U.S. Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards
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The organization U.S. Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards represents an institution, an association, or corporate body that is associated with resources found in Missouri University of Science & Technology Library.
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U.S. Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards
Resource Information
The organization U.S. Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards represents an institution, an association, or corporate body that is associated with resources found in Missouri University of Science & Technology Library.
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- U.S. Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards
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- Office of Nuclear Material Safety and Safeguards
454 Items by the Organization U.S. Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards
7 Items that are about the Organization U.S. Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards
Context
Context of U.S. Nuclear Regulatory Commission, Office of Nuclear Material Safety and SafeguardsCreator of
No resources found
No enriched resources found
- Status of decommissioning program
- Final generic environmental impact statement on uranium milling, Project M-25
- Transient shipment rule value-impact analysis
- Final environmental impact statement on 10 CFR part 61 "licensing requirements for land disposal of radioactive waste."
- The U.S. Nuclear Regulatory Commission and how it works
- Environmental impact statement for the Reno Creek in Situ Recovery Project in Campbell County, Wyoming : supplement to the generic environmental impact statement for in-situ leach uranium milling facilities, final report
- NMSS news link
- Environmental impact statement for the Reno Creek in Situ Recovery Project in Campbell County, Wyoming : supplement to the generic environmental impact statement for in-situ leach uranium milling facilities, draft report for comment
- NMSS licensee newsletter
- Draft environmental impact statement on 10 CFR part 61 "licensing requirements for land disposal of radioactive waste."
- NMSS licensee newsletter
- NMSS licensee newsletter
- Descriptions of United States uranium resource areas : a supplement to the Generic environmental impact statement on uranium milling
- A radiological assessment of radon-222 released from uranium mills and other natural and technologically enhanced sources : final report
Contributor of
No resources found
No enriched resources found
- Year 2000 effect on computer system software
- (1) Erroneous data in "Nuclear safety guide, TID-7016, Revision 2," (NUREG/CR-0095, ORNL/NUREG/CSD-6 (1978)) and (2) Thermal scattering data limitation in the cross-section sets provided with the KENO and Scale codes
- 10 CFR 34.20, final effective date
- 10 CFR 34.43 (a) 1; Effective date for radiographer certification and plans for enforcement discretion
- 1997 enforcement sanctions for deliberate violations of NRC employee protection requirements
- 1998 enforcement sanctions as a result of deliberate violations of NRC employee protection requirements
- 1999 enforcement sanctions for deliberate violations of NRC employee protection requirements
- A compendium of spent fuel transportation package response analyses to severe fire accident scenarios : draft report for comment
- A compendium of spent fuel transportation package response analyses to severe fire accident scenarios, final report
- A compilation of current regulations, standards, and guidelines in remote afterloading brachytherapy
- A method of generating multigroup transfer matrices using an analytic angular integration free of truncation error
- A probabilistic safety analysis for solidified high-level nuclear waste management systems : a status report
- A review of geoscience characteristics and disposal experience at the commercial low-level radioactive waste disposal facility near West Valley, New York
- ANSI N14.5-2014 revision and leakage rate testing considerations
- AUTOCASK (AUTOmatic generation of 3-D CASK models) : a microcomputer based system for shipping cask design review analysis
- Acceptability of corrective action programs for fuel cycle facilities : draft report for comment
- Acceptable standard format and content for the material control and accounting plan required for low-enriched uranium enrichment facilities : draft report for comment
- Accidental disposal of radioactive materials
- Accidental radiation overexposures to personnel due to industrial radiography accessory equipment malfunctions
- Accuracy of Information provided to NRC during the licensing process
- Additional controls for transport ot the Amersham Model no. 660 Series radiographic exposure devices
- Analysis of severe railway accidents involving long duration fires
- Analysis of severe roadway accidents involving long duration fires
- Analysis of structural materials exposed to a severe fire environment
- Annual financial surety update requirements for uranium recovery licenses
- Antifreeze agents in fire water sprinkler systems
- Applicability of patient intervention in determining medical events for gamma stereotactic radiosurgery and other therapy procedures
- Appointment of radiation safety officers and authorized users under 10 CFR Part 28
- Assessing the environmental availability of uranium in soils and sediments
- Authorized contents of spent fuel casks
- Availability of U.S. Food and Drug Administration (FDA)-approved potassium Iodide for use in emergencies involving radioactive iodine
- Best practice concepts for patient release
- Bias estimates used in lieu of validation of fission products and minor actinides in MCNP Keff calculations for PWR burnup credit casks
- Biodiesel in fuel oil could adversely impact diesel engine performance
- Blocking, bracing, and securing of radio-active materials packages in transportation
- Brachytherapy incidents involving iridium-192 wire used in endobronchial treatments
- Brachytherapy incidents involving treatment planning errors
- Brachytherapy source management
- Broad-scope licensees' responsibilities for reviewing and approving unregistered sealed sources and devices
- Buckling analysis of spent fuel basket
- CSRL-V, processed ENDF/B-V 227-neutron-group and pointwise cross-section libraries for critical safety, reactor and shielding studies
- Calculation of surface activity for contaminated equipment and materials
- Changes to 10 CFR Parts 71 and 72 quality assurance programs
- Changes to 10 CFR part 71 packages
- Clarification of CFR 10.22, small quantities of source material
- Clarification of criticality reporting criteria
- Clarification of the recent revisions to the regulatory requirements for packaging of uranium hexafluoride (UF6) for transportation
- Clarification of transportation requirements applicable to return of spent radiopharmacy dosages from users to suppliers
- Classification of transportation emergencies
- Collapse of an Isocam II, dual-headed nuclear medicine gamma camera
- Combustibility of epoxy floor coatings at commercial nuclear power plants
- Commercial-grade dedication issues identified during NRC inspections
- Compliance with 10 CFR Part 20 for airborne thorium
- Compliance with 10 CFR Part 21, "Reporting of Defects and Noncompliance"
- Compliance with new decommissioning rule
- Compliance with the general license provisions of 10 CFR Part 31
- Computational fluid dynamics best practice guidelines for dry cask applications : final report
