Event Notification Report for March 10, 2018
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
03/09/2018 - 03/10/2018
Agreement State
Event Number: 53255
Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: ALPHA-OMEGA SERVICES, INC.
Region: 4
City: VINTON State: LA
County:
License #: LA-10025-L01,
Agreement: Y
Docket:
NRC Notified By: JOE NOBLE
HQ OPS Officer: HOWIE CROUCH
Licensee: ALPHA-OMEGA SERVICES, INC.
Region: 4
City: VINTON State: LA
County:
License #: LA-10025-L01,
Agreement: Y
Docket:
NRC Notified By: JOE NOBLE
HQ OPS Officer: HOWIE CROUCH
Notification Date: 03/12/2018
Notification Time: 13:54 [ET]
Event Date: 03/10/2018
Event Time: 15:15 [CST]
Last Update Date: 03/12/2018
Notification Time: 13:54 [ET]
Event Date: 03/10/2018
Event Time: 15:15 [CST]
Last Update Date: 03/12/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
MARC FERDAS (R1DO)
JESSE ROLLINS (R4DO)
ILTAB (EMAI)
NMSS EVENTS RESOURCE (EMAI)
MARC FERDAS (R1DO)
JESSE ROLLINS (R4DO)
ILTAB (EMAI)
NMSS EVENTS RESOURCE (EMAI)
LOUISIANA AGREEMENT STATE REPORT - LOST IRIDIUM-192 SOURCE
The following information was received from the state of Louisiana via email:
"On March 10, 2018, at approximately 3:15 pm [CST], [the RSO of Alpha-Omega Services, Inc.] contacted the Department [Louisiana Department of Environmental Quality] to inform us that [the common carrier] had not delivered an HDR Radioactive Sealed Source to Lancaster General Suburban Hospital (LGSH), Lancaster, PA 17604.
"The shipping date from Alpha-Omega Services in Vinton, LA. was 02/26/2018. The source has not been delivered to LGSH. On March 10, 2018, [the RSO] for [the common carrier] communicated to [Alpha-Omega's RSO], they could not locate the source in the tracking system or in the Memphis, TN hub. It needed to be reported as lost or missing to the NRC. On 03/12/2018, the source has not been located.
"The Ir-192 source is a GammaMed 232, 383 GBq, (10.4 Ci), S/N 24-01-6226-001-020818-12254-81, Transportation Index - 6."
Louisiana Event Report ID No.: LA-180004
THIS MATERIAL EVENT CONTAINS A "CATEGORY 3" LEVEL OF RADIOACTIVE MATERIAL
Category 3 sources, if not safely managed or securely protected, could cause permanent injury to a person who handled them, or were otherwise in contact with them, for some hours. It could possibly - although it is unlikely - be fatal to be close to this amount of unshielded radioactive material for a period of days to weeks. These sources are typically used in practices such as fixed industrial gauges involving high activity sources (for example: level gauges, dredger gauges, conveyor gauges and spinning pipe gauges) and well logging. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf
Note: This device is assigned an IAEA Category 3 value based on the actual radioactivity of the source, not on the device type. (Reference IAEA RG-G-1.9)
The following information was received from the state of Louisiana via email:
"On March 10, 2018, at approximately 3:15 pm [CST], [the RSO of Alpha-Omega Services, Inc.] contacted the Department [Louisiana Department of Environmental Quality] to inform us that [the common carrier] had not delivered an HDR Radioactive Sealed Source to Lancaster General Suburban Hospital (LGSH), Lancaster, PA 17604.
"The shipping date from Alpha-Omega Services in Vinton, LA. was 02/26/2018. The source has not been delivered to LGSH. On March 10, 2018, [the RSO] for [the common carrier] communicated to [Alpha-Omega's RSO], they could not locate the source in the tracking system or in the Memphis, TN hub. It needed to be reported as lost or missing to the NRC. On 03/12/2018, the source has not been located.
"The Ir-192 source is a GammaMed 232, 383 GBq, (10.4 Ci), S/N 24-01-6226-001-020818-12254-81, Transportation Index - 6."
