Event Notification Report for February 12, 2014
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
02/11/2014 - 02/12/2014
EVENT NUMBERS
5015249823498244982049821
Agreement State
Event Number: 50152
Rep Org: RI DEPT OF RADIOLOGICAL HEALTH
Licensee: CARDIOVASCULAR INSTITUTE OF NEW ENGLAND
Region: 1
City: PROVIDENCE State: RI
County:
License #: 7b-137-01
Agreement: Y
Docket:
NRC Notified By: CHARMA WARING
HQ OPS Officer: MARK ABRAMOVITZ
Licensee: CARDIOVASCULAR INSTITUTE OF NEW ENGLAND
Region: 1
City: PROVIDENCE State: RI
County:
License #: 7b-137-01
Agreement: Y
Docket:
NRC Notified By: CHARMA WARING
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 05/30/2014
Notification Time: 12:15 [ET]
Event Date: 02/12/2014
Event Time: 00:00 [EDT]
Last Update Date: 03/05/2015
Notification Time: 12:15 [ET]
Event Date: 02/12/2014
Event Time: 00:00 [EDT]
Last Update Date: 03/05/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
JOHN ROGGE (R1DO)
FSME EVENT RESOURCES (E-MA)
JOHN ROGGE (R1DO)
FSME EVENT RESOURCES (E-MA)
AGREEMENT STATE REPORT - LOST CALIBRATION SOURCE
"On February 12, 2014, the nuclear cardiology and radiation safety staff concluded, a Cesium-137 Rod
Source; 1059 microCi on November 11/11/2003; Manufactured by Bench Mark; Serial Number: BM0837- 002-23; Model Number: BM08, was lost.
"Following discovery of the lost source, the nuclear cardiology staff and this consultant conducted an extensive search of the nuclear cardiology imaging room and hot lab in an effort to find the source. Unfortunately, we were unsuccessful in locating the calibration rod. The lost source was routinely stored in the locked hot lab cabinet in a leaded pig. The only time the source was removed from the leaded pig was to perform daily calibrations of the well counter. Through our internal investigation we were unable to ascertain the event that attributed to the missing source.
"Subsequently, contacted [the Rhode Island Department of Health], to provide official notice that the source was lost. At the time of the incident, the activity of the source was calculated at 0.083 microCi. On February 21,2014 a replacement Cs-137 Button Source; 6.60 microCi on 12/18/2009; Manufactured by NEN was added to the Sealed Source Inventory. The new source is stored in the locked hot lab cabinet in a leaded vial. The new source is used for instrument calibrations on the well counter. The nuclear cardiology staff will conduct a daily inventory of the sealed sources to assure completeness."
RI Event Reference 2014-002
* * * UPDATE FROM CHARMA WARING (VIA FAX) ON 3/5/15 AT 1535 EST
The State of Rhode Island considers this report closed.
NMED Item #120538.
Notified R1DO (Burritt) via email.
THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL
Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf
"On February 12, 2014, the nuclear cardiology and radiation safety staff concluded, a Cesium-137 Rod
Source; 1059 microCi on November 11/11/2003; Manufactured by Bench Mark; Serial Number: BM0837- 002-23; Model Number: BM08, was lost.
"Following discovery of the lost source, the nuclear cardiology staff and this consultant conducted an extensive search of the nuclear cardiology imaging room and hot lab in an effort to find the source. Unfortunately, we were unsuccessful in locating the calibration rod. The lost source was routinely stored in the locked hot lab cabinet in a leaded pig. The only time the source was removed from the leaded pig was to perform daily calibrations of the well counter. Through our internal investigation we were unable to ascertain the event that attributed to the missing source.
"Subsequently, contacted [the Rhode Island Department of Health], to provide official notice that the source was lost. At the time of the incident, the activity of the source was calculated at 0.083 microCi. On February 21,2014 a replacement Cs-137 Button Source; 6.60 microCi on 12/18/2009; Manufactured by NEN was added to the Sealed Source Inventory. The new source is stored in the locked hot lab cabinet in a leaded vial. The new source is used for instrument calibrations on the well counter. The nuclear cardiology staff will conduct a daily inventory of the sealed sources to assure completeness."
RI Event Reference 2014-002
* * * UPDATE FROM CHARMA WARING (VIA FAX) ON 3/5/15 AT 1535 EST
The State of Rhode Island considers this report closed.
NMED Item #120538.
Notified R1DO (Burritt) via email.
THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL
Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf
Power Reactor
Event Number: 49823
Facility: MILLSTONE
Region: 1 State: CT
Unit: [] [2] []
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: WALTER ORF
HQ OPS Officer: DONG HWA PARK
Region: 1 State: CT
Unit: [] [2] []
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: WALTER ORF
HQ OPS Officer: DONG HWA PARK
Notification Date: 02/12/2014
Notification Time: 15:48 [ET]
Event Date: 02/12/2014
Event Time: 10:47 [EST]
Last Update Date: 02/12/2014
Notification Time: 15:48 [ET]
Event Date: 02/12/2014
Event Time: 10:47 [EST]
Last Update Date: 02/12/2014
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):
RAY POWELL (R1DO)
RAY POWELL (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
HIGH RANGE STACK RADIATION MONITOR REMOVED FROM SERVICE FOR PLANNED MAINTENANCE
At 1047 EST on 2/12/14, Millstone Unit 2 removed the Stack High Range Radiation Monitor, RM 8168, from service for pre-planned maintenance. Functional test was completed and operability was restored at 1426 EST on 2/12/2014.
The licensee informed the Connecticut Department of Environmental Protection, Waterford Dispatch and the NRC Resident Inspector.
At 1047 EST on 2/12/14, Millstone Unit 2 removed the Stack High Range Radiation Monitor, RM 8168, from service for pre-planned maintenance. Functional test was completed and operability was restored at 1426 EST on 2/12/2014.
The licensee informed the Connecticut Department of Environmental Protection, Waterford Dispatch and the NRC Resident Inspector.
Power Reactor
Event Number: 49824
Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [1] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: DARRYL LAPCINSKI
HQ OPS Officer: PETE SNYDER
Region: 3 State: MN
Unit: [1] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: DARRYL LAPCINSKI
HQ OPS Officer: PETE SNYDER
Notification Date: 02/12/2014
Notification Time: 16:17 [ET]
Event Date: 02/12/2014
Event Time: 11:13 [CST]
Last Update Date: 02/12/2014
Notification Time: 16:17 [ET]
Event Date: 02/12/2014
Event Time: 11:13 [CST]
Last Update Date: 02/12/2014
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):
ROBERT DALEY (R3DO)
ROBERT DALEY (R3DO)
| 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 | 10 | Power Operation |
CIRCULATING WATER DISCHARGE MONITOR OUT OF SERVICE
"At 1113 CST on February 12, 2014, R-21 Circulating Water Discharge Monitor failed during routine surveillance testing and was declared nonfunctional. This monitor has no compensatory measure that will allow timely classification of two Emergency Action Levels (EALs) - NUE (Notification of Unusual Event) and Alert classifications - when out of service. This results in a Loss of Emergency Assessment Capability while R-21 is out of service. This is a reportable condition in accordance with 10 CFR 50.72(b)(3)(xiii).
"There are no radioactive leaks that will impact the Circulating Water System as evidenced by normal readings on R-21 prior to its failure. In addition all other liquid effluent radiation monitors that monitor releases to the Circulating Water Discharge are in-service and have normal readings. Corrective maintenance is in progress and will continue until the monitor is returned to service. Maintenance will not result in the unplanned release of 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 1113 CST on February 12, 2014, R-21 Circulating Water Discharge Monitor failed during routine surveillance testing and was declared nonfunctional. This monitor has no compensatory measure that will allow timely classification of two Emergency Action Levels (EALs) - NUE (Notification of Unusual Event) and Alert classifications - when out of service. This results in a Loss of Emergency Assessment Capability while R-21 is out of service. This is a reportable condition in accordance with 10 CFR 50.72(b)(3)(xiii).
"There are no radioactive leaks that will impact the Circulating Water System as evidenced by normal readings on R-21 prior to its failure. In addition all other liquid effluent radiation monitors that monitor releases to the Circulating Water Discharge are in-service and have normal readings. Corrective maintenance is in progress and will continue until the monitor is returned to service. Maintenance will not result in the unplanned release of 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: 49820
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: RANDY SAND
HQ OPS Officer: DANIEL MILLS
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: RANDY SAND
HQ OPS Officer: DANIEL MILLS
Notification Date: 02/12/2014
Notification Time: 09:27 [ET]
Event Date: 02/12/2014
Event Time: 08:15 [CST]
Last Update Date: 02/12/2014
Notification Time: 09:27 [ET]
Event Date: 02/12/2014
Event Time: 08:15 [CST]
Last Update Date: 02/12/2014
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):
ROBERT DALEY (R3DO)
ROBERT DALEY (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 |
SERVICE WATER RADIATION MONITOR REMOVED FROM SERVICE FOR PLANNED MAINTENANCE
"Planned preventive maintenance on service water piping will remove the service water radiation monitor from service. As a result, this represents a loss of emergency assessment capability under NUREG 1022, Revision 3, since the radiation monitor is used to assess NUE [Notification of Unusual Event] and Alert thresholds. The planned maintenance is expected to last 8 hours. During this time, the site Chemistry Department will perform sampling at this location every 30 minutes. The sampling is documented in a station procedure and allows the ability to detect NUE levels in a timely manner. As a result of sampling, reasonable assurance exists to monitor and detect rising radiation levels in order to protect the health and safety of the public.