- Concrete degradation by alkali-silica reaction
- Conference proceedings for Workshop on Radiological Surveys in Support of the Edgemont Clean-up Action Program : held at Denver, Colorado, January 21-22, 1981
- Consolidated guidance about materials licenses : guidance about admiistrative licensing procedures: draft report for comment
- Nuclear fuel thermal conductivity degradation
- Numerical modeling of ground-water flow systems in the vicinity of the Reference Repository location, Hanford Site, Washington
- Out-of-service equipment connected to in-service process line results in fissile solution spill at fuel cycle facility
- Oversight of design and fabrication facilities for metal components used in spent fuel dry storage systems
- Patient skin contamination events associated with I-131 metaiodobenzylguanidine during neuroblastoma treatments
- Pending expiration of the NRC type B transportation package certificate for Sentinel Model 660 Series radiographic projectors on June 30, 2013
- Personnel injuries resulting from improper operation of radwaste incinerators
- Pipe support anchors installed improperly
- Portable moisture/density gauges : recent incidents of portable gauges being stolen or lost
- Possession limits for special nuclear material at the Envirocare of Utah low-level radioactive waste disposal facility
- Possible flaws in certain piping systems fabricated by Associated Piping and Engineering
- Potential absence of required lock washers in BSI Instruments, Inc. LB 7400 series fixed gauges
- Potential chloride-induced stress corrosion cracking of austenitic stainless steel and maintenance of dry storage casks system canisters
- Potential electrical equipment problems
- Potential errors in manual brachytherapy dose calculations generated using a computerized treatment planning system
- Potential failure of fire water supply pumps to automatically start due to a fire
- Potential for failure of the Omega Series sprinkler heads
- Potential hazards due to volatilization of radionuclides
- Potential non-conservative error in modeling geometric regions in the Keno-V.A criticality code
- Potential non-conservative error in preparing problem-dependent cross sections for use with the Keno V.A or Keno-vi criticality code
- Potential nonconservative errors in the working format Hansen-Roach cross-section set provided with the KENO and Scale codes
- Potential overpressurization of high specific-activity alpha-emititng radioactivity sources
- Potential problems associated with loss of electrical power in certain teletherapy units
- Potential safety enhancements to spent fuel pool storage
- Potential safety issue regarding the shipment of fissile material
- Potential security equipment weaknesses
- Potential vulnerabilities of time-reliant computer-based systems due to change in daylight saving time dates
- Potentially defective uf6 cylinder valves (1-inch)
- Potentially nonconservative screening value for dam failure frequency in probabilistic risk assessments
- Premature degradation of spent fuel storage cask structures and components from environmental moisture
- Probable misadministrations occurring during intravascular brachtherapy with the Novoste Beta-Cath system
- Problems encountered when manually editing treatment data on the Nucletron microSelectron-HDR (new) model 105.999
- Problems experienced with loading and unloading spent nuclear fuel storage and transportation casks
- Problems involved in monitoring dose to the hands resulting from the handling of radiopharmaceuticals
- Problems with criticality alarm components/systems
- Proceedings of the Conference on High-Level Radioactive Solid Waste Forms : held at Denver, Colorado, December 19-21, 1978
- Proceedings of the Conference on the Application of Geochemical Models to High-level Nuclear Waste Repository Assessment : held at Oak Ridge, Tennessee, October 2-5, 1984
- Proceedings of the State Workshop on Shallow Land Burial and Alternative Disposal Concepts held at Bethesda, Maryland, May 2-3, 1984
- Proceedings of the Symposium on Low-Level Waste Disposal
- Proceedings of the Symposium on Unsaturated Flow and Transport Modeling : held at Seattle, Washington, March 23-24, 1982
- Proceedings of the Workshop on Review of Dose Modeling Methods for Demonstration of Compliance with the Radiological Criteria for License Termination : held at NRC headquarters auditorium, Rockville, Maryland, USA, November 13-14, 1997
- Prompt reporting to NRC of significant incidents involving radioactive material
- Proposed amendments to 40 CFR Part 61, Air Emission Standards for Radionuclides
- Pump explosions involving ammonium nitrate
- Radiation exposures during an event invoving a fixed nuclear gauge [electronic resource]
- Radiation exposures to members of the public in excess of regulatory limits caused by failures to perform appropriate radiation surveys during well logging operations
- Radiography events at operating power reactors
- Radiological controls create criticality safety accident scenario for fissile solution container transport at fuel cycle facility
- Radiopharmaceutical vial breakage during preparation
- Re-evaluation of the indoor resuspension factor for the screening analysis of the building occupancy scenario for NRC's license termination rule : draft report for comment
- Reactivity insertion transient and accident limits for high burnup fuel
- Reactor safety information for states during exercises and emergencies
- Recall of Star brand fire protection sprinkler heads
- Recall of mechanical rate of rise and fixed-temperature heat detectors
- Recent contamination incidences resulting from failure to perform adequate surveys
- Recent events resulting in extremity exposures exceeding regulatory limits
- Recent events resulting in whole body exposures exceeding regulatory limits
- Recent failures of control cables used on Amersham Model 660 postlock radiographic systems
- Recent findings concerning implementation of quality assurance programs by suppliers of transport packages
- Recent hydrogen fluoride exposures at fuel cycle facilities
- Recent incidents invoiving potential loss of control of licensed material
- Recent incidents resulting in offsite contamination [electronic resource]
- Recent issues related to the qualification and commercial grade dedication of safety-related components
- Recent licensing submittals containing personally identifiable information
- Recent medical misadministrations resulting from inattenton to detail
- Recent misadministrations caused by incorrect calibrations of strontium-90 eye applicators
- Recent nuclear material safety and safeguards decision on bundling exempt quantities
- Recent problems involving the model SPEC 2-T radiographic exposure device
- Recent reported medical events involving the administration of yttrium-90 microspheres for therapeutic medical procedures
- Recent revisions to 10 CFR Part 20 and change of implementation date to January 1, 1994
- Recent safety-related event at panoramic wet-source-storage irradiator
- Recent safety-related incidents at large irradiators
- Recent safety-related violations of NRC requirements by industrial radiography licensees
- Reciprocity: notification of agreement state radiation control directors before beginning work in agreement states
- Recordkeeping, decommissioning notifications for disposals of radioactive waste land burial authorized under former 10 CFR 20.304, 20.302, and current 20.2002
- Registration, use, and quality assurance requirements for NRC-certified transportation packages
- Regulatory requirements when no operations are being performed
