Event Notification Report for March 20, 2014
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
03/19/2014 - 03/20/2014
EVENT NUMBERS
4994149938499444993549937
Power Reactor
Event Number: 49941
Facility: FITZPATRICK
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: MARK HAWES
HQ OPS Officer: JOHN SHOEMAKER
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: MARK HAWES
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 03/21/2014
Notification Time: 12:53 [ET]
Event Date: 03/20/2014
Event Time: 15:22 [EDT]
Last Update Date: 03/21/2014
Notification Time: 12:53 [ET]
Event Date: 03/20/2014
Event Time: 15:22 [EDT]
Last Update Date: 03/21/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
BLAKE WELLING (R1DO)
BLAKE WELLING (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 |
FITNESS FOR DUTY - SIGNIFICANT PROGRAM VULNERABILITY
"A significant Fitness for Duty (FFD) programmatic vulnerability was discovered during an NRC inspection. A potential exists that some members of the FFD site's random drug test pool could control and predict the date and time that the random list is run; thus mitigating the effectiveness of the 'random aspect' for the staff. Per 10 CFR 26.31(d)(2)(i), 'Random testing. Random testing must - Be administered in a manner that provides reasonable assurance that individuals are unable to predict the time periods during which specimens will be collected.' Since, these individuals may be able to predict the timeliness of random drug test events this condition is reportable per 10 CFR 26.719(b)(4) as a discovered programmatic vulnerability of the FFD program that may permit undetected drug or alcohol use by individuals who are assigned to perform duties that require them to be subject to the FFD program."
The licensee has notified the NRC Resident Inspector.
"A significant Fitness for Duty (FFD) programmatic vulnerability was discovered during an NRC inspection. A potential exists that some members of the FFD site's random drug test pool could control and predict the date and time that the random list is run; thus mitigating the effectiveness of the 'random aspect' for the staff. Per 10 CFR 26.31(d)(2)(i), 'Random testing. Random testing must - Be administered in a manner that provides reasonable assurance that individuals are unable to predict the time periods during which specimens will be collected.' Since, these individuals may be able to predict the timeliness of random drug test events this condition is reportable per 10 CFR 26.719(b)(4) as a discovered programmatic vulnerability of the FFD program that may permit undetected drug or alcohol use by individuals who are assigned to perform duties that require them to be subject to the FFD program."
The licensee has notified the NRC Resident Inspector.
Power Reactor
Event Number: 49938
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: TOM PROELL
HQ OPS Officer: DONALD NORWOOD
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: TOM PROELL
HQ OPS Officer: DONALD NORWOOD
Notification Date: 03/20/2014
Notification Time: 17:17 [ET]
Event Date: 03/20/2014
Event Time: 10:20 [CDT]
Last Update Date: 03/20/2014
Notification Time: 17:17 [ET]
Event Date: 03/20/2014
Event Time: 10:20 [CDT]
Last Update Date: 03/20/2014
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):
JULIO LARA (R3DO)
JULIO LARA (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 93 | Power Operation | 93 | Power Operation |
APPENDIX R FIRE DOOR FAILED TO CLOSE AND LATCH
"At 1020 CDT, door 410B did not automatically close and latch as required. Door 410 B is an Appendix R fire door that is required for divisional separation of safe shutdown equipment. Due to the doors inability to close and latch as required, divisional separation could not be assured in the event of a fire. A continuous fire watch was established once the deficiency was discovered. The door was repaired and verified to be working properly. The door was non-functional for approximately one hour and fifteen minutes from the time of discovery.
"Health and safety of the public was maintained as the plant was in a normal condition and there has been no actual condition needing the door to close and latch.
"The NRC Resident Inspector has been notified."
"At 1020 CDT, door 410B did not automatically close and latch as required. Door 410 B is an Appendix R fire door that is required for divisional separation of safe shutdown equipment. Due to the doors inability to close and latch as required, divisional separation could not be assured in the event of a fire. A continuous fire watch was established once the deficiency was discovered. The door was repaired and verified to be working properly. The door was non-functional for approximately one hour and fifteen minutes from the time of discovery.
"Health and safety of the public was maintained as the plant was in a normal condition and there has been no actual condition needing the door to close and latch.
"The NRC Resident Inspector has been notified."
