NCRP REPORT No 118 RADIATION PROTECTION IN THE MINERAL EXTRACTION INDUSTRY Recommendations of the NATIONAL COUNCIL O N RADIATION PROTECTION AND MEASUREMENTS Issued November 30,1993 National Council on Radiation Protection and Measurements 7910 Woodmont Avenue Bethesda, MD 20814-3095 LEGAL NOTICE This report was prepared by the National Council on Radiation Protection and Measurements (NCRP) The Council strives to provide accurate, complete and useful information in its reports However, neither the NCRP, the members of NCRP, other persons contributing to or assisting in the preparation of this Report, nor any person actingon the behalf of any of these parties: (a) makes any warranty or representation, express or implied, with respect to the accuracy, completeness or usefulness of the information contained in this Report, or that the use of any information, method or process disclosed in this Report may not infringe on privately owned rights; or (b) assumes any liability with respect to the use of, or for damages resulting from the use of any information, method or process disclosed in this Report, under the Civil Rights Act of 1964, Section 701 et seq as amended 42 U.S.C Section 2000e et seq (Title VII) or any other statutory or common law theory governing liability Library of Congress Cataloging-in-Publication Data National Council on Radiation Protection and Measurements Radiation protection in the mineral extraction industry : recommendations of the National Council on Radiation Protection and Measurements cm.-(NCRP report ; no 118) p "Prepared by Scientific Committee 46-2 on Uranium Mining and MillingRadiation Safety Programs"-Pref "Issued November 30, 1993." Includes bibliographical references (p ) and index ISBN 0-929600-33-9 Mine safety Ore-dressing plants-Safety measures RadiationSafety measures I National Council on Radiation Protection and Measurements, Scientific Committee 46-2 on Uranium Mining and MillingRadiation Safety Programs IT Title 111 Series TN295.N28 1993 622l.8-dc20 93-33554 CIP Copyright O National Council on Radiation Protection and Measurements 1993 All rights reserved This publication is protected by copyright No part of this publication may be reproduced in any form or by any means, including photocopying, or utilized by any information storage and retrieval system without written permission from the copyright owner, except for brief quotation in critical articles or reviews Preface This Report was originally intended as radiation protection recommendations for the uranium mining and milling industry The Committee early on, however, recognized t h a t there were known radiation problems connected with the mining and milling of several minerals Further, the Committee recognized that the extraction and processing of virtually any mineral might result in some level of radiation exposure and that the application of radiation protection practices may be warranted in some cases Therefore, the Report that evolved addresses the whole mineral industry and the material prepared for the uranium mining and milling industry was retained to provide examples of the more complex problems encountered and solutions to those problems The Report was written for a specific audience-management and its technical staff-who either have been made aware of radiation problems by the imposition of a regulation or perceive the importance of evaluating facility design and operations in the societal context of a greater awareness about occupational and environmental risks The International System of Units (SI) is used herein and, in accordance with the recommendations set forth in NCRP Report No 82, SI Units in Radiation Protection and Measurements, the use of conventional units has been discontinued Appendix B contains a conversion table of SI units and conventional units This Report was prepared by Scientific Committee 46-2 on Uranium Mining and Milling-Radiation Safety Programs, working under the auspices of Scientific Committee 46 on Operational Radiation Safety Serving on Scientific Committee 46-2 were: Richard L Doty, Chairman Pennsylvania Power and Light Company Allentown, Pennsylvania Members Albert J Hazle Arvada, Colorado Noel Savignac Albuquerque, New Mexico iv PREFACE Charles E Roessler University of Florida Gainesville, Florida Edwin T Still Kerr-McGee Corporation Oklahoma City, Oklahoma Scientific Committee 46 Liaison Member Keith Schiager University of Utah Salt Lake City, Utah Serving on Scientific Committee 46 were: Kenneth R Kase, Chairman (1990Stanford Linear Accelerator Center Stanford, California ) Charles B Meinhold, Chairman (1983-1990) Brookhaven National Laboratory Upton, New York Members Ernest A Belvin (1983-1987) Marietta, Georgia David S Myers (1987Lawrence Livermore National Laboratory Livermore, California W Robert Casey (1983-1989) Brookhaven National Laboratory Upton, New York John