| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
09/16/2015 - 09/17/2015 ** EVENT NUMBERS ** |
 | Non-Agreement State | Event Number: 51376 | Rep Org: KAKIVIK ASSET MANAGEMENT, LLC
Licensee: KAKIVIK ASSET MANAGEMENT, LLC
Region: 4
City: ANCHORAGE State: AK
County:
License #: 50-27667-01
Agreement: N
Docket:
NRC Notified By: PATTON PETTIJOHN
HQ OPS Officer: DONALD NORWOOD | Notification Date: 09/08/2015
Notification Time: 16:41 [ET]
Event Date: 09/07/2015
Event Time: 12:05 [YDT]
Last Update Date: 09/08/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
| Person (Organization):
JAMES DRAKE (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)
| Event Text FAILURE OF CAMERA SOURCE LOCK SLIDE TO LOCK
The following event occurred at the Kuparuk Oil Field on the North Slope of Alaska: After performing a routine exposure with a QSA model 880D camera containing a 65.8 curie Iridium-192 source, the source was cranked back into the camera. The radiographer noted that the lock slide did not lock the source as it should have. While using a survey meter, the radiographer then approached the camera. After noting that the source was fully shielded, the radiographer was able to manually lock the slide into the locked position. Supervision was then called. The camera was taken out-of-service. The camera locking mechanism was cleaned and tested. After determining that the locking mechanism was operating properly, the camera was returned to service. |
| Non-Agreement State | Event Number: 51377 | Rep Org: UNIVERSITY OF NOTRE DAME
Licensee: UNIVERSITY OF NOTRE DAME
Region: 3
City: NOTRE DAME State: IN
County:
License #: 13-01983-15
Agreement: N
Docket:
NRC Notified By: ANDREW WELDING
HQ OPS Officer: JEFF ROTTON | Notification Date: 09/08/2015
Notification Time: 16:52 [ET]
Event Date: 09/08/2015
Event Time: 09:35 [EDT]
Last Update Date: 09/09/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
| Person (Organization):
PATTY PELKE (R3DO)
NMSS_EVENTS_NOTIFIC (EMAI)
| Event Text LEAKING NI-63 SOURCE
While preparing a Varian Ni-63 source for shipment, the Radiation Safety Specialist was performing wipes for a leak test. After multiple attempts, the leak test kept returning the same results, which were 0.012 milliCi and the limit is 0.005 milliCi. The source is part of a Hewlett-Packard gas chromatograph, model number 0201972-00. The source is a Varian Ni-63 15 milliCi source with a current activity of 14.1 milliCi. The source serial number is A-15296. The source has been wrapped and stored in a sealed bag and placed in the facilities waste building.
* * * UPDATE ON 9/9/15 AT 0823 EDT FROM ANDREW WELDING TO DONG PARK * * *
The leak test results were 0.012 microCi and the limit is 0.005 microCi; not 0.012 milliCi and 0.005 milliCi.
Notified the R3DO (Pelke) and NMSS Events Resource via e-mail. |
| Agreement State | Event Number: 51378 | Rep Org: UTAH DIVISION OF RADIATION CONTROL
Licensee: UTAH DEPARTMENT OF TRANSPORTATION
Region: 4
City: SALT LAKE CITY State: UT
County:
License #: UT 1800131
Agreement: Y
Docket:
NRC Notified By: PHILIP GRIFFIN
HQ OPS Officer: DONALD NORWOOD | Notification Date: 09/08/2015
Notification Time: 17:59 [ET]
Event Date: 09/04/2015
Event Time: 14:45 [MDT]
Last Update Date: 09/14/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
JAMES DRAKE (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)
| Event Text AGREEMENT STATE REPORT - DAMAGED PORTABLE DENSITY GUAGE
The following information was received via facsimile:
"The RSO of the Utah Department of Transportation (UDOT), called [the State of Utah, Department of Environmental Quality, Division of Waste Management and Radiation Control] to report an incident involving one of their thin lift, Troxler 4640 gauges containing a 9 mCi Cs-137 source. The incident occurred at about 1400 MDT on Friday, September 4, 2015, at a construction site on eastbound I-215 at Redwood Road. A survey vehicle entered the construction zone at freeway speeds and ran over the gauge while the operator was making a measurement. The gauge was 'destroyed,' but the sealed source remained intact. However, the gauge's shielding for the source was demolished.
