DOE Standard Guide of Good Practices for Occupational Radiological Protection in Uranium Facilities

• DOE Standard Guide of Good Practices for Occupational Radiological Protection in Uranium Facilities
• This document has been reproduced from the best available copy
• Foreword
• Table of Contents
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• Introduction
• Properties and Relative Hazards
• Table 2 -1. Typical Isotopic Abundances
• Table 2 -2. Properties of Radionuclides That May Be Found at Uranium Facilities(a)
• Decay Chains
• Table 2-3. Uranium Series (4n + 2)
• Table 2-3. Uranium Series (4n + 3)
• Enrichment
• Example 1
• Figure 2-1. Specific Activity for Mixtures
• Figure 2-2. % Total Radioactivity by Isotope vs. % Weight  235U Enrichment
• Figure 2-4. Estimated Uranium Specific Activity for Laser Enrichment (of natural uranium)
• Transuranics
• Table 2 -6. ALIs and DACs for Uranium and Selected Contaminants in Recycled Uranium
• Example 2
• Transuranics cont'd
• Technetium
• Uranium Fuel Processing
• Radiological Characteristics and Effects
• Figure 2-5. 238U Decay Product Ingrowth
• Mode of Uranium Entry into the Body
• Ingestion
• Table 2 -8. Toxicological Limits on Airborne Concentrations of Transportable (soluble) Uranium
• Table 2 -9. Uranium Levels for Various Effects
• Human Response Indicators
• Transfer to the Fetus
• Table 2 -11. Inhalation Classification for Some Uranium Compounds
• Chemical Versus Radiological Hazards
• Table 2-12. Determination of "Dividing Line" Enrichments Above Which Radiological Monitoring Requirements Become Limiting
• Table 2 -13. Impact of Requirement To Monitor at 2%
• Example 3b - General Solution, Chronic Exposure
• Industrial Hazards
• Fire
• Radiation Protection
• Administrative Controls
• Administrative Controls cont'd
• Adequacy of Personnel and Equipment
• Technician Staffing and Qualifications
• ALARA Program
• Achievement of Goals
• Attributes of Effective Review and Audit
• External Dosimetry Program
• Radiological Surveys and Data Trending cont'd
• Radiological Surveys and Data Trending cont'd
• Instrumentation Considerations
• Instrumentation Considerations cont'd
• Airborne Contamination Monitors
• Criticality Accident Alarm Systems (CAAS)
• Work Authorizations
• Facility Posting and Labeling
• Emergency Exposure Situations
• Radiation Safety Training
• Training for Other Facility Personnel
• Onsite Packaging and Transportation
• Control
• Conduct of Operations
• Radiological Work Procedures
• Decommissioning of Weapons and Weapon Facilities
• Contamination Control
• Purpose of Air Monitoring
• General Air Samplers (GAS)
• Theoretical Considerations and Uncertainties
• Airborne Concentration cont'd
• Figure 4-1. PAS versus GAS versus CAM Example of the Degree of Correlation between Type of Sampling TMI-1983
• Breathing Rates and Tidal Volumes
• Samplers and Instrumentation
• Filter Media
• Size -Selective Devices
• Sample Activity Measurement
• Continuous Air Monitors
• Potential Sources of Airborne Contamination
• Characterization of Controls
• Reporting and Documenting Contamination Levels
• Monitoring
• Contamination Surveys of the Workplace
• External Exposure Surveys
• Surveys for Removable Contamination cont'd
• Table 4 -1. Surface Contamination Values,(a) dpm/100 cm2
• Release Criteria
• Figure 4-2. Protocol for Release of Materials
• Release Criteria cont'd
• Uranium Contamination Detection
• Personnel Contamination Control
• Protective Clothing
• ALARA Guidelines
• Equipment and Surface Decontamination
• Equipment and Surface Decontamination cont'd
• Internal Dosimetry
• Performance Capabilities for Internal Exposure Monitoring
• Performance Capabilities for Internal Exposure Monitoring cont'd
• Table 5-1. Urine Intake Retention Fractions (IRF) and Bioassay Goals
• Table 5-2. Feces Intake Retention Fractions (IRF) and Bioassay Goals
• Table 5-3. Lung Intake Retention Fractions (IRF) and Bioassay Goals
• Table 5 -4. Dose Conversion Factors for 238U  (a)
• Characterization of Internal Hazards
• Scope of Bioassay Program
• Classification of Bioassay Measurements
• Monitoring Requirements and Selection of Employees
• Table 5 -5. Minimum Uranium Bioassay Monitoring(a,b)