Agreement State
Event Number: 49944
Rep Org: PA BUREAU OF RADIATION PROTECTION
Licensee: APPLUS RTD INC.
Region: 1
City: SHUNK State: PA
County:
License #: PA-1482
Agreement: Y
Docket:
NRC Notified By: JOSEPH MELNIC
HQ OPS Officer: DONALD NORWOOD
Licensee: APPLUS RTD INC.
Region: 1
City: SHUNK State: PA
County:
License #: PA-1482
Agreement: Y
Docket:
NRC Notified By: JOSEPH MELNIC
HQ OPS Officer: DONALD NORWOOD
Notification Date: 03/21/2014
Notification Time: 13:59 [ET]
Event Date: 03/20/2014
Event Time: 00:00 [EDT]
Last Update Date: 03/21/2014
Notification Time: 13:59 [ET]
Event Date: 03/20/2014
Event Time: 00:00 [EDT]
Last Update Date: 03/21/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
BLAKE WELLING (R1DO)
FSME EVENTS RESOURCE (EMAI)
BLAKE WELLING (R1DO)
FSME EVENTS RESOURCE (EMAI)
AGREEMENT STATE REPORT - INABILITY TO RETRACT RADIOGRAPHY SOURCE TO ITS FULLY SHIELDED POSITION
The following information was received via facsimile:
"The Department's [PA Department of Environmental Protection Bureau of Radiation Protection] Central Office was informed of this event on March 20, 2014. This event is reportable within 24 hours per 10 CFR 30.50(b)(2) and within 30 days per 10 CFR 34.101(a)(2).
"Upon completion of a shot, the source was found to be stuck within the collimator and unable to be retracted. The area was roped off and controlled, the Radiation Safety Officer was notified, and a service provider (QSA Global) was called to perform retrieval operations. The source was returned to its fully shielded position at 0002 EDT on March 21, 2014. The radiographer, assistant radiographer, and recovery team received minimal exposure from this source retrieval operation. No one from the general public was exposed to radiation from this operation. Additional information will be provided upon receipt.
"Camera Model: QSA Global 880 Delta; Isotope: Ir-192; Activity: 68 Ci.
"The cause of the event is unknown at this time. The camera and cables are being returned to the manufacturer to be inspected. The Department plans a reactive inspection."
PA Event Report ID No: PA140010
The following information was received via facsimile:
"The Department's [PA Department of Environmental Protection Bureau of Radiation Protection] Central Office was informed of this event on March 20, 2014. This event is reportable within 24 hours per 10 CFR 30.50(b)(2) and within 30 days per 10 CFR 34.101(a)(2).
"Upon completion of a shot, the source was found to be stuck within the collimator and unable to be retracted. The area was roped off and controlled, the Radiation Safety Officer was notified, and a service provider (QSA Global) was called to perform retrieval operations. The source was returned to its fully shielded position at 0002 EDT on March 21, 2014. The radiographer, assistant radiographer, and recovery team received minimal exposure from this source retrieval operation. No one from the general public was exposed to radiation from this operation. Additional information will be provided upon receipt.
"Camera Model: QSA Global 880 Delta; Isotope: Ir-192; Activity: 68 Ci.
"The cause of the event is unknown at this time. The camera and cables are being returned to the manufacturer to be inspected. The Department plans a reactive inspection."
PA Event Report ID No: PA140010
Power Reactor
Event Number: 49935
Facility: BRUNSWICK
Region: 2 State: NC
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: CRAIG OLIVER
HQ OPS Officer: CHARLES TEAL
Region: 2 State: NC
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: CRAIG OLIVER
HQ OPS Officer: CHARLES TEAL
Notification Date: 03/20/2014
Notification Time: 11:34 [ET]
Event Date: 03/20/2014
Event Time: 09:11 [EDT]
Last Update Date: 03/20/2014
Notification Time: 11:34 [ET]
Event Date: 03/20/2014
Event Time: 09:11 [EDT]
Last Update Date: 03/20/2014
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):
SCOTT SHAEFFER (R2DO)
SCOTT SHAEFFER (R2DO)
| 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 |
FIRE-RELATED UNANALYZED CONDITION THAT COULD IMPACT CREDITED SAFE SHUTDOWN ANALYSIS
"This is a non-emergency notification. In preparation for converting from 10 CFR 50, Appendix R, to NFPA (National Fire Protection Association) Standard 805, an update to the Brunswick Steam Electric Plant (BSEP) Safe Shutdown Analysis has been performed which identified circuit configurations where fire damage, under certain postulated fire scenarios, could impact the ability to safely shut down following a fire, in accordance with 10 CFR 50, Appendix R.
