| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
04/30/2014 - 05/01/2014 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 50048 | Rep Org: UTAH DIVISION OF RADIATION CONTROL
Licensee: CHURCH OF JESUS CHRIST OF LATTER DAY SAINTS
Region: 4
City: MAGNA State: UT
County:
License #:
Agreement: Y
Docket:
NRC Notified By: MIKE GIVENS
HQ OPS Officer: STEVE SANDIN | Notification Date: 04/22/2014
Notification Time: 10:25 [ET]
Event Date: 05/13/2013
Event Time: [MDT]
Last Update Date: 04/22/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
RAY AZUA (R4DO)
FSME_EVENTS RESOURCE (EMAI)
| Event Text AGREEMENT STATE REPORT INVOLVING A TRITIUM EXIT SIGN DESTROYED IN A FIRE
The following information was received from the State of Utah via fax.
"The Utah Division of Radiation Control [DRC] was notified at 1:38 p.m. MST on Wednesday, August 13, 2013 of an incident where a church chapel was destroyed by fire. The fire had occurred three months earlier on May 13, 2013. No one noticed the radiation symbol mixed with the trash until a representative of the church, watching the residue being shoveled from the chapel. He noted the radiation symbol stuck to the remains of the melted sign.
"The DRC contacted the church representative and was informed of the details of the fire.
"The DRC Radioactive Materials Section Manager was notified of the incident.
"Notification to the NRC was completed on January 24, 2014.
"The tritium sign was melted by the high heat of the fire. There were no remaining identifiable components. The debris from the sign was mixed with other burnt materials and the trash had been shoveled into waste containers. The church representative said there was nothing recoverable in the fire's residue.
"The EXIT sign (Model B-100) was manufactured by SRB Technologies in 2005. The sign was designed to operate for 20 years using 18.9 curies of tritium. The estimated activity of tritium remaining inside the sign when it was destroyed was approximately 12 Curies."
Utah Event Report ID No.: UT140001 |
| Agreement State | Event Number: 50050 | Rep Org: KANSAS DEPT OF HEALTH & ENVIRONMENT
Licensee: IRISNDT
Region: 4
City: McPherson State: KS
County:
License #: 21-B982
Agreement: Y
Docket:
NRC Notified By: TOM CONLEY
HQ OPS Officer: DANIEL MILLS | Notification Date: 04/23/2014
Notification Time: 09:46 [ET]
Event Date: 04/22/2014
Event Time: [CDT]
Last Update Date: 04/23/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
RAY AZUA (R4DO)
FSME EVENTS RESOURCE (EMAI)
| Event Text AGREEMENT STATE REPORT - RADIOGRAPHY SOURCE HANG-UP
The following was received from the State of Kansas via fax:
"Today [on] 4/22/14, [the] x-ray radiography crew had a source hang-up, at the NCRA plant in McPherson, Kansas, at approximately 0930 CDT. [The] radiography crew performed their operational and emergency procedures very well. A 35 curie Ir-192 source hung up in the source guide tube. [The crew] made the necessary adjustments to their boundaries, kept watch over them, allowed no one to enter, notified [the crew supervisor] and the Kansas RSO. They re-adjusted the crankouts and pulled them to straighten out the cranks and guide tube, and were able to retract the source into the device with one attempt, and were successful. There was no disconnect or anyone exposed to radiation levels above regulatory limits.
"Notification of the incident was given to the plant safety coordinators at the time of the incident, and they remained at distance to avoid exposure, the full time of the incident lasted approximately 10-15 minutes from the initial determination of a stuck source to retraction of the source into the device."
Three monitored IRISNDT staff were onsite and they watched over the boundaries while the retraction was completed. After the incident, all IRISNDT staff read their Instadose film badges and got readings from their personal dosimeters ranging from 1.2 to 3.8 mRem.
