Semantic search

Jump to navigation Jump to search
 Entered dateEvent description
ENS 5478115 July 2020 14:58:00At 0835 EDT on July 15, 2020, it was discovered that the main control room (MCR) envelope was inoperable due to a MCR door being found ajar; therefore, this condition is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(v). The door was closed, restoring the MCR envelope to operable at 0839 EDT. There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.
ENS 5478516 July 2020 13:09:00The following is a synopsis of information received via E-mail and phone: On July 15, 2020, at 1445 CDT, the Radiation Safety Officer (RSO) for Syngenta Crop Protection, LLC contacted the Louisiana Department of Environmental Quality / Emergency and Radiological Services Division / Radiation Section to report that shutters had failed to close on two fixed density gauges during routine maintenance. The shutters are stuck in the open position and do not affect operation. The gauges are Ronan Engineering Model SAI, s/n's 5832GK and 5835GK, each with a 50 mCi Cs-137 sealed source, at the time of installation. The licensee contacted the contractor, BBP Sales, LLC, to determine whether the gauges should be disposed of or repaired. The decision will be made on July 16, 2020 on how to deal with the stuck shutters. Repair or disposal of the gauges should be accomplished by July 20, 2020. Louisiana Event Report ID No.: LA20200005
ENS 5478015 July 2020 12:25:00

EN Revision Text: UNAUTHORIZED USE OF A RESTRICTED RADIATION ROOM AS A TOUCHDOWN SPACE On July 14, 2020, at approximately 1115 MDT, the Radiation Safety Officer was notified that a restricted radiation room was used intermittently for 30-45 minute periods as a touchdown space for Billings Clinic's Internal Medicine residents. The room had not been decommissioned. The restricted radiation room being used was the Billings Clinic Hospital I-131 Inpatient Therapy Room (room 3501; general inpatient medical floor). This room was last used for (a 153 mCi I-131 Sodium Iodine) radiation treatment on June 21, 2017. Beginning June 4, 2020, the room began being used as a touchdown space for Internal Medicine residents. Surveys were performed on July 14, 2020 using survey meters. Wipes for removable contamination were performed on a table, two computers, phone, and the floor around the area where staff were working. All items had activity levels indistinguishable from background readings. The items were removed from the room. The room has been secured with a new lock and radiation warning signs have been reposted. The radiation signs had been removed at an unknown time between June 4, 2020 and July 14, 2020. The licensee is not aware of any radiation exposure as a result of this reported event. The licensee is making this report as a deviation from 10 CFR 35.13(f) as required by reporting requirement 10 CFR 30.50(b)(1)(iii).

  • * * RETRACTION ON 07/28/2020 AT 1428 EDT FROM CHRIS FITZ TO THOMAS KENDZIA * * *

This is a summary of information received from the licensee via telephone: After discussion with NRC RIV personnel the licensee determined that this event is not reportable in accordance with 10 CFR 30.50(b)(1)(iii). Notified R4DO (Gepford) and NMSS Events (email).

ENS 5478215 July 2020 14:35:00The following information was received via E-mail: On 7/15/2020, at 1340 EDT, the licensee reported that yesterday, 7/14/2020, sometime between 0915 and 0930 EDT, a male patient receiving TheraSphere treatment was underdosed by approximately 30 percent due to a leak in the delivery assembly. This was discovered around half-way through the procedure. No exposure to anyone other than the patient occurred. Contamination has been contained and removed. The prescribed activity was 5.7 GBq and dose was 150 Gy. The actual activity delivered is estimated to be 3.99 GBq and dose was 105 Gy. The patient is scheduled to return next week for follow-up treatment. Florida Incident Number: FL20-080 A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.
ENS 546934 May 2020 23:40:00

EN Revision Text: DIESEL GENERATOR COOLING WATER SYSTEM DECLARED INOPERABLE This report is being made pursuant to 10 CFR 50.72(b)(3)(v)(D), Event or Condition that could have prevented fulfillment of a Safety Function needed to mitigate the Consequences of an Accident. A through wall leak was found on piping connected to the Division 3 Diesel Generator (DG) Cooling Water Strainer. This condition has been evaluated and the Division 3 DG Cooling Water System has been declared inoperable. The Division 3 DG Cooling Water System is a support system for the Division 3 Emergency DG and the High Pressure Core Spray System (HPCS). The NRC Resident Inspector has been notified.

  • * * RETRACTION ON MAY 8, 2020 AT 1709 EDT FROM JOE MESSINA TO BRIAN LIN * * *

This update retracts Event Notification #54693, which reported a condition that could have potentially prevented fulfillment of a safety function needed to mitigate the consequences of an accident. An evaluation of the flaw on the piping connected to the Unit 2 Division 3 Diesel Generator (DG) Cooling Water strainer concluded that the system would have remained operable. The High Pressure Core Spray system, supported by the operable DG Cooling Water system, remained operable and capable of performing its safety function. The NRC Resident Inspector has been notified. Notified R3DO (Stone).

