | 98 | Power Operation | Event Text UNDERVOLTAGE CONDITION INITIATES AN AUTOMATIC START OF THE DIESEL GENERATOR
"At 0946 CDT on 9/26/2018, a disruption in power to the offsite 138 kV line and the subsequent trip of the Emergency Reserve Auxiliary Transformer (ERAT) Static VAR Compensator (SVC) resulted in a degraded voltage signal on the Division 1- 4.16 kV safety bus. The degraded voltage signal resulted in a trip of the ERAT feed to the bus, blocking closure of the 345 kV Reserve Auxiliary Transformer (RAT) feed to the bus and auto start of the Division 1 Emergency Diesel Generator (EDG). The Division 1 EDG successfully started and re-energized the Division 1- 4.16 kV bus as designed. The unit is stable with the Division 1 EDG carrying the Division 1- 4.16 kV bus.
"The Ameren Transmission System Operator in St. Louis, MO informed the station that they had received a report that a 138 kV to 13.8 kV transformer at Clinton Route 54 substation was on fire and the South feed to the Tabor substation cycled as a result of this fault.
"The NRC Resident Inspector and Illinois Emergency Management Agency Resident Inspector have been notified." |
| Power Reactor | Event Number: 53625 | Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: LAURA MYERS
HQ OPS Officer: VINCE KLCO | Notification Date: 09/26/2018
Notification Time: 21:43 [ET]
Event Date: 09/26/2018
Event Time: 00:00 [EDT]
Last Update Date: 09/26/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
FRANK ARNER (R1DO) | | Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text HIGH PRESSURE CORE INJECTION (HPCI) SYSTEM INOPERABLE
"On 9/26/2018 at 1530 EDT, it was discovered that the HPCI system was inoperable due to a blown fuse in the 10C617 Panel, E21-F15A. Therefore, this condition Is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(v)(D). The blown fuse also impacts 'A' channel Residual Heat Removal (RHR) subsystem and 'A' Core Spray (CS) subsystem. These Emergency Core Cooling subsystems have been declared inoperable. Remaining Emergency Core Cooling subsystems and the Reactor Core Isolation Cooling (RCIC) system remain OPERABLE.
"There was no impact on the health and safety of the public or plant personnel."
The licensee notified the NRC Resident Inspector and will notify the local authorities. |
| Power Reactor | Event Number: 53626 | Facility: QUAD CITIES
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: MATT SEELEY
HQ OPS Officer: VINCE KLCO | Notification Date: 09/26/2018
Notification Time: 23:25 [ET]
Event Date: 09/26/2018
Event Time: 00:00 [CDT]
Last Update Date: 09/26/2018 | 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
| Person (Organization):
LAURA KOZAK (R3DO) | | Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | A/R | Y | 100 | Power Operation | 0 | Hot Shutdown | Event Text AUTOMATIC SCRAM DUE TO GENERATOR OUTPUT BREAKER TRIP
"On September 26, 2018 at 1908 CDT. an automatic scram was received on U1 following main generator 345 kV output breaker 7-8 trip with 345 kV output breaker 6-7 already opened for maintenance on line 0401. Following the reactor scram, reactor water level decreased to approximately minus 15 inches, which resulted in automatic Group II and Group Ill isolations (expected response). Reactor pressure rose to approximately 1083 psig, and the 3B and 3C low set relief valves opened briefly to control reactor pressure. Reactor water level and reactor pressure have been restored to their normal bands. All systems responded properly to the event. Unit 1 remains in Mode 3, with reactor pressure being controlled on the turbine bypass valves. The cause and details of the event are under investigation.
"Unit 2 was unaffected by the event and remains at 100% power.
"This report is being made in accordance with 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A)."
All control rods inserted. Decay heat is being removed via the main condenser.
The licensee notified the NRC Resident Inspector. | |