"The NRC Resident Inspector will be notified prior to removing the service water radiation monitor from service."
"Planned preventive maintenance on service water piping will remove the service water radiation monitor from service. As a result, this represents a loss of emergency assessment capability under NUREG 1022, Revision 3, since the radiation monitor is used to assess NUE [Notification of Unusual Event] and Alert thresholds. The planned maintenance is expected to last 8 hours. During this time, the site Chemistry Department will perform sampling at this location every 30 minutes. The sampling is documented in a station procedure and allows the ability to detect NUE levels in a timely manner. As a result of sampling, reasonable assurance exists to monitor and detect rising radiation levels in order to protect the health and safety of the public.
"The NRC Resident Inspector will be notified prior to removing the service water radiation monitor from service."
Power Reactor
Event Number: 49821
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: MARTIN LICHTNER
HQ OPS Officer: DONG HWA PARK
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: MARTIN LICHTNER
HQ OPS Officer: DONG HWA PARK
Notification Date: 02/12/2014
Notification Time: 14:18 [ET]
Event Date: 02/12/2014
Event Time: 07:11 [EST]
Last Update Date: 02/12/2014
Notification Time: 14:18 [ET]
Event Date: 02/12/2014
Event Time: 07:11 [EST]
Last Update Date: 02/12/2014
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):
RAY POWELL (R1DO)
RAY POWELL (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 99 | Power Operation | 99 | Power Operation |
| 2 | N | Y | 99 | Power Operation | 99 | Power Operation |
SECONDARY CONTAINMENT BOUNDRY DOOR FOUND AJAR
"On February 12, 2014 at 0711 EST, secondary containment (Unit 1 reactor building) boundary door-612 was found propped ajar with a secondary containment boundary sign stuck in the door jam, holding the door open. Upon discovery, the sign was removed from the door jam and the door was verified closed. A status walk down was performed and no other doors were found in this condition.
"Although secondary containment differential pressure was maintained throughout the time period that the door was open, the door serves as a secondary containment boundary and is required to be closed for secondary containment operability.
"Secondary containment alignment for removal of the 818 foot elevation (refuel floor) hatch removal had been performed at 0105 EST, February 12, 2014 and the last record of access to the area by security card reader occurred at 0044 EST by the operator performing the ventilation alignment. The potential duration of inoperability based on the available information is approximately 6.5 hours. Past operability evaluation is being performed.
"This event is being reported under 10 CFR 50.72(b)(3)(v) and per the guidance of NUREG 1022 Rev. 3 section 3.2.7 as a loss of a safety function. There is no redundant Susquehanna secondary containment system."
The licensee notified the NRC Resident Inspector.
"On February 12, 2014 at 0711 EST, secondary containment (Unit 1 reactor building) boundary door-612 was found propped ajar with a secondary containment boundary sign stuck in the door jam, holding the door open. Upon discovery, the sign was removed from the door jam and the door was verified closed. A status walk down was performed and no other doors were found in this condition.
"Although secondary containment differential pressure was maintained throughout the time period that the door was open, the door serves as a secondary containment boundary and is required to be closed for secondary containment operability.
"Secondary containment alignment for removal of the 818 foot elevation (refuel floor) hatch removal had been performed at 0105 EST, February 12, 2014 and the last record of access to the area by security card reader occurred at 0044 EST by the operator performing the ventilation alignment. The potential duration of inoperability based on the available information is approximately 6.5 hours. Past operability evaluation is being performed.
"This event is being reported under 10 CFR 50.72(b)(3)(v) and per the guidance of NUREG 1022 Rev. 3 section 3.2.7 as a loss of a safety function. There is no redundant Susquehanna secondary containment system."
The licensee notified the NRC Resident Inspector.