NCRP report no 127 operational radiation safety program

NCRP REPORT No 127 OPERATIONAL RADIATION SAFETY PROGRAM Recommendations of the NATIONAL COUNCIL ON RADIATION PROTECTION AND MEASUREMENTS Issued June 12,1998 National Council on Radiation Protection and Measurement 7910 Woodmont Avenue / Bethesda, Maryland 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 documents However, neither the NCRP, the members of NCRP, other persons contributing to or assisting in the preparation of this Report, nor any person acting on 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 thc 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 a s amended 42 U.S.C Section 2000e et seq (Title VII) or any other statutory or common law theorygoverning liability Library of Congress Cataloging-in-PublicationData National Council on Radiation Protection and Measurements Operational radiation safety program : recommendations of the National Council on Radiation Protection and Measurements p cm (NCRP report ; no 127) "Issued June 1998." Includes bibliographical references and index ISBN 0-929600-59-2 Radiation-Safety measures I National Council on Radiation Protection and Measurements 11 Series TK9152.063 1998 363.17'996 dc21 98-4407 CIP Copyright O National Council on Radiation Protection and Measurements 1998 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 copyrightowner, except for brief quotation in critical articles or reviews Preface NCRP Report No 59, Operational Radiation Safety Program, was published in 1978 That report provided the philosophy, basic principles and requirements for a radiation safety program In the intervening years, there have been many new developments including: new NCRP recommendations for limiting exposure to ionizing radiation (NCRP Report No 91 in 1987 which was superseded by NCRP Report No 116 in 1993); new techniques for the measurement and control of exposures and the disposal of radioactive waste; and new applications for ionizing radiation and radioactive materials These developments served as the Council's rationale for preparing the current Report which supersedes NCRP Report No 59 This Report reiterates the basic principles for establishing and maintaining an effective operational radiation safety program Relevant aspects of such a program are discussed including: facility design criteria, organizationaVmanagementissues, training, internal and external radiation control strategies, radioactive waste disposal, environmental monitoring, radiation safety instrumentation, and emergency response planning This Report does not attempt to summarize the regulatory or licensing requirements of the various federal, state or local authorities that may have jurisdiction over matters addressed in this publication This Report was prepared by NCRP Scientific Committee 46 Serving on the Committee were: Kenneth R Kase, Chairman (1991-1 Stanford Linear Accelerator Center Menlo Park, California Members John W.Baum (1993-) Brookhaven National Laboratory Upton, New York Kenneth L Miller (1995-) M.S Hershey Medical Center Hershey, Pennsylvania iv / PREFACE Joyce P Davis (1991-) Defense Nuclear Facilities Safety Board Washington, D.C David S Myers (1991-1 Lawrence Livermore National Laboratory Livermore, California Steven M Garry (1996-) Florida Power Corporation Crystal River, Florida J o h n W Poston, Sr (1991-1 Texas A&M University College Station, Texas Duane C Hall (1995-) 3M Health Physics Services St Paul, Minnesota Keith Schiager (1991-1997) Salt Lake City, Utah William R Hendee (1991-1995) Medical College of Wisconsin Milwaukee, Wisconsin Ralph H Thomas (1991-1996) Moraga, California Kathryn A Higley (1997-) Oregon State University Corvallis, Oregon Paul G Voillequk (1993-) M J P Risk Assessment, Inc Idaho Falls, Idaho Susan M Langhorst (1995) University of MissouriColumbia Columbia, Missouri Robert G wissink* (1991-1995) 3M Health Physics Services St Paul, M i ~ e S o t a James E ~ c ~ a u ~ h l i n * (1991-1995) Sante Fe, New Mexico NCRP Secretariat Eric E Kearsley (1997-), Staff Scientist Thomas M Koval(1993-1997), Senior Staff Scientist J a m e s A Spahn, Jr (1991-1993), Senior Staffscientist Cindy L O'Brien, Editorial Assistant PREFACE / V The Council wishes to express its appreciation to the Committee members for the time and effort devoted to the preparation of this Report The