Kansas incident # KS140007 |
| Agreement State | Event Number: 50053 | Rep Org: ARIZONA RADIATION REGULATORY AGENCY
Licensee: ALPHA GEOTECHNICAL AND MATERIALS
Region: 4
City: TEMPE State: AZ
County:
License #: AZ 7-444
Agreement: Y
Docket:
NRC Notified By: AUBREY GODWIN
HQ OPS Officer: CHARLES TEAL | Notification Date: 04/23/2014
Notification Time: 16:46 [ET]
Event Date: 04/22/2014
Event Time: 14:00 [MST]
Last Update Date: 04/23/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
RAY AZUA (R4DO)
FSME EVENT RESOURCE (EMAI)
|
| This material event contains a "Less than Cat 3 " level of radioactive material. | Event Text AGREEMENT STATE REPORT - LOST AND FOUND MOISTURE DENSITY GAUGE
The following was received from the State of Arizona via email:
"The Agency [State of Arizona] was informed by the Licensee at approximately 2:45 PM [MDT], April 22, 2014 that at approximately 2:00 PM a worker had lost a Campbell-Pacific Model MC-1, SN MD41007631 moisture density gauge off a pickup truck. The worker forgot to close the tailgate. The gauge contained 10 millicuries of Cesium 137 and 50 millicuries of Americium 241. At approximately 3:15 PM, the Mesa Fire Department reported they had possession of a gauge found on a freeway near the work site.
"A review of the situation confirmed that this was the lost source by the Licensee. The Agency [State of Arizona] has released the gauge to the Licensee for leak testing.
"The NRC, FBI and Governor's Offices are being notified of this event.
"The Agency continues to investigate this event."
First Notice: 14-008
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: 50072 | Facility: HATCH
Region: 2 State: GA
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: KENNETH HUNTER
HQ OPS Officer: DONG HWA PARK | Notification Date: 04/30/2014
Notification Time: 08:09 [ET]
Event Date: 04/30/2014
Event Time: 08:00 [EDT]
Last Update Date: 04/30/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
DAVID AYRES (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 | Event Text TSC OUT OF SERVICE DUE TO MAINTENANCE
"On April 30, 2014, at 0800 EDT, the Technical Support Center (TSC) will be unavailable due to pre-planned maintenance on a motor control center associated with the TSC. The TSC is expected to be restored to a functional status in approximately 13 hours.
"If an emergency is declared requiring TSC activation during this period, the TSC will be staffed and activated using existing emergency planning procedures, and the TSC staff will relocate to an alternate TSC location in accordance with the Hatch emergency plan and applicable site procedures.
"This notification is being made in accordance with 10CFR 50.72 (b)(3)(xiii) due to the planned loss of an emergency response facility (ERF). An update will be provided once the TSC has been restored to normal operation. The NRC Resident Inspector has been notified."
* * * UPDATE PROVIDED BY JOHN SELLERS TO JEFF ROTTON AT 2011 EDT ON 04/30/2014 * * *
"The planned maintenance activities have been completed. The power was restored to the TSC at 1802 EDT on 4/30/14. Ventilation has been confirmed to be functional. The TSC was fully functional at 1802 EDT on 04/30/14."
The licensee has notified the NRC Resident Inspector. Notified R2DO (Ayres). |
| Fuel Cycle Facility | Event Number: 50073 | Facility: HONEYWELL INTERNATIONAL, INC.
RX Type: URANIUM HEXAFLUORIDE PRODUCTION
Comments: UF6 CONVERSION (DRY PROCESS)
Region: 2
City: METROPOLIS State: IL
County: MASSAC
License #: SUB-526
Agreement: Y
Docket: 04003392
NRC Notified By: MICHAEL ABEL
HQ OPS Officer: DONALD NORWOOD | Notification Date: 04/30/2014
Notification Time: 14:35 [ET]
Event Date: 04/30/2014
Event Time: 09:10 [CDT]
Last Update Date: 04/30/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
40.60(b)(3) - MED TREAT INVOLVING CONTAM
| Person (Organization):
DAVID AYRES (R2DO)
MIKE FRANOVICH (NMSS)
| Event Text ON-SITE MEDICAL TREATMENT OF A CONTAMINATED INDIVIDUAL
"An employee with low blood sugar reported to the on-site dispensary this morning. The plant nurse administered first aid and then sent the employee to an off-site medical facility for further evaluation. A whole body survey of the employee in her plant clothing was performed. The maximum amount of contamination present was on the employee's right boot (7,887 dpm/100cm2). Prior to leaving the Restricted Area, the employee removed all plant clothing, changed into her personal clothing, and was whole body frisked out of the plant. The employee was free of contamination upon release."