Louisiana Event Report ID No.: LA-180004
THIS MATERIAL EVENT CONTAINS A "CATEGORY 3" LEVEL OF RADIOACTIVE MATERIAL
Category 3 sources, if not safely managed or securely protected, could cause permanent injury to a person who handled them, or were otherwise in contact with them, for some hours. It could possibly - although it is unlikely - be fatal to be close to this amount of unshielded radioactive material for a period of days to weeks. These sources are typically used in practices such as fixed industrial gauges involving high activity sources (for example: level gauges, dredger gauges, conveyor gauges and spinning pipe gauges) and well logging. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf
Note: This device is assigned an IAEA Category 3 value based on the actual radioactivity of the source, not on the device type. (Reference IAEA RG-G-1.9)
Power Reactor
Event Number: 53253
Facility: COOPER
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: RYAN LYNN
HQ OPS Officer: OSSY FONT
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: RYAN LYNN
HQ OPS Officer: OSSY FONT
Notification Date: 03/10/2018
Notification Time: 13:54 [ET]
Event Date: 03/10/2018
Event Time: 07:09 [CST]
Last Update Date: 03/10/2018
Notification Time: 13:54 [ET]
Event Date: 03/10/2018
Event Time: 07:09 [CST]
Last Update Date: 03/10/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
MICHAEL VASQUEZ (R4DO)
MICHAEL VASQUEZ (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 |
HIGH PRESSURE COOLANT INJECTION SYSTEM DECLARED INOPERABLE
"HPCI [High Pressure Coolant Injection] was removed from service (unplanned) on 3/10/2018 at time 0709 [CST] by closing HPCI-MO-15, STEAM SUPPLY INBOARD ISOLATION. The inboard steam supply isolation valve is inside Primary Containment. The steam supply valve was closed in an effort to isolate [unidentified] leakage to Primary Containment from a suspected packing leak from HPCI-MO-15. After closing the HPCI-MO-15, Reactor Coolant System Leakage parameters returned to within Technical Specification [TS] LCO [Limiting Condition of Operations] 3.4.4 limits.
"Entered into Technical Specification LCO 3.5.1 Condition C - HPCI System Inoperable.
"Required Actions for Condition 'C' are to verify by administrative means RCIC [Reactor Core Isolation Cooling] System is operable within 1 hour and restore HPCI System to operable status within 14 days. RCIC was verified operable by administrative means concurrent with declaration of HPCI inoperable.
"Normal plant shutdown activities are being planned [for 03/11/2018 at 1200 CDT] to support entry into Primary Containment to initiate any necessary repairs.
"HPCI is a single train safety system. This report is submitted as a condition that at time of discovery could prevent the fulfillment of the safety function of an SSC [System, Structure, or Component] needed to mitigate the consequences of an accident.
"This condition has been entered into the CNS [Cooper Nuclear Station] Corrective Action Program. CR-CNS-2018-01346"
LCO 3.4.4 was entered during unplanned maintenance of the HPCI system. When the HPCI-MO-15 was cycled from closed to open, unidentified leakage in the containment increased above 2 gallons per minute (gpm) in less than a 24 hour period. Also, total unidentified leakage exceeded 5 gpm. The licensee closed the HPCI-MO-15 valve resulting in a decrease in unidentified leakage below TS shutdown limit.
The NRC Resident Inspector was notified.
"HPCI [High Pressure Coolant Injection] was removed from service (unplanned) on 3/10/2018 at time 0709 [CST] by closing HPCI-MO-15, STEAM SUPPLY INBOARD ISOLATION. The inboard steam supply isolation valve is inside Primary Containment. The steam supply valve was closed in an effort to isolate [unidentified] leakage to Primary Containment from a suspected packing leak from HPCI-MO-15. After closing the HPCI-MO-15, Reactor Coolant System Leakage parameters returned to within Technical Specification [TS] LCO [Limiting Condition of Operations] 3.4.4 limits.
"Entered into Technical Specification LCO 3.5.1 Condition C - HPCI System Inoperable.
"Required Actions for Condition 'C' are to verify by administrative means RCIC [Reactor Core Isolation Cooling] System is operable within 1 hour and restore HPCI System to operable status within 14 days. RCIC was verified operable by administrative means concurrent with declaration of HPCI inoperable.
"Normal plant shutdown activities are being planned [for 03/11/2018 at 1200 CDT] to support entry into Primary Containment to initiate any necessary repairs.
"HPCI is a single train safety system. This report is submitted as a condition that at time of discovery could prevent the fulfillment of the safety function of an SSC [System, Structure, or Component] needed to mitigate the consequences of an accident.
"This condition has been entered into the CNS [Cooper Nuclear Station] Corrective Action Program. CR-CNS-2018-01346"
LCO 3.4.4 was entered during unplanned maintenance of the HPCI system. When the HPCI-MO-15 was cycled from closed to open, unidentified leakage in the containment increased above 2 gallons per minute (gpm) in less than a 24 hour period. Also, total unidentified leakage exceeded 5 gpm. The licensee closed the HPCI-MO-15 valve resulting in a decrease in unidentified leakage below TS shutdown limit.
The NRC Resident Inspector was notified.