Event Notification Report for April 23, 2014
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
04/22/2014 - 04/23/2014
EVENT NUMBERS
50056500515005250054
Power Reactor
Event Number: 50056
Facility: CALLAWAY
Region: 4 State: MO
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: RICHARD HUGHEY
HQ OPS Officer: HOWIE CROUCH
Region: 4 State: MO
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: RICHARD HUGHEY
HQ OPS Officer: HOWIE CROUCH
Notification Date: 04/24/2014
Notification Time: 14:08 [ET]
Event Date: 04/23/2014
Event Time: 15:30 [CDT]
Last Update Date: 04/24/2014
Notification Time: 14:08 [ET]
Event Date: 04/23/2014
Event Time: 15:30 [CDT]
Last Update Date: 04/24/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
RAY AZUA (R4DO)
RAY AZUA (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 |
FITNESS FOR DUTY REPORT - FALSE NEGATIVE ERROR OCCURRED ON QUALITY ASSURANCE TEST
"Contrary to the requirements in 10 CFR 26.137(b), a Department of Health and Human Services (DHHS) certified laboratory returned results for a blind specimen that was inconsistent with what was expected.
"On 04/22/2014, blind specimens from the same lot number were sent to the two contracted DHHS laboratories. On 04/23/2014, one of the labs reported unexpected results while the other laboratory reported the expected results. At approximately 1530 [CDT] on 04/23/2014, the lab report was reviewed by Fitness For Duty Management at Callaway Plant and the inaccurate result was identified. On 04/24/2014, the Medical Review Officer (MRO) contacted Clinical Reference Laboratory (CRL) to discuss the testing discrepancy and directed the lab to retest the specimen. The MRO requested that CRL initiate an investigation to determine the reason for the inaccurate result and provide a report of the results of that investigation within 20 days.
"10 CFR 26.719(c)(3), 'Reporting Requirements,' requires that 'if a false negative error occurs on a quality assurance check of validity screening tests, as required in 26.137(b), the licensee or other entity shall notify the NRC within 24 hours after discovery of the error.'"
The licensee has notified the NRC Resident Inspector.
"Contrary to the requirements in 10 CFR 26.137(b), a Department of Health and Human Services (DHHS) certified laboratory returned results for a blind specimen that was inconsistent with what was expected.
"On 04/22/2014, blind specimens from the same lot number were sent to the two contracted DHHS laboratories. On 04/23/2014, one of the labs reported unexpected results while the other laboratory reported the expected results. At approximately 1530 [CDT] on 04/23/2014, the lab report was reviewed by Fitness For Duty Management at Callaway Plant and the inaccurate result was identified. On 04/24/2014, the Medical Review Officer (MRO) contacted Clinical Reference Laboratory (CRL) to discuss the testing discrepancy and directed the lab to retest the specimen. The MRO requested that CRL initiate an investigation to determine the reason for the inaccurate result and provide a report of the results of that investigation within 20 days.
"10 CFR 26.719(c)(3), 'Reporting Requirements,' requires that 'if a false negative error occurs on a quality assurance check of validity screening tests, as required in 26.137(b), the licensee or other entity shall notify the NRC within 24 hours after discovery of the error.'"
The licensee has notified the NRC Resident Inspector.
Power Reactor
Event Number: 50051
Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: STEVE INGALLS
HQ OPS Officer: CHARLES TEAL
Region: 3 State: MN
Unit: [] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: STEVE INGALLS
HQ OPS Officer: CHARLES TEAL
Notification Date: 04/23/2014
Notification Time: 11:47 [ET]
Event Date: 04/23/2014
Event Time: 10:00 [CDT]
Last Update Date: 04/23/2014
Notification Time: 11:47 [ET]
Event Date: 04/23/2014
Event Time: 10:00 [CDT]
Last Update Date: 04/23/2014
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):
JAMNES CAMERON (R3DO)
JAMNES CAMERON (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
2R-22 SHIELD BUILDING VENT GAS RADIATION MONITOR REMOVED FROM SERVICE FOR PLANNED MAINTENANCE
"At 1000 CDT on April 23, 2014, 2R-22, Shield Building Vent Gas Radiation Monitor was removed from service for planned maintenance. This monitor has no compensatory measures that will allow timely classification of two Emergency Action Levels (EALs); NUE (Notification of Unusual Event) and Alert classifications when out of service. It is also used for offsite dose projection calculations. This results in a loss of emergency assessment capability while 2R-22 is out of service. This is a reportable condition in accordance with 10 CFR 50.72(b)(3)(xiii).
"The Unit 2 Shield Building Ventilation Stack is also monitored by the high range monitor, 2R-50, which is used for the same purpose in Site Area Emergency classifications. 2R-50 is being monitored and is indicating normal values. There are no radioactive leaks that will impact the Shield Building as evidence by normal reading on 2R-22 prior to its removal from service. Maintenance is expected to last approximately 4 hours and will continue until the monitor is returned to service. Maintenance will not result in the unplanned release of the radioactivity to the environment and will not adversely affect the safe operation of the plant or health and safety of the public.