W Poston, Sr (1991- ) Texas A&M University College Station, Texas Robert J Catlin (1983-1992) University of Texas Houston, Texas Keith Schiager (1983University of Utah Salt Lake City, Utah Joyce P Davis (1990- ) Defense Nuclear Facilities Safety Board Washington, D.C William R Hendee (1983- ) Medical College of Wisconsin Milwaukee, Wisconsin ) ) Ralph H Thomas (1989- ) Lawrence Livermore National Laboratory Livermore, California Robert G.Wissink (1983- ) Minnesota Mining and Manufacturing (3M) Center St Paul, Minnesota PREFACE James E McLaughlin (1983- ) Santa Fe, New Mexico V Paul L Ziemer (1983-1990) U.S Department of Energy Washington, D.C Thomas D Murphy (1983-1992) U.S Nuclear Regulatory Commission Washington, D.C NCRP Secretariat James A Spahn, Jr (1986- ) Robert T Wangemann (1986) E Ivan White (1983-1985) The Council wishes to express its appreciation to the members of the Committee for the time and effort devoted to the preparation of this Report Charles B Meinhold President, NCRP Bethesda, Maryland August 1,1993 Contents Preface Introduction 1.1 Purpose 1.2 Concepts of Radiation Protection 1.3 Scope of Report Design of Radiation Protection Programs 2.1 Criteria for Radiation Protection Programs 2.2 Program Management 2.3 Radiation Safety Officer 2.4 Radiation Safety Committee 2.5 Preparation and Maintenance of Records 2.6 Quality Assurance Program 2.7 Coordination Among Safety Programs Sources of Potential Radiation Exposures 3.1 Source Characterization 3.1.1 Naturally Occurring Radioactive Materials 3.1.2 Distribution of Radioactivity in Ore Product, By-Products and Wastes 3.1.3 Characteristics Related to Radiation Dose 3.2 Occupational Exposures 3.2.1 External Radiation 3.2.2 Airborne Radioactivity 3.2.3 Surface Contamination 3.3 Releases to the Environment 3.3.1 Airborne 3.3.2 Waterborne 3.3.3 External Radiation 3.4 Process By-Products and Waste Materials Exposure Management Program 4.1 Exposure Limits 4.2 Exposure Environment 4.2.1 External Radiation 4.2.2 Ore Dust 4.2.3 Airborne Radon and Radon Progeny 4.3 Facility Design and Engineering 4.3.1 Site Selection 4.3.2 Facility Layout 4.3.3 Equipment and System Design vii viii I CONTENTS 4.4 Facility Procedures and Practices 4.4.1 Access Control 4.4.2 Radioactive Material Control 4.4.2.1 Materials Handling 4.4.2.2 Waste Management 4.4.2.3 Sealed Source Control 4.4.3 Personnel Protective Equipment 4.4.3.1 Respiratory Protection 4.4.3.2 Protective Clothing 4.5 Employee Training Monitoring of Occupational Exposure 5.1 Monitoring Objectives 5.1.1 Characterization of the Workplace 5.1.2 Personnel Exposure Assessment 5.2 Monitoring Program 5.3 External Radiation 5.3.1 Characterization of the Workplace 5.3.2 Personal Monitoring-External 5.4 Long-Lived Airborne Radionuclides 5.4.1 Characterization of the Workplace 5.4.2 Personnel Exposure Assessment-Internal 5.5 Airborne Radon and Progeny 5.5.1 Characterization of the Workpla~e-~~~Rn and Progeny 5.5.2 Personnel Exposure Asse~sment-~~~Rn and Progeny 5.5.3 Radon-220 and Progeny 5.5.4 Monitoring for Control Purposes 5.6 Surface Contamination 5.6.1 Area Monitoring 5.6.2 Monitoring of Personnel 5.6.3 Monitoring Other Items 5.7 Bioassay 5.7.1 Bioassay Methods 5.7.2 Bioassay Program Content 5.7.3 Routine Bioassay 5.7.4 Post-Exposure and Follow-Up Measurements Effluent Monitoring and Environmental Surveillance 6.1 Environmental Pathways 6.2 Effluent Monitoring 6.2.1 Effluent Monitoring Objectives 6.2.2 Program Design 6.2.3 Air Monitoring 6.2.4 Water Monitoring CONTENTS 6.3 Environmental Surveillance 6.3.1 Environmental Monitoring Objectives 6.3.2 Program Design 6.3.3 Radon 6.3.4 Radon Progeny 6.3.5 Long-Lived Airborne Radionuclides 6.3.6 Soil and Vegetation 6.3.7 Water 6.3.8 External Radiation Guidelines Standards and Regulations 7.1 General 7.2 Sources of Guidance and Standards 7.2.1 Scientific Recommendations 7.2.2 Consensus Standards 7.2.3 Federal Guidance and Policy 7.2.4 Rules and Regulations 7.3 Approaches to Radiation Limits 7.4 Occupational Exposures 7.4.1 Introduction 7.4.2 Recommendations 7.4.3 Standards and Regulations 7.5 Effluents and the Environment 7.5.1 Emuents 7.5.2 Wastes 7.5.3 Uranium and Thorium Processing Sites 7.5.4 Other Radiation Emergency Response Planning 8.1 General 8.2 Operations 8.3 Environment 8.4 Transportation Radiation Protection in Specific Applications 9.1 Introduction 9.2 Heap-Leach Extraction 9.3 I n situ Mineral Extraction 9.4 Side-Stream Extractions of Uranium 9.4.1 Uranium Recovery from Phosphoric Acid 9.4.2 Occupational Exposure Considerations 9.4.3 Shipping and Transportation 9.4.4 Efluents and Environmental Monitoring 9.4.5 Solid Radioactive Waste and Equipment Reuse or Salvage 9.5 Thorium and Rare-Earths Processing 9.6 Phosphate X CONTENTS 9.6.1 Mining Beneficiation and Wet Rock Handling 9.6.1.1 Occupational Exposure 9.6.1.2 Mining and Beneficiation Wastes and Post-Mining Land 9.6.1.3 Liquid Releases and Water Quality 9.6.2 Phosphate Rock Drying and Dry Rock Handling 9.6.2.1 Occupational Exposure 9.6.2.2 Emissions 9.6.3 Wet-Process Phosphoric Acid Plants 9.6.3.1 Occupational Exposure-Protection Operations 9.6.3.2 Occupational Exposure-Clean-up and Maintenance 9.6.3.3 Occupational Exposure-Filter Pan Repair 9.6.3.4 Waste Management 9.6.3.5 Phosphogypsum 9.6.4 Production of Phosphate Products 9.6.5 Thermal Process (Elemental Phosphorus) Appendix A Radioactive Serie~.