| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
07/03/2012 - 07/05/2012 ** EVENT NUMBERS ** |
 | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Fuel Cycle Facility | Event Number: 48048 | Facility: WESTINGHOUSE HEMATITE
RX Type: URANIUM FUEL FABRICATION
Comments: LEU CONVERSION (UF6 to UO2)
COMMERCIAL LWR FUEL
Region: 3
City: HEMATITE State: MO
County: JEFFERSON
License #: SNM-33
Agreement: N
Docket: 07000036
NRC Notified By: KEVIN DAVIS
HQ OPS Officer: PETE SNYDER | Notification Date: 06/26/2012
Notification Time: 17:16 [ET]
Event Date: 06/26/2012
Event Time: 15:30 [CDT]
Last Update Date: 07/04/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
PART 70 APP A (a)(4) - ALL SAFETY ITEMS UNAVAILABLE
| Person (Organization):
NICK VALOS (R3DO)
JONATHAN BARTLEY (R2DO)
SCOTT MORRIS (IRD)
MERAJ RAHIMI (NMSS)
| Event Text DRUM MISTAKENLY SET ASIDE WITH NO CRITICALITY SAFETY CONTROLS
During the excavation of the burial pits area the licensee has requirements that 2 people survey the excavated materials. Excavated material was placed into a 5 gallon plastic container. After placing the material into the container a reading is taken on the bottom of the container in counts per minute which is then equated to a gram level (mass) of material present. If the mass of material is less than 15 grams (about 300,000 counts per minute) then no criticality safety controls are required.
One container, packed to a level of 325,000 counts per minute, was put aside briefly near a waste bin where those materials requiring no controls can be placed. Both people assigned to the work mistook this container for a container requiring no controls. A level of 325,000 counts per minutes equates to a mass of 20 grams of Uranium 235. At that level this item was far from the amount of material needed for a criticality accident but additional controls were required.
When the personnel realized their mistake they took that container to another area for overpack into a drum that provides additional spacing needed to provide additional criticality safety protection. At this time the container has the appropriate level of controls. The amount of material present was small enough that it could not have caused a criticality accident.
* * * RETRACTION ON 7/4/12 AT 1556 EDT FROM KEVIN DAVIS TO DONG PARK * * *
"Retraction of the initial notification is appropriate since subsequent, more detailed surveys via gamma spectroscopy (ISOCS) [In Situ Object Counting System] determined that only 2.83g of U-235 were present in the 5 gallon container. The subsequent, more detailed survey was conducted on 6/28/12, after the initial notification was made. This mass quantity is below the threshold for being exempt from criticality safety controls (i.e., no more than 15 g of U-235 in a 5L or larger container). Thus, an unsafe condition was not present when the container was set aside without safety controls since no safety controls are required for 2.83g of U-235 in a 5 gallon container. Based on this retraction, a written report will not be submitted to NRC.
"The container was retrieved and the container was placed in a drum with a safety collar that provides additional spacing needed to provide additional criticality safety protection. The cause of the event was personnel inattention to the procedure, which contained the correct numerical decision points and controls. Personnel were retrained, particularly on: (a) Independence of redundant surveys and reviews; (b) Use of the procedure to provide numerical setpoints and action steps. Management and independent oversight of burial pit work activities are emphasizing independence of redundant surveys/reviews and use of the procedure."
Notified R3DO (Daley), R2DO (Bonser), IRD (Marshall), and NMSS (Damon) via email. |
| Agreement State | Event Number: 48049 | Rep Org: ILLINOIS EMERGENCY MGMT. AGENCY
Licensee: INTERRA INC.
Region: 3
City: BOLINGBROOK State: IL
County:
License #: IL-02000-01
Agreement: Y
Docket:
NRC Notified By: GIBB VINSON
HQ OPS Officer: PETE SNYDER | Notification Date: 06/26/2012
Notification Time: 16:52 [ET]
Event Date: 06/26/2012
Event Time: [CDT]
Last Update Date: 06/26/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
NICK VALOS (R3DO)
FSME EVENTS RESOURCE (EMAI)
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text AGREEMENT STATE REPORT - TROXLER GAUGE STRUCK BY VEHICLE AT CONSTRUCTION SITE
The State of Illinois submitted the following report via email:
"On the morning of June 26, 2012, the Agency's Communication Center contacted the Radiological Duty Officer about a Troxler [Model 3411-B] gauge that had been hit by a truck on the Westbound I-90 in Chicago. The licensee, Interra, Inc., reported that an asphalt truck crossed the barriers and ran over the gauge while it was in use in an inactive traffic lane. The source rod was subsequently thrown from the gauge housing. [Illinois Emergency Management] Agency inspectors were dispatched to the scene. State police were also dispatched for traffic control.