"Affected fire areas are CB-23E, RB1-N, RB1-S, RB2-N, RB2-S, TB1, DG-07, and DG-16E. A fire in one of these areas could potentially affect the post fire capability of the following safe shutdown systems: 1) Containment Overpressure Protection, 2) Emergency Bus Load Shed, 3) Control Room HVAC, or 4) Emergency Diesel Generator Building HVAC.
"This is reportable as an unanalyzed condition that significantly degrades plant safety in accordance with 10 CFR 50.72(b)(3)(ii)(B).
"Fire protection compensatory measures (i.e. roving fire watches) currently exist in the affected fire areas.
"This event did not result in any adverse impact to the health and safety of the public. The safety significance is minimal. Fire watches were already ongoing in these areas prior to the time of discovery. The conditions identified here are based on hypothetical fire scenarios that have not actually occurred.
"This condition has been entered into the Corrective Action Program (i.e. CR 676576). Previous similar events were reported in NRC Event Reports 47341 and 49222, and in Brunswick LERs 1-2011-002 and 1-2013-002.
"The NRC Resident Inspector has been notified."
"This is a non-emergency notification. In preparation for converting from 10 CFR 50, Appendix R, to NFPA (National Fire Protection Association) Standard 805, an update to the Brunswick Steam Electric Plant (BSEP) Safe Shutdown Analysis has been performed which identified circuit configurations where fire damage, under certain postulated fire scenarios, could impact the ability to safely shut down following a fire, in accordance with 10 CFR 50, Appendix R.
"Affected fire areas are CB-23E, RB1-N, RB1-S, RB2-N, RB2-S, TB1, DG-07, and DG-16E. A fire in one of these areas could potentially affect the post fire capability of the following safe shutdown systems: 1) Containment Overpressure Protection, 2) Emergency Bus Load Shed, 3) Control Room HVAC, or 4) Emergency Diesel Generator Building HVAC.
"This is reportable as an unanalyzed condition that significantly degrades plant safety in accordance with 10 CFR 50.72(b)(3)(ii)(B).
"Fire protection compensatory measures (i.e. roving fire watches) currently exist in the affected fire areas.
"This event did not result in any adverse impact to the health and safety of the public. The safety significance is minimal. Fire watches were already ongoing in these areas prior to the time of discovery. The conditions identified here are based on hypothetical fire scenarios that have not actually occurred.
"This condition has been entered into the Corrective Action Program (i.e. CR 676576). Previous similar events were reported in NRC Event Reports 47341 and 49222, and in Brunswick LERs 1-2011-002 and 1-2013-002.
"The NRC Resident Inspector has been notified."
Power Reactor
Event Number: 49937
Facility: FERMI
Region: 3 State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: PAUL GRESH
HQ OPS Officer: JOHN SHOEMAKER
Region: 3 State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: PAUL GRESH
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 03/20/2014
Notification Time: 14:15 [ET]
Event Date: 03/20/2014
Event Time: 14:05 [EDT]
Last Update Date: 03/20/2014
Notification Time: 14:15 [ET]
Event Date: 03/20/2014
Event Time: 14:05 [EDT]
Last Update Date: 03/20/2014
Emergency Class: ALERT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
JULIO LARA (R3DO)
CYNTHIA PEDERSON (RA)
DAN DORMAN (NRR)
SCOTT MORRIS (IRD)
JULIO LARA (R3DO)
CYNTHIA PEDERSON (RA)
DAN DORMAN (NRR)
SCOTT MORRIS (IRD)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
FERMI DECLARES ALERT DUE TO A FIRE IN AN EMERGENCY DIESEL GENERATOR TURBO CHARGER LAGGING
At 1405 EDT on 3/20/14, Fermi Nuclear Station declared an Alert due to a fire in the lagging of an Emergency Diesel Generator Turbo Charger. The Alert notification was based on EAL HA02, fire or explosion affecting the operability of plant safety systems required to establish or maintain safe shutdown.