~~'U and ='U Appendix B Conversion Factors Glossary References The NCRP NCRP Publications Index Introduction 1.1 Purpose The National Council on Radiation Protection and Measurements (NCRP) develops recommendations dealing with various aspects of operational radiation protection The basic principles and practices of radiation safety are well established However, specific facilities present specific problems To serve the needs of a particular facility, effective programs should recognize and account for variables such as the complexity of radiation exposure pathways and the magnitude of potential radiation exposure a t a given facility This Report describes the vital parts of an effective radiation safety program for mineral extraction facilities It provides information useful for choosing appropriate techniques of radiation control and monitoring a t such facilities Because radioactive material occurs naturally throughout the earth's crust, any mineral extraction operation or process, not just those commonly perceived to be processing radioactive materials, is a candidate for radiation safety measures This Report draws on examples from the uranium mining and milling industry, but principles and practices common across the entire mineral extraction industry are emphasized Mining, milling and beneficiation have long been accepted technologies for extracting and processing ores However, they are among the technologies that have come under increasing scrutiny from a society concerned about occupational and environmental risks Increasing awareness and attention has been placed on the potential uses and risks of radioactive materials Therefore, assessing the radiation protection requirements and practices of the mineral extraction industry is both timely and consistent with good work practices This Report is written so that individuals with a basic technical background can apply the concepts of radiation protection to evaluate any mineral extraction operation Management can use the Report to define the degree to which radiation safety should be considered in designing facilities and planning their operation Design engineers as well a s health and safety professionals will find useful NCRP Publications NCRP publications are distributed by the NCRP Publications Office Information on prices and how to order may be obtained by directing an inquiry to: NCRP Publications 7910 Woodmont Avenue Suite 800 Bethesda, MD 20814-3095 The currently available publications are listed below No NCRP Reports Title Control and Removal ofRadioactive Contamination in Laboratories (1951) Maximum Permissible Body Burdens and Maximum Permissible Concentrations of Radionuclides in Air and in Water for Occupational Exposure (1959)[Includes Addendum issued in August 19631 Measurement of Neutron Flux and Spectra for Physical and Biological Applications (1960) Measurement of Absorbed Dose ofNeutrons,and of Mixtures of Neutrons and Gamma Rays (1961) Stopping Powers for Use with Cavity Chambers (1961) Safe Hand1ing of Radioactive Materials (1964) Radiation Protection in Educational Institutions (1966) Dental X-Ray Protection (1970) Radiation Protection in Veterinary Medicine (1970) Precautions in the Management of Patients Who Have Received Therapeutic Amounts of Radionuclides (1970) Protection Against Neutron Radiation (1971) Protection Against Radiation from Brachytherapy Sources (1972) Specification of Gamma-Ray Brachytherapy Sources (1974) Radiological Factors Affecting Decision-Making i n a Nuclear Attack (1974) / NCRP PUBLICATIONS Krypton-85 in the Atmosphere-Accumulation, Biological Significance, and Control Technology (1975) Alpha-Emitting Particles in Lungs (1975) Tritium Measurement Techniques (1976) Structural Shielding Design and Evaluation for Medical Use of X Rays and Gamma Rays of Energies Up to 10 MeV (1976) Environmental Radiation Measurements (1976) Radiation Protection Design Guidelines for 0.1-100 MeV Particle Accelerator Facilities (1977) Cesium-137 from the Environment to Man: Metabolism and Dose (1977) Medical Radiation Exposure of Pregnant and Potentially Pregnant Women (1977) Protection of the Thyroid Gland in the Event of Releases of Radioiodine (1977) Instrumentation and Monitoring Methods for Radiation Protection (1978) A Handbook of Radioactivity Measurements Procedures, 2nd ed (1985) Operational Radiation Safety Program (1978) Physical, Chemical, and Biological Properties of Radiocerium Relevant to Radiation Protection Guidelines (1978) Radiation Safety Training Criteria for InduWid Radiography (1978) Tritium in the Environment (1979) Tritium and Other Radionuclide Labeled Organic Compounds Incorporated in Genetic Material (1979) Influence of Dose and Its Distribution in Time on DoseResponse Relationships for Low-LET Radiations (1980) Management of Persons Accidentally Contaminated with Radionuclides (1980) Radiofrequency Electromagnetic Fields-Properties, Quantities and Units, Biophysical Interaction, and Measurements (1981) Radiation Protection in Pediatric Radiology (1981) Dosimetry of X-Ray and Gamma-Ray Beams for Radiation Therapy in the Energy Range 10 keV to 50 MeV (1981) Nuclear Medicine-Factors Influencing the Choice and Use of Radionuclides i n Diagnosis and Thempy (1982) Opemtional Radiation Safety-Training (1983) Radiation Protection and Measurement for Low -Voltage Neutron Generators (1983) NCRP PUBLICATIONS 127 Protection in Nuclear Medicine and Ultrasound Diagnostic Procedures in Children (1983) Biological Effects of Ultrasound: Mechanisms and Clinical Implications (1983) Iodine-129: Evaluation of Releases from Nuclear Power Genemtion (1983) Radiological Assessment: Predicting the Transport, Bioaccumulation, and Uptake by Man of Radionuclides Released to the Environment (1984) Exposures from the Uranium Series with Emphasis on Radon and Its Daughters (1984) Evaluation of Occupational and Environmental Exposures toRadon and Radon Daughters in the United States (1984) Neutron Contamination from Medical Electron Accelemtors (1984) Induction of Thyroid Cancer by Ionizing Radiation (1985) Carbon-14 in the Environment (1985) SI Units in Radiation Protection and Measurements (1985) The Experimental Basis for Absorbed-Dose Calculations in Medical Uses of Radionuclides (1985) General Concepts for the Dosimetry of Internally Deposited Radionuclides (1985) Mammography-A User's Guide (1986) Biological Effects and Exposure Criteria for Radiofrequency Electromagnetic Fields (1986) Use of Bioassay Procedures for Assessment c Internal Radionuclide Deposition (1987) Radiation Alarms and Access Control Systems (1986) Genetic Effects from Internally Deposited Radionuclides (1987) Neptunium: Radiation Protection Guidelines (1988) Public Radiation Exposure from Nuclear Power Generation in the United States (1987) Ionizing Radiation Exposure of the Population of the United States (1987) Exposure of the Population in the United States and Canada from Natural Background Radiation (1987) Radiation Exposure of the U.S Population from Consumer Products and Miscellaneous Sources (1987) Comparative Carcinogenicity of Ionizing Radiation and Chemicals (1989) Measurement of Radon and Radon Daughters in Air (1988) Guidance on Radiation Received in Space Activities (1989) Quality Assurance for Diagnostic Imaging (1988) 128 NCRP PUBLICATIONS Exposure of the U.S Population from Diagnostic Medical Radiation (1989) 101 Exposure of the U.S Population from Occupational Radiation (1989) 102 Medical X-Ray, Electron Beam and Gamma-Ray Protection for Energies Up to 50 MeV (Equipment Design, Performance and Use) (1989) 103 Control of Radon in Houses (1989) 104 The Relative Biological Effectiveness ofRadiations ofDifferent Quality (1990) 105 Radiation Protection for Medical a n d Allied Health Personnel (1989) 106 Limit for Exposure to "Hot Particles" on the Skin (1989) 107 Implementation of the Principle of As Low As Reasonably Achievable (ALARA) for Medical and Dental Personnel (1990) Conceptual Basis for Calculations of Absorbed-Dose 108 Distributions (1991) 109 Effects of Ionizing Radiation on Aquatic Organisms (1991) 110 Some Aspects of Strontium Radiobiology (1991) 111 Developing Radiation Emergency Plans forAcademic, Medical or Industrial Facilities (1991) 112 Calibration of Survey Instruments Used in Radiation Protection for the Assessment of Ionizing Radiation Fields and Radioactive Surface Contamination (1991) 113 Exposure Criteria for Medical Diagnostic Ultrasound:I Criteria Based on Thermal Mechanisms (1992) 114 Maintaining Radiation Protection Records (1992) 115 Risk Estimates for Radiation Protection (1993) 116 Limitation of Exposure to Ionizing Radiation (1993) 117 Research Needs for Radiation Protection (1993) 118 Radiation Protection i n the Mineral Extraction Industry (1993) Binders for NCRP reports are available Two sizes make it possible to collect into small binders the "old series" of reports (NCRP Reports Nos 8-30)and into large binders the more recent publications (NCRP Reports Nos 32-118).Each binder will accommodate from five to seven reports The binders carry the identification "NCRP Reports" and come with label holders which permit the user to attach labels showing the reports contained in each binder The following bound sets of NCRP reports