"The licensee performed surveys of the accident site and of the vehicle involved. No contamination was found. The licensee transported the damaged gauge and source back to the licensee's gauge storage room. The licensee has ordered a replacement base for the gauge to provide shielding for the source so that the source can be safely shipped back to the gauge manufacturer.
"The licensee has a report from the gauge operator, reports from eyewitnesses to the incident, and a report from the Highway Patrol. It will take the licensee about a week to compile all of the information into a written report to send to the Division [of Waste Management and Radiation Control]."
Utah Event Report ID No.: UT150004
* * * UPDATE PROVIDED BY PHILIP GRIFFIN TO JEFF ROTTON AT 1347 EDT ON 09/14/2015 * * *
The following information was provided by the State of Utah via email:
The event took place at 1445 MDT on September 4, 2015 versus 1400 initially reported. The gauge contains 8 mCi Cs-137 versus the 9 mCi that was originally reported and the gauge serial number is 65867. A black 4 door car entered the construction zone and ran over the gauge followed by two other vehicles. The manufactured is sending an appropriate shipping container for the licensee to use when returning the source to the manufacturer.
"The licensee is authorized to remove portable gauge source rods from their gauges to perform non-routine maintenance on their gauges. Because of this, the licensee has a source rod shield that will be used (per the manufacturer's instructions) to shield the source rod taken from the damaged gauge during transport to the manufacturer."
Notified R4DO (Farnholtz) and NMSS Events Notification group via email. |
| Agreement State | Event Number: 51380 | Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: LGC GEOTECHNICAL, INC
Region: 4
City: SAN CLEMENTE State: CA
County:
License #: 6934-30
Agreement: Y
Docket:
NRC Notified By: DONALD OESTERLE
HQ OPS Officer: JEFF ROTTON | Notification Date: 07/08/2015
Notification Time: 16:02 [ET]
Event Date: 07/08/2015
Event Time: [PDT]
Last Update Date: 09/09/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
JAMES DRAKE (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)
CNSNS (MEXICO) (EMAI)
ILTAB (EMAI)
|
| This material event contains a "Less than Cat 3 " level of radioactive material. | Event Text CALIFORNIA AGREEMENT STATE REPORT - STOLEN DENSITY GAUGE
The following information was provided by the State of California on 07/08/2015 via email:
"On July 8, 2015, RHB [CA Radiation Health Branch] was notified that a SUV containing a CPN MC-1 DR # MD60608339 portable soil gauge containing 50 mCi of Am-241/Be and 10 mCi of Cs-137 was stolen in San Clemente. An authorized gauge user parked his SUV, with the gauge secured in the rear of the vehicle, in the driveway of his house. The vehicle containing the gauge was stolen during the night. The vehicle and its contents were reported stolen to the police (Orange County Sheriff / San Clemente Station). RHB will continue to work with the licensee regarding this ongoing investigation."
CA 5010 Number - 070815
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 |
| Agreement State | Event Number: 51381 | Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: ALPHA-OMEGA (A&O) SERVICES, INC.
Region: 4
City: VINTON State: LA
County:
License #: LA-10025-L01
Agreement: Y
Docket:
NRC Notified By: JOE NOBLE
HQ OPS Officer: JEFF ROTTON | Notification Date: 09/09/2015
Notification Time: 15:50 [ET]
Event Date: 09/02/2015
Event Time: [CDT]
Last Update Date: 09/09/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
JAMES DRAKE (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)
|
| This material event contains a "Category 3 " level of radioactive material. | Event Text LOUISIANA AGREEMENT STATE REPORT - DELIVERY OF CATEGORY 3 SOURCE TO WRONG ADDRESS
The following information was provided State of Louisiana via email:
"On 09/02/2015, the RSO for A&O [Alpha-Omega Services, Inc.] called in a mis-delivery/wrong delivery of 11.6 Ci Ir-192 source intended for the Radiation Oncology Center at Sibley Memorial Hospital (SMH) in Washington, DC. SMH is a client/customer of A&O in association with ELEKTA. SMH purchased and attempted to possess the radioactive source under a license NRC 08-07398-03. A&O packaged the Ir-192 source and addressed it to SMH, Dept. of Radiation Oncology, 5255 Loughboro Road NW, Washington, DC 20016. The source was shipped from the [A&O] Vinton, LA address to SMH on August 31, 2015. However, [common carrier] delivered the source to Howard University Hospital, Cancer Center, 2041 Georgia Avenue NW, Washington, DC 20060 [on September 2, 2015]."
