Semantic search
Start date | Report date | Site | Reporting criterion | System | Event description | |
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ENS 56503 | 4 May 2023 15:45:00 | Indian Point | 10 CFR 20.1906(d)(2) | The following summary was provided by the licensee via phone: On May 4, 2023 at 1145 EDT, the licensee found contact dose rates of 215 and 555 millirem-per-hour at 2 separate spots on the top of an exclusive use package during receipt survey. These dose rates are above the 200 millirem-per-hour allowable. No loose surface contamination was identified. The package contains tools from Holtec and was intact on delivery. The package has subsequently been secured in a locked radiation storage building. No overexposure or unauthorized exposure resulted to plant personnel. The licensee suspects shielding, internal to the package, may have shifted and the licensee will investigate further. Dose rates at one foot from the package were recorded at 65 millirem per hour. | ||
ENS 53030 | 23 October 2017 11:40:00 | West Branch Regional Medical Center | 10 CFR 20.1906(d)(2) | At 0740 EDT on 10/23/2017, while performing equipment quality control, the nuclear medical technician identified that the incoming case containing less than 100 milliCuries of Tc-99 measured from 190-220 mR/hr on contact. The technician performed a surface wipe to identify contamination and determined that there was no leakage or spill of contamination. At 0850 the radiation safety officer was notified of the event. The case was then placed into a waste decay storage area away from other personnel. The company that shipped the package was also contacted regarding the situation. The type of isotopes provided were provided based on the ordered quantity, however, the technician reported that there might be other isotopes in the container, however could not verify without opening the container to look inside. | ||
ENS 52779 | 30 May 2017 12:00:00 | Veterans Health Administration | 10 CFR 20.1906(d)(2) | Pursuant to 10 CFR 20.1906, Veterans Health Administration (VHA) National Health Physics Program is notifying NRC of the receipt of two packages of radioactive material with removable surface contamination on the outside that exceeded NRC reporting limits. The packages were received on the morning of Tuesday, May 30, 2017, by the Robert J. Dole VA Medical Center in Wichita, Kansas. This facility is a site of use under the VA St. Louis Health Care System, St. Louis, Missouri, which holds VHA permit number 24-00144-05 under the VHA master materials license. The packages were surveyed at about 0700 CDT. The wipe tests performed on the external surfaces of the packages indicated removable contamination of about 1,450 and 1,390 dpm/cm2 as compared to the regulatory limit of 240 dpm/cm2 for beta-gamma emitters. The packages contained unit dosages of fluorine-18 fluorodeoxyglucose. The packages were shipped from Cardinal Health in Wichita, Kansas, which was also the final delivery carrier. A facility nuclear medicine technologist notified the final delivery carrier by telephone of the contaminated packages soon after discovery of the contamination. VHA National Health Physics Program, which manages the master materials license, was notified of the incident at about 1700 CDT on Wednesday May 31, 2017. The VHA is aware that this notification does not conform to the timeliness requirements in 10 CFR 20.1906. VHA will take appropriate action regarding this apparent noncompliance. VHA will notify our NRC Region III Project Manager of this incident.
On July 18, 2017, the review by the facility Radiation Safety Officer (RSO) determined the event was 'suspect' due to radiation levels from a dose calibrator inducing spurious results in the well counter used for package surveys. The package did not have external radioactive contamination. The root cause of the report of contamination was identified by the PET (Positron Emission Tomography) technologist. It was a result of counting the package wipes with a radioactive source in the adjacent dose calibrator causing crosstalk between the two instruments. Correct technique was discussed by the RSO with the PET technologist. In addition, staff training of the correct technique was provided for all department personnel. During an onsite inspection in January 2018, the root cause was verified with the inspector having a high degree of confidence that the Wichita facility did not receive an externally contaminated package on May 30, 2017. The licensee notified R3 (Parker). Notified R3DO (Orth) and NMSS Events Notification E-mail group. | ||