are also available: Volume I NCRP Reports Nos 8,22 Volume 11 NCRP Reports Nos 23,25,27,30 Volume 111 NCRP Reports Nos 32,35,36,37 100 NCRP PUBLICATIONS 129 Volume IV NCRP Reports Nos 38,40,41 Volume V NCRP Reports Nos 42,44,46 Volume VI NCRP Reports Nos 47,49,50,51 Volume VII NCRP Reports Nos 52,53,54,55,57 Volume VIII NCRP Report No 58 Volume IX NCRP Reports Nos 59,60,61,62,63 Volume X NCRP Reports Nos 64,65,66,67 Volume XI NCRP Reports Nos 68,69,70,71,72 Volume XII NCRP Reports Nos 73,74,75,76 Volume XIII NCRP Reports Nos 77,78,79,80 Volume XIV NCRP Reports Nos 81,82,83,84,85 Volume XV NCRP Reports Nos 86,87,88,89 Volume XVI NCRP Reports Nos 90,91,92,93 Volume XVII NCRP Reports Nos 94,95,96,97 Volume XVIII NCRP Reports Nos 98,99,100 Volume XIX NCRP Reports Nos 101,102,103,104 Volume XX NCRP Reports Nos 105,106,107,108 Volume XXI NCRP Reports Nos 109,110,111 Volume XXII NCRP Reports Nos 112,113,114 (Titles of the individual reports contained in each volume are given above.) NCRP Commentaries No Title Kryljton85 in the Atmosphere With Specific Reference to the Public Health Significance of the Proposed Controlled Release at Three Mile Island (1980) Preliminary Evaluation of Criteria for the Disposal of Transuranic Contaminated Waste (1982) Screening Techniques for Determining Compliance with Environmental Standards-Releases of Radionuclides to the Atmosphere (19861,Revised (1989) Guidelines for the Release of Waste Water from Nuclear Facilities with Special Reference to the Public Health Significance of the Proposed Release of Treated Waste Waters at Three Mile Island (1987) Review of the Publication, Living Without Landfills (1989) Radon Exposure of the U.S Population-Status of the Problem (1991) Misadministration of Radioactive Material in MedicineScientific Background (1991) 130 / NCRP PUBLICATIONS Uncertainty in NCRP Screening Models Relating to Atmospheric Transport, Deposition and Uptake by Humans (1993) Proceedings of the Annual Meeting No Title Perceptions of Risk, Proceedings of the Fifteenth Annual Meeting held on March 14-15, 1979 (including Taylor Lecture No 3) (1980) Critical Issues in Setting Radiation Dose Limits, Proceedings of the Seventeenth Annual Meeting held on April 89, 1981 (including Taylor Lecture No 5) (1982) Radiation Protection and New Medical Diagnostic Approaches, Proceedings of the Eighteenth Annual Meeting held on April 6-7, 1982 (including Taylor Lecture No 6) (1983) Environmental Radioactivity, Proceedings of the Nineteenth Annual Meeting held on April 6-7,1983 (including Taylor Lecture No 7) (1983) Some Issues Important in Developing Basic Radiation Protection Recommendations, Proceedings of the Twentieth Annual Meeting held on April 4-5,1984 (includingTaylor Lecture No 8) (1985) Radioactive Waste, Proceedings of the Twenty-first Annual Meeting held on April 3-4,1985 (includingTaylor Lecture No 9) (1986) Nonionizing Electromagnetic Radiations and Ultmsound, Proceedings of the Twenty-second Annual Meeting held on April 2-3, 1986 (including Taylor Lecture No 10) (1988) New Dosimetry a t Hiroshima and Nagasaki and Its Implications for Risk Estimates, Proceedings of the Twenty-third Annual Meeting held on April 8-9,1987 (includingTaylor Lecture No 11)(1988) Radon, Proceedings of the Twenty-fourth Annual Meeting held on March 30-31, 1988 (including Taylor Lecture No 12) (1989) RadiationProtection Today The NCRP a t Sixty Years, Proceedings of the Twenty-Mth Annual Meeting held on April 5-6, 1989 (including Taylor Lecture No 13) (1990) Health and Ecological Implications of Radioactively Contaminated Environments, Proceedings of the Twenty- NCRP PUBLICATIONS / 131 sixth Annual Meeting held on April 4-5,1990 (including Taylor Lecture No 14) (1991) Genes, Cancer and Radiation Protection, Proceedings of the Twenty-seventh Annual Meeting held on April 3-4,1991 (including Taylor Lecture No 15) (1992) Radiation Protection in Medicine, Proaxdings of the Twentyeighth Annual Meeting held on April 1-2,1992 (including Taylor Lecture No 16) (1993) Lauriston S Taylor Lectures No Title The Squares of the Natural Numbers inRadiation Protection by Herbert M Parker (1977) Why be Quantitative about Radiation Risk Estimates? by Sir Edward Pochin (1978) Radiation Protection Concepts and Trade Offs by Hymer L Friedell (1979) [Available also in Perceptions of Risk, see abovel From "Quantity of Radiation" and "Dose" to "Exposure" and "Absorbed Dose9'-An Historical Review by Harold Wyckoff (1980) How Well Can We Assess Genetic Risk? Not Very by James F Crow (1981)[Available also in CriticalIssues in Setting Radiation Dose Limits, see abovel Ethics, Trade-offs and Medical Radiation by Eugene L Saenger (1982) [Available also in Radiation Protection and New Medical Diagnostic Approaches, see abovel The Human Environment-Past, Present and Future by Merril Eisenbud (1983) [Available also in Environmental