• In Vitro Analysis
• Fecal Analysis
• Table 5 -6. Categories and Performance Criteria for Uranium Bioassay
• Frequency Based on Potential Risk of Intake
• Long-term Follow-up Bioassay Programs
• In Vivo Monitoring
• Urine Sampling
• Urine Sampling cont'd
• Fecal Sampling
• Modeling The Behavior of Uranium in the Body
• Table 5 -8. GI Tract Absorption Factors for Uranium(a)
• Fisher-Modified Wrenn-Lipsztein Uranium Systemic Retention Function
• Urinary Excretion of Uranium
• Fisher-Modified Wrenn-Lipsztein Uranium Urinary Excretion Model
• Fisher-Modified Wrenn-Lipsztein Uranium Urinary Excretion Model cont'd
• Chemical Toxicity
• Table 5 -13. Health Effects from Acute Intake of Soluble Uranium(a)
• Mother-to-Fetus Transfer
• In Vivo Count Results
• Urine Sample Results
• Fecal Sample Results
• Dose Assessment
• Methods of Estimating Intake
• Alternate Methods of Intake Assessment
• Table 5 -15. Uranium Levels for Internal Dosimetry Notification
• Table 5 -16. Uranium Contamination Levels for Notification of Occupational Medicine Physician
• Responseto Suspected Intakes
• Table 5 -17. Early Bioassay Measurement Results Corresponding to the Therapeutic Intervention
• Emergency Action Planning
• Immediate Medical Care
• External Dosimetry
• Table 6 -2. Tissue Weighing Factors
• Table 6 -3. Radiation Dose Limits for DOE and DOE Contractors
• Radiations In Uranium Facilities
• Figure 6-1. Beta Radiation Readings at Surface of Uranium Metal vs. % Enrichment by Weight
• Figure 6-2. Absorbed Dose Rate as a Function of Depth in Mylar
• Alpha and Beta Doses
• Gamma Doses
• Table 6 -4. Spontaneous Fission Neutron Yields
• Table 6 -5. Neutron Yields from Alpha-Neutron Reactions for Oxides and Fluorides
• Portable Survey Instruments --Beta Radiation Response
• Table 6 -7. Instrument Response to Uranium Beta Fields
• Angular Response
• Source-Detector Geometry
• Figure 6-7. Average Ion Chamber Survey Meter Response by Group to X or Gamma Photon Radiation
• Figure 6-9. High Resolution Gamma Spectrum of Slightly Enriched Uranium Oxide (1% U-235) recorded with Ge (Li) Detector
• Table 6 -8. Gamma Flux and Ratios at Various Locations and Sources at Fernald Plant
• Personnel Dosimetry
• Angular Dependence
• Extremity Dosimetry
• Table 6-9. Performance Test Categories, Radiation Sources, and Test Ranges for the DOELAP and NVLAP Programs
• External Dose Control
• Table 6 -10. Uranium Beta Shielding
• Recordkeeping
• Nuclear Criticality Safety
• Criticality Control Factors
• Mass
• Interaction or Arrays
• Administrative Practices
• Nuclear Facility Safety Analysis
• Summary of Past Criticality Accidents
• Criticality Alarms and Nuclear Accident Dosimetry
• Nuclear Accident Dosimetry
• Fixed and Personnel Nuclear Accident Dosimeters
• Biological Indicators
• Routine Operations
• Special Considerations During Decommissioning Activities
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• Waste Management
• Dseign of Waste Processing Systems
• Airborne Wastes
• Monitoring
• Water Collection System
• Waste Minimization
• Emergency Management
• Classification of Emergencies and Graded Response
• Hazards Assessment
• Characterizing the Hazards
• Estimating Potential Event Consequences
• Notification
• Protective Actions
• Decontamination and Decommissioning
• Other Regulations
• Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) (USC 1980) and 40 CFR 300 (EPA 1992a)
• Residual Radionuclides in Soil
• Residual Radionuclides in Air and Water
• Ventilation Systems
• Soil-Contamination Considerations
• Pre -Operational and Operational Activities
• Environmental Review Process
• Decontamination (DECON)
• Decommissioning Project Plan
• Decommissioning Operations
• Post-Decommissioning Activities
• Decontamination and Decommissioning Experience
• References
• References cont'd
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• Appendix A Glossary
• Glossary cont'd
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• Concluding Material
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DOE Standard Guide of Good Practices for Occupational Radiological Protection in Uranium Facilities

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