ENS 52676 | 13 April 2017 15:40:00 | Qal-Tek Associates, Llc | 10 CFR 20.1906(d)(2) | The following was received via email from the Licensee: At 0940 (MDT) on April 13th, 2017 (the common carrier) dropped off a 20 gallon drum (37.8 Kg) at Qal-Tek Associates (QTA) Idaho (ID) facility with an on-contact reading of 1.45 R/hr and a TI (Transport Index) of 15, both in excess of 10CFR20.1906(d)(2). No contamination existed on the inside or outside of the package. Upon further investigation, all three sources (Cs-137, 19.4 mCi; Cs-137, 23 mCi; and Co-60, 2.5 mCi) shipped in a gray lead pig were outside their gray lead pig and in the Type 7A drum. The gray lead pig was found packaged upright in the drum with a slight tilt. The pig lid was intact and properly seated on the pig base. Apparently, the lid was displaced enough during shipment that all three sources came out of the pig by the time they arrive(d) at QTA ID. The root cause appears to be from improper sealing of the gray pig. The pig wasn't taped or strapped shut to prevent displacement of the pig and lid resulting in the release of the sources. The shipper confirmed the sources where originally placed in the gray pig around 1100 (MDT). The (common) carrier was contact(ed) at 1140 (MDT). Assuming the maximally exposed member of the public was (the common carrier) transport employee, and they were on-contact with the drum at the highest reading, they could have potentially received 100 mrem in a little over 4 minutes. Likewise, they could have received 2 mrem in 5 seconds. Considering the TI of 15 mrem/hour, the MEI (maximally exposed individual) could potentially receive 100 mrem in 6.67 hours and 2 mrem in 0.13 hours. | ||
ENS 52658 | 3 April 2017 14:45:00 | Susquehanna | 10 CFR 20.1906(d)(2) 10 CFR 20.1906(d)(1) | This is being reported under 10CFR20.1906(d)(1,2). At 1045 hours (EDT), the SSES (Susquehanna Steam Electric Station) Radwaste shipper was notified by the RP (Radiation Protection) shipping technician performing a receipt survey of an open transport vehicle shipped exclusive use carrying an empty radwaste liner exceeded the 10CFR71.47(b)(1) vehicle contact dose rates of 200 mR/hr. Per NDAP-QA-0720 (Nuclear Department Administrative Procedure) Attachment E, contaminated /radioactive shipments this is a 1 hour notification for exceeding the radiological receipt survey requirements of 200 mR/hr at any point on the outer surface of the vehicle. The vehicle was from Energy Solutions. The licensee will be using the vehicle to transport radwaste from the facility. The licensee has notified the Pennsylvania Emergency Management Agency and the NRC Resident Inspector. | ||
ENS 52144 | 29 July 2016 12:00:00 | Gainesville Veterans Administration Medical Center | 10 CFR 20.1906(d)(2) | Per 10 CFR 20.1906(d), Veterans Health Administration (VHA) National Health Physics Program is reporting receipt of a package of radioactive material with removable surface contamination on the outside of the package greater than NRC reporting limits. The package was received Friday, July 29, 2016, at around 0700 EDT by the North Florida / South Georgia Veterans Health System in Gainesville, Florida. This facility holds permit number 09-12467-02 under the VHA master materials license. The package was checked-in and surveyed upon receipt around 0700 EDT. Wipe tests performed on the external surface of the package indicated a removable contamination level of around 347 dpm/cm2 as compared to the regulatory limit of 220 dpm/cm2 for beta-gamma emitters. The package contained one unit dosage of about 57 millicuries of fluorine-18 (as fluorodeoxyglucose) at the time of receipt. The dosage was shipped from PETNET Solutions, Inc., out of Jacksonville, Florida, who was also the delivery carrier. The facility nuclear medicine technologist immediately notified the delivery carrier by phone about the contaminated package around 0710 EDT. The patient dosage inside the package was not impacted and was able to be used. As corrective actions, the packaging materials were set aside in a restricted area at the facility. VHA National Health Physics Program, who manages the master materials license, was notified of the incident around 1030 EDT on August 2, 2016. In addition, we notified our NRC Region III Project Manager of the event. This event was reported to the State of Florida by the shipper, PETNET Solutions, Inc., and entered by the NRC as an Agreement State report (EN 52141). | ||
