Event Notification Report for February 27, 2015
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
02/26/2015 - 02/27/2015
EVENT NUMBERS
50877508545085250853
Agreement State
Event Number: 50877
Rep Org: ARIZONA RADIATION REGULATORY AGENCY
Licensee: PHOENIX BAPTIST HOSPITAL AND MEDICAL CENTER
Region: 4
City: PHOENIX State: AZ
County:
License #: 07-146
Agreement: Y
Docket:
NRC Notified By: AUBREY GODWIN
HQ OPS Officer: CHARLES TEAL
Licensee: PHOENIX BAPTIST HOSPITAL AND MEDICAL CENTER
Region: 4
City: PHOENIX State: AZ
County:
License #: 07-146
Agreement: Y
Docket:
NRC Notified By: AUBREY GODWIN
HQ OPS Officer: CHARLES TEAL
Notification Date: 03/10/2015
Notification Time: 16:50 [ET]
Event Date: 02/27/2015
Event Time: 00:00 [MST]
Last Update Date: 07/13/2015
Notification Time: 16:50 [ET]
Event Date: 02/27/2015
Event Time: 00:00 [MST]
Last Update Date: 07/13/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
NEIL OKEEFE (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)
PATRICIA MILLIGAN (EMAI)
NEIL OKEEFE (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)
PATRICIA MILLIGAN (EMAI)
AGREEMENT STATE REPORT - NUCLEAR MEDICINE TECHNOLOGIST RECEIVED OVEREXPOSURE
The following was received from the State of Arizona via email:
"On February 27, 2015, the licensee received notification from Landauer that one of their nuclear medicine technologists received a dynamic whole body dose of 11 Rem for the wear period of September 1, 2014 to October 31, 2014. The technologist only works at the hospital 1 day a week.
"The Agency [State of Arizona] continues to investigate the event."
Arizona First Notice: 15-006
* * * UPDATE ON 7/13/15 AT 1650 EDT FROM BRIAN GORETZKI TO JEFF HERRERA * * *
The following update was received from the State of Arizona via email:
"The Agency [Arizona Radiation Regulatory Agency] has made a determination that the 11 Rem exposure to the individual at Phoenix Baptist Hospital is valid and has assigned the technologist 10 Rem in year 2014 and 1.01 Rem in year 2015."
Notified R4DO (Gaddy), INES National Officer (Milligan) and NMSS Events (via email).
The following was received from the State of Arizona via email:
"On February 27, 2015, the licensee received notification from Landauer that one of their nuclear medicine technologists received a dynamic whole body dose of 11 Rem for the wear period of September 1, 2014 to October 31, 2014. The technologist only works at the hospital 1 day a week.
"The Agency [State of Arizona] continues to investigate the event."
Arizona First Notice: 15-006
* * * UPDATE ON 7/13/15 AT 1650 EDT FROM BRIAN GORETZKI TO JEFF HERRERA * * *
The following update was received from the State of Arizona via email:
"The Agency [Arizona Radiation Regulatory Agency] has made a determination that the 11 Rem exposure to the individual at Phoenix Baptist Hospital is valid and has assigned the technologist 10 Rem in year 2014 and 1.01 Rem in year 2015."
Notified R4DO (Gaddy), INES National Officer (Milligan) and NMSS Events (via email).
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 50854
Facility: COOPER
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: RANDY KOUBA
HQ OPS Officer: DANIEL MILLS
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: RANDY KOUBA
HQ OPS Officer: DANIEL MILLS
Notification Date: 02/28/2015
Notification Time: 01:20 [ET]
Event Date: 02/27/2015
Event Time: 17:56 [CST]
Last Update Date: 04/16/2015
Notification Time: 01:20 [ET]
Event Date: 02/27/2015
Event Time: 17:56 [CST]
Last Update Date: 04/16/2015
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):
GREG PICK (R4DO)
GREG PICK (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 |
UNANALYZED CONDITION CONCERNING CONTROL ROOM HABITABILITY ANALYSIS
"Cooper Nuclear Station became aware of the installation of two 12,000 gallon anhydrous ammonia tanks approximately 1.5 miles from the site. This amount of anhydrous ammonia at that distance exceeds the control room habitability hazardous chemical analysis previously evaluated for the nuclear station. The control room staff has been informed of the condition and have reviewed the appropriate abnormal procedures for actions to take in the case of a leak. This potentially represents an unanalyzed condition that significantly degrades plant safety and is reportable under 10 CFR 50.72(b)(3)(ii)(B)."
The licensee has notified the NRC Resident Inspector.