"In the interim, the licensee located the source rod two lanes over near the center median using their own survey meter. With instruction from the duty officer, they were able to scoop the rod up in an asphalt shovel and put it in a 5 gallon bucket full of sand for shielding. Approximately one hour later, [Illinois Emergency Management] Agency inspectors arrived and were able to secure the source rod back into the damaged gauge housing. A leak test was done and no removable contamination was noted. The shield and shutter were intact and radiation levels were 0.5 mR/hr at a meter once secured. The device was transported back the licensees storage area for further investigation.
"[Illinois Emergency Management] Agency inspectors arrived at the licensee's facility at 2:00 pm that same afternoon to inspect the gauge, the storage area, and interview the RSO. The gauge was in view of the authorized user about 5 feet away when the truck crossed the barrier so it does not appear to be a surveillance violation by the licensee. The condition of the gauge was confirmed. The gauge is secure in its Type A container and radiation levels are 0.5 TI [Transportation Index]. All records for transportation were present and correct. The licensee appears to have followed their operating procedures correctly for this type of event. Pending leak test results, film badge results and return of the device to Troxler, we are considering this matter closed."
The gauge is a Troxler Model 3411-B, Serial number 40-9314, with a Cs-137 0.009 Ci and Am-241 0.04 Ci source.
IL Item Number: IL12010
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: 48050 | Rep Org: OR DEPT OF HEALTH RAD PROTECTION
Licensee: METRO METALS
Region: 4
City: PORTLAND State: OR
County: MULTNOMAH
License #:
Agreement: Y
Docket: 12-0551
NRC Notified By: KEVIN SIEBERT
HQ OPS Officer: STEVE SANDIN | Notification Date: 06/27/2012
Notification Time: 11:30 [ET]
Event Date: 06/25/2012
Event Time: 13:00 [PDT]
Last Update Date: 06/27/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
JEFF CLARK (R4DO)
FSME RESOURCE (EMAI)
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text STATIC ELIMINATOR BAR FOUND IN SCRAP YARD
"[Metro Metals] phoned that a flatbed truck with metal scrap from a recycler in WA (Paymore Recycling & Salvage, Montesano, WA) set off their portal monitor. Hand-held exposure meters were used to survey the load and levels were found at 4000 microrem/hr. This load is waiting for RPS [Radiation Protection Services] to check.
"Responded to Metro Metals. Found a static bar. Wrapped and sent back to recycler. Max reading, with Ludlum 2401 EC, at front edge of bar was 6 mR/hr. Exploranium identified Am-241. Static bar was about 5 to 6 feet in length and was cut in half. Item was wrapped in plastic and placed in a drum for return to the recycler."
Radiation Protection Services No: 12-0020
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: 48061 | Facility: FERMI
Region: 3 State: MI
Unit: [2] [ ] [ ]
RX Type: [2] GE-4
NRC Notified By: DEREK ETUE
HQ OPS Officer: CHARLES TEAL | Notification Date: 07/02/2012
Notification Time: 08:25 [ET]
Event Date: 07/02/2012
Event Time: 08:00 [EDT]
Last Update Date: 07/03/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
NICK VALOS (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown | Event Text SPDS AND ERDS OUT OF SERVICE FOR MAINTENANCE
"Beginning July 2, 2012, at approximately 0800, the Fermi 2 Integrated Plant Computer System (IPCS) will be removed from service to support installation of a Cyber Security Modification. The Safety Parameters Display System (SPDS) and Emergency Response Data System (ERDS) reside on the IPCS platform and will be out of service when the IPCS is removed from service. These systems will be unavailable to the Control Room and all other Emergency Response Facilities (ERFs) for approximately 20 hours. By 0300 on July 3, 2012, it is planned to restore IPCS, including SPDS and ERDS, to the Control Room, Operational Support Center, the Technical Support Center, and alternate facilities. During this time dose assessment capability will only be available in the manual data input mode. The majority of the Control Room indications remain available to the plant staff, and will be used for emergency response, if needed. Information will be communicated to the NRC using other available communication systems as needed. A follow-up notification will be submitted when the IPCS is completely restored. This notification is being made per the requirements of 8 Hour Non-Emergency Notification 10 CFR 50.72(b)(3)(xiii), any event that results in a major loss of emergency assessment capability."
The licensee has notified the NRC Resident Inspector.
* * * UPDATE ON 7/03/12 AT 0113 EDT FROM GROFF TO HUFFMAN * * *
"On July 3, 2012, at 01:00, the Fermi 2 Integrated Plant Computer System (IPCS) has been returned to service. Emergency assessment capabilities have been restored to all onsite emergency response facilities. Due to equipment problems, the Cyber Security Modification was not installed and the original IPCS configuration was restored."
The licensee has notified the NRC Resident Inspector. R3DO (Daley) notified.
* * * UPDATE ON 7/03/12 AT 0556 EDT FROM GROFF TO HUFFMAN * * *
"At approximately 02:04 on July 3, the Fermi 2 Integrated Plant Computer System (IPCS) failed. The Safety Parameters Display System (SPDS) and Emergency Response Data System (ERDS) reside on the IPCS platform. IPCS had previously been removed from service on 7/2/12 for a Cyber Security Modification and restored at 0100 on 7/3/12.