Radioactivity, see abovel Limitation and Assessment in Radiation Protection by Harald H Rossi (1984) [Available also in Some Issues Important in Developing Basic Radiation Protection Recommendations, see above] Truth (and Beauty) in Radiation Measurement by John H Harley (1985) [Available also in Radioactive Waste, see above] Biological Effects of Non-ionizing Radiations: Cellular Properties and Interactions by Herman P Schwan (1987) [Available also in Nonionizing Electromagnetic Radiations and Ultrasound, see abovel How to be Quantitative about Radiation Risk Estimates by 12 13 14 15 16 Seymour Jablon (1988) [Available also in New Dosimetry at Hiroshima and Nagasaki and its Implications for Risk Estimates, see abovel How Safe is Safe Enough? by Bo Lindell(1988) [Available also in Radon, see abovel Radiobiology and Radiation Protection: The Past Century and Prospects for the Future by Arthur C Upton (1989) [Available also in Radiation Protection Today, see abovel Radiation Protection and the Internal Emitter Saga by J Newel1 Stannard (1990) [Available also in Health and Ecological Implications of Radioactively Contaminated Environments, see above] When is a Dose Not a Dose? by Victor P Bond (1992) [Available also in Genes, Cancer and Radiation Protection, see above] Dose and Risk i n Diagnostic Radiology: How Big? How Little? by Edward W Webster (1992)[Available also in Radiation Protection in Medicine, see abovel Symposium Proceedings The Control of Exposure of the Public to Ionizing Radiation i n the Event ofAccident or Attack, Proceedings of a Symposium held April 27-29, 1981 (1982) NCRP Statements No Title "Blood Counts, Statement of the National Committee on Radiation Protection," Radiology 63, 428 (1954) ''Statements on Maximum Permissible Dose from Television Receivers and Maximum Permissible Dose to the Skin of the Whole Body," Am J Roentgenol., Radium Ther and Nucl Med 84, 152 (1960) and Radiology 75, 122 (1960) X-Ray Protection Standards for Home Television Receivers, Interim Statement of the National Council on Radiation Protection and Measurements (1968) Specification of Units ofNatura1 Uranium and Natural Thorium, Statement of the National Council on Radiation Protection and Measurements, (1973) NCRP Statement on Dose Limit for Neutrons (1980) Control of Air Emissions of Radionuclides (1984) NCRP PUBLICATIONS 133 The Probability That a Particular Malignancy May Have Been Caused by a Specified Zrmdiation (1992) Other Documents The following documents of the NCRP were published outside of the NCRP Report, Commentary and Statement series: Somatic Radiation Dose for the General Population, Report of the Ad Hoc Committee of the National Council on Radiation Protection and Measurements, May 1959, Science, February 19, 1960, Vol 131, No 3399, pages 482-486 Dose Effect Modihing Factors In Radiation Protection, Report of Subcommittee M-4 (Relative Biological Effectiveness) of the National Council on Radiation Protection and Measurements, Report BNL 50073 (T-471) (1967)Brookhaven National Laboratory (National Technical Information Service Springfield, Virginia) The following documents are now superseded andlor out of print: NCRP Reports No Title X-Ray Protection (1931) [Superseded by NCRP Report No 31 Radium Protection (1934) [Superseded by NCRP Report No 41 X-Ray Protection (1936) [Superseded by NCRP Report No 61 Radium Protedion (1938) [Supersededby NCRP Report No 131 Safe Handling of Radioactive Luminous Compound (1941) [Out of Printl Medical X-Ray Protection Up to Two Million Volts (1949) [Superseded by NCRP Report No 181 Safe Handling of Radioactive Isotopes (1949) [Superseded by NCRP Report No 301 Recommendations for WasteDisposal ofPhosphorus32 and Zodine-131 for Medical Users (1951) [Out of Printl Radiological Monitoring Methods and Instruments (1952) [Superseded by NCRP Report No 571 Maximum Permissible Amounts of Radioisotopes i n the Human Body and Maximum Permissible Concentrations in Air and Water (1953) [Superseded by NCRP Report No 221 Recommendations for the Disposal of Carbon-14 Wastes (1953) [Superseded by NCRP Report No 811 134 / NCRP PUBLICATIONS Protection Against Radiations from Radium, Cobalt-60 and Cesium-137 (1954)[Superseded by NCRP Report No 241 Protection Against Betatron-Synchrotron Radiations Up to 100 Million Electron Volts (1954)[Superseded by NCRP Report No 511 Safe Handling of Cadavers Containing Radioactive Isotopes (1953)[Superseded by NCRP Report No 211 Radioactive-Waste Disposal i n the Ocean (1954)[Out of Print] Permissible Dose from External Sources of Ionizing Radiation (1954)including Maximum Permissible Exposures to Man, Addendum to National Bureau of Standards Handbook 59 (1958)[Superseded by NCRP Report No 391 X-Ray Protection (1955)[Superseded by NCRP Report No 261 Regulation of Radiation Exposure by Legislative Means (1955)[Out of Print] Protection Against Neutron