Common carrier was notified of the delivery error and took possession of the source on September 3, 2015 and delivered to the proper address [SMH] that day. The source shielding and shipping container was intact during the incident. It was not damaged nor was the container opened until it reached the final destination.
Source information: Elekta Model 105.002 source: 11.6 Ci Ir-192, Serial Number - D36F5755
LA Event Report ID No.: LA-150015; T165946
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: 51397 | Facility: PALISADES
Region: 3 State: MI
Unit: [1] [ ] [ ]
RX Type: [1] CE
NRC Notified By: KRIS RUETZ
HQ OPS Officer: HOWIE CROUCH | Notification Date: 09/16/2015
Notification Time: 03:59 [ET]
Event Date: 09/16/2015
Event Time: 01:17 [EDT]
Last Update Date: 09/16/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
KENNETH RIEMER (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | A/R | Y | 85 | Power Operation | 0 | Hot Standby | Event Text AUTOMATIC REACTOR TRIP DUE TO TURBINE TRIP
"At 0117 [EDT] on 9/16/2015 a reactor trip occurred (4-hr non-emergency). The plant was at approximately 85% power performing a coastdown in preparation for a refueling outage when a Digital Electro-Hydraulic (DEH) alarm was received in the control room. Shortly following receipt of the alarm the turbine tripped. This resulted in an RPS actuation and a reactor trip on Loss of Load. The crew entered EOP-1 Standard Post Trip Actions and completed all required actions. The crew subsequently entered EOP-2 Reactor Trip Recovery.
"All full-length control rods inserted fully. Auxiliary Feedwater System actuated in response to low steam generator water levels (8-hr non-emergency). Steam generator water levels are in progress of being returned to normal operating levels. No known primary to secondary leakage. Atmospheric Steam Dump Valves lifted after the trip and subsequently reseated.
"The plant is currently stable in Mode 3 at NOP/NOT being maintained by the Turbine Bypass Valve.
"Initial investigation into the cause of the turbine trip appears to be from a DEH power supply failure.
"The NRC Resident Inspector was notified of the reactor trip at 0139 on 9/16/2015." |
| Power Reactor | Event Number: 51398 | Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: TODD CHRISTENSEN
HQ OPS Officer: HOWIE CROUCH | Notification Date: 09/16/2015
Notification Time: 10:10 [ET]
Event Date: 09/16/2015
Event Time: 02:00 [CDT]
Last Update Date: 09/16/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
BINOY DESAI (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text HIGH PRESSURE COOLANT INJECTION SYSTEM DECLARED INOPERABLE DUE TO VALVE STEM PACKING STEAM LEAK
"At 0200 CDT on 9/16/2015, the High Pressure Coolant Injection (HPCI) System was manually isolated to stop a steam leak from the stem packing of the HPCI Steam Supply Valve 2-FCV-073-0016. The leak occurred following performance of 2-SR-3.6.1.3.5 (HPCI) HPCI System Motor Operated Valve Operability, which cycled 2-FCV-073-0016. No Area Radiation Monitoring (ARM) or PCIS Area High Temperature alarms were received and no automatic isolation setpoints were reached. HPCI was declared inoperable per Technical Specification (TS) Limiting Condition for Operation (LCO) 3.5.1 Emergency Core Cooling Systems (ECCS)- Operating, Condition C.
"This constitutes an unplanned HPCI system inoperability and requires an 8-hour ENS notification in accordance with 10 CFR 50.72(b)(3)(v)(D), due to the failure of a single train system affecting accident mitigation, and a 60-day written report in accordance with 10 CFR 50.73(a)(2)(v)(D).