ENS 546923 May 2020 22:28:00On 5/3/2020 at 1100 EDT, Operations identified a step change in the Main Control Room ambient noise. The cause of the noise was a rise in vibrations on the Number 11 fan motor of the Main Control Room Ventilation Circulating Fan. Another step change in noise occurred and Operations swapped from the Number 11 fan motor to its redundant Number 12 fan motor, but the noise and vibrations did not improve. The two independent motors are connected to the blower shaft with belts on either end of the shaft. This entire fan and motor assembly is contained within the Main Control Room ventilation ducting and is not visible. At 1118 EDT, Operations shut off the Main Control Room Ventilation Circulating Fan due to Number 11 fan motor vibrations, declared the Main Control Room Air Treatment System inoperable, and entered the Technical Specification 3.4.5.e, 7-day action statement. At 1750 EDT, Maintenance entered the ductwork and informed Operations that the Number 11 fan bearing had catastrophically failed and because of the extent of damage and close physical proximity to the Number 12 fan motor, jeopardized its continued operation. As a result, Operations also declared the Number 12 fan motor inoperable and determined the event was reportable as a loss of safety function per 10 CFR 50.72(b)(3)(v)(D). The licensee notified the NRC Resident Inspector.
ENS 546913 May 2020 11:43:00At 0821 EDT on May 3, 2020, the Susquehanna Steam Electric Station Unit 1 reactor automatically scrammed due to a trip of the Main Turbine. The Unit 1 reactor was operating at 76 percent reactor power following a ramp schedule to full power subsequent to a maintenance outage. The Control Room received indication of a Main Turbine trip with both divisions of the Reactor Protection System actuated and all control rods inserted. The Reactor Recirculation Pumps tripped on End of Cycle - Recirculation Pump Trip. Reactor water level lowered to -1 inch causing Level 3 (+13 inches) isolations. No Emergency Core Cooling System or Reactor Core Isolation Cooling actuations occurred. The operations crew subsequently maintained reactor water level at the normal operating band using Reactor Feed Water. No Steam Relief Valves opened. The reactor is currently stable in Mode 3. Investigation into the trip of the Main Turbine is in progress. The NRC Resident Inspector was notified. A voluntary notification to the Pennsylvania Emergency Management Agency and press release will occur. This event requires a 4-hour Emergency Notification System (ENS) notification in accordance with 10 CFR 50.72(b)(2)(iv)(B) and an 8-hour ENS notification in accordance with 10 CFR 50.72(b)(3)(iv)(A) and 10 CFR 50.72(b)(3)(iv)(B).
ENS 546881 May 2020 13:16:00

At approximately 1238 EDT on May 1, 2020, an alarm indicated smoke on a non-safety related electrical switchgear bus in the turbine building. Plant personnel were dispatched to investigate. Smoke and heat were found coming from the bus. At 1253 EDT, a Notification of Unusual Event was declared. At 1308 EDT the fire was declared out and fire watches posted. Offsite assistance was requested during the event and the Jenkinsville, SC fire department responded to the site. There were no plant personnel injuries or impact to the health and safety of the public. The cause of this event is unknown at the present time. The electrical bus has been de-energized. The unit is currently in a planned refueling outage. The licensee notified the NRC Resident Inspector. Notified DHS SWO, FEMA Operations Center, CISA IOCC, FEMA NWC (email), DHS Nuclear SSA (email), and FEMA NRCC SASC (email).

  • * * UPDATE FROM GEORGE SHEALY TO DONALD NORWOOD AT 1754 EDT * * *

The Notification of Unusual Event was terminated at 1737 EDT on May 1, 2020. The cause of the event is currently being investigated. The licensee will notify the NRC Resident Inspector. Notified R2DO (Miller). NRR EO (Miller), IRD MOC (Grant). Additionally, notified DHS SWO, FEMA Operations Center, CISA IOCC, FEMA NWC (email), DHS Nuclear SSA (email), and FEMA NRCC SASC (email).

ENS 546901 May 2020 15:34:00At 0831 CDT, the Main Control Room received a 'Reactor Building 903 ft. Access Both Doors Open' alarm. Investigation found the interlock between the inner and outer doors did not prevent the opening of both doors while personnel were accessing the Reactor Building. The doors were immediately closed. Based on alarm times, both doors were open for less than one second. With both doors open, SR 3.6.4.1.3 was not met and Secondary Containment was declared inoperable. This unplanned Secondary Containment inoperability constitutes a condition reportable under 10 CFR 50.72(b)(3)(v)(c) and (d), 'An event or condition that at the time of discovery could have prevented the fulfillment of the safety function of SSCs that are needed to control the release of radioactive material and mitigate the consequences of an accident.' Secondary Containment was declared operable at 0836 CDT after independently verifying at least one Secondary Containment access door was closed. The NRC Senior Resident Inspector has been informed.
ENS 546871 May 2020 11:53:00

EN Revision Text: TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO REACTOR COOLANT SYSTEM PRESSURE BOUNDARY LEAKAGE At 1000 EDT on May 1 2020, Operations commenced a shutdown of DC Cook Unit 2 to comply with LCO 3.4.13, Condition B Reactor Coolant System (RCS) pressure boundary leakage. At 0354 EDT on May 1, 2020, Operations detected an estimated 8 gpm Reactor Coolant System leak. The source of the leak could not be identified and Tech Spec 3.4.13, Condition A was entered for unidentified RCS leakage in excess of the 0.8 gpm limit. At 0745 EDT on May 1, 2020, Unit 2 entered LCO 3.4.13, Condition B when the 4-hour limit to complete the required actions of Condition A could not be met. At 0945 EDT on May 1, 2020, Unit 2 entered LCO 3.4.13, Condition B when the 4-hour limit to complete the required actions of Condition A could not be met. At 0945 EDT on May 1, 2020, inspections inside containment identified the leak as pressure boundary leakage from a pressurizer spray line which also requires entry into LCO 3.4.13, Condition B. At 1059 EDT on May 1, Unit 2 was tripped from 15 percent power. All systems functioned normally. This event is reportable under 10 CFR 50.72(b)(2)(i), the initiation of any nuclear plant shutdown required by the plant's Technical Specifications as a 4-hour report and under 10 CFR 50.72 (b)(3)(ii)(A), degraded condition, as an 8-hour report. The NRC Resident Inspector has been notified.