- Release of patients with residual radioactivity from medical treatment and control of areas due to presence of patients containing radioactiviity following implementation of revised CFR Part 20
- Release of patlents treated with temporary implants
- Reporting fuel cycle and materials events to the NRC Operations Center
- Reporting requirements for bankruptcy
- Requirements for import and distribution of neutron-irradiated gems
- Requirements for processing financial assurance submittals for decommissioning
- Requirements for use of Nuclear Regulatory Commission-(NRC-) approved transport packages for shipment of Type A quantities of radioactive material
- Residual contamination remaining in krypton-85 handling system after venting
- Resolution of recurring loss alarms
- Response to indications of potential tampering, vandalism, or malicious michief
- Respository environmental parameters relevant to assessing the performance of high-level waste packages
- Results of Hemyc electrical raceway fire barrier system full scale fire testing
- Results of a special NRC inspection at Dresden Nuclear Power Station Unit 1 following a rupture of service water inside containment
- Retrofit to Amersham 660 Posilock radiography camera to correct inconsistency in 10 CFR Part 34 compatibility
- Retrofit to Industrial Nuclear Company (INC) IR100 radiography camera to correct inconsistency in 10 CFR Part 34 incompatibility
- Review and recommendations of dose conversion factors and environmental transport parameters for 210Pb and 226Ra : final report
- Review of exemptions and general licenses for fissile material in 10 CFR 71
- Revised analyses of decommissioning reference non-fuel-cycle-facilities
- Revised analyses of decommissioning reference non-fuel-cycle-facilities
- Safety and economic consequences of misleading marketing information
- Safety concerns related to repeated control unit failures of the nucletron classic model high-dose-rate remote afterloading brachytherapy devices
- Safety concerns related to the design of the door interlock circuit on nucletron high-dose and pulsed dose rate remote afterloading brachytherapy devices
- Safety defect in Gammamed 12i bronchial catheter clamping adapters
- Safety evaluation report for the Eagle Rock enrichment facility in Bonneville County, Idaho
- Safety evaluation report for the General Electric-Hitachi Global Laser Enrichment LLC laser-based uranium enrichment plant in Wilmington, North Carolina
- Safety evaluation report for the International Isotopes Fluorine Products, Inc. Fluorine Extraction Process and Depleted Uranium Deconversion Plant in Lea County, New Mexico : Docket No. 40-9086, International Isotopes Fluorine Products, Inc.
- Safety evaluation report related to disposal of high-level radioactive wastes in a geologic repository at Yucca Mountain, Nevada
- Second retrofit to Industrial Nuclear Company IR 100 radiography camera, to correct inconsistency in 10 CFR Part 34 compatibility
- Security Training Symposium : "meeting the challenge--firearms & explosives recognition and detection" : proceedings of the U.S. Nuclear Regulatory Commission : held at Hyatt Regency Bethesda, Bethesda, Maryland, November 28-30, 1989
- Slab hopper bulging
- Small arms firing range safety issues
- Soil and water contamination at fuel cycle facilities
- Solid state protection system card failure results in spurious safety injection actuation and reactor trip
- Solubility criteria for liquid effluent releases to sanitary sewage under the revised 10 CFR Part 20
- Source positioning errors and system malfunctions during administration of intravascular brachytherapy
- Sources of information related to potential cyber security vulnerabilities
- Spent fuel storage or transportation system misloading
- Spent fuel transportation package response to the Baltimore Tunnel fire scenario
- Spent fuel transportation package response to the Caldecott Tunnel fire scenario
- Spent fuel transportation package response to the MacArthur Maze fire scenario, final report
- Spent fuel transportation package response to the MacAuthor Maze fire scenario : draft report for comment
- Spent fuel transportation package response to the Newhall Pass tunnel fire scenario, final report
- Spent fuel transportation risk assessment : draft report for comment
- Spent fuel transportation risk assessment : final report
- Standard review plan for dry cask storage systems, final report
- Standard review plan for fuel cycle facilities license applications : final report
- Standard review plan for license applications for fuel cycle facilities : draft report for comment
- Standard review plan for renewal of specific licenses and certificates of compliance for dry storage of spent nuclear fuel : draft report for comment
- Standard review plan for renewal of specific licenses and certificates of compliance for dry storage of spent nuclear fuel : final report
- Standard review plan for renewal of spent fuel dry cask storage system licenses and certificates of compliance : final report
- Standard review plan for spent fuel dry storage systems and facilities : draft report for comment
- Standard review plan renewal of independent spent fuel storage installation licenses and dry cask storage system certificates of compliance : draft report for comment
- Strontium 82/rubidium 82 generator elution events and issues
- Strontium-90 eye applications : new calibration valiues and use
- Strontium-90 eye applicators : submission of quality management plan (QMP), calibration, and use
- Suggested guidance related to development and implementation of corrective action
- Suggested nuclear waste management radiological performance objectives
- Summary of fitness for duty program performance reports for calendar year 2008
- Summary of fitness-for-duty program performance reports for calendar year 2007
- Supplement to the U.S. Department of Energy's environmental impact statement for a geologic repository for the disposal of spent nuclear fuel and high-level radioactive waste at Yucca Mountain, Nye County, Nevada : draft report for comment
- Supplement to the U.S. Department of Energy's environmental impact statement for a geologic repository for the disposal of spent nuclear fuel and high-level radioactive waste at Yucca Mountain, Nye County, Nevada : final report
- Technical evaluation report on the content of the U.S. Department of Energy's Yucca Mountain repository license application : administrative and programmatic volume
- Technical evaluation report on the content of the U.S. Department of Energy's Yucca Mountain repository license application : postclosure volume : repository safety after permanent closure
- Technical evaluation report on the content of the U.S. Department of Energy's Yucca Mountain repository license application : preclosure volume : repository safety before permanent closure
- Teletherapy events
- Temporary suspension of e-quip system to affect pending background investigations
- The Use of process monitoring data for nuclear material accounting
- Thefts of portable gauges
- Themal issues identified during loading of spent fuel storage casks
- Tohoku-Taiheiyou-Oki earthquake effects on Japanese nuclear power plants--for fuel cycle faciliites
- Training and supervision of individuals supervised by an authorized user
- Training of nurses responsible for the care of patients with brachytherapy implants
- Transformer failures--recent operating experiience
- Transportation of model Spec 2-T radiographic exposure device
- Transportation of radiography devices (update of Information Notice no. 81-02, January 23, 1981)