ENS 51042 | 5 May 2015 11:15:00 | Department Of Veteran Affairs | 10 CFR 20.1906(d)(2) | Per 10 CFR 20.1906(d)(1), (the Veterans Health Administration (VHA) is) reporting receipt of a package of radioactive material with removable surface contamination on the outside of the package greater than NRC reporting limits. The package was received today (May 5, 2015) and surveyed for contamination around 0615 CDT by Captain James A. Lovell Federal Health Care Center, North Chicago, Illinois. The health care center holds permit number 12-10057-04 issued by VHA per the MML (Master Materials License). Wipe tests performed on the external surface of the package indicated a removable contamination level of 690 dpm/cm2 as compared to the regulatory reporting limit of 240 dpm/cm2 for beta-gamma emitters. The package contained five unit dosages of Technetium-99m (about 144 millicuries total) and was shipped and delivered by Triad Isotopes in Elk Grove, Illinois. The nuclear medicine technologist who surveyed the package immediately notified, by telephone, the Pharmacy Manager at Triad Isotopes about the contaminated package. The exterior of the package was able to be decontaminated by the nuclear medicine technologist to levels below reporting limits by performing successive wipes on the surface. The inner packaging materials and dosage containers were surveyed and no contamination was identified such that the dosages were not impacted. There was no spread of contamination at the health care center from the package. The contaminated materials have been isolated in a restricted area at the health care center and will be held for decay. Veterans Health Administration (T. Huston) has also notified NRC Region III (K. Null) by telephone of this event. | ||
ENS 50852 | 27 February 2015 20:18:00 | Perry | 10 CFR 20.1906(d)(2) | Control Rod | At 1518 EST on Feb 27, 2015, the Perry Shift Manager received notice from the Radiation Protection group that an Exclusive Use closed transport vehicle arrived on site exceeding the 10 CFR 71.47 radiation levels on contact with a box on the vehicle. The truck that arrived had two boxes containing four rebuilt control rod drive mechanisms to be used during the Perry refueling outage. One of the boxes had a contact dose reading of 1290 MR/HR. This is above the 1000 MR/HR limit as noted in 10 CFR 71.47. No other limits were exceeded on the exterior of the vehicle. Specifically, the cab of the truck was reading 0.1 MR/HR which is less than the 2 MR/HR limit. Also at 2 meters around the truck, the highest level reading was 1.2 MR/HR which is below the 10 MR/HR (limit). Also on direct contact with the outside of the vehicle, the highest reading was 30 MR/HR, which is below the 200 MR/HR limit. The Site Radiation Protection Shipping Coordinator contacted the shipping organization of this finding at Perry. This was the Director of Operations of Energy Solutions in Memphis, Tennessee. The box was taken into the Perry Fuel Handling Building and is posted per the Perry Radiation Control Program. The vehicle is parked outside the Fuel Handling Building and is being controlled. The NRC Resident Inspector has been informed. | |
ENS 49612 | 6 December 2013 06:00:00 | Missouri Baptist Medical Center | 10 CFR 20.1906(d)(2) | The Missouri Baptist Medical Center, in Saint Louis, MO, received an unlabeled package from a supplier in Valencia, CA, which contained 2 spot markers, each containing 50 microCi of Co-57. The package was an expected shipment; however, there was no labeling on the outside of the package indicating the presence of radioactive material. The radiation reading on the outside of the package was 1 mR/hr. The package was opened to verify contents and the material is being maintained in a secure location. No personnel over exposures occurred. The supplier was notified by the licensee of the mislabeling. | ||
ENS 49380 | 24 September 2013 05:00:00 | Carroll County Memorial Hospital | 10 CFR 20.1906(d)(2) | The licensee's RSO (Radiation Safety Officer) reported that a package received from the pharmaceutical supplier was contaminated externally. Swipes from the outside of the package had counts of 91,500 cpm (counts per minute) with a background count reading of 588 cpm. Swipes from inside the package had counts of 1008 cpm. There were no indications of contamination to personnel or the surrounding area. The pharmaceutical supplier was contacted and has verified the driver was not contaminated. They will also check the delivery vehicle. The package, containing Iodine-131 (18 mCi) and Technetium-99m (6 mCi) sources, has been placed in a secure location pending further investigation. | ||