  • * * PARTIAL RETRACTION ON 5/15/2020 AT 1442 EDT FROM BUD HINCKLEY TO THOMAS HERRITY * * *

The condition identified in EN #54687, pursuant to 10 CFR 50.72 (b)(3)(ii)(a) has been evaluated, and has been determined not to be RCS pressure boundary leakage. As such, the 8-hour report is being retracted, as it is not an event or condition that results in, 'the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded.' The leakage was subsequently determined to be from the tell-tale nipple of a pressurizer spray valve, not from the pressurizer spray line piping as previously reported. The Reactor Coolant Pressure Boundary (RCPB) is formed by the valve body, plug, seat, body to bonnet extension, and bonnet of the pressurizer spray valve. Therefore, the leakage is not RCPB leakage. There is no change to the 4-hour report made under 10 CFR 50.72(b)(2)(i), the initiation of any nuclear plant shutdown required by the plant's Technical Specifications. The NRC Resident Inspector was notified of this retraction. Notified R3DO (Stone).

ENS 534411 June 2018 15:50:00

The following information was received via E-mail: On May 31, 2018, during a turn-around at Calcasieu Refining Co., lockout and tagout procedures were not performed for two fixed gauges. Two non-radiation workers were over-exposed for the limit of 2 mR/hr. External radiation exposures are currently estimated at between 20 to 40 millirem whole body. The two sources were 50 mCi Cs-137 sources in Ohmart Vega Model SH-F1 gauges with serial numbers 70012 and 69998.

This event was reported by the facility on June 1, 2018. LA Event Report ID No.: LA20180010