- Transportation of type A quantities of non-fissile radioactive materials
- Treatment of natural phenomena hazards in fuel cycle facilities
- U.S. Department of Health and Human Services letter, to medical device manfacturers, on the year 2000 problem
- U.S. Food and Drug Administration announcement related to certain sleep disorder drugs
- Unauthorized administration of byproduct material for medical use
- Unauthorized removal of industrial nuclear gauges
- Unauthorized transfer of ownership or control of licensed activities
- Undetected failures that may ocurr during patient treatments with teletherapy devices
- Unmonitored release pathways from slightly contaminated recycle and recirculation water systems at a fuel facility
- Unplanned radiation exposures to radiographers, resulting from failures to follow proper radiation safety procedures
- Update on NRC's year 2000 activities for materials licensees and fuel cycle licensees and certificate holders
- Update on waste form and high integrity container topical report review status, identification of problems with cement solidification, and reporting of waste mishaps
- Uranium accumulation in fuel cycle facility ventilation and scrubber systems
- Uranium hexafluoride cylinders with potentially defective 1-inch valves
- Uranium hexafluoride cylinders--deviations in coupling welds
- Uranium oxide fires at fuel cycle facilities
- Use of as-found conditions to evaluate criticality-related process upsets at fuel cycle facilities
- Use of blanl ammunition
- Use of concentration control for criticality safety
- Use of galvanized supports and cable trays with Meggitt si 2400 stainless-steel-jacketed electrical cables
- Use of less than optimal bounding assumptions in criticality safety analysis at fuel cycle facilities
- Use of seal cap enclosures to mitigate leakage from joints that use A-286 bolts
- Valve failure during patient treatment with gamma stereotactic radiosurgery unit
- Vulnerability of stainless steel to corrosion when sensitized
- Vulnerablity of stainless steel to corrosion when sensitized
- Waste management technical support project, FY 78 end-of-year report
- Welding and nondestructive examination issues
- Welding defects in replacement steam generators
- Willful misconduct/record falsification and nuclear safety culture
- Consolidated guidance about materials licenses : guidance about changes of control and about bankruptcy involving byproduct, source, or special nuclear materials licenses, final report
- Consolidated guidance about materials licenses : guidance for agreement state licensees about NRC form 241 "Report of Proposed Activities in Non-Agreement States, Areas of Exclusive Federal Jurisdiction, or Offshore Waters" and guidance for NRC licensees proposing to work in agreement state jurisdiction (reciprocity), final report
- Consolidated guidance about materials licenses : program-specific guidance about academic, research and development, and other licenses of limited scope, including electron capture devices devices and x-ray fluorescence analyzers : final report
- Consolidated guidance about materials licenses : program-specific guidance about commercial radiopharmacy licenses, draft report for comment
- Consolidated guidance about materials licenses : program-specific guidance about exempt distribution licenses, draft report for comment
- Consolidated guidance about materials licenses : program-specific guidance about exempt distribution licenses, final report
- Consolidated guidance about materials licenses : program-specific guidance about fixed gauge licenses, final report
- Consolidated guidance about materials licenses : program-specific guidance about industrial radiography licenses : final report
- Consolidated guidance about materials licenses : program-specific guidance about licenses authorizing distribution to general licensees : draft report for comment
- Consolidated guidance about materials licenses : program-specific guidance about licenses of broad scope, final report
- Consolidated guidance about materials licenses : program-specific guidance about master materials licenses, final report
- Consolidated guidance about materials licenses : program-specific guidance about medical use licenses, draft report for comment
- Consolidated guidance about materials licenses : program-specific guidance about portable gauge licenses, final report
- Consolidated guidance about materials licenses : program-specific guidance about possession licenses for manufacturing and distribution, draft report for comment
- Consolidated guidance about materials licenses : program-specific guidance about self-shielded irradiator licenses, draft report for comment
- Consolidated guidance about materials licenses : program-specific guidance about self-shielded irradiator licenses: final report
- Consolidated guidance about materials licenses : program-specific guidance about special nuclear material of less than critical mass licenses, draft report for comment
- Consolidated guidance about materials licenses : program-specific guidance about special nuclear material of less than critical mass licenses, final report
- Contaminated lead products
- Contingency planning for the year 2000 computer problem
- Control and surveillance of portable gauges during field operations
- Control of licensed material during reorganization employee-management disagreements, and financial crises
- Corrosion in fire protection piping due to air and water interaction
- Counterfeit, fraudulent, suspect item (CSFI) training offerings
- Cracked insertion rods on Troxler model 3400 series portable moisture density gauges
- Cracks in stiffening rings on 48-Inch-diameter UF6 cylinders
- Crane and heavy lift issues identified during NRC inspections
- Criminal prosecution of licensee's former president for intentional safety violations
- Criticality analysis of assembly misload in a PWR burnup credit cask
- Criticality and chemical safety events involving unanalyzed condiitons and unanticipated unavailabllity of IROFS at fuel cycle facilities
- Criticality monitoring system degradation at BWX Technologies, Inc., Nuclear Products Division, Lynchburg, VA
- Criticality safety-related events relating from fissile material operations under procedures not reviewed by criticality safety staff
- DOT safety advisory : high pressure aluminum seamless and aluminum composite hoop-wrapped cylinders
- Damage of industrial radiographic equipment due to falling equipment and improper mounting
- Deficiencies with effluent radiation monitoring system Instrumentation
- Degradation of wire rope used in fuel handling applications
- Demonstration of associated equipment compliance with 10 CFR 34.20
- Denial of access to current low-level radioactive waste disposal facilities
- Derating Whiting cranes purchased before 1980
- Determination of management measures for process isolation controls designated as items relied on for safety and implementation of adequate quality assurance measures for plant features and procedures
- Development and testing of ENDF/B-VI.8 and ENDF/B-VII.0 coupled neutron-gamma libraries for SCALE 6
- Diesel generator voltage regulation system component due to latent manufacturing defect
- Directory of certificates of compliance for radioactive materials packages
- Directory of certificates of compliance for radioactive materials packages : certificates of compliance
- Dissolution kinetics of commercial spent nuclear fuels in the potential Yucca Mountain repository environment
- Distribution of sources and devices without authorization
- Dose calibrator quality control
- Dose calibrator quality control