ENS 49231 | 1 August 2013 13:00:00 | B&W Nuclear Operating Group, Inc. | 10 CFR 20.1906(d)(2) | The conditions for reporting under the requirements of 10 CFR 20.1906(d) have been met. QWI 14.1.10, Classification & Notification Criteria for Unusual Incidents Radiation Protection section - for shipments, bases reporting requirements on receipt of a shipment with radiation or contamination levels in excess of 10 CFR 20.1906(d). This requirement was exceeded and an NRC report is required. The truck cab sleeping area (normally occupied space) dose rate of 5.4 mrem/hr is greater than the allowable limit of 2.0 mrem/hr. The carrier drivers (2) state that they do not have dosimetry. Immediate actions that have been taken: - The area was secured. - Confirmatory measurements were taken. - Digital photographs have been taken. - The shipper has been notified. - A review of the associated regulations was performed. - The carrier has been notified. - The truck has been unloaded and released. The shipment contained Am241/Be sources sent from QSA Global in Burlington, MA for use in refurbishing sources, typically well-logging. The estimated departure time/date was 0800 EDT on 07/31/13 with estimated arrival time/date of 0800 EDT on 08/01/13. The driver team consisted of two (2) individuals during the 24-hour transit time. The shipment was off-loaded and secured following the receipt rad survey. The licensee notified the shipper, the carrier, the Commonwealth of Virginia and informed the NRC Resident Inspector. * * * RETRACTION FROM TONY ENGLAND TO PETE SNYDER AT 1702 EDT ON 8/5/13 * * * This event has been reported to the Commonwealth of Virginia under Event Number VA-13-04. The material involved in this event is regulated under Commonwealth of Virginia License. Notified R2DO (King), R1DO (Trapp), FSME Event Resource (email), and FUELS OUO (email). | ||
ENS 49229 | 31 July 2013 15:15:00 | Va Southern Nevada Healthcare System | 10 CFR 20.1906(d)(2) | Per 10 CFR 20.1906(d)(2), the Veterans Health Administration (VHA) reported receipt of a package of radioactive material with external radiation levels exceeding NRC reporting limits (as referenced in 10 CFR 71.47). The package was received today (July 31, 2013) around 0815 PDT by the VA Southern Nevada Healthcare System, North Las Vegas, Nevada. This medical center holds permit number 27-00593-01 under the VHA master materials license. The package was surveyed by the VA facility nuclear medicine technologist with a pressurized ionization chamber. Readings were 160 mR/hr on the top surface of the shipping container and 32 mR/hr at 1 meter away from the top of the container (i.e., Transport Index = 32, which exceeded the NRC reporting limit of 10). Removable radioactivity tests of the external package surfaces were within regulatory limits. The shipping container lacked proper shielding on the top and bottom. The package contained 2 lead pigs each containing F-18 (half-life 110 minutes). One source was assayed at 0929 PDT on 7/31/2013 at 350 mCi. The other source was calibrated for 12 mCi at 1100 PDT. The VA facility Nuclear Medicine Technologist immediately notified, by telephone, Cardinal Health in Las Vegas, NV, who was the package shipper and final delivery carrier, regarding the high readings from the package. The vendor contact person acknowledged that the incorrect shipping box was used and the source should have been shipped later in the day. As corrective actions, the VA facility technologist isolated the package in the VA medical center hot lab, and additional lead shielding was placed on the top of the package. VHA has also notified NRC Region III (Null) by telephone of this event. | ||
ENS 47712 | 1 March 2012 14:15:00 | B&W Nuclear Operating Group, Inc. | 10 CFR 20.1906(d)(2) | Evaluation of LTC (Lynchburg Technology Center) AmBe Shipment issues for 03/01/12 receipt. The conditions for reporting under the requirements of 10 CFR 20 1906(d) have been met. QWI 14.1.10 Classification & Notification Criteria for Unusual Incidents Radiation Protection section - for shipments, bases reporting requirements on receipt of a shipment with radiation or contamination levels in excess of 10 CFR 20.1906(d). This requirement was exceeded and an NRC report is required. The truck cab sleeping area (normally occupied space) dose rate of 3.4 mRem/hr is greater than the allowable limit of 2.0 mRem/hr. The private carrier personnel state that they do not have dosimetry. Immediate Actions Taken: Digital photographs have been taken, confirmatory surveys (with other instruments) were taken, additional spot surveys were taken, the shipper has been notified, and an evaluation of the regulations has been made. The licensee informed the NRC Resident Inspector. | ||