"The licensee has notified the NRC Resident Inspector."
"At 1000 CDT on April 23, 2014, 2R-22, Shield Building Vent Gas Radiation Monitor was removed from service for planned maintenance. This monitor has no compensatory measures that will allow timely classification of two Emergency Action Levels (EALs); NUE (Notification of Unusual Event) and Alert classifications when out of service. It is also used for offsite dose projection calculations. This results in a loss of emergency assessment capability while 2R-22 is out of service. This is a reportable condition in accordance with 10 CFR 50.72(b)(3)(xiii).
"The Unit 2 Shield Building Ventilation Stack is also monitored by the high range monitor, 2R-50, which is used for the same purpose in Site Area Emergency classifications. 2R-50 is being monitored and is indicating normal values. There are no radioactive leaks that will impact the Shield Building as evidence by normal reading on 2R-22 prior to its removal from service. Maintenance is expected to last approximately 4 hours and will continue until the monitor is returned to service. Maintenance will not result in the unplanned release of the radioactivity to the environment and will not adversely affect the safe operation of the plant or health and safety of the public.
"The licensee has notified the NRC Resident Inspector."
Power Reactor
Event Number: 50052
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: JEREMY TANNER
HQ OPS Officer: HOWIE CROUCH
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: JEREMY TANNER
HQ OPS Officer: HOWIE CROUCH
Notification Date: 04/23/2014
Notification Time: 12:51 [ET]
Event Date: 04/23/2014
Event Time: 10:00 [CDT]
Last Update Date: 04/23/2014
Notification Time: 12:51 [ET]
Event Date: 04/23/2014
Event Time: 10:00 [CDT]
Last Update Date: 04/23/2014
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):
JAMNES CAMERON (R3DO)
JAMNES CAMERON (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 88 | Power Operation | 88 | Power Operation |
OFFSITE NOTIFICATION DUE TO DECEASED MIGRATORY BIRD FOUND ON PLANT PROPERTY
"Monticello Nuclear Generating Plant personnel discovered the remains of a deceased migratory bird on plant property. The cause of death was not immediately apparent and no work was ongoing in the vicinity at the time the bird was found. Notifications to the United States Fish and Wildlife Service will be made for this discovery. This event is being reported per 10CFR50.72(b)(2)(xi)."
The licensee has informed the NRC Resident Inspector.
"Monticello Nuclear Generating Plant personnel discovered the remains of a deceased migratory bird on plant property. The cause of death was not immediately apparent and no work was ongoing in the vicinity at the time the bird was found. Notifications to the United States Fish and Wildlife Service will be made for this discovery. This event is being reported per 10CFR50.72(b)(2)(xi)."
The licensee has informed the NRC Resident Inspector.
Power Reactor
Event Number: 50054
Facility: TURKEY POINT
Region: 2 State: FL
Unit: [3] [] []
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: MICHAEL COHEN
HQ OPS Officer: DANIEL MILLS
Region: 2 State: FL
Unit: [3] [] []
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: MICHAEL COHEN
HQ OPS Officer: DANIEL MILLS
Notification Date: 04/23/2014
Notification Time: 17:18 [ET]
Event Date: 04/23/2014
Event Time: 13:02 [EDT]
Last Update Date: 04/23/2014
Notification Time: 17:18 [ET]
Event Date: 04/23/2014
Event Time: 13:02 [EDT]
Last Update Date: 04/23/2014
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):
MICHAEL F. KING (R2DO)
MICHAEL F. KING (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | N | 0 | Hot Standby | 0 | Hot Standby |
SPECIFIED SYSTEM ACTUATION DURING ROD TESTING
"This is a non-emergency eight hour notification in accordance with 10 CFR 50.72(b)(3)(iv)(A), for a valid manual actuation of the Reactor Protection System.
"While performing rod control system testing with the reactor subcritical in MODE 3, a rod control demand position indicator failed when one bank of rods were withdrawn. The group step counter demand exceeded the Technical Specification allowable value. On 4/23/2014 at approximately 1302 [EDT], the Unit 3 reactor trip breakers were manually opened to comply with Technical Specification 3.1.3.3 action. The rods being tested were fully inserted when the reactor trip breakers were opened. All other rods remained fully inserted. Unit 3 remains in MODE 3."
The licensee notified the NRC Resident Inspector.
"This is a non-emergency eight hour notification in accordance with 10 CFR 50.72(b)(3)(iv)(A), for a valid manual actuation of the Reactor Protection System.
"While performing rod control system testing with the reactor subcritical in MODE 3, a rod control demand position indicator failed when one bank of rods were withdrawn. The group step counter demand exceeded the Technical Specification allowable value. On 4/23/2014 at approximately 1302 [EDT], the Unit 3 reactor trip breakers were manually opened to comply with Technical Specification 3.1.3.3 action. The rods being tested were fully inserted when the reactor trip breakers were opened. All other rods remained fully inserted. Unit 3 remains in MODE 3."
The licensee notified the NRC Resident Inspector.