ENS 534361 June 2018 11:39:00The following information was received via E-mail: On May 31, 2018, the Department (PA DEP Bureau of Radiation Protection) was notified by the licensee that a malfunction of a roll pin on a shutter handle occurred at a temporary jobsite in Eighty Four, Pennsylvania. It is initially reportable per 10 CFR 30.50(b)(2). A roll pin, which holds the shutter handle to the shutter shaft on a Berthhold Model LB 8010 in-line density gauge containing 20 milliCuries of cesium-137 became sheared off during an attempt to move the shutter to the open position, rendering the gauge unusable. The gauge is currently being stored at their Punxsutawney, PA location. The shutter is in the closed position and the gauge is out of service awaiting repair from the manufacturer. There was no other damage to the gauge. No overexposures have occurred. Radionuclide: Cs-137 Manufacturer: Berthold Model: LB 8010 Serial Number: 10485 Activity: 20 mCi The cause of the event has been attributed to normal wear and tear on the gauge. A reactive inspection is planned by the Department. PA Event Report ID No: PA180013
ENS 5466915 April 2020 14:50:00The following information was received via e-mail: The State of Maine Radiation Control Program became aware of a breaking news item, reporting that the Pixelle Androscoggin paper mill in Jay, Maine had suffered an explosion. https://www.wabi.tv/content/news/Explosion-reported-at-Jay-mill-details-limited-569661451.html The precise location of the explosion is unknown at this time but it may be the boiler or power plant. Later report from MEMA - Maine Emergency Management Agency - says that it was 'the Digester of Pulp Mill A or maybe B.' The Maine Radiation Control Program will confirm the information as it comes in. There were no fatalities or injuries reported. 'A' Pulp Mill contains six gauges, 'B' Pulp Mill contains three gauges, and the Power Plant/Boiler contains five gauges. There could be from three to six gauges involved in the explosion, depending on which building exploded. The Maine Radiation Control Program has not been notified by the mill. This report is the first written notification to NMED. Maine Event Report ID No.: ME 20-003
ENS 5466614 April 2020 23:36:00On April 14, 2020 at 1645 CDT, the Control Room Emergency Ventilation Air Conditioning (CREV AC) system was declared inoperable when the electrical feed breaker to the Refrigeration Compressor Unit (RCU) was found in a tripped condition. As a result, both units entered Technical Specification 3.7.5 Condition A. Investigation is in progress to determine the cause and corrective actions of the RCU feed breaker trip. The CREV AC system maintains a habitable control room environment and ensures the operability of components in the control room emergency zone during accident conditions. This notification is being made in accordance with 10 CFR 50.72(b)(3)(v)(D) because the CREV system is a single train system, and loss of the CREV AC could impact the plant's ability to mitigate the consequences of an accident.
ENS 5466514 April 2020 17:29:00The following information was received via E-mail: 21 tritium exit signs, each containing 9.21 Ci, are unaccounted for. There has been no response for annual general license registrations since 2015. 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
ENS 5465710 April 2020 10:58:00On April 10, 2020, at 0300 (EDT), an oil leak from 23PCV-12, HPCI (High Pressure Core Injection) Trip System Pressure Control Valve (PCV), resulted in the system being declared inoperable. This condition is being reported as a condition that could have prevented the fulfillment of the safety function of a system needed to mitigate the consequences of an accident per 10 CFR 50.72(b)(3)(v)(D). The licensee notified the NRC Resident Inspector.
ENS 546529 April 2020 03:37:00On April 9, 2020 at 0100 EDT, while performing a containment walkdown due to a small increased Reactor Coolant System (RCS) unidentified leakage, a leak was identified on the 'A' Reactor Coolant Pump (RCP) seal injection piping. The source of the leakage cannot be isolated and is considered RCS pressure boundary leakage. At that time, Condition B of Technical Specification (TS) LCO 3.4.13, 'RCS Operational Leakage' was entered due to pressure boundary leakage. TS 3.4.4 'RCS Loops - Mode 1 and 2' and Technical Requirement (TR) 3.4.6 'ASME Code Class 1, 2, and 3 Components' are also applicable. Unit 2 is projected to be taken to Mode 5 for repairs. This event is reportable in accordance with 10 CFR 50.72(b)(2) for 'Initiation of plant shutdown required by Technical Specifications' and 10 CFR 50.72(b)(3)(ii)(A) for 'Any event or condition that results in the condition of the nuclear power plant, including its principle safety barriers, being seriously degraded.' The licensee notified the NRC Resident Inspector. There is no effect on Unit 1
ENS 546498 April 2020 11:25:00The following is a summary of the report received from the licensee: On 4/7/2020 a trained technician was in the process of performing the bi-annual inventory/shutter checks when he reported that an Ohmart gauge (Model Number ED-6, Serial Number 65902, 100 mCi, Cs-137) located on 9B DTU (Deslime Thickener U/Flow) in the Deslime basement had a frozen shutter mechanism, rendering the shutter non-operable. The technician notified the Radiation Safety Officer who then instructed the technician to replace the gauge with the stuck shutter with a spare gauge. However, the replacement will not take place until the line it is on goes down for repair (estimated May 1, 2020). If the line goes down prior to this time, the licensee will replace the gauge at that time. The licensee noted that they have had events similar to this in the past and have not had an exposure to any individuals. The licensee additionally noted that in the event of an emergency, the gauge will be removed, placed on a piece of lead and brought into storage.
ENS 546549 April 2020 09:21:00The following information was received via E-mail: The aperture electronic opening and closing mechanism malfunctioned on a J.L. Shepard Mark I series irradiator while the aperture was open. There was a smell of burning wires and visible smoke. The analysts cut power to the unit and notified department management. Utilizing portable shielding, and following ALARA principles, the attenuator of the device was able to be closed, which significantly reduced dose rates. Currently, the aperture is stuck partially open and the attenuator is closed. At 1.5 meters from the point of highest dose, the rate is approximately 10 mR/hr. Both analysts were wearing Mirion Instadose dosimeters and the measured dose to both dosimeters was less than the minimum read amount of 1 mrem. The irradiator is located in a shielded calibration room located in the waste building. There is no dose rate above background in any area, accessible by either non-radiation workers or members of the public, around the building where the calibration room is located. The area has been securely locked, the door alarm is activated, and there are signs placed to remind everyone to not use the device. Utah Department of Environmental Quality, Division of Waste Management and Radiation Control personnel were notified of the incident via normal work E-mail after the conclusion of the business of the day on April 8, 2020. The notification was not read until the morning of April 9, 2020 when normal business resumed and was then assigned to appropriate staff. The device manufacturer has been contacted to determine repair options. Utah Event Report ID No.: UT 200004
ENS 546301 April 2020 19:07:00A licensed operator had a confirmed positive for alcohol during a random fitness-for-duty test. The employee's access to the plant has been terminated. The NRC Resident Inspector has been notified.
ENS 545726 March 2020 15:14:00The following is a synopsis of information received via E-mail: At 1430 EST on 3/6/2020, the Bristol Myers Squibb Radiation Safety Officer made a notification to the New Jersey Bureau of Environmental Radiation that following the Tritium exit sign inventory for their campus, six exit signs were unaccounted for. The exit signs contained a total of approximately 130 Curies of Tritium. New Jersey State Event Report ID Number: TBD 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
ENS 545562 March 2020 20:45:00A non-licensed contract employee supervisor had a confirmed positive for illegal drugs during a random fitness-for-duty test. The employee's access to the plant has been terminated. The licensee notified the NRC Resident Inspector.
ENS 545531 March 2020 13:52:00The following information was received via E-mail: This event occurred in Austin, Texas. On March 1, 2020, one of the licensee's technicians had pulled off the road and was parked in a parking area, sleeping, when local law enforcement pulled up. Local law enforcement wanted to take the technician in for suspicion of DWI. At approximately 0800 CST the technician called the site radiation safety officer and told him of the situation. Law enforcement stayed with the technician until the tow truck came and took the vehicle to impound at approximately 0830 CST. The vehicle was locked, the alarm on the dark room was activated and the technician took all the keys to the dark room and camera with him. The vehicle was carrying a radiography camera (Spec 150) containing an 80 Curie Iridium-192 source. The licensee dispatched employees to the impound yard and they arrived at approximately 1015 CST and provided surveillance of the vehicle until it was released to them. They verified that the alarm system on the dark room was still armed and that the camera was present. The truck is being returned to the licensee's facility. At last report from the licensee, law enforcement had not performed any testing to determine if the technician was under-the-influence. More information will be provided as it is obtained in accordance with SA-300. Texas Incident Number: Not Yet Assigned
ENS 545542 March 2020 12:45:00

EN Revision Text: STOLEN PORTABLE DENSITY MOISTURE GAUGE The licensee left a locked trailer at a job site in Rolla, Missouri Friday evening, 2/28/2020. The trailer contained a locked case, which was chained and locked to the trailer. The case contained a Seaman's portable density moisture gauge, Model Number C300, Serial Number 21274, with a 4.5 mCi Radium-226 source. The trailer, with the gauge inside, was stolen from the job site sometime between Friday evening 2/28/2020 and mid-day Saturday 2/29/2020 when employees of the licensee returned to the job site. The trailer is an enclosed trailer, approximately 14 feet in length, white in color, with no lettering or other readily distinguishable markings on the outside. The licensee notified the Phelps' county sheriff's office. The sheriff's office issued report number 20200263 for this event.