Radiation Up to 30 Million Electron Volts (1957)[Superseded by NCRP Report No 381 Safe Handling of Bodies Containing Radioactive Isotopes (1958)[Superseded by NCRP Report No 371 Protection Against Radiations from Sealed Gamma Sources (1960)[Superseded by NCRP Reports No 33,34and 401 Medical X-Ray Protection Up to Three Million Volts (1961) [Superseded by NCRP Reports No 33,34,35and 361 A Manual of Radioactivity Procedures (1961)[Superseded by NCRP Report No 581 Exposure to Radiation in an Emergency (1962)[Superseded by NCRP Report No 421 Shielding for High-Energy Electron Accelerator Installations (1964)[Superseded by NCRP Report No 511 Medical X-Ray and Gamma-Ray Protection for Energies up to 10 MeV-Equipment Design and Use (1968)[Superseded by NCRP Report No 1021 Medical X-Ray and Gamma-Ray Protection for Energies Up to 10 MeV-Structural Shielding Design and Evaluation Handbook (1970)[Superseded by NCRP Report No 491 Basic Radiation Protection Criteria (1971)[Superseded by NCRP Report No 911 Review of the Current State of Radiation Protection Philosophy (19751[Superseded by NCRP Report No 911 Natural Background Radiation in the United States (1975) [Superseded by NCRP Report No 941 NCRP PUBLICATIONS / 135 Radiation Protection for Medical and Allied Health Personnel (1976) [Superseded by NCRP Report No 1051 Review ofNCRP RadiationDose Limit forEmbryo and Fetus in Occupationally-Exposed Women (1977) [Out of Print] Radiation Exposure from Consumer Products and Miscellaneous Sources (1977) [Superseded by NCRP Report No 951 A Handbook of Radioactivity Measurements Procedures, 1st ed (1978) [Superseded by NCRP Report No 58,2nd ed.] Mammography (1980) [Out of Print] Recommendations on Limits for Exposure toIonizing Radiation (1987) [Superseded by NCRP Report No 1161 NCRP Proceedings No Title Quantitative Risk in Standards Setting, F'roceedings of the Sixteenth Annual Meeting held on April 2-3, 1980 [Out of Print] Index Access control, 27, 31-32, 80, 83, 85 Airborne radioactivity, 19-21 Airborne radionuclides (longlived), 9, 15, 36, 42-44, 62, 64, 80, 82, 84, 88, 89, 91, 94 Airborne radon and radon progeny, 25-26,44-46,63-64 Alpha-specific survey probe, 47 Aluminum, 16 Ammonium diuranate, 82 Ammonium uranyl tricarbonate, 81 Area monitoring, 39,43,45,47 As low as reasonably achievable (ALARA), 3,22-24,27,30,32, 48, 70, 72, 89, 90, 101 Beneficiation, 86, 101 Beta radiation fields, 19, 24, 84 Bioassay, 10, 49-52, 86, 101, 102 Breathing zone sampling, 44 By-product material, 68, 70 By-products, 17, 22, 71, 80, 90 Calcining, 21, 82, 83, 94 Changelshower rooms, 34,47,83 Chemical element influences, 53, 65 Consultants, outside assistance, 6, 40, 56, 76 Contamination control, 20, 27, 30, 33, 47, 48 Contamination, surface, 9, 20, 22, 47,92, 101 Copper, 16,81 Crushing and grinding, 19-21, 25, 29, 32, 42 Decommissioning, 4, Design of facility, 10, 26, 90 Dilution, dispersion, 54.56, 60 Dissolved fraction in water, 58, 64 Dose determinants, general, 18, 24 Dosimetry accreditation program, 41 Dry rock handling, 86, 89 Effluent control systems, 29, 30, 53,55, 59, 83 Effluent monitoring, 53,55-58, 61,62, 89 air monitoring, 56-58 frequency, 57, 58 objectives, 58-59 program design, 59-63 water monitoring, 58-59 Effluent monitoring and environmental surveillance, 53-65 effluent monitoring, 55-58 environmental pathways, 54-55 environmental surveillance, 58-65 Effluents, 10, 20, 21, 53 Elevated radiation levels, 17, 88, 92 Emergency preparedness and response, 62-63, 75, 83 Enhanced radiation levels, 17, 25 Environmental impact assessment, 10,55, 56,81, 93 modeling, 10,56, 59 Environmental monitoring, 53, 58-61, 78,80,84 baseline, 53,59-61 desirability, 60 heap leaching, 78 in situ facility, 80 objectives, 58-59 side-stream extraction facility, 84 Environmental surveillance, 58-65 INDEX Equilibrium, 15, 25, 44, 85, 86, 90,102 Equipment and system design, 28-31,80,85,87 Exposure environment, 24 Exposure limits, personnel, 23, 38,48, 59, 70, 72 Exposure management program, 23-35 employee training, 34, 35 exposure environment, exposure limits, 23, 24 facility design and engineering, 26-31 facility procedures and practices, 31-34 Exposure pathways, 14,54 External radiation sources, 18, 19, 22, 24, 29, 38-42, 65 Extractive processes, 15, 17 Facility layout, 27-28 Ferrophosphorus, 94 Film badges, 40, 41 Filter pan repair, 91 Fluorimetry, 43 Fluorospar, 16 Gamma radiation field, 19, 24, 39, 61, 79,80, 82, 84, 88, 90, 91, 93, 94 environmental measurements, 61,65 Gauges, 19,32,88 Geiger-Mueller meters, 39 Green salt (UF,), 82 Guidance and consensus standards, 66, 67 Guidelines, standards and regulations, 66-74 approaches to limits, 70-71 effluents and the environment, 73-74 occupational exposure, 71-73 public exposure, 73-74 rules and regulations, 68-70 sources, 67-68 / 137 Heap leaching, 77-79, 102 Housekeeping, 32, 80 In situ (solution) mining, 