- Draft environmental impact statement for the construction and operation of an independent spent fuel storage installation on the Reservation of the Skull Valley Band of Goshute Indians and the related transportation facility in Tooele County, Utah
- Dry storage and transportation of high-burnup spent nuclear fuel : draft report for comment
- EPA's interim final rule on medical waste tracking and management
- Effect of the year 2000 computer problems on NRC licensees and certificate holders
- Effective cyber security practices to protect digital assets of byproduct materials licensees
- Effective use of radiation safety committees to exercise control over medical use programs
- Emergency access to low-level radioactive waste disposal facilities
- Emergency response information requirements for radioactive material shipments
- Emplacement of support pads for spent fuel dry storage installations at reactor sites
- Employee training and shipper registration requirements for transporting radioactive materials
- Enforcement of safety requirements for radiographers
- Enforcement sanctions issued as a result of deliberate violations of NRC requirements
- Ensuring compatible use of drive cables incorporating Industrial Nuclear Company ball-type male connectors
- Equipment failiure at irradiation facilities
- Erroneous criticality alarm monitoring signal caused by incorrect data acquisition module configuration
- Erroneous data from defective thermocouple results in a fire
- Errors in the use of radioactive iodine-131
- Evaluation and reporting of fires and unplanned chemical reaction events at fuel cycle facilities
- Evaluation of an integrated approach to safeguards regulations
- Examination of the use of continuum verus discontinuum models for design and performance assessment for the Yucca Mountain Site
- Excessively large criticality safety limits fail to provide double contingency at fuel cycle facility
- Exercising due diligence when transferring radioactive materials
- Exothermic reactions involving dried uranium oxide powder (yellowcake)
- Extended interim storage of low-level radioactive waste by fuel cycle and materials licensees
- Extended storage of sealed sources
- Facility management responsibilities for purchased or contracted services for radiation therapy programs
- Failure of criticality safety control to prevent uranium dioxide (uo2) powder accumulation
- Failure of double contingency based on administrative controls involving laboratory sampling and spectroscopic analysis of wet uranium waste
- Failure of intrauterine tandem of Fletcher Suit Applicator brachytherapy devices during patient treatment
- Failure of packing nuts on one-Inch uranium hexafluoride cylinder valves
- Failure of packing nuts on one-inch uranium hexafluoride cylinder valves
- Failure of safety systems on self-shielded irradiators because of inadequate maintenance and training
- Failure to disable unsafe geometry bandsaw reservior results in critcality safety-related alert
- Failure to verify the continuity of shunt trip contact attachments in manual safety injection and reactor trip switches
- Failures of high-dose-rate remote afterloading (HDR) device source guide tubes, catherters, and applicators
- Failures of motor operated valve actuator motors with magnesium alloy rotors
- Failures of motor-operated valves due to degraded stem lubricant
- False alarms of alarm ratemeters because of radiofrequency interference
- Final environmental impact statement for the construction and operation of an independent spent fuel storage installation on the reservation of the Skull Valley Band of Goshute Indians and the related transportation facility in Tooele County, Utah : docket no. 72-22, Private Fuel Storage, L.L.C.
- Final environmental statement related to the Exxon Minerals Company, U.S.A. Highland Uranium Solution Mining project (Converse County, Wyoming), docket no. 40-8102
- Flow-accelerated corrosion events
- Fuel cycle facilty configuration management errors
- Geoscience data base handbook for modeling a nuclear waste repository
- Guidance for conducting technical analyses for 10 CFR Part 61 : draft report for comment
- Guidance on the implementation of integrated safety analysis requirements for 10 CFR Part 40 facilities authorized to possess 2,000 kilograms or more of uranium hexafluoride : draft report for comment
- Guidance on the implementation of integrated safety analysis requirements for 10 CFR Part 40 facilities authorized to possess 2,000 kliograms or more of uranium hexafluoride : draft report for comment
- Guidance to users on the implementation of a new single-source dose-calibration formalism and revised air-kerma strength standard for iodine-125 sealed sources
- Guide to hazardous, radioactive, and mixed waste generators on the elements of a waste minimization program
- Handling uncontained yellowcake outside of a facility processing circuit
- Heightened awareness for patients containing detectable amounts of radiation from medical administrations
- High dose-rate-remote-afterloader equipment failure
- High-efficiency particulate air filter exceeds mass limlt before reaching expected differential pressure
- Hostile action-based emergency preparedness drills
- Human errors that result in inadvertent transfers of special nuclear material at fuel cycle facilities
- Hydrogen fire at nuclear power station
- ISOO notice 2015-02, message from OPM to security clearance holders
- Icing conditions between bottom of dry storage system and storage pad
- Identification of certain uranium hexafluoride hexafluoride cylinders that do not comply with ANSI N14.1 fabrication standards
- Identified problems in gamma stereotactic radiosurgery
- Identifying waste generators in shipments of low-level waste to land disposal facilities
- Impact of non-safety related electrical support system vulnerabilities on safety systems
- Impact of variation in environmental conditions on the thermal performance of dry storage casks : final report
- Implementation guidance for 10 CFR Part 37, "Physical protection of category 1 and category 2 quantities of radioactive material"
- Implementation of a new constraint on radioactive air effluents
- Implementation of human use research protocols involving U.S. Nuclear Regulatory Commission regulated materials
- Implementation of the deliberate misconduct rule
- Implementation of the revised 10 CFR Part 20
- Importance of proper response to self-identified violations by licensees
- Importance of understanding circuit breaker control power indications
- Improper control of chemicals in nuclear fuel fabrication
- Improper handling of ophthalmic strontium-90 beta radiation applicators
- Improper operation of spent fuel transfer cask neutron shield equipment leading to elevated radiation levels adjacent to spent fuel transfer cask
- Improving material control and accountability interface with criticality safety activities at fuel cycle facilities
- Inadequate 10 CFR 72.48 safety evaluation of independent spent fuel storage installations
- Inadequate calibration of thermoluminescent dosimeters utilized to monitor extremity dose at uranium processing and fabrication facilities
- Inadequate controls of respiratory protection accessibility, training, and maintenance
- Inadequate criticality safety analysis of ventilation systems at fuel cycle facilities
- Inadequate implementation of 10 CFR Part 21 requirements by vendors who supply basic components to nuclear power plant licensees
- Inadequate operational checks of alarm ratemeters
- Inadequate puncture tests for type B packages under 10 CFR 71.73(c)(3)