  • * * RETRACTION ON 3/16/2020 AT 1227 EDT FROM DWAYNE MULLER TO BETHANY CECERE * * *

This event is being retracted because the trailer was not stolen. The trailer was moved to the corporate location, but all parties were not aware of the move. The licensee notified the NRC R3 Inspector (O'Dowd) and the Phelps' county sheriff's office. Notified R3DO (Hanna), NMSS Events, and ILTAB. 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

ENS 5454827 February 2020 15:54:00The following information was received from the state of Florida via E-mail: (The licensee) reported to the BRC (Bureau of Radiation Control) on 25 Feb 2020, and e-mailed an incident report on 26 Feb 2020 at 1224 EST that on 24 Feb 2020 at 1315 EST an HDR (high dose rate) incident occurred to a patient receiving skin therapy. The patient was prescribed 7.5 Gray x 5 fractions, on five different parts of the left hand. On the first dose of the first fraction, it was observed that catheter numbers 1 - 15 were reversed, causing an underdose to the patient by 56.25 percent. No Authorized Users were exposed to the source or otherwise contaminated. Florida Incident Number: FL20-022 A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.
ENS 5453119 February 2020 10:20:00

EN Revision Text: NOTIFICATION OF UNUSUAL EVENT DUE TO FIRE IN CONTROL BUILDING At 0957 EST on February 19, 2020, a Notification of Unusual Event (NOUE) has been determined to be present at the Watts Bar plant Unit 1 under criteria HU4 for a fire potentially degrading the safety of the plant (fire for more than 15 minutes). The NRC Senior Resident Inspector has been notified for this event. Notified DHS SWO, FEMA Operations Center, CISA IOCC, FEMA NWC (email), DHS Nuclear SSA (email), and FEMA NRCC SASC (email).

  • * * UPDATE ON 02/19/2020 AT 1151 EST FROM ANDREW WALDMANN TO DONALD NORWOOD * * *

The fire was declared extinguished at 1033 EST. The NOUE was terminated at 1126 EST. The investigation into the cause of the fire is in progress. Notified R2DO (Musser), NRR EO (Miller), and IRD MOC (Kennedy). Additionally, notified DHS SWO, FEMA Operations Center, CISA IOCC, FEMA NWC (email), DHS Nuclear SSA (email), and FEMA NRCC SASC (email).

  • * * RETRACTION ON 2/20/2020 AT 1453 EST FROM MICHAEL BUTHEY TO RICHARD L. SMITH * * *

Watts Bar Nuclear Plant (WBN) is retracting Event Notice 54531 (NOUE notification) based on the following additional information. WBN reported a condition that was determined to meet the definition of a FIRE in the plant Emergency Preparedness Implementing Procedures (EPIP) based on indications available to the decision-maker at the time the declaration was made. A fire, without observation of flame, is considered present if large quantities of smoke and heat are observed. Moderate quantities of smoke were observed coming from an electrical cabinet not required to support safe plant operation. Once Fire Brigade personnel were able to access the affected room, no evidence of flame or significant heat was observed. Plant personnel ultimately determined that an overheated electrical component (transformer) resulted in the smoke. As such, the actual conditions did not meet the EPIP definition of a fire. The NRC Resident Inspector has been notified of this retraction. Notified R2DO (Musser), NRR EO (Miller), and IRD MOC (Kennedy).