Council also gratefdly acknowledges the support provided by the Health Physics Society in 1998 that permitted the completion of this Report Charles B Meinhold President Contents F'reface 111 Introduction 1.1 Purpose of this Report 1.2 Purpose of the Operational Radiation Safety Program 2 Application of ALARA 2.1 Applicability of Cost-Benefit Analysis in the ALARA Process 2.2 Concepts of a Cost-Benefit Approach to ALARA 2.2.1 Applicability of Collective Effective Dose 2.23 Dose Magnitude and Distributions 2.2.3 Monetary Value of Avoided Dose 2.3 Screening for ALARA Assessment 11 Organization and Administration 12 3.1 Management Commitment and Policy 12 3.2 Radiation Safety Organization 13 3.2.1 Radiation Safety Advisory Organization 13 3.2.2 Radiation Safety Officer 14 3.3 Accreditation and Certification 14 3.4 Radiation Safety Program Policies and Procedures 15 3.4.1 Radiation Safety Manual 15 3.4.2 Radiation Safety Operating Procedures 16 3.5 Responsibility 17 3.6 Quality Assurance 18 3.6.1 Management Goals 19 3.6.2 Surveillance 19 3.6.3 Program Audits 20 3.6.4 Incident and Accident Investigations 21 3.6.5 Deficiency Tracking 22 3.7 Records Management 23 3.8 Occupational Medicine 23 3.9 Recommended Additional Reading 24 Facility Design 26 4.1 Site Selection 26 4.2 Facility Layout .28 vii viii / CONTENTS Equipment and System Design 29 Shielding 30 Ventilation 32 Radioactive Material Waste Management 35 Instrumentation and Access Control Systems 36 Nuclear Criticality Safety 36 Recommended Additional Reading 36 Orientation and Training 38 5.1 General Principles 38 5.2 Design of a General Training Program 39 5.3 Specific Training Requirements 41 External Radiation Exposure Control 42 6.1 Radiation Dose Controls 43 6.1.1 Limits 43 6.1.2 Administrative Dose Guidelines 43' 6.2 Radiation Dose Control Techniques 43 6.2.1 Time Distance and Shielding 44 6.2.2 Access Control and Alarm Systems 45 6.2.3 Radiation Safety Procedures and Radiation Work Permits 48 6.2.4 Exposure Planning and Dose Reduction Activities 49 6.3 External Radiation Dosimetry 49 6.3.1 Personal Monitoring 49 6.3.2 Dose Assessment 51 6.4 Monitoring and Surveillance Program 51 6.4.1 Radiation Surveys 51 6.4.2 Area Monitoring 53 6.5 Protective Clothing 53 6.6 Records 54 6.7 Recommended Additional Reading 55 Internal Radiation Exposure Control .56 7.1 Radiation Dose Controls 57 7.1.1 Limits 57 7.1.2 Administrative Exposure Guidelines and Reference Levels 57 7.2 Contamination Control Programs 57 7.2.1 Access Control and Alarm Systems 59 7.2.2 Radiation Safety Procedures and Radiation Work Permits 60 7.2.3 Exposure Planning and Dose Reduction Activities 61 7.3 Internal Radiation Dosimetry 62 4.3 4.4 4.5 4.6 4.7 4.8 4.9 CONTENTS / i~ 7.3.1 Personal Monitoring 62 7.3.2 Bioassay Measurements 63 7.3.3 Dose Assessment Monitoring and Surveillance Program 66 7.4.1 Monitoring for Airborne Radioactivity 66 7.4.2 Contamination Surveys 69 7.5 Protective Equipment and Devices 69 7.5.1 Containment Systems 69 7.5.2 Respiratory Protection 70 7.5.3 Protective Clothing 70 7.6 Records Control of Low-Level Radioactive Waste 73 8.1 Minimizing the Production of Waste 74 8.1.1 Practices for Minimizing Waste 74 8.1.2 Practices for Reducing Mixed Waste 75 8.2 Decontamination and Reuse of Tools and Equipment 76 8.3 Collecting Sorting and Classifying Waste 76 8.4 Radioactive Waste Volume Reduction 77 8.5 Storage o f w a s t e 78 8.6 Disposal of Waste 78 8.7 Recycling of Waste 79 8.8 Records 79 8.9 Recommended Additional Reading 80 Control of Exposure to the Public 81 9.1 Standards and Guidance 81 9.2 Control of Off-Site Exposures 82 9.2.1 Determining the Need for Monitoring 9.2.2 Monitoring Airborne Effluents 84 9.2.3 Monitoring Liquid Effluents 86 9.2.4 Monitoring Solid Waste 86 9.3 Environmental Monitoring 87 9.3.1 Preoperational Monitoring 88 9.3.2 Operational Monitoring 89 9.4 Measurement Methods 90 9.5 Dose Assessment 9.6 Quality Assurance 92 9.7 Records 93 10 Radiation Safety Instrumentation 94 10.1 Instrument Specification 95 102 Calibration 96 10.3 Instrument Maintenance 98 10.4 Use of Instruments and Acceptable Uncertainty 99 7.4 x / CONTENTS 10.5 Selection of Instruments for Various Applications 100 10.6 Records for an Instrument Program 106 10.7 Recommended Additional Reading 107 11 Planning for Radiation Emergencies 108 11.1 Development of the Emergency Plan 