ENS 47641 | 6 February 2012 18:15:00 | Va Medical Center | 10 CFR 20.1906(d)(2) | Per 10 CFR 20.1906(d), (The Department of Veterans Affairs is) reporting receipt of a package of radioactive material with removable surface contamination on the outside of the package greater than NRC reporting limits. The package was received today (February 6, 2012) at around 12:15 PM ET by VA Medical Center, West Palm Beach, Florida. The VA Medical Center, West Palm Beach, Florida, holds permit number 09-25328-01 under the master materials license. A wipe test performed on the external surface of the package indicated a removable contamination level of 962 dpm/cm2 as compared to the regulatory limit of 220 dpm/cm2. The package contained Technetium-99m labeled radiopharmaceuticals and was shipped from Cardinal Health in Jupiter, Florida. The vendor/shipper serves as the final delivery carrier. The VA facility Radiation Safety Officer immediately notified the vendor about the contaminated package at about 12:30 PM ET. As corrective action, the package was set aside in a restricted area at the VA Medical Center to provide time for decay. The permittee does not plan to use the dosage. | ||
ENS 47394 | 1 November 2011 12:10:00 | Providence Park Hospital | 10 CFR 20.1906(d)(2) | Providence Park Hospital received an externally contaminated package from Hot Shots Nuclear Pharmacy (HSNP). Upon receipt of the package, the Nuclear Medical Technologist (NMT) performed a routine wipe test and determined the package was externally contaminated. Wipe test indicated surface contamination of 60,608 dpm (disintegrations per minute). The Radiation Safety Officer (RSO) was notified and the package was bagged and stored in a hot lab for decay. The package contained approximately 70 mCi of technetium-99m. There was no indication of any personnel contamination or exposure. The package will be shipped back to HSNP, after isotope decay is complete, for follow up investigation and recommendation. HOO Note: See EN #47392 for similar report. | ||
ENS 46378 | 26 October 2010 17:00:00 | Ge Health Care | 10 CFR 20.1906(d)(2) | The licensee reported receipt of a package of radioactive material with removable surface contamination on the outside of the package greater than the reporting limits of 220 dpm per cm squared. The package contained returned material, Tc-99m (Technetium), that was being shipped back to the company from a nearby customer in Rodchester Hills, MI. A wipe test performed on the external surface of the package indicated a removable contamination level of 583 dpm per cm squared. A survey inspection of the receiving area did not find any contamination and other survey results were inconclusive. The surface contamination appears to be Tc-99m. No personnel contamination resulted from the incident and the package is being stored in a secured area. | ||
ENS 45948 | 24 May 2010 12:45:00 | Department Of Veterans Affairs | 10 CFR 20.1906(d)(2) | (A representative) with the Department of Veterans Affairs, VHA National Health Physics Program provided the following report. This report involves NRC master materials license no. 03-23853-01VA. (The VHA representative) called, as required by 10 CFR 20.1906(d), to report receipt of a package of radioactive material with removable surface contamination on the outside of the package greater than reporting limits. The package was received today (May 24, 2010) at around 7:45 AM CT by the Central Texas Veterans Healthcare System, Temple, Texas. A wipe test performed on the external surface of the package indicated a removable contamination level of 562 dpm/cm2 as compared to the regulatory limit of 220 dpm/cm2. Surveys inside the package did not indicate elevated contamination. The package contained Tc-99m (Technetium) labeled radiopharmaceuticals and was shipped from Specialty Pharmaceutical Services, Inc., in Temple, Texas. The vendor/shipper also serves as the delivery carrier. The VA facility staff immediately notified Specialty Pharmaceutical Services, Inc. about the contaminated package at about 9:30 AM CT. (The VHA representative) will notify the NRC Project Manager at NRC Region III of this event. The permittee holds VHA Permit Number 42-10739-03. | ||
ENS 44539 | 3 October 2008 22:21:00 | Vermont Yankee | 10 CFR 20.1906(d)(2) | Received Shipment from Pilgrim Station of temporary lead shielding that exceeds 10 CFR 20 requirements for a non-exclusive use limited quantity shipment of 0.5 mR on contact. Receipt inspection readings of the last container in the shipment measured between 1.3 mR and 1.85 mR (taken via 3 readings, using 3 separate meters and 2 different technicians). Per 10CFR20 subpart 1906 paragraph D, which states: (d) The licensee shall immediately notify the final delivery carrier and the NRC Operations Center (301-816-5100), by telephone, when -- (1) Removable radioactive surface contamination exceeds the limits of section 71.87(i) of this chapter; or (2) External radiation levels exceed the limits of section 71.47 of this chapter. The licensee notified the NRC Resident Inspector.