77, 79-80 Instrument calibration, 40 Ion chamber meters, 40 Iron, 16 Isokinetic sampling, 57, 58 Job analysis, 34-35 Layout of facility, 27,80,82, 85 Lead, 15 Linear no-threshold hypothesis, Lower limits of detection, 57, 64 Lunch rooms, 20,27,47 Maintenance shops, 27,47,91 Management principles, 7, 10, 23, 55, 58-59, 61 Meteorological data, 56 Mill exhaust stacks, 21, 55, 57 Mine ventilation, 21, 28, 46, 56-57 Mine waters, 30,55, 79 Molybdenum, 16,81 Monazite, 16,84 Monitoring program, 37-38 Natural gas, 15, 16, 77 Naturally occurring radioactive materials, 14-18 Natural radiation environment, 1, 14, 103 Niobium, 16 Occupational exposure monitoring, 36-52 airborne radon and progeny, 44-46 bioassay, 49-52 external radiation, 38-42 long-lived airborne radionuclides, 42-44 monitoring program, 37-38 surface contamination, 47-48 138 / INDEX Open pit or surface mines, 27, 29, 57, 86, 88 Ore dust, 25, 29, 42, 47, 58, 78 Ore stockpiles, 21, 27, 29 Particle sizes, 18, 64 Personal monitoring, 37, 40, 43-45, 48, 49, 79, 80, 82, 83 Personal protective equipment, 33,80, 83, 85, 89 Personal samplers, 44 Personnel monitoring (see personal monitoring) Personnel protective equipment, 33-34 Petroleum, 15, 16, 77 Phosphate, , mining, beneficiation and wet rock handling, 86-87 occupational exposure, 87-88, 89, 90, 91 phosphate rock drying and dry handling, 89-90 production of phosphate products, 93-94 wet process phosphoric acid plants, 90-94 Phosphate rock, 87, 103 Phosphogypsum, 90,93-94 Phosphoric acid, 81, 86 Phosphorus (thermal process), 86 Potash, 16 Procedures and practices, 10, 31-34, 48, 66,80, 83, 85 Product packaging, 20,21, 25,29, 42-44, 82 Program documentation, 10 Protective clothing, 33-34 Purpose of report, Quality assurance program, 10-12,41, 56,58 Radiation conditions documentation, 9, 10 Radiation emergency response planning, 75-76 environment, 76 operations, 75 transportation, 76 Radiation exposure management, 23,26 Radiation monitoring, 36, 37, 40, 43, 45, 46, 48, 49 personnel exposure assessment, 36, 37, 40, 43, 45,48, 49 workplace characterization, 36, 43, 45, 46 Radiation protection organization, 5, Radiation protection program, design of, 5-13 criteria for, 5-6 integration into overall safety program, 12-13 management of, 6-7 quality assurance, 11-12 records, preparation and maintenance of, 9-11 Radiation safety committee, Radiation safety officer, 8, 92 Radiation safety role, Radioactive decay series, 14, 85, 86,96-99,103 Radioactive material control, 32 Radium, 16-18, 25,28, 53, 64, 80,81,88,90,92-94 Radon, 9, 15, 19, 25, 28, 30, 44-46, 63, 80, 84,87, 91, 93, 94,104 Radon flux, 63, 93,104 Radon monitor, etched track, 63 Radon progeny, 9, 15, 19,25, 28, 29,44, 46, 63, 85,87, 94, 104 Rare earths, 16,84 Recordkeeping, Regulations, 5, 66, 68, 72, 73, 88 Release for unrestricted use, 22, 31,48, 92, 93 Residues in equipment, 25, 39, 72,80,90-92 Respirators, 33, 48,49, 89 Respiratory protection, 33 Reuse and salvage, 17, 22, 84 Risk, 2, 5, 12 Rutile, 84 INDEX Safety program, overall, 12 Sample preservation, 65 Sampling, 36, 43, 45,55, 58, 61-65, 78, 80, 81, 87, 89, 93, 104 Sanitary or storm sewers, 56 Sealed source control, 32 Scintillation meters, 39 Screening models, 59-60 Settling pond, 21, 31 Side-stream extraction, 77, 80-84,104 Silica, 12 Site selection, 26-27 Slag, 94 Soil and vegetation, monitoring and surveillance, 64 Solubility, 18 Source material, 68, 70 Sources of exposure, 14-22 characterization, 14-18 environmental releases, 20-22 occupational, 18-20 process by-products, 22 waste, 22 Surface contamination, 20, 47-48 Surveys, 9, 36, 37, 39, 47, 85, 88, 90,92 Suspended fraction in water, 58, 64 / 139 Tailings, 30, 80, 84, 87, 104 Thermal process (phosphorus), 94 Thermoluminescent dosimeters, 40, 41, 63, 65, 104 Thorium, 14, 16, 18, 68, 74, 84, 87,104 Thorium and rare earths processing, 84-86 Tin, 16,81 Titanium, 16 Training, 10, 32,34, 75, 80, 85 Tungsten, 81 Uranium, 4, 12, 14, 16, 18, 24, 43, 49, 68, 74, 80, 81, 84, 87, 96 Vanadium, 16 Waste management, 32 Wastes, 18, 22, 30, 32, 84, 87, 92 Waterborne effluents, 21,64-65 Wet process phosphoric acid, 90 Wet rock handling, 86, 87 Workers role in safety program, Working levels, 26, 104 Workplace characterization, 36, 43,45, 46 Zinc, 15, 16 Zirconium, 16 ... draws on examples from the uranium mining and milling industry, but principles and practices common across the entire mineral extraction industry are emphasized Mining, milling and beneficiation... This Report was originally intended as radiation protection recommendations for the uranium mining and milling industry The Committee early on, however, recognized t h a t there were known radiation. .. connected with the mining and milling of several minerals Further, the Committee recognized that the extraction and processing of virtually any mineral might result in some level of radiation exposure