- Inadequate test procedure fails to detect inoperable criticality accident alarm horns
- Inadvertent discharge of halon 1301 fire-suppression system from incorrect and/or out-of-date procedures
- Inadvertent shipment of a radioactive source in a container thought to be empty
- Inadvertent transfer of licensed material to uncontrolled locations
- Inappropriate use of a single-parameter limit as a nuclear-criticality safety limit
- Inappropriate use of certified material test report yield stress and age-hardened concrete compressive strength in design calculations
- Incident reporting requirements for radiography licensees
- Incident reporting requirements for radiography licensees
- Incident-reporting requirements involving intakes, during a 24-hour period that may cause a total effective dose equivalent in excess of 0.05 Sv (5 rem)
- Incidents involving the use of radioactive iodine-131
- Incomplete or inaccurate information provided to the licensee and/or NRC by any contractor or subcontractor employee
- Industrial radiography inspection and enforcement
- Information likely to be requested if an emergency is declared
- Instructions and guidance for completing physical inventory summary reports : NRC form 327, draft report for comment
- Instructions for completing nuclear material transaction reports : (DOE/NRC forms 741 and 740M) : effective date, January 1, 2009
- Instructions for completing nuclear material transaction reports : (DOE/NRC forms 741 and 740M), effective date: April 1, 2017
- Instructions for the preparation and distribution of material status reports : (DOE/NRC forms 742 and 742C)
- Instructions for the preparation and distribution of material status reports : (DOE/NRC forms 742 and 742C), effective date: April 1, 2017
- Instructions for the preparation and distribution of material status reports : (DOE/NRC forms 742, and 742C) : effective date February 1, 2000
- Interim guidance on transportation of steam generators
- Investigation and reporting of misadministrations by the radiation safety officer
- Issues associated with use of strontium-89 and other beta emitting radiopharmaceuticals
- Issues potentially affecting nuclear facility fire safety
- Joint Canada-United States guide for approval of type B(U) and fissile material transportation packages : draft report for comment
- Joint Canada-United States guide for approval of type B(U) and fissile material transportation packages : final report
- KENO-IV/CG, the combinatorial geometry version of the KENO Monte Carlo criticality safety program
- Kobe Steel quality assurance record falsification
- Labeling requirements for transporting multi-hazard radioactive materials
- Leak testing of packaging in the transport of radioactive material
- Licensed fuel facility status report
- Licensee responsibility for quality assurance oversight of contractor activities regarding fabrication and use of spent fuel storage cask systems
- Licensee violations of NRC regulations, which led to medical diagnostic misadministrations
- Licensees' responsibilities regarding reporting and follow-up requirements for nuclear-powered pacemakers
- Locking of radiography exposure devices
- Long-term fissile material accumulation due to unanalyzed or improperly analyzed conditions at fuel cycle facilities
- Loss and theft of unsecured licensed material
- Lost or stolen gauges
- Low-dose rate manual brachytherapy-equipment-related medical events
- Maintenance of teletherapy units
- Maintenance procedures compromise double-contingency of uo2 powder-handling equipment at fuel cycle facility
- Malfunction of lockbox on radiography device
- Malfunction of source retraction mechanism in cobalt-60 teletherapy treatment units
- Management attention to the establishment and maintenance of a nuclear criticality safety program
- Management concepts and safety applications for nuclear fuel facilities
- Management of wastes contaminated with radioactive materials
- Management of wastes contaminated with radioactive materials ("red bag" waste and ordinary trash)
- Manual brachytherapy source jamming
- Materials licensees : lack of management controls over licensed programs
- Mechanical integrity of in-situ leach injection wells and piping
- Medical misadministrations caused by failure to properly perform tests on dose calibrators for beta- and low-energy photon-emitting radionuclides
- Medical misadministrations caused by human errors involving gamma stereotactic radiosurgery (gamma knife)
- Medical use of strontium-90 eye applicators : new requirements for calibration and decay correction
- Memorandum of understanding between NRC and OSHA relating to NRC-licensed facilities (53 FR 43950, October 31, 1988)
- Methods to prevent medical events
- Minimization of methane gas in plant systems and radwaste shipping containers
- Misadministration caused by a bent interstitlal needle during brachytherapy procedure
- Model feasibility study of radioactive pathways from atmosphere to surface water
- Model plutonium recycle reactors for environmental analysis of the mixed-oxide fuel cycle
- Monitoring of neutron-absorbing materials in spent fuel pools
- NIOSH respiratory user notices, "Inadvertent separation of the mask-mounted regulator (MMR) from the facepiece on the Mine Safety Appliances (MSA) Company MMR self-contained breathing apparatus (SCBA) and status update"
- NMSS licensees' and certificate holders' year 2000 readiness programs
- NRC requirements for evaluation of wipe test results : calibration of count rate survey instruments
- National response framework
- Need for continuous monitoring of active systems in loaded spent fuel storage canisters (including vacuum drying process)
- New exposure limits for airborne uranium and thorium
- Noble fission gas releases during spent fuel cask loading operations
- Non-conservative errors in minimum critical power ratio limits
- Nonconforming Magnaflux magnetic particle (14AM) prepared bath
- Notification of permanent injunction against Neutron Products Incorporated of Dickerson, Maryland
- Notifications, records, and reports of misadministrations
- Nuclear criticality safety
Focus of
No resources found
No enriched resources found
- U.S. Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards -- Decision making
- U.S. Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards
- U.S. Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards
- U.S. Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards -- Periodicals
- U.S. Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards -- Evaluation
Author of
No resources found
No enriched resources found
- The U.S. Nuclear Regulatory Commission and how it works
- Supplement to the U.S. Department of Energy's environmental impact statement for a geologic repository for the disposal of spent nuclear fuel and high-level radioactive waste at Yucca Mountain, Nye County, Nevada : draft report for comment
- Draft environmental impact statement on 10 CFR part 61 "licensing requirements for land disposal of radioactive waste."
- Environmental impact statement for the Reno Creek in Situ Recovery Project in Campbell County, Wyoming : supplement to the generic environmental impact statement for in-situ leach uranium milling facilities, final report
- NMSS news link
- Supplement to the U.S. Department of Energy's environmental impact statement for a geologic repository for the disposal of spent nuclear fuel and high-level radioactive waste at Yucca Mountain, Nye County, Nevada : final report
- Status of decommissioning program
- Final environmental impact statement on 10 CFR part 61 "licensing requirements for land disposal of radioactive waste."