NRC Notification 44539 was conservatively made due to conservative procedural guidance. 10 CFR 20.1906(d)(2) requires immediate notification of the final delivery carrier and the NRC Operations Center when external radioactive levels exceed the limits of section 71.47 of this chapter. The reporting threshold contained in 10 CFR 71.47 is 200 mR (per hour) at any point on the external surface of the package. Since actual measured levels were between 1.3 mR (per hour) and 1.85 mR (per hour) this event is not reportable. ENS Event Number 44539, made on 10/03/08, is being retracted. The NRC Resident Inspector will be notified by the licensee of this retraction. Notified R1DO (Jackson) & NMSS EO (Regan). | ||
ENS 44389 | 15 July 2008 04:00:00 | Va Medical Center, Fayetteville, North Carolina | 10 CFR 20.1906(d)(2) | The package was received July 15, 2008 by the VA Medical Center in Fayetteville, North Carolina. The VHA National Health Physics Program was notified of the event on August 7, 2008, at 9:30 AM ET. A wipe test performed on the external surface of the package upon receipt on July 15, 2008 indicated a removable contamination level of 254 (disintegrations per minute per square centimeter) as compared to the regulatory limit of 220 (disintegrations per minute per square centimeter). Surveys inside the package did not indicate elevated contamination. The package contained radiopharmaceuticals with Tc-99m and was shipped from Cardinal Health in Fayetteville, North Carolina. The vendor/shipper also serves as the delivery carrier. The shipper/delivery carrier was immediately notified of the contaminated package after the receipt survey on July 15, 2008 by a nuclear medicine technologist at the VA Medical Center. | ||
ENS 44101 | 27 March 2008 20:00:00 | Hiro Makino | 10 CFR 20.1906(d)(2) | At 1000 HST on 03/27/08 a package containing 3 unit doses of Tech 99 (M) was delivered by Pacific Radiopharmacy to the licensee. Wipe survey of shipping bag handle revealed 20000 dpm on a 300 square centimeter wipe. A single wipe of all three unit dose pigs revealed 14000 dpm. The delivery carrier was notified and reported that no contamination was found on the transport vehicle or the driver. The unit dose pigs were decontaminated and the shipping bag was stored for decay. | ||
ENS 44026 | 3 March 2008 16:26:00 | Areva Np Inc | 10 CFR 20.1906(d)(2) | On March 3, 2008 at approximately 1126 EST, the Radiation Protection organization at AREVA NP Inc. Lynchburg, determined that a shipment of fuel services equipment (Box 0454) exceeded the 200 mrem/hour dose rate specified in 10 CFR 71.47 (b)(1). The equipment was being returned after use during a refueling outage. Radiation Protection surveyed the shipping container and obtained a reading of approximately 340 mrem/hour. In accordance with 10 CFR 20.1906(d)(2) the final delivery carrier has also been notified. This immediate notification is being made in accordance with the requirements of 10 CFR 20.1906(d)(2) and 10CFR 71.47(b)(1). The fuel cleaning equipment had been recently used during a refueling outage at Watts Bar.
Mr. Wertz reported that area around the hot spot on the container was smeared, and no evidence of loose surface contamination exists. Notified R1DO(Caruso), FSME(Morell), and NMSS(Giitter) | ||
ENS 43957 | 4 February 2008 15:20:00 | Watts Bar | 10 CFR 20.1906(d)(2) | On February 4, 2008 at approximately 10:20 EST, the Radiation Protection organization at Watts Bar Nuclear Plant (WBN), notified the Shift Manager (Licensed SRO) that a shipment of miscellaneous equipment exceeded the 200 mrem/hour dose rate specified in 10 CFR 71.47. The equipment was being received for use in an upcoming refueling outage. Radiation Protection surveyed the shipping container and obtained a reading of approximately 2000 mrem/hour. In accordance with 10 CFR 10.1906(d) the final delivery carrier has also been notified. This immediate notification is being made in accordance with the requirements of 10 CFR 20.1906(d)(2) and 10 CFR 71.47. The licensee notified the NRC Resident Inspector. | ||
ENS 43918 | 18 January 2008 22:03:00 | Susquehanna | 10 CFR 20.1906(d)(2) 10 CFR 50.72(b)(2)(xi), Notification to Government Agency or News Release | At 1703 EST on 1/18/2008, Susquehanna LLC personnel became aware that a shipment received from GE Hitachi Nuclear Energy exceeded the allowable limit of 200 mr/hr contact dose rate. The external radiation limit of 200 mrem/hr was exceeded on one of the two boxes comprising the shipment. The limit per NDAP-QA-0648 is 200 mrem/hr on contact for a shipment type for a transport vehicle which is not designated exclusive use. The actual value was determined to be 350 mrem/hr, therefore reportable per the requirements of 10CFR20.1906(d)(2). The NRC Resident Inspector and the Shipper (GE Hitachi Nuclear Energy) were notified. The transport vehicle left Wilmington NC on 1/17/2008 at 1435 and was received by SSES (Susquehanna Steam Electric Station) on 1/18/2008 at 0800. There was no surface contamination noted on the shipment. The original survey completed prior to shipment noted the highest on contact dose rate was 170 mr/hr. This item is reportable under 50.72(b)(2)(xi) for offsite notification of an event of public interest. The boxes contained various pieces of equipment that GE uses to support refueling. The licensee has notified the NRC Resident Inspector and will be notifying the Pennsylvania Emergency Management Agency. | ||