108 11.2 Preparation of Implementing Procedures 109 11.3 Classification of Emergencies 110 11.4 Practical Considerations 111 11.5 Evaluation of the Plan 112 Glossary 114 References 119 TheNCRP 128 NCRPPublications 137 Index 146 Introduction 1.1 Purpose of this Report In 1978, the National Council on Radiation Protection and Measurements (NCRP) published Report No 59, Operational Radiation Safety Program (NCRP, 1978a) to provide, in a systematic way, the philosophy and the basic principles and requirements for a n operational radiation safety program Since that time, a number of reports detailing specific aspects of operational radiation safety have been published by the Council These include, NCRP Report No 71, Operational Radiation Safety-Training (NCRP, 1983a); NCRP Report No 88, Radiation Alarms and Access Control Systems (NCRP, 1986);NCRP Report No 105,Radiation Protection for Medical and Allied Health Personnel (NCRP, 1989a); NCRP Report No 107, Implementation of the Principle of As Low as Reasonably Achievable MLARA) for Medical and Dental Personnel (NCRP, 1990); NCRP Report No 111, Developing Radiation Emergency Plans for Academic, Medical or Industrial Facilities (NCRP, 1991a); NCRP Report No 112, Calibration of Survey Instruments Used i n Radiation Protection for the Assessment of Ionizing Radiation Fields and Radioactive Surface Contamination (NCRP, 1991b); NCRP Report No 114, Maintaining Radiation Protection Records (NCRF', 1992); NCRP Report No 118, Radiation Protection i n the Mineral Extraction Industry (NCRP, 1993a); NCRP Report NO 120, Dose Control a t Nuclear Power Plants (NCRP, 1994); and NCRP Report No 122, Use of Personal Monitors to Estimate Effective Dose Equivalent and Effective Dose to Workers for External Exposure to Low-LET Radiation (NCRP, 1995a) Reports in progress in the area of operational radiation safety include those on radiation safety design guidelines for particle accelerator facilities, assessment of occupational exposure from internally deposited radionuclides, radiation safety related to special medical procedures, and shielding design for radiotherapy facilities Since the publication of NCRP Report No 59 (NCRP, 1978a1, new recommendations have been made by the NCRP for limiting exposure to ionizing radiation (NCRP, 1993b) In addition, new applications for radiation and radioactive materials in research, 134 / THE NCRP The NCRP has found its relationships with these organizations to be extremely valuable to continued progress in its program Another aspect of the cooperative efforts of the NCRP relates to the Special Liaison relationships established with various governmental organizations that have an interest in radiation protection and measurements This liaison relationship provides: (1) an opportunity for participating organizations to designate an individual to provide liaison between the organization and the NCRP; (2) that the individual designated will receive copies of draft NCRP reports (at the time that these are submitted to the members of the Council) with an invitation to comment, but not vote; and (3) that new NCRP efforts might be discussed with liaison individuals as appropriate, so that they might have a n opportunity to make suggestions on new studies and related matters The following organizations participate in the Special Liaison Program: Australian Radiation Laboratory Central Laboratory for Radiological Protection (Poland) European Commission Federal Office for Radiation Protection (Germany) Health Council of the Netherlands Institute de Protection et de Surete Nucleaire (France) International Commission on Non-Ionizing Radiation Protection Japan Radiation Council Korea Institute of Nuclear Safety National Radiological Protection Board (United Kingdom) National Research Council (Canada) Russian Scientific Commission on Radiation Protection South &can Forum for Radiation Protection Ultrasonics Institute (Australia) The NCRP values highly the participation of these organizations in the Special Liaison Program The Council also benefits significantly from the relationships established pursuant to the Corporate Sponsor's Program The program facilitates the interchange of information and ideas and corporate sponsors provide valuable fiscal support for the Council's program This developing program currently includes the following Corporate