Issuing body of
No resources found
No enriched resources found
- Consolidated guidance about materials licenses : guidance about changes of control and about bankruptcy involving byproduct, source, or special nuclear materials licenses, final report
- Standard review plan for spent fuel dry storage systems and facilities : draft report for comment
- Improper control of chemicals in nuclear fuel fabrication
- Consolidated guidance about materials licenses : guidance for agreement state licensees about NRC form 241 "Report of Proposed Activities in Non-Agreement States, Areas of Exclusive Federal Jurisdiction, or Offshore Waters" and guidance for NRC licensees proposing to work in agreement state jurisdiction (reciprocity), final report
- Consolidated guidance about materials licenses : program-specific guidance about academic, research and development, and other licenses of limited scope, including electron capture devices devices and x-ray fluorescence analyzers : final report
- Tohoku-Taiheiyou-Oki earthquake effects on Japanese nuclear power plants--for fuel cycle faciliites
- Consolidated guidance about materials licenses : program-specific guidance about commercial radiopharmacy licenses, draft report for comment
- Improper handling of ophthalmic strontium-90 beta radiation applicators
- Consolidated guidance about materials licenses : program-specific guidance about exempt distribution licenses, draft report for comment
- Improper operation of spent fuel transfer cask neutron shield equipment leading to elevated radiation levels adjacent to spent fuel transfer cask
- Nuclear criticality safety
- Consolidated guidance about materials licenses : program-specific guidance about exempt distribution licenses, final report
- Recent findings concerning implementation of quality assurance programs by suppliers of transport packages
- Consolidated guidance about materials licenses : program-specific guidance about fixed gauge licenses, final report
- Accidental radiation overexposures to personnel due to industrial radiography accessory equipment malfunctions
- Consolidated guidance about materials licenses : program-specific guidance about industrial radiography licenses : final report
- Inadequate calibration of thermoluminescent dosimeters utilized to monitor extremity dose at uranium processing and fabrication facilities
- Consolidated guidance about materials licenses : program-specific guidance about licenses authorizing distribution to general licensees : draft report for comment
- Safety evaluation report for the General Electric-Hitachi Global Laser Enrichment LLC laser-based uranium enrichment plant in Wilmington, North Carolina
- Consolidated guidance about materials licenses : program-specific guidance about licenses of broad scope, final report
- Safety evaluation report for the International Isotopes Fluorine Products, Inc. Fluorine Extraction Process and Depleted Uranium Deconversion Plant in Lea County, New Mexico : Docket No. 40-9086, International Isotopes Fluorine Products, Inc.
- Consolidated guidance about materials licenses : program-specific guidance about master materials licenses, final report
- Consolidated guidance about materials licenses : program-specific guidance about medical use licenses, draft report for comment
- Inadequate controls of respiratory protection accessibility, training, and maintenance
- Accidental disposal of radioactive materials
- Consolidated guidance about materials licenses : program-specific guidance about portable gauge licenses, final report
- Consolidated guidance about materials licenses : program-specific guidance about possession licenses for manufacturing and distribution, draft report for comment
- Patient skin contamination events associated with I-131 metaiodobenzylguanidine during neuroblastoma treatments
- Consolidated guidance about materials licenses : program-specific guidance about self-shielded irradiator licenses, draft report for comment
- Strontium 82/rubidium 82 generator elution events and issues
- Pending expiration of the NRC type B transportation package certificate for Sentinel Model 660 Series radiographic projectors on June 30, 2013
- Consolidated guidance about materials licenses : program-specific guidance about self-shielded irradiator licenses: final report
- Recent issues related to the qualification and commercial grade dedication of safety-related components
- Consolidated guidance about materials licenses : program-specific guidance about special nuclear material of less than critical mass licenses, draft report for comment
- Consolidated guidance about materials licenses : program-specific guidance about special nuclear material of less than critical mass licenses, final report
- Personnel injuries resulting from improper operation of radwaste incinerators
- Recent licensing submittals containing personally identifiable information
- Inadvertent shipment of a radioactive source in a container thought to be empty
- Training and supervision of individuals supervised by an authorized user
- Inadvertent transfer of licensed material to uncontrolled locations
- Portable moisture/density gauges : recent incidents of portable gauges being stolen or lost
- Corrosion in fire protection piping due to air and water interaction
- Inappropriate use of certified material test report yield stress and age-hardened concrete compressive strength in design calculations
- Counterfeit, fraudulent, suspect item (CSFI) training offerings
- Unauthorized transfer of ownership or control of licensed activities
- (1) Erroneous data in "Nuclear safety guide, TID-7016, Revision 2," (NUREG/CR-0095, ORNL/NUREG/CSD-6 (1978)) and (2) Thermal scattering data limitation in the cross-section sets provided with the KENO and Scale codes
- Cracks in stiffening rings on 48-Inch-diameter UF6 cylinders
- Crane and heavy lift issues identified during NRC inspections
- Possible flaws in certain piping systems fabricated by Associated Piping and Engineering
- Potential absence of required lock washers in BSI Instruments, Inc. LB 7400 series fixed gauges
- Criminal prosecution of licensee's former president for intentional safety violations
- Uranium hexafluoride cylinders with potentially defective 1-inch valves
- Soil and water contamination at fuel cycle facilities
- Criticality and chemical safety events involving unanalyzed condiitons and unanticipated unavailabllity of IROFS at fuel cycle facilities
- Potential chloride-induced stress corrosion cracking of austenitic stainless steel and maintenance of dry storage casks system canisters
- Industrial radiography inspection and enforcement
- Potential electrical equipment problems
- Instructions and guidance for completing physical inventory summary reports : NRC form 327, draft report for comment
- Damage of industrial radiographic equipment due to falling equipment and improper mounting
- Deficiencies with effluent radiation monitoring system Instrumentation
- Recent problems involving the model SPEC 2-T radiographic exposure device
- Recent reported medical events involving the administration of yttrium-90 microspheres for therapeutic medical procedures
- A compendium of spent fuel transportation package response analyses to severe fire accident scenarios : draft report for comment
- Denial of access to current low-level radioactive waste disposal facilities
- Instructions for completing nuclear material transaction reports : (DOE/NRC forms 741 and 740M), effective date: April 1, 2017
- Transportation of model Spec 2-T radiographic exposure device
- Consolidated guidance about materials licenses : guidance about admiistrative licensing procedures: draft report for comment