ENS 43587 | 23 August 2007 18:54:00 | Grand Gulf | 10 CFR 20.1906(d)(2) | A package removed from the transport flatbed had a gamma dose rate of 224 (millirem per hour) on contact which exceeded the 10 CFR 71.47 limit, and is therefore reportable per 10 CFR 20.1906(d)(2). No issue with personnel exposure or a dose to public since the highest dose rate was found on the bottom of the package which was secured to the flatbed. No other limits were exceeded. The licensee notified the NRC Resident Inspector. | ||
ENS 42824 | 1 September 2006 15:15:00 | Susquehanna | 10 CFR 20.1906(d)(2) | At 1115 EDT on 9/01/2006, Susquehanna LLC personnel became aware that a shipment received from another site exceeded the 10CFR71.47(b)(2) limit of 200 mr/hr contact dose rate. Contact dose rates on the bottom of the shipment are 820 mr/hr, and therefore reportable per the requirements of 10CFR20.1906(d)(2). There is no identified surface contamination on the shipment, and the shipment only exceeded the dose rate limit on the bottom once it was lifted off the transport trailer. Doses under the trailer prior to lifting the shipment did not exceed the limit The transport company and the originating site have been notified. The transport vehicle left the Vermont Yankee facility on 8/31/06 and was received by SSES on 9/1/06 at 0805." . . . The driver has been contacted by the transport company. The vehicle made two stops during transport. The first was at the first rest stop traveling west on the Massachusetts Turnpike. The second was at the first rest stop on I-87 south after exiting I-90. No one to the knowledge of the driver came in contact with the shipment. The driver arrived at Susquehanna on 8/31/06 at 2045, and slept in the truck. The driver was wearing dosimetry (TLD). The licensee will notify State of Pennsylvania Emergency Management and has notified the NRC Resident Inspector. | ||
ENS 42344 | 16 February 2006 18:00:00 | St Marys Health Care | 10 CFR 20.1906(d)(2) | The RSO for St Marys Health Care performed receipt inspections on two packages delivered from Cardinal Health Pharmacy in Denison, MI that contained 9 milliCuries of I-131 and 14 milliCuries of I-131. The package that contained the 9 milliCurie source had external radiation levels of 0.08 mRem/hr at 3 feet and 1.5 mRem/hr on the surface, and external removable contamination of 16,000 DPM of Tech 99 (gamma emitter). That package also had removable surface contamination on the exterior of the source container inside the packaging material of 619,000 DPM of Tech 99. The second package that contained the 14 milliCurie source had external radiation levels of 0.08 mRem/hr at 3 feet and 1.5 mRem/hr on the surface, and external removable contamination of 5,000 DPM of Tech 99. That package also had removable surface contamination on the exterior of the source container inside the packaging material of 320,000 DPM of Tech 99. The licensee immediately notified the RSO for Cardinal Health Pharmacy in Denison, MI concerning the delivery. | ||
ENS 41427 | 21 February 2005 18:45:00 | BWX Technologies | 10 CFR 20.1906(d)(2) | THIS IS NOT A NEW REPORT. This event report was originally withheld from public release under the NRC's policy for protecting sensitive unclassified information. The NRC has reevaluated this policy and is now making this event report available to the public with suitable redactions.
EXTERNAL RADIATION LEVELS EXCEEDED THE TRANSPORTATION INDEX (TI) LIMIT OF 10. On 2/16/05 a radioactive Yellow - III shipment containing eight well logging sources was shipped from Baker Hughes Inteq in Houston, TX. The shipment of sources, Am-241/Be (1480 GBq), arrived at BWXT in Lynchburg, VA. On 02/21/05. Emery Worldwide indicated the shipment mode had a Transportation Index (TI) reading of 9, however, BWXT's reading was 12.6. BWXT placed the package in a restricted area to minimize exposure to personnel, which has a surface contact reading of 83.3 millirem/hr, and at one meter away it read 12.6 millirem/hr. Since this shipment had a TI >10 it was reportable under 10CFR 20.1906. (Note: Transportation Index is the radiation reading in millirem/hr at a distance of one meter.) Licensee notified NRC Resident Inspector and final carrier.
THIS IS NOT A NEW REPORT. This event report was originally withheld from public release under the NRC's policy for protecting sensitive unclassified information. The NRC has reevaluated this policy and is now making this event report available to the public with suitable redactions.