* * * RETRACTION AT 1153 EDT ON 4/16/2015 FROM DAVE VANDERKAMP TO MARK ABRAMOVITZ * * *
"Subsequently it was determined that the Control Room Habitability Analysis that was performed in response to the NRC's post-TMI requirements bounds the identified condition. This analysis includes the potential of a toxic chemical leak from a 725-ton tank on a river barge carrying anhydrous ammonia. The volume of chemical, and distance from the control room, included in the post-TMI habitability analysis bounds the conditions found with the newly constructed anhydrous ammonia tanks."
The licensee notified the NRC Resident Inspector.
Notified the R4DO (Farnholtz).
"Cooper Nuclear Station became aware of the installation of two 12,000 gallon anhydrous ammonia tanks approximately 1.5 miles from the site. This amount of anhydrous ammonia at that distance exceeds the control room habitability hazardous chemical analysis previously evaluated for the nuclear station. The control room staff has been informed of the condition and have reviewed the appropriate abnormal procedures for actions to take in the case of a leak. This potentially represents an unanalyzed condition that significantly degrades plant safety and is reportable under 10 CFR 50.72(b)(3)(ii)(B)."
The licensee has notified the NRC Resident Inspector.
* * * RETRACTION AT 1153 EDT ON 4/16/2015 FROM DAVE VANDERKAMP TO MARK ABRAMOVITZ * * *
"Subsequently it was determined that the Control Room Habitability Analysis that was performed in response to the NRC's post-TMI requirements bounds the identified condition. This analysis includes the potential of a toxic chemical leak from a 725-ton tank on a river barge carrying anhydrous ammonia. The volume of chemical, and distance from the control room, included in the post-TMI habitability analysis bounds the conditions found with the newly constructed anhydrous ammonia tanks."
The licensee notified the NRC Resident Inspector.
Notified the R4DO (Farnholtz).
Power Reactor
Event Number: 50852
Facility: PERRY
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: MICHAEL BROGAN
HQ OPS Officer: CHARLES TEAL
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: MICHAEL BROGAN
HQ OPS Officer: CHARLES TEAL
Notification Date: 02/27/2015
Notification Time: 16:10 [ET]
Event Date: 02/27/2015
Event Time: 15:18 [EST]
Last Update Date: 02/27/2015
Notification Time: 16:10 [ET]
Event Date: 02/27/2015
Event Time: 15:18 [EST]
Last Update Date: 02/27/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
20.1906(d)(2) - EXTERNAL RAD LEVELS > LIMITS
10 CFR Section:
20.1906(d)(2) - EXTERNAL RAD LEVELS > LIMITS
Person (Organization):
ANN MARIE STONE (R3DO)
NMSS_EVENTS_NOTIFIC (EMAI)
ANN MARIE STONE (R3DO)
NMSS_EVENTS_NOTIFIC (EMAI)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 87 | Power Operation | 87 | Power Operation |
SHIPMENT OF CONTROL ROD MECHANISMS EXCEEDED EXTERNAL RADIATION LIMITS
"At 1518 EST on Feb 27, 2015, the Perry Shift Manager received notice from the Radiation Protection group that an Exclusive Use closed transport vehicle arrived on site exceeding the 10 CFR 71.47 radiation levels on contact with a box on the vehicle. The truck that arrived had two boxes containing four rebuilt control rod drive mechanisms to be used during the Perry refueling outage. One of the boxes had a contact dose reading of 1290 MR/HR. This is above the 1000 MR/HR limit as noted in 10 CFR 71.47. No other limits were exceeded on the exterior of the vehicle. Specifically, the cab of the truck was reading 0.1 MR/HR which is less than the 2 MR/HR limit. Also at 2 meters around the truck, the highest level reading was 1.2 MR/HR which is below the 10 MR/HR [limit]. Also on direct contact with the outside of the vehicle, the highest reading was 30 MR/HR, which is below the 200 MR/HR limit.
"The Site Radiation Protection Shipping Coordinator contacted the shipping organization of this finding at Perry. This was the Director of Operations of Energy Solutions in Memphis, Tennessee. The box was taken into the Perry Fuel Handling Building and is posted per the Perry Radiation Control Program. The vehicle is parked outside the Fuel Handling Building and is being controlled."
The NRC Resident Inspector has been informed.