ENS 5453219 February 2020 10:20:00At 0936 EST on February 19, 2020, the Watts Bar Unit 1 reactor was manually tripped while operating at 100 percent power in response to loss of control of water level for steam generator number 3. All control and shutdown bank rods inserted properly in response to the manual reactor trip. All safety systems including Auxiliary Feedwater actuated as designed. The plant is stable with decay heat removal through Auxiliary Feedwater and Steam Dump Systems. There is no impact to Unit 2. The manual actuation of the Reactor Protection System (RPS) is being reported as a four-hour report under 10 CFR 50. 72(b)(2)(iv)(B). The expected actuation of the Auxiliary Feedwater System (an engineered safety feature) is being reported as an eight-hour report under 10 CFR 50.72 (b)(3)(iv)(A). The NRC Senior Resident Inspector has been notified for this event.
ENS 545081 February 2020 23:06:00At 1845 CST on 2/1/2020, during surveillance testing (STS PE-015, Containment Purge Valve Leakage Test) containment leakage in excess of Technical Specification requirements was observed. A Technical Specification required shutdown was initiated at 2030 CST and Mode 3 was achieved at 2154 CST. All systems functioned as required during and following shutdown. The unit is proceeding to Mode 5. The licensee notified the NRC Resident Inspector.
ENS 5450531 January 2020 15:35:00The following information was received via E-mail: The Department (Arizona Department of Health Services) received notification from the licensee that a technician had backed up over a portable moisture density gauge with their truck. The gauge is a Troxler 3430, Serial Number 35062, containing approximately 8 milliCuries of cesium-137 and 40 milliCuries of americium-241:beryllium. The Department has requested additional information and continues to investigate the event. Arizona Incident: 20-002
ENS 5448115 January 2020 16:16:00The following information was received via E-mail: On January 15, 2020, at 1400 CST, the DOW Chemical Radiation Safety Officer contacted the supervisor of the Louisiana Department of Environmental Quality/ERSD/Radiation Section to report that a shutter failed to shut during routine maintenance. The shutter which failed to shut was found on January 14, 2020, at approximately 1500 CST, at DOW Chemicals Company. The shutter is stuck in the open condition and does not effect operation. The gauge is a Vega Americas model number SHF2B, s/n 38953125, with a 500 mCi Cs-137 sealed source, s/n 0368CR. The licensee has contacted the contractor for repair and is awaiting a date and time for the repair. Event Report ID No.: LA20200001
ENS 5447915 January 2020 11:42:00The following information was received via E-mail: An unknown device was discovered at a metal scrap yard in Ohio. The device has no markings or labels. A Cs-137 source of unknown activity was identified in the device. No loose contamination was detected. Maximum dose rate on the device is 500 mr/hr and 6 mr/hr at one meter. The device is secure at the facility pending disposal. The Ohio Department of Health will continue to track down the origin of the source. Ohio Item Number: OH200001
ENS 544623 January 2020 13:15:00On 1/2/2020, it was discovered that the shutter on a centrifuge process level gauge was stuck in the open position. The gauge is a Berthold model LB7442F, serial number 6005 containing a 3000 mCi Cs-137 source. The source serial number is 5559GN. The shutter is normally open during process operation and closed during maintenance. Red tape and plywood have been erected in order to prevent inadvertent personnel entry into the area. No over-exposures have occurred. A Berthold representative should be on-site next week to repair the shutter.
ENS 5440722 November 2019 14:46:00The following information was received via E-mail: On 11/20/2019, Massachusetts Radiation Control Program (MARCP) was informed by Schnitzer Steel Industries, Inc., that a scrap metal shipment from Devens Recycling in Danvers, MA set off the radiation monitor alarm. The vehicle was redirected back to Devens Recycling for follow-up survey and mitigation in accordance with MA RCP DOT Special Permit MA-MA-19-11. On 11/21/2019, the material was identified and segregated from the scrap metal load by an independent radiation consultant. The radioactive material discovered was radium-226 painted on the dial of an abandoned (lost), old Aircraft Altimeter instrument. The dose rate at 6 inches from the instrument was 150 microR/hr. The background dose rate was 20 microR/hour. The radiation survey instrument used to locate the source was a Ludlum Model 193-6. A Ludlum Model 9DP-1 ion chamber was used for direct measurements on the instrument. A Ludlum Model 702 Multi Channel Analyzer was used to identify the radioisotope. The radium-226 activity was estimated to be approximately 4.73 microCuries based on the dose rate measured. This material is being stored in a sealed polyethylene bag placed in a sealed 55 gallon drum and labeled as radioactive material held for disposal. This activity meets the 30-day event report requirement for lost or abandoned radioactive material greater than 10 times the quantities specified in 10 CFR 20 Appendix C, or the Massachusetts equivalent, 105 CMR 120.297 Appendix C, which is ten times reportable quantity for Radium-226 (1 microCurie). The Agency (MARCP) considers this event to be open until proper disposal of this instrument is confirmed. Massachusetts Docket No.: TBD 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
ENS 5439720 November 2019 16:39:00The following information was received via E-mail: On November 20, 2019, the licensee notified the Virginia Office of Radiological Health (ORH) that a medical event occurred as a result of treating a patient using a High Dose Remote Afterloader Unit (HDR). According to the written directive, 18 Gray (Gy) dose to the neck, in three (3) fractions of 6 Gy, was prescribed. On November 19, 2019, the first of the three fractions was delivered. However, the dose was delivered at 91.5 cm instead of the intended 118.1 cm. This resulted in a dose to the treatment site of approximately 0.3 Gy. The report indicated that the error was discovered on November 20, 2019 at 0830 EST after the medical physicist re-measured the guide tube and catheter. It was discovered that the guide tube and catheter were not connected properly and this caused the dose to be delivered at 91.5 cm. The prescribing physician and the patient were notified immediately (at 0915 EST). ORH will review the licensee's written report and determine additional actions to be taken. Virginia Event Report ID No.: VA-19-005 A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.
ENS 5440622 November 2019 14:46:00The following information was received via E-mail: On 11/18/2019, Massachusetts Radiation Control Program (MARCP) was informed by Schnitzer Steel Industries, Inc., that a scrap metal shipment from Devens Recycling in Danvers, MA set off the radiation monitor alarm. The vehicle was redirected back to Devens Recycling for follow-up survey and mitigation in accordance with MA RCP DOT Special Permit MA-MA-19-10. On 11/19/2019, the material was identified and segregated from the scrap metal load by an independent radiation consultant. The radioactive material discovered was radium-226 painted on the dial of an abandoned (lost), old Aircraft Turn/Slip Coordinator instrument. The dose rate at 6 inches from the instrument was 200 microR/hr. The background dose rate was 20 microR/hour. The radiation survey instrument used to locate the source was a Ludlum Model 193-6. A Ludlum Model 9DP-1 ion chamber was used for direct measurements on the instrument. A Ludlum Model 702 Multi Channel Analyzer was used to identify the radioisotope. The radium-226 activity was estimated to be approximately 6.31 microCuries based on the dose rate measured. This material is being stored in a sealed polyethylene bag placed in a sealed 55 gallon drum and labeled as radioactive material held for disposal. This activity meets the 30-day event report requirement for lost or abandoned radioactive material greater than 10 times the quantities specified in 10 CFR 20 Appendix C, or the Massachusetts equivalent, 105 CMR 120.297 Appendix C, which is ten times reportable quantity for Radium-226 (1 microCurie). The Agency (MARCP) considers this event to be open until proper disposal of this instrument is confirmed. Massachusetts Docket No.: 23-3968 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
ENS 543641 November 2019 10:03:00On November 1, 2019 at 0316 EDT, Nine Mile Point Unit 2 (NMP2) received Control Room annunciation for HPCS SYSTEM INOPERABLE and inoperable status light indication for TRIP UNITS OUT OF FILE/POWER FAIL. Initial investigation has identified a potential failed 24 vdc power supply which supplies power to the HPCS trip units for system initiation and control. The HPCS system has been declared inoperable per TS 3.5.1 resulting in an unplanned 14 day LCO. All other plant systems functioned as required. NMP2 is currently at 100 percent power in Mode 1. This condition is reportable under 10 CFR 50.72(b)(3)(v)(D) as, 'Any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to: (D) Mitigate the consequences of an accident.' The licensee notified the NRC Resident Inspector.
ENS 5436230 October 2019 01:20:00

On 10/30/19 at 0026 EDT, an Unusual Event (HU3) was declared due to a release of flammable gas to the Unit 1 Pipe Penetration area (Reactor Auxiliary Building). The hydrogen supply valve to the area has been isolated. The area is being ventilated and follow-up air sampling will be performed. The NRC Resident Inspector has been notified. Notified DHS SWO, FEMA Ops Center, DHS NICC, FEMA NWC (email), DHS Nuclear SSA (email), and FEMA NRCC SASC (email).