- Uranium hexafluoride cylinders--deviations in coupling welds
- Determination of management measures for process isolation controls designated as items relied on for safety and implementation of adequate quality assurance measures for plant features and procedures
- Instructions for the preparation and distribution of material status reports : (DOE/NRC forms 742 and 742C), effective date: April 1, 2017
- Unmonitored release pathways from slightly contaminated recycle and recirculation water systems at a fuel facility
- Directory of certificates of compliance for radioactive materials packages
- Recent safety-related incidents at large irradiators
- Potential nonconservative errors in the working format Hansen-Roach cross-section set provided with the KENO and Scale codes
- Recent safety-related violations of NRC requirements by industrial radiography licensees
- Acceptable standard format and content for the material control and accounting plan required for low-enriched uranium enrichment facilities : draft report for comment
- Dose calibrator quality control
- Issues potentially affecting nuclear facility fire safety
- Potential overpressurization of high specific-activity alpha-emititng radioactivity sources
- Reciprocity: notification of agreement state radiation control directors before beginning work in agreement states
- Concrete degradation by alkali-silica reaction
- Computational fluid dynamics best practice guidelines for dry cask applications : final report
- Dry storage and transportation of high-burnup spent nuclear fuel : draft report for comment
- Spent fuel storage or transportation system misloading
- Kobe Steel quality assurance record falsification
- EPA's interim final rule on medical waste tracking and management
- Potential safety enhancements to spent fuel pool storage
- Effective cyber security practices to protect digital assets of byproduct materials licensees
- Labeling requirements for transporting multi-hazard radioactive materials
- Transportation of radiography devices (update of Information Notice no. 81-02, January 23, 1981)
- Effective use of radiation safety committees to exercise control over medical use programs
- Emergency access to low-level radioactive waste disposal facilities
- Acceptability of corrective action programs for fuel cycle facilities : draft report for comment
- Emergency response information requirements for radioactive material shipments
- Potential security equipment weaknesses
- Use of seal cap enclosures to mitigate leakage from joints that use A-286 bolts
- Regulatory requirements when no operations are being performed
- Employee training and shipper registration requirements for transporting radioactive materials
- Enforcement of safety requirements for radiographers
- Licensee violations of NRC regulations, which led to medical diagnostic misadministrations
- Transportation of type A quantities of non-fissile radioactive materials
- Potentially nonconservative screening value for dam failure frequency in probabilistic risk assessments
- Compliance with the general license provisions of 10 CFR Part 31
- Environmental impact statement for the Reno Creek in Situ Recovery Project in Campbell County, Wyoming : supplement to the generic environmental impact statement for in-situ leach uranium milling facilities, draft report for comment
- Compliance with new decommissioning rule
- Compliance with 10 CFR Part 21, "Reporting of Defects and Noncompliance"
- Premature degradation of spent fuel storage cask structures and components from environmental moisture
- Long-term fissile material accumulation due to unanalyzed or improperly analyzed conditions at fuel cycle facilities
- Erroneous criticality alarm monitoring signal caused by incorrect data acquisition module configuration
- Release of patlents treated with temporary implants
- Errors in the use of radioactive iodine-131
- Loss and theft of unsecured licensed material
- Lost or stolen gauges
- Availability of U.S. Food and Drug Administration (FDA)-approved potassium Iodide for use in emergencies involving radioactive iodine
- Willful misconduct/record falsification and nuclear safety culture
- Maintenance of teletherapy units
- Spent fuel transportation package response to the MacAuthor Maze fire scenario : draft report for comment
- Reporting requirements for bankruptcy
- Requirements for import and distribution of neutron-irradiated gems
- Extended interim storage of low-level radioactive waste by fuel cycle and materials licensees
- Malfunction of lockbox on radiography device
- Problems with criticality alarm components/systems
- Treatment of natural phenomena hazards in fuel cycle facilities
- Management attention to the establishment and maintenance of a nuclear criticality safety program
- Antifreeze agents in fire water sprinkler systems
- Failure of intrauterine tandem of Fletcher Suit Applicator brachytherapy devices during patient treatment
- Failure of packing nuts on one-Inch uranium hexafluoride cylinder valves
- Requirements for processing financial assurance submittals for decommissioning
- Temporary suspension of e-quip system to affect pending background investigations
- Management of wastes contaminated with radioactive materials ("red bag" waste and ordinary trash)
- Requirements for use of Nuclear Regulatory Commission-(NRC-) approved transport packages for shipment of Type A quantities of radioactive material
- Materials licensees : lack of management controls over licensed programs
- Spent fuel transportation risk assessment : draft report for comment
- Prompt reporting to NRC of significant incidents involving radioactive material
- Uranium oxide fires at fuel cycle facilities
- False alarms of alarm ratemeters because of radiofrequency interference
- Spent fuel transportation risk assessment : final report
- Proposed amendments to 40 CFR Part 61, Air Emission Standards for Radionuclides
- Commercial-grade dedication issues identified during NRC inspections
- Clarification of transportation requirements applicable to return of spent radiopharmacy dosages from users to suppliers
- Memorandum of understanding between NRC and OSHA relating to NRC-licensed facilities (53 FR 43950, October 31, 1988)
- Clarification of the recent revisions to the regulatory requirements for packaging of uranium hexafluoride (UF6) for transportation
- Standard review plan for dry cask storage systems, final report
- Flow-accelerated corrosion events
- Pump explosions involving ammonium nitrate
- Methods to prevent medical events
- Minimization of methane gas in plant systems and radwaste shipping containers
- Guidance for conducting technical analyses for 10 CFR Part 61 : draft report for comment
- ANSI N14.5-2014 revision and leakage rate testing considerations
- A compendium of spent fuel transportation package response analyses to severe fire accident scenarios, final report
- Radiography events at operating power reactors
- Standard review plan for fuel cycle facilities license applications : final report
- Update on waste form and high integrity container topical report review status, identification of problems with cement solidification, and reporting of waste mishaps
- Monitoring of neutron-absorbing materials in spent fuel pools
- Standard review plan for license applications for fuel cycle facilities : draft report for comment
- Brachytherapy source management
- Brachytherapy incidents involving iridium-192 wire used in endobronchial treatments
- Human errors that result in inadvertent transfers of special nuclear material at fuel cycle facilities
- Blocking, bracing, and securing of radio-active materials packages in transportation
- Uranium accumulation in fuel cycle facility ventilation and scrubber systems