"The NRC resident inspector has been notified." |
| Power Reactor | Event Number: 51401 | Facility: BYRON
Region: 3 State: IL
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: SHANE HARVEY
HQ OPS Officer: JEFF ROTTON | Notification Date: 09/16/2015
Notification Time: 21:17 [ET]
Event Date: 09/16/2015
Event Time: 22:00 [CDT]
Last Update Date: 09/16/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
KENNETH RIEMER (R3DO)
|
| 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 | Event Text LOSS OF SEISMIC MONITORING INSTRUMENTATION DURING PLANNED MAINTENANCE
"At 2200 CDT on September 16, 2015, Byron Station's Seismic Instrumentation will be removed from service to support an electrical bus outage. During this time, the seismic instrumentation will not be able to generate Main Control Room annunciation or provide ground acceleration information necessary for Emergency Action Level (EAL) threshold determination until the seismic instrumentation is restored, which is scheduled for 1700 CDT on September 19, 2015. Since the duration of maintenance activity may last greater than 72 hours, with viable compensatory measures in place and communicated to applicable Emergency Response Decision Makers, this condition will result in a Loss of Emergency Assessment Capability while the Seismic Instrumentation is out of service and results in a reportable condition in accordance with 10 CFR 50.72(b)(xiii).
"The Licensee has notified the NRC Resident Inspector and informed the State of Illinois Resident Engineer ." |
| Power Reactor | Event Number: 51402 | Facility: SURRY
Region: 2 State: VA
Unit: [ ] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: GEOFFREY HILL
HQ OPS Officer: HOWIE CROUCH | Notification Date: 09/17/2015
Notification Time: 00:36 [ET]
Event Date: 09/16/2015
Event Time: 20:14 [EDT]
Last Update Date: 09/17/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
BINOY DESAI (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text AUTOMATIC START AND LOADING OF THE #2 EMERGENCY DIESEL GENERATOR
"While performing degraded voltage/under voltage Instrumentation & Control testing with both Units at 100%, the Unit 2 'H' Emergency Bus was lost when an inadvertent under voltage matrix was satisfied. The #2 Emergency Diesel Generator auto-started and assumed the 2H Emergency Bus as designed. The cause of the under voltage matrix coincidence is currently being investigated by station personnel. All testing activities have been terminated and recovery efforts are in progress in accordance with station procedures. Current status is both Units stable at 100% with the #2 Emergency Diesel Generator carrying the 2H Emergency Bus."
The loss of the bus places the Unit in a 7-day action statement for the loss of offsite power to the 2H bus and a 14-day action statement for the auxiliary feed cross tie to Unit 1.
The licensee has notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 51403 | Facility: PALO VERDE
Region: 4 State: AZ
Unit: [ ] [2] [ ]
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: ROBERT PIERCE
HQ OPS Officer: JEFF HERRERA | Notification Date: 09/17/2015
Notification Time: 02:53 [ET]
Event Date: 09/16/2015
Event Time: 23:01 [MST]
Last Update Date: 09/17/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
| Person (Organization):
THOMAS FARNHOLTZ (R4DO)
WILLIAM GOTT (IRD)
MARC DAPAS (RA)
SCOTT MORRIS (NRR)
WILLIAM DEAN (NRR)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text NOTIFICATION OF UNUSUAL EVENT DUE TO RAPID COMBUSTION OF A LOAD CENTER BREAKER
"The following event description is based on information currently available. If through subsequent reviews of this event, additional information is identified that is pertinent to this event, or alters the information being provided at this time a follow-up notification will be made via the ENS or under the reporting requirements of 10CFR50.73.
"Non Class Load Center Breaker, 2ENGN-L04 failed, resulting an a visible observation of rapid combustion and resultant charring (burned area) of the breaker enclosure and housing. No physical deformation to the breaker housing or surrounding area has been identified. The rapid combustion self-extinguished immediately following the audible and visible combustion event. As a result, an Emergency Classification of HU2.2, EXPLOSION was declared due to the Load Center breaker failure and noise and visible indication observed in the field.
"The plant was, and continues to operate at 100% full power operations on normal power alignment. The 2ENGN-L04 Non-Class Load Center breaker supplies power to non-essential service loads and has no immediate impact to plant operation or safety mitigating systems. The plant remains stable and the event did not adversely affect the safe operation of the plant or health and safety of the public.
"The NRC Resident Inspector has been notified." | |