"At 1518 EST on Feb 27, 2015, the Perry Shift Manager received notice from the Radiation Protection group that an Exclusive Use closed transport vehicle arrived on site exceeding the 10 CFR 71.47 radiation levels on contact with a box on the vehicle. The truck that arrived had two boxes containing four rebuilt control rod drive mechanisms to be used during the Perry refueling outage. One of the boxes had a contact dose reading of 1290 MR/HR. This is above the 1000 MR/HR limit as noted in 10 CFR 71.47. No other limits were exceeded on the exterior of the vehicle. Specifically, the cab of the truck was reading 0.1 MR/HR which is less than the 2 MR/HR limit. Also at 2 meters around the truck, the highest level reading was 1.2 MR/HR which is below the 10 MR/HR [limit]. Also on direct contact with the outside of the vehicle, the highest reading was 30 MR/HR, which is below the 200 MR/HR limit.
"The Site Radiation Protection Shipping Coordinator contacted the shipping organization of this finding at Perry. This was the Director of Operations of Energy Solutions in Memphis, Tennessee. The box was taken into the Perry Fuel Handling Building and is posted per the Perry Radiation Control Program. The vehicle is parked outside the Fuel Handling Building and is being controlled."
The NRC Resident Inspector has been informed.
Power Reactor
Event Number: 50853
Facility: SEQUOYAH
Region: 2 State: TN
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: SAM NAKAMINE
HQ OPS Officer: DONALD NORWOOD
Region: 2 State: TN
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: SAM NAKAMINE
HQ OPS Officer: DONALD NORWOOD
Notification Date: 02/27/2015
Notification Time: 17:04 [ET]
Event Date: 02/27/2015
Event Time: 13:05 [EST]
Last Update Date: 02/27/2015
Notification Time: 17:04 [ET]
Event Date: 02/27/2015
Event Time: 13:05 [EST]
Last Update Date: 02/27/2015
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):
DEBORAH SEYMOUR (R2DO)
DEBORAH SEYMOUR (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 |
EMERGENCY NOTIFICATION SYSTEM AND HEALTH PHYSICS NETWORK TELEPHONE LINES OUT OF SERVICE
"On February 27, 2015, from 1305 to 1323 [EST], a loss of the ENS [Emergency Notification System] communication line, the HPN [Health Physics Network] line, and the other communication systems that the MCR [Main Control Room] operators use as part of the emergency plan occurred at TVA Sequoyah Units 1 and 2. A loss of these systems was experienced when transferring from a backup generator to an uninterruptible power supply (UPS) during fueling of the backup generator. Earlier in the day the normal power supply to the two (2) plant communications buildings was deenergized due to an unrelated electrical issue and backup diesel generators were supplying power to the buildings. While refueling one of the backup generators, the power supply was transferred to the UPS for personal safety reasons, however, the load on the UPS was greater than its capacity and its output [breaker] tripped.
"This loss of communications was corrected in approximately 18 minutes once the fuel tank was filled and the generator was started. Phone line capability has been restored and verified to be functional. Sequoyah is currently investigating why the load was greater than the UPS capacity. The radiological emergency plan (REP) was reviewed and other acceptable methods for communications were available. There were no personnel injuries as a result of this event and no impact on plant operations. Both units remain at 100% power. The NRC Resident Inspector has been notified.
"This notification is being made in accordance with 10CFR50.72(b)(3)(xiii) due to the loss of communications capability which includes events that would significantly impair the ability of the licensee to implement the functions of its emergency plans if an emergency were to occur."
"On February 27, 2015, from 1305 to 1323 [EST], a loss of the ENS [Emergency Notification System] communication line, the HPN [Health Physics Network] line, and the other communication systems that the MCR [Main Control Room] operators use as part of the emergency plan occurred at TVA Sequoyah Units 1 and 2. A loss of these systems was experienced when transferring from a backup generator to an uninterruptible power supply (UPS) during fueling of the backup generator. Earlier in the day the normal power supply to the two (2) plant communications buildings was deenergized due to an unrelated electrical issue and backup diesel generators were supplying power to the buildings. While refueling one of the backup generators, the power supply was transferred to the UPS for personal safety reasons, however, the load on the UPS was greater than its capacity and its output [breaker] tripped.
"This loss of communications was corrected in approximately 18 minutes once the fuel tank was filled and the generator was started. Phone line capability has been restored and verified to be functional. Sequoyah is currently investigating why the load was greater than the UPS capacity. The radiological emergency plan (REP) was reviewed and other acceptable methods for communications were available. There were no personnel injuries as a result of this event and no impact on plant operations. Both units remain at 100% power. The NRC Resident Inspector has been notified.
"This notification is being made in accordance with 10CFR50.72(b)(3)(xiii) due to the loss of communications capability which includes events that would significantly impair the ability of the licensee to implement the functions of its emergency plans if an emergency were to occur."