  • * * UPDATE FROM FRED POLLAK TO DONALD NORWOOD AT 0521 EDT ON 10/30/2019 * * *

The Notice of Unusual Event was terminated at 0454 EDT on 10/30/19. The area has been purged and normal access restored. The licensee notified the NRC Resident Inspector. Notified R2DO (McCoy), NRR EO (Miller), and IRD (Grant). Notified DHS SWO, FEMA Ops Center, DHS NICC, FEMA NWC (email), DHS Nuclear SSA (email), and FEMA NRCC SASC (email).

ENS 5434824 October 2019 16:25:00At 1035 CDT the Automatic Depressurization System (ADS) was rendered inoperable due to the failure of the 'A' Safety Vent Valve (SVV) Compressor (SVV-C4A) to manually start with SVV-C4B tagged out. System pressure slowly dropped below 131 psig (normal pressure is 165 psig). This caused the ADS safety relief valves to be declared inoperable. The station entered Technical Specification 3.5.1 Condition G. The Required Action was to be in Mode 3 in 12 hours. As a result, the station was in a condition that could have prevented the fulfillment of a safety function. The breaker for SVV-C4B was reset and the clearance for SVV-V4B was released. System pressure was restored to greater than 131 psig at 1116 CDT which allowed exit of the action statement to be in Mode 3 in 12 hours. System parameters are currently stable in the normal pressure range. Investigation for the cause of the system failure is ongoing. No radiological releases have occurred due to this event from the unit. The licensee notified the NRC Resident Inspector.
ENS 5434624 October 2019 11:51:00The following information was received via E-mail: The licensee informed the Department (Pennsylvania Department of Radiation Protection) that a brachytherapy seed set was implanted in the wrong patient. It is reportable per 10 CFR 35.3045(a)(2)(iii)(B). On October 23, 2019, the licensee was performing a permanent brachytherapy during which an incorrect prostate brachytherapy seed set (lsoRay Model CS-1) was brought to the procedure room and 6 Cs-131 seeds were implanted into the prostate of a patient. The procedure was stopped immediately when the error was recognized. The correct seeds were then brought to the operating room and the procedure was completed using the correct seeds. Forty Seven (47) seeds, 85 gray, (3.135 mCi) were prescribed and 3.03 mCi given. The Authorized User notified the urologist and patient this morning (10/24/19). No harm is expected to the patient. The cause of the event is unknown at this time. The Department will perform a reactive inspection. More information will be provided as received. Pennsylvania Event Report ID No: PA190024 A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.
ENS 5432812 October 2019 15:54:00One unopened can of beer was discovered in a break room refrigerator within the plant's Protected Area. The individual that brought in the can of beer was identified. That individual is a Pacific Gas and Electric employee but does not normally work at Diablo Canyon. That individual was brought in to support work during the Unit 2 refueling outage. When questioned, the individual stated that the can of beer had been brought in to give to another person to see if that person liked that brand of beer (the beer was apparently from a small specialty brewery). A behavioral observation was performed on the individual who brought in the can of beer. There was no indication of alcohol use by the individual. The individual's access to the plant has been suspended pending further investigation.
ENS 5432511 October 2019 14:22:00At 1300 EDT, a Technical Specification required shutdown was initiated at Calvert Cliffs Unit 1. Technical Specification Action 3.1.4.C (Restore Control Element Assembly (CEA) alignment) was entered on 10/11/2019 at 1100 EDT, with a Required Action to reduce thermal power to less than 70 percent Rated Thermal Power and restore CEA alignment within 2 hours. This Required Action was not completed within the Completion Time; therefore, a Technical Specification required shutdown was initiated, and this event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(i). At 1345 EDT, CEA alignment was restored and Technical Specification 3.1.4 (Control Element Assembly Alignment) was met. Reactor Power is being stabilized. There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.
ENS 5432711 October 2019 18:29:00The following information was received from the Texas Department of State Health Services (the Agency) via E-mail: On October 11, 2019, the Agency was contacted by the licensee's radiation safety officer (RSO) who reported a medical event had occurred at their facility. The RSO stated that the event involved a patient who was to receive a treatment with yttrium-90 microspheres. The administering physician had difficulties setting up the injection apparatus and installed an additional piece of tubing in-line with the injection tubing. Because of the additional length of tubing, the patient received only five percent of the prescribed activity. The RSO stated there would be no adverse effects on the patient. The RSO stated both the patient and the prescribing physician have been notified of the error. The RSO stated that the bulk of the microspheres (activity) remained in the tubing and no contamination was found in the area where the treatment occurred. The RSO stated the physician decided they would perform the procedure again and use the activity needed to bring total activity administered to the activity initially prescribed. Additional information will be provided as it is received in accordance with SA-300. Texas Incident No.: I-9721 A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.
ENS 5432611 October 2019 16:35:00The following information was receive from the Texas Department of State Health Services (the Agency) vial e-mail: On October 11, 2019, the Agency was notified by the licensee's radiation safety officer (RSO) that the shutter on a Vega Americas SHLG-2 source holder containing a 5,000 milliCurie cesium-137 source was stuck in the open position. The stuck shutter was found during a routine check of the gauge. Open is the normal operating position. The RSO stated the gauge does not pose an exposure risk to any individual. The RSO stated a service company has been contacted to look at the gauge. The RSO stated they have not determined if they will repair or replace the gauge. Additional information will be provided as it is received in accordance with SA 300. Texas Incident No.: I-9720