The licensee notified the NRC Fuel Facility Inspector. |
| Power Reactor | Event Number: 50075 | Facility: BEAVER VALLEY
Region: 1 State: PA
Unit: [1] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: ROBERT KRISTOPHEL
HQ OPS Officer: JEFF ROTTON | Notification Date: 04/30/2014
Notification Time: 16:59 [ET]
Event Date: 04/30/2014
Event Time: 11:40 [EDT]
Last Update Date: 04/30/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
WILLIAM COOK (R1DO)
|
| 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 | N | 0 | Defueled | 0 | Defueled | Event Text POSTULATED HOT SHORT FIRE EVENT COULD ADVERSELY IMPACT SAFE SHUTDOWN EQUIPMENT
"Based on a review of industry operating experience, it was identified that each unit has two un-fused DC control circuits for non safety-related DC motors which are routed from the turbine building through other separate fire areas including the Control Room. The DC breakers used to protect the motor power conductors are insufficient to protect the control conductors for these circuits. It is postulated that a fire induced short in one fire area could adversely impact safe shutdown equipment by overheating the cable and causing a secondary fire in other fire areas where the cable is routed. At Unit 1, cables for the affected circuits are routed in the Turbine Building, Cable Spreading Area and Control Room. At Unit 2, cables for the affected circuits are routed in the Turbine Building, Normal Switchgear, Service Building Cable Tray Area, Cable Vault, Instrument Relay Room, Control Building West Communication Room, Control Building Cable Spreading Area and Control Room.
"The postulated secondary fires or cable failures are outside the assumptions of each unit's fire protection analysis. A preliminary investigation of the issue indicates that existing fire protection safe shutdown procedures could be used to safely shut down the plant if needed. This condition is reportable as an 8-hour report in accordance with 10 CFR 50.72(b)(3)(ii)(B). Interim compensatory measures will be implemented for affected areas of the plant.
"The NRC Resident Inspector has been notified." |
| Power Reactor | Event Number: 50076 | Facility: LASALLE
Region: 3 State: IL
Unit: [1] [2] [ ]
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: ANDREW WARREN
HQ OPS Officer: JEFF ROTTON | Notification Date: 04/30/2014
Notification Time: 17:36 [ET]
Event Date: 04/30/2014
Event Time: 10:37 [CDT]
Last Update Date: 04/30/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
LAURA KOZAK (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 | N | 0 | Refueling | 0 | Refueling | Event Text MOMENTARY LOSS OF SECONDARY CONTAINMENT DUE TO AIRLOCK INTERLOCK MALFUNCTION
"This report is being made pursuant to 10CFR50.72(b)(3)(v)(C), Event or Condition that could have prevented fulfillment of a Safety Function needed to Control the Release of Radioactive Material and 10CFR50.72(b)(3)(v)(D), Event or Condition that could have prevented fulfillment of a Safety Function needed to Mitigate the Consequences of an Accident. Unit 1 was in mode 1 and in a condition of moving irradiated fuel in the secondary containment. Unit 2 was in mode 5 and in the condition of moving irradiated fuel in the secondary containment, core alterations, and operations with the potential to drain the reactor vessel. An employee entered a secondary containment interlock [Unit 2] and identified that both doors of the interlock opened simultaneously when the door on the auxiliary building side was opened. The employee immediately secured both doors in the interlock and notified the Main Control Room Supervisor. Both doors in the interlock were open for approximately 5 seconds. With both doors open, TS SR 3.6.4.1.2 [Technical Specification Surveillance Requirement] was not met. This rendered secondary containment inoperable per TS 3.6.4.1. Reactor Building differential pressure, as observed in the Main Control Room, has remained less that -0.25 inches of water column at all times. Initial investigation determined that the interlock for the doors was malfunctioning. Administrative controls have been put in place to ensure the doors remain closed pending repairs to the interlock."
The licensee has notified the NRC Resident Inspector. | |