Sponsors: 3M Health Physics Services Amersham Corporation Commonwealth Edison Consolidated Edison Duke Energy Corporation Landauer, Inc New York Power Authority Nuclear Energy Institute Southern California Edison Westinghouse Electric Corporation NCRP Publications Information on NCRP publications may be obtained from the NCRP website (http://www.ncrp.com) or by telephone (800-229-2652) and fax (301-907-8768) The address is: NCRP Publications 7910 Woodmont Avenue Suite 800 Bethesda, MD 20814-3095 Abstracts of NCRP reports published since 1980, abstracts of all NCRP commentaries, and the text of all NCRP statements are available at the NCRP website Currently available publications are listed below NCRP Reports No 22 25 27 30 32 35 36 37 38 41 42 Title Control and Removal of Radioactive Contamination in Laboratories (1951) Maximum Permissible Body Burdens and Maximum Permissible Concentrations of Rudionuclides in Air and in Water for Occupational Exposure (1959)Dncludes Addendum issued in August 19631 Measurement ofAbsorbed Dose of Neutrons, and of Mixtures of Neutrons and Gamma Rays (1961) Stopping Powers for Use with Cavity Chambers (1961) Safe Handling 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 TherapeuticAmounts of Radionuclides (1970) Protection Against Neutron Radiation (1971) Specification of Gamma-Ray Brachytherapy Sources (1974) Radiological Factors Affecting Decision-Making in a Nuclear Attack (1974) 138 / NCRP PUBLICATIONS 44 Krypton-85 in the Atmosphere-Accumulation, Biological Significance, and Control Technology (1975) 46 Alpha-Emitting Particles in Lungs (1975) 47 Ditium Measurement Techniques (1976) 49 Structural Shielding Design and Evaluation for Medical Use o f X Rays and Gamma Rays of Energies Up to 10 MeV (1976) 50 Environmental Radiation Measurements (1976) 52 Cesium-I37 from the Environment to Man: Metabolism and Dose (1977) 54 Medical Radiation Exposure ofpregnant and Potentially Pregnant Women (1977) 55 Protection of the Thyroid Gland in the Event of Releases of Radioiodine (1977) 57 Instrumentation and Monitoring Methods for Radiation Protection (1978) 58 A Handbook of Radioactivity Measurements Procedures, 2nd ed (1985) 59 Operational Radiution Safety Program (1978) 60 Physical, Chemical, and Biological Properties of Radiocerium Relevant to Radiation Protection Guidelines (1978) 61 Radiation Safety k i n i n g Criteria for Industrial Radiography (1978) 62 Tritium i n the Environment (1979) 63 Tritium and Other Radionuclide Labeled Organic Compounds Incorporated i n Genetic Material (1979) 64 Influence of Dose and Its Distribution in Time on Dose-Response Relationships for Low-LET Radiations (1980) 65 Management of Persons Accidentally Contaminated with Radionuclides (1980) 67 Radwfrequency Electromagnetic Fields-Properties, Quantities and Units, Biophysical Interaction, and Measurements (1981) 68 Radiation Protection in Pediatric Radiology (1981) 69 Dosimetry of X-Ray and Gamma-Ray Beams for Radiation Therapy in the Energy Range 10 keVto 50 MeV (1981) 70 Nuclear Medicine-Fattors Influencing the Choice and Use of Radionuclides in Diagnosis and Therapy (1982) 71 Operational Radiation Safety-Training (1983) 72 Radiation Protection and Measurement for Low-Voltage Neutron Generators (1983) 73 Protection in Nuclear Medicine and Ultrasound Diagnostic Procedures i n Children (1983) 74 Biological Effects of Ultrasound: Mechanisms and Clinical Implications (1983) 75 Iodine-129: Eoalwrtion of Releases from Nuclear Power Generation (1983) 77 Exposures from the Uranium Series with Emphasis on Radon and Its Daughters (1984) NCRP PUBLICATIONS / 139 78 Evaluation of Occupational and Environmental Exposures to Radon and Radon Daughters in the United States (1984) 79 Neutron Contamination from Medical Electron Accelerators (1984) 80 Induction of Thyroid Cancer by Ionizing Radiation (1985) 81 Carbon-14 in the Environment (1985) 82 S I Units in Radiation Protection and Measurements (1985) 83 The Experimental Basis for Absorbed-Dose Calculations in Medical Uses of Radionuclides (1985) 84 General Concepts for the Dosimetry of Internally Deposited Radionuclides (1985) 86 Biological Effects and Exposure Criteria for Radiofrequency Electromagnetic Fields (1986) 87 Use of Bioassay Procedures for Assessment of Internal Radionuclide Deposition (1987) 88 Radiation Alarms and Access Control Systems (1986) 89 Genetic Effectsfrom Internally Deposited Radionuclides (1987) 90 Neptunium: Radiation Protection Guidelines (1988) 92 Public Radiation Exposure from Nuclear Power Generation in the United States (1987) 93 IonizingRadiation Exposure of the Population of the United States (1987) 94 Exposure of the Population i n the United States and Canada from Natural Background Radiation (1987) 95 Radiation Exposure of the U S Population from Consumer Products and Miscellaneous Sources (1987) 96 Comparative Carcinogenicity of Ionizing Radiation and Chemicals (1989) 97 Measurement of Radon and Radon Daughters in Air (1988) 98 Guidance on Radiation Received in Space Activities (1989) 99 Quality Assurance for Diagnostic Imaging (1988) 100 Exposure of the U S Population from Diagnostic Medical 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 of Radiations of Different Quality (1990) 105 Radiation Protection for Medical and Allied Health Personnel (1989) 106 Limit for Exposure to uHot Particles" on the Skin (1989) 107 Implementation of the Principle o f A s Low As Reasonably Achievable (ALARQ)for Medical and Dental Personnel (1990) 108 Conceptual Basis for Calculations ofAbsorbed-Dose Distributions (1991) 109 Effects of Ionizing Radiation on Aquatic Organisms (1991) 140 / NCRP PUBLICATIONS 110 Some Aspects of Strontium Radiobiology (1991) 111 Developing Radiation Emergency Plans for Academic, Medical or Industrial Facilities (1991) 112 Calibration of Survey Instruments Used in Radiation Protection 113 114 115 116 117 118 119 120 121 122 123 124 125 126 127 for the Assessment of Ionizing Radiation Fields and Radioactive Surface Contamination (1991) Exposure Criteria for Mcdical Diagnostic Ultrasound: I Criteria Based on Thermal Mechanisms (1992) Maintaining Radiation Protection Records (1992) Risk Estimates for Radiation Protection (1993) Limitation of Exposure to Ionizing Radiation (1993) Research Needs for Radiation Protection (1993) Radiation Protection in the Mineral Extraction Industry (1993) A Practical Guide to the Determination of Human Exposure to Radiofrequency Fields (1993) Dose Control at Nuclear Power Plants (1994) Principles and Application of Collective Dose in Radiation Protection (1995) Use of Personal Monitors to Estimate Effective Dose Equivalent and Effective Dose to Workersfor E x t e m l Exposure to Low-LET Radiation (1995) Screening Models for Releases of Radionuclides to Atmosphere, Surface Water, and Ground (1996) Sources and Magnitude of Occupational and Public Exposures from Nuclear Medicine Procedures (1996) Deposition, Retention and Dosimetry of Inhaled Radioactive Substances (1997) Uncertainties in Fatal Cancer Risk Estimates Used in Radiation Protection (1997) Operational Radiation Safety Program (1998) 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 32-127).Each binder will accommodate from five to seven reports The binders cany 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 Volume W NCRP Reports Nos 38,40,41 Volume V NCRP Reports Nos 42,44,46 Volume VI NCRP Reports Nos 47,49,50,51 Volume MI NCRP Reports Nos 52,53,54,55,57 NCRP PUBLICATIONS / 141 Volume VIII NCRP Report No 58 Volume M.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 XM 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 Volume XXIII NCRP Reports Nos 115,116,117,118 Volume XXnr NCRP Reports Nos 119,120,121,122 Volume MCV NCRP Report No 1231 and 12311 (Titles of t h e individual reports contained in each volume a r e given above.) NCRP Commentaries Title No Krypton-85 in the Atmosphere-With spec if^ Reference to the Public Health Significance of the Proposed Controlled Release at Three Mile Island (1980) Screening Techniques for Determining Compliance with Environmental Standards-Releases of Radionuclides to the Atmosphere (1986).Revised (1989) Guidelines for the Release of Waste Water @ m 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 PopulationStatus of the Problem (1991) Misadministration of Radioactive Material i n Medicine-Scientific Background (1991) Uncertainty in NCRP Screening Models Relating to Atmospheric Dansport, Deposition and Uptake by Humans (1993) Considerations Regarding the Unintended Radiation Exposure of the Embryo, Fetus or Nursing Child (1994) 142 / NCRP PUBLICATIONS 10 Advising the Public about Radiation Emergencies:A Document for Public Comment (1994) 11 