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ENS 41289 | 23 December 2004 05:00:00 | Framatome Anp | 10 CFR 20.1906(d)(2) | On a shipment received from Hope Creek, one of eight packages had a high radiation level on the bottom of the package. The radiation level was 236 millirem/hour. The packages contained nuclear service equipment. Packages were offloaded and placed in a secure area of the plant. The package has not been opened. Framatome has notified Hope Creek and will notify the shipper. | ||
ENS 40989 | 27 August 2004 12:15:00 | Va Medical Center | 10 CFR 20.1906(d)(2) | The event occurred at a medical broad-scope permittee authorized under the master materials license issued to the Department of Veterans Affairs, NRC License 03-23853-OIVA. The permittee is VA Medical Center, Durham, North Carolina. The event occurred on August 27, 2004, and was discovered at 8:15 AM EDT on the same day. The basis for the event is under 10 CFR 20.1906(d)(2) in that a package received in the nuclear medicine service of the: VA Medical Center, Durham, North Carolina measured 250 mrem/hr at a point on the external surface of the package. Photon Imaging Corporation (a commercial radiopharmacy located in Raleigh, North Carolina) delivered the package containing a Tc-99m baulk vial to the nuclear medicine service of the VA Medical Center, Durham, North Carolina. .A survey of the surface of the delivery container indicated a point on its external surface that measured 250 mrem/hr and 4 mrem/hr @) 1 meter. Wipe surveys, however, did not indicate any removable contamination. Upon inspection of the package, it was discovered that the cap of the shield containing a baulk dose of Tc-99m of 137.6 mCi had inadvertently fallen loose and was no longer shielding the vial. There was no indication that the vial itself was damaged or that any of the Tc-99m had leaked into the package. The permittee user does not anticipate any adverse medical effects to patients, staff or members of the public. The permittee immediately notified the commercial vendor. The Department of Veterans Affairs will evaluate the circumstances related to the event and submit a written report to NRC Region 3, within 15 days. | ||
ENS 40560 | 2 March 2004 14:30:00 | Grand Gulf | 10 CFR 20.1906(d)(2) | The license received a 20 box shipment of fuel sipping equipment from Framatone ANP, Inc out of Richland, WA. One of the 20 boxes was determined to have an external surface contact reading >200 millirem (actual reading 202 millirem). The box was opened and contents surveyed resulting in a reading of 400 millirem/hr coming from a support stand that was in the package. A hot particle was captured from the stand and properly disposed of with their rad waste. After the particle had been removed, the stand, readings went from 400 millirem/hr to 20 millirem/hr. The licensee notified Framatone ANP about the incident. The Resident Inspector was notified | ||
ENS 40485 | 28 January 2004 13:00:00 | BWX Technologies | 10 CFR 20.1906(d)(2) | THIS IS NOT A NEW REPORT. This event report was originally withheld from public release under the NRC's policy for protecting sensitive unclassified information. The NRC has reevaluated this policy and is now making this event report available to the public with suitable redactions.
THE LICENSEE RECEIVED A PACKAGE CONTAINING Cs-137 WHICH EXCEEDED EXTERNAL RADIATION LIMITS BWXT received two type A packages packed inside a larger package from Baker Hughes in Houston, TX on 1/27/04. When they opened the larger package, they discovered that one of the type A packages containing a single 2.5 curie Cs-137 source exceeded the limits (200 mr/hr) for external radiation. The package was measuring 375 mr/hr, however the surface smears were within limits and the package was intact. The seal numbers on the package and manifest matched. The licensee notified both Baker Hughes and the transport company, Emery Worldwide, of the problem. The NRC Resident Inspector was notified.
THIS IS NOT A NEW REPORT. This event report was originally withheld from public release under the NRC's policy for protecting sensitive unclassified information. The NRC has reevaluated this policy and is now making this event report available to the public with suitable redactions. | ||
ENS 40397 | 17 December 2003 17:30:00 | LaSalle | 10 CFR 20.1906(d)(2) | This notification is being made in pursuant to Exelon Reportability manual RAD 1.11 and 10 CFR 20.1906(d)(2). At 11:30 CST on 12/17/03, Radiation Protection Technician notified the Shift Manager that a Radiation Shipment (03-1216-02) was received at LaSalle from Duratek (Memphis, TN) that exceeded 200 mrem/hr on the external surface of the package. In accordance with 10 CFR 71.47(b)(1) the package was not in a closed transport vehicle and thus did not meet the exclusion to allow the package to be greater than 200 mrem/hr and less than 1000 mrem/hr. The as found readings on the package were measured at 211 mrem/hr and verified with a second instrument at 207 mrem/hr. The package was also surveyed for contamination and found to be free of loose contamination. Pursuant to 10 CFR 20.1906(d)(2), the final delivery carrier (R&R Trucking Co) was also notified of this event. The licensee has notified the NRC Resident Inspector. |