ENS 5432210 October 2019 12:14:00At 1122 EDT, on October 10, 2019, Duke Energy initiated voluntary notification of North Carolina State and local officials per the guidance in Nuclear Energy Institute (NEI) 07-07, 'Industry Groundwater Protection Initiative - Final Guidance Document,' due to release of tritiated water in excess of 100 gallons. On October 8, 2019, at approximately 1300 EDT, Brunswick plant personnel drilling as part of an ongoing site project, damaged a storm drain discharge line. The resulting leak was isolated and water around the impacted area was sampled for gamma emitters and tritium. No gamma emitters were detected. The tritium concentration was below the Environmental Protection Agency (EPA) drinking water limit of 20,000 pCi/L. The leak has been stopped and excavation and repair efforts are in progress. This notification is being made solely as a four-hour, non-emergency notification for a notification of other government agency. This event is reportable in accordance with 10 CFR 50.72(b)(2)(xi). There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.
ENS 5432310 October 2019 15:22:00The following information was received via e-mail: A Troxler 3430 portable surface moisture-density gauge, S/N 19274, was damaged when it was hit by an excavator at a temporary job site in Shoreline, Washington. Damage included: the screws had been ripped out of the top shell of the gauge, and the metal base of the gauge was cracked on the side. The gauge operator verified that the source rod was intact and retracted into the safe position, and returned the gauge to the licensee's main office for storage, as directed by his radiation safety officer. A Washington Department of Health inspector surveyed the gauge and verified that the neutron and gamma readings were similar to the radiation profile shown in the sealed source and device registry certificate for the gauge. The inspector checked for removable radioactive material contamination on the outside of the gauge by wiping the crack in the side of the base of the gauge, the seam where the top shell joins with the metal base of the gauge, and the source rod opening and bottom plate. No removable contamination was found. The damaged gauge will be shipped for disposal in the near future. The gauge contained a 40 mCi Am-Be source, S/N 47-14734, and a 4 mCi Cs-137 source, S/N 50-8931. Washington Reference Number: WA-19-028
ENS 543021 October 2019 07:05:00On 10/1/2019, at 0307 CDT, Unit 2 was conducting a normal reactor startup and received a valid Reactor Protection System (RPS) scram. The reactor was critical in MODE 2 at the Point of Adding Heat. Operators began withdrawing Source Range Monitor (SRM) Instrumentation per procedure. When the operator depressed the SRM Drive Out pushbutton to withdraw the last two SRMs (C and D), an unexpected full Reactor Scram was received. Annunciator indication in the Main Control Room indicated a Neutron Monitoring Scram. The Intermediate Range Monitors (IRM) D, E, F, H and G all indicated Upscale High High. There were no Emergency Core Cooling System (ECCS) or Containment Isolation System actuations. All other systems functioned as designed. The cause of the Reactor Scram is still under investigation. This event requires a 4-hour report per 10 CFR 50.72(b)(2)(iv)(B), 'Any event or condition that results in actuation of the reactor protection system (RPS) when the reactor is critical except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation.' This event also requires an 8-hour report per 10 CFR 50.72(b)(3)(iv)(A), 'Any event or condition that results in valid actuation of any of the systems listed in paragraph (b)(3)(iv)(B), (1) Reactor protection system (RPS) including: reactor scram or reactor trip, except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation.' The NRC Resident Inspector has been notified.
ENS 5429930 September 2019 01:22:00On September 29, 2019 at 2228 EDT, during a planned swap of Reactor Building HVAC trains, the exhaust fan discharge damper for the train being removed from service failed to close when the train was shutdown, which resulted in the Technical Specification (TS) for secondary containment pressure not being met for approximately 2 minutes and 15 seconds. The maximum secondary containment pressure observed during that time was approximately 0.1 inches of water gauge (positive). Secondary containment pressure was returned to within the TS operability limit of greater than or equal to 0.125 inches of vacuum water gauge (TS SR 3.6.4.1.1) by restarting the train of RBHVAC. Secondary containment pressure is currently stable. Secondary containment was declared Operable at 2235 EDT. There were no radiological releases associated with this event. Declaring secondary containment inoperable is reportable under 10 CFR 50.72(b)(3)(v)(C) as an event or condition that could have prevented the fulfillment of a safety function needed to control the release of radioactive material. The Licensee has notified the NRC Resident Inspector.
ENS 543031 October 2019 09:15:00The following information was received via E-mail: A general licensee reports that following a recent inventory audit, they could not account for 17 missing tritium exit signs. The missing signs could not be accounted for physically by the licensee or verified through formal documentation that the signs were sent for disposal. The signs are believed to be Safety Light Corporation model number 2040 signs. The serial numbers were not reported. NC Tracking Number: NC 190033 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
ENS 5426811 September 2019 17:58:00A non-licensed contract supervisor had a confirmed positive for illegal drugs during a random fitness-for-duty test. The individual's authorization for site access has been terminated. The NRC Resident Inspector has been notified.
ENS 5427011 September 2019 19:00:00The following information was received from the Arizona Department of Health Services via E-mail: The Department (Arizona Department of Health Services) received notification that a tritium exit sign has been lost/stolen. The model is an Isolite 2040 with an activity of approximately 7.5 curies. The Department has requested additional information and continues to investigate the event. Arizona Incident Number: 19-018 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