Dose Limits for Individuals Who Receive Exposure from Radionuclide Therapy Patients (1995) 12 Radiation Exposure and High-Altitude Flight (1995) 13 An Introduction to Efficacy in Diagnostic Radiology and Nuclear Medicine (Justification of Medical Radiation Exposure) (1995) 14 A Guide for Uncertainty Analysis in Dose and Risk Assessments Related to Environmental Contamination (1996) 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 8-9, 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 (including Taylor Lecture No 8) (1985) Radioactive Waste, Proceedings of the Twenty-first Annual Meeting held on April 3-4, 1985 (including Taylor Lecture No 9)(1986) Nonionizing Electromagnetic Radiations and Ultrasound, Proceedings of the Twenty-second Annual Meeting held on April 2-3, 1986 (including Taylor Lecture No 10) (1988) New Dosimetry at Hiroshima and Nagasaki and Its Implications for Risk Estimates, Proceedings of the Twenty-third Annual Meeting held on April 8-9, 1987 (including Taylor Lecture No 11) (1988) 10 Radon, Proceedings of the Twenty-fourth Annual Meeting held on March 30-31, 1988 (including Taylor Lecture No 12) (1989) 11 Radiation Protection Today-The NCRP at Sixty Years, Proceedings of the Twenty-fifth Annual Meeting held on April 5-6, 1989 (including Taylor Lecture No 13) (1990) NCRP PUBLICATIONS / 143 Health and Ecological Implications of Radioactively Contaminated Environments, Proceedings of the Twenty-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 i n Medicine, Proceedings of the Twenty-eighth Annual Meeting held on April 1-2, 1992 (including Taylor Lecture No 16) (1993) Radiation Science and Societal Decision Making, Proceedings of the Twenty-ninth Annual Meeting held on April 7-8, 1993 (including Taylor Lecture No 17) (1994) Environmental Dose Reconstruction and Risk Implications, Proceedings of the Thirty-first Annual Meeting held on April 12-13, 1995 (including Taylor Lecture No 19) (1996) Implications ofNew Data on Radiation Cancer Risk, Proceedings o f the Thirty-second Annual Meeting held on April 3-4,1996 (including Taylor Lecture No 20) (1997) Lauriston S Taylor Lectures No Title The Squares of the Natural Numbers i n Radiation Protection by Herbert M Parker (1977) Why be Quantitative about Radiation Risk Estimates? by Sir Edward Pochin (1978) Radiation Protection Concepts and n u d e Offs by Hymer L Friedell (1979) [Available also in Perceptions of Risk, see abovel From "Quantity of Radiation" and "Dose" to "Exposure" and "Absorbed Dosen-An Historical Review by Harold 0.Wyckoff (1980) How Well Can We Assess Genetic Risk? Not Very by James F.Crow (1981) [Available also in Critical Issues i n Setting Radiation Dose Limits, see above] Ethics, Dude-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 i n Radiation Protection by Harald H Rossi (1984) [Available also in Some Issues Important i n Developing Basic Radiation Protection Recommendations, see above] 144 / NCRP PUBLICATIONS Truth (and Beauty) in Radiation Measurement by John H Harley (1985) [Available also in Radioactive Waste, see abovel Biological Effects of Non-ionizing Radiations: Cellular Properties and Interactions by Herman I? Schwan (1987)[Available also in Nonionizing Electromagnetic Radiations and Ultrasound, see above] How to be Quantitative about Radiation Risk Estimates by Seymour Jablon (1988) [Available also in New Dosimetry at Hiroshima and Nagasaki and its Implications for Risk Estimates, see above] How Safe is Safe Enough? by Bo Lindell(1988) [Available also in Radon, see above] Radiobiology and Rudiation 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 abovel Dose and Risk in Diagnostic Radiology: How Big? How Little? by Edward W Webster (1992)[Available also in Radiation Protection in Medicine, see above] Science, Radiation Protection and the NCRP by Warren K Sinclair (1993)[Available also in Radiation Science and Societal Decision Making, see above] Mice, Myths and Men by R.J Michael Fry (1995) Symposium Proceedings No Title The Control of Exposure of the Public to Ionizing Radiation in the Event of Accident or Attack, Proceedings of a Symposium held April 27-29, 1981 (1982) Radioactive and Mixed Waste-Risk as a Basis for Waste Classification, Proceedings of a Symposium held November 9, 1994 (1995) Acceptability of Risk from Radiation-Application to Human Space Flight, Proceedings of