The fire in the EDG-11 turbocharger lagging occurred during testing. The fire was extinguished using handheld CO2 fire extinguishers and a reflash watch was set. EDG-11 has been removed from service and damage is minimal. The plant is shutdown in Mode 4 for Refueling Outage 16. All parameters associated with the reactor are stable. RHR Pump D remains in service in Shutdown Cooling and is unaffected by the EDG-11 fire.
There has been no other impact on the plant electrical systems or shutdown cooling and Fermi Nuclear Station remains in an Alert pending further evaluation. The NRC remained in Normal Mode.
The licensee has informed the NRC Resident Inspector.
Notified DHS SWO, DOE, FEMA, HHS, NICC, USDA, EPA, and FDA. Notified NuclearSSA via email only.
* * * UPDATE FROM SAM HASSOUN TO JOHN SHOEMAKER AT 1535 EDT ON 3/20/13 * * *
"At 1359 [EDT on 3/20/14], with the plant in Mode 4, a fire was confirmed on Emergency Diesel Generator (EDG)-11 turbocharger. At 1402, the fire was extinguished with a CO2 extinguisher. An ALERT was declared at 1405 and Assembly and Accountability was ordered by the Emergency Director. The Assembly and Accountability was completed satisfactorily by 1441. The fire was from oil soaked lagging on the engine turbocharger. The insulation was removed and the engine exhaust header was inspected. The damage was limited to only the lagging. The room has been ventilated using the Engine room fans and has been cleared of all of the smoke. The Emergency Director terminated the event at 1532 [EDT on 3/20/14]. The Resident Inspector has been notified."
Notified R3RA (Pederson), NRR (Dorman), R3DO (Lara), IRD (Grant), IRD (Morris), DHS SWO, DOE, FEMA, HHS, NICC, USDA, EPA, FDA, and Canadian Nuclear Safety Commission (Tennant). Notified NuclearSSA via email only.
At 1405 EDT on 3/20/14, Fermi Nuclear Station declared an Alert due to a fire in the lagging of an Emergency Diesel Generator Turbo Charger. The Alert notification was based on EAL HA02, fire or explosion affecting the operability of plant safety systems required to establish or maintain safe shutdown.
The fire in the EDG-11 turbocharger lagging occurred during testing. The fire was extinguished using handheld CO2 fire extinguishers and a reflash watch was set. EDG-11 has been removed from service and damage is minimal. The plant is shutdown in Mode 4 for Refueling Outage 16. All parameters associated with the reactor are stable. RHR Pump D remains in service in Shutdown Cooling and is unaffected by the EDG-11 fire.
There has been no other impact on the plant electrical systems or shutdown cooling and Fermi Nuclear Station remains in an Alert pending further evaluation. The NRC remained in Normal Mode.
The licensee has informed the NRC Resident Inspector.
Notified DHS SWO, DOE, FEMA, HHS, NICC, USDA, EPA, and FDA. Notified NuclearSSA via email only.
* * * UPDATE FROM SAM HASSOUN TO JOHN SHOEMAKER AT 1535 EDT ON 3/20/13 * * *
"At 1359 [EDT on 3/20/14], with the plant in Mode 4, a fire was confirmed on Emergency Diesel Generator (EDG)-11 turbocharger. At 1402, the fire was extinguished with a CO2 extinguisher. An ALERT was declared at 1405 and Assembly and Accountability was ordered by the Emergency Director. The Assembly and Accountability was completed satisfactorily by 1441. The fire was from oil soaked lagging on the engine turbocharger. The insulation was removed and the engine exhaust header was inspected. The damage was limited to only the lagging. The room has been ventilated using the Engine room fans and has been cleared of all of the smoke. The Emergency Director terminated the event at 1532 [EDT on 3/20/14]. The Resident Inspector has been notified."
Notified R3RA (Pederson), NRR (Dorman), R3DO (Lara), IRD (Grant), IRD (Morris), DHS SWO, DOE, FEMA, HHS, NICC, USDA, EPA, FDA, and Canadian Nuclear Safety Commission (Tennant). Notified NuclearSSA via email only.