"At 0354, plant personnel were able to reboot IPCS and restore the system to normal with a Prime and Backup CPUs. Emergency assessment capabilities have been restored to all onsite emergency response facilities.
"This notification is being made per the requirements of 8 Hour Non-Emergency Notification 10 CFR 50.72(b)(3)(xiii), any event that results in a major loss of emergency assessment capability."
The licensee has notified the NRC Resident Inspector. R3DO (Daley) notified. |
| Power Reactor | Event Number: 48066 | Facility: FERMI
Region: 3 State: MI
Unit: [2] [ ] [ ]
RX Type: [2] GE-4
NRC Notified By: MARK EGHIGIAN
HQ OPS Officer: DONG HWA PARK | Notification Date: 07/03/2012
Notification Time: 13:21 [ET]
Event Date: 07/03/2012
Event Time: 09:40 [EDT]
Last Update Date: 07/03/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
ROBERT DALEY (R3DO)
MARK KING (NRR)
JANE MARSHALL (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 | Event Text OFFSITE NOTIFICATION DUE TO A FATALITY
"At 0940 hours on July 3, 2012, Detroit Edison notified the Michigan Occupational Safety and Health Administration (MIOSHA) that an employee had suffered a fatality.
"On July 2, 2012, at 1504 hours, a Detroit Edison employee reported to the nurse's office with symptoms of shortness of breath and chest pain. The individual was transported offsite via ambulance to a local hospital for care. At approximately 1700 hours on July 2, 2012, notification was received that the individual had passed away.
"There was no radioactive contamination involved in this event. The licensee has not notified any other government agencies besides MIOSHA.
"This ENS report is being made in accordance with 50.72(b)(2)(xi). The NRC Resident Inspector was notified." |
| Power Reactor | Event Number: 48067 | Facility: HATCH
Region: 2 State: GA
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: JIM ANDERSON
HQ OPS Officer: DONG HWA PARK | Notification Date: 07/03/2012
Notification Time: 16:53 [ET]
Event Date: 07/03/2012
Event Time: 10:32 [EDT]
Last Update Date: 07/03/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
JONATHAN BARTLEY (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 98 | Power Operation | | 2 | N | Y | 100 | Power Operation | 99 | Power Operation | Event Text TSC OUTAGE RESULTING FROM MAINTENANCE
"Planned maintenance activities are being performed today (July 3, 2012) to remove temporary power from and restore normal power to the Technical Support Center (TSC) 480 VAC Distribution Panel 1R25-S012. This panel provides power to the TSC Emergency HVAC (TSC air handling unit, TSC condensing unit, TSC filter train and the fan unit for the TSC filter train) rendering the TSC non-functional (TRM - Section T 3.10.1 EMERGENCY RESPONSE FACILITIES) during the performance of this work activity. This work activity is planned to be performed and completed expeditiously within about 5 hours including establishing and removing the clearances. The temporary power was installed on 6/19/12 to support work activities on the Hatch Nuclear Plant's 1R24-S026-600/208V MCC under Work Order Number 1050889203 which is the normal power supply.
"If an emergency condition occurs that requires activation of the Technical Support Center, plans are to utilize the TSC during the time this work activity is being performed, as long as habitability conditions allow. Procedure 73EP-EIP-063-0, Technical Support Center Activation provides instructions to direct TSC management to the Control Room and TSC support personnel to the Simulator Building to continue TSC activities if it is necessary to relocate from the primary TSC.
"This event is reportable per 10CFR50.72(b)(3)(xiii) as described in NUREG-1022, Rev. 1 since this work activity affects an emergency response facility for the duration of the evolution.
"The TSC was returned to service today at 1645 EDT on 7/3/2012."
The licensee has notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 48069 | Facility: PERRY
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: THOMAS MORSE
HQ OPS Officer: DONG HWA PARK | Notification Date: 07/03/2012
Notification Time: 20:35 [ET]
Event Date: 07/03/2012
Event Time: 17:38 [EDT]
Last Update Date: 07/03/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
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 | Event Text INADVERTENT EMERGENCY SIREN ACTUATION
"This event is being reported in accordance with 10CFR50.72(b)(2)(xi). On July 3, 2012, at approximately 1738 hours, an inadvertent actuation of the Perry Nuclear Power Plant's (PNPP) alert notification system occurred. Seventy-five of seventy-six sirens sounded for three minutes, affecting Ashtabula, Geauga, and Lake Counties. Following the actuation, county agencies received calls from members of the public.
"PNPP's capability to notify the public in an emergency has been retained. The siren actuation was not related to any condition or event at the PNPP. An investigation is in progress to determine the cause of the inadvertent actuation. At the time of the event, the plant was in Mode 1 at 100 percent rated thermal power.
"The public was informed of the inadvertent actuation by way of the Emergency Alert System (EAS).
"The NRC Resident Inspector has been notified."
The licensee has notified State and Local agencies. | |