Event Notification Report for January 16, 2019
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
01/15/2019 - 01/16/2019
Power Reactor
Event Number: 53830
Facility: FERMI
Region: 3 State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: JEFF MEYERS
HQ OPS Officer: THOMAS KENDZIA
Region: 3 State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: JEFF MEYERS
HQ OPS Officer: THOMAS KENDZIA
Notification Date: 01/16/2019
Notification Time: 18:38 [ET]
Event Date: 01/16/2019
Event Time: 09:00 [EST]
Last Update Date: 01/16/2019
Notification Time: 18:38 [ET]
Event Date: 01/16/2019
Event Time: 09:00 [EST]
Last Update Date: 01/16/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
PATRICIA PELKE (R3DO)
FFD GROUP (EMAIL)
WILLIAM GOTT (IRD)
PATRICIA PELKE (R3DO)
FFD GROUP (EMAIL)
WILLIAM GOTT (IRD)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
SIGNIFICANT FITNESS-FOR-DUTY POLICY VIOLATION
"At 0900 EST on 01/16/2019, it was discovered that a licensee manager intentionally failed to re-approve the list of individuals granted unescorted access to verify each individual was subject to a behavioral observation program. Compensatory actions have been taken in response to this event. Personnel affected have had their access authorization suspended.
"This is reportable under the provisions of 10 CFR 26.719(b)(3) as an intentional act that casts doubt on the integrity of the Fitness-For-Duty program.
"The licensee notified the NRC Resident Inspector."
"At 0900 EST on 01/16/2019, it was discovered that a licensee manager intentionally failed to re-approve the list of individuals granted unescorted access to verify each individual was subject to a behavioral observation program. Compensatory actions have been taken in response to this event. Personnel affected have had their access authorization suspended.
"This is reportable under the provisions of 10 CFR 26.719(b)(3) as an intentional act that casts doubt on the integrity of the Fitness-For-Duty program.
"The licensee notified the NRC Resident Inspector."
Power Reactor
Event Number: 53831
Facility: FORT CALHOUN
Region: 4 State: NE
Unit: [1] [] []
RX Type: (1) CE
NRC Notified By: SHERYL LEMIEUX
HQ OPS Officer: BRIAN P. SMITH
Region: 4 State: NE
Unit: [1] [] []
RX Type: (1) CE
NRC Notified By: SHERYL LEMIEUX
HQ OPS Officer: BRIAN P. SMITH
Notification Date: 01/16/2019
Notification Time: 23:51 [ET]
Event Date: 01/16/2019
Event Time: 19:08 [CST]
Last Update Date: 01/16/2019
Notification Time: 23:51 [ET]
Event Date: 01/16/2019
Event Time: 19:08 [CST]
Last Update Date: 01/16/2019
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):
JAMES DRAKE (R4DO)
JAMES DRAKE (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Defueled | 0 | Defueled |
OFFSITE NOTIFICATION DUE TO FIRE REQUIRING LOCAL FIRE DEPARTMENT RESPONSE
"At 1908 CST, a fire was reported in an unoccupied exclusion area opening (EAO) enclosure outside of the Fort Calhoun Station protected area. Offsite fire departments responded at 1923 CST and the fire was extinguished by 1930 CST. There were no injuries reported.
"The State Fire Marshal of Nebraska was notified by the Blair (Nebraska) Fire Department at approximately 1913 CST. His investigation determined the cause to be a malfunctioning heating element in a climate control unit. There was no release of radioactivity or hazardous materials."
The climate control unit was clarified to be a ceiling mounted heater in the enclosure.
The licensee notified the NRC Decommissioning Inspector.
"At 1908 CST, a fire was reported in an unoccupied exclusion area opening (EAO) enclosure outside of the Fort Calhoun Station protected area. Offsite fire departments responded at 1923 CST and the fire was extinguished by 1930 CST. There were no injuries reported.
"The State Fire Marshal of Nebraska was notified by the Blair (Nebraska) Fire Department at approximately 1913 CST. His investigation determined the cause to be a malfunctioning heating element in a climate control unit. There was no release of radioactivity or hazardous materials."
The climate control unit was clarified to be a ceiling mounted heater in the enclosure.
The licensee notified the NRC Decommissioning Inspector.
Power Reactor
Event Number: 53828
Facility: FITZPATRICK
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: JOHN WALKOWIAK
HQ OPS Officer: DONALD NORWOOD
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: JOHN WALKOWIAK
HQ OPS Officer: DONALD NORWOOD
Notification Date: 01/16/2019
Notification Time: 08:12 [ET]
Event Date: 01/16/2019
Event Time: 01:37 [EST]
Last Update Date: 01/16/2019
Notification Time: 08:12 [ET]
Event Date: 01/16/2019
Event Time: 01:37 [EST]
Last Update Date: 01/16/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
ERIN CARFANG (R1DO)
ERIN CARFANG (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 |
SECONDARY CONTAINMENT DIFFERENTIAL PRESSURE EXCEEDED TECHNICAL SPECIFICATION ALLOWED VALUE
"On January 16, 2019, with James A. Fitzpatrick Nuclear Power Plant operating at 100 percent power, the Emergency and Plant Information Computer (EPIC) indicated that Secondary Containment differential pressure exceeded the Technical Specification Surveillance Requirement of greater than or equal to 0.25 inches of vacuum water gauge while isolating Reactor Building Ventilation. The Secondary Containment differential pressure was less than 0.25 inches of vacuum water gauge for approximately ten (10) seconds, and then immediately returned to greater than or equal to 0.25 inches of vacuum water gauge.
"This condition did not impact the leak tightness of Secondary Containment or the ability of the Standby Gas Treatment system to establish and maintain the required differential pressure. When Secondary Containment did not meet the Technical Specification Surveillance Requirement 3.6.4.1.1 for differential pressure, the Limiting Condition of Operation (LCO) was not met. Therefore, Secondary Containment was inoperable. This event is being reported under 10 CFR 50.72(b)(3)(v)(C)."
"The licensee has notified the NRC Resident Inspector."
"On January 16, 2019, with James A. Fitzpatrick Nuclear Power Plant operating at 100 percent power, the Emergency and Plant Information Computer (EPIC) indicated that Secondary Containment differential pressure exceeded the Technical Specification Surveillance Requirement of greater than or equal to 0.25 inches of vacuum water gauge while isolating Reactor Building Ventilation. The Secondary Containment differential pressure was less than 0.25 inches of vacuum water gauge for approximately ten (10) seconds, and then immediately returned to greater than or equal to 0.25 inches of vacuum water gauge.
"This condition did not impact the leak tightness of Secondary Containment or the ability of the Standby Gas Treatment system to establish and maintain the required differential pressure. When Secondary Containment did not meet the Technical Specification Surveillance Requirement 3.6.4.1.1 for differential pressure, the Limiting Condition of Operation (LCO) was not met. Therefore, Secondary Containment was inoperable. This event is being reported under 10 CFR 50.72(b)(3)(v)(C)."
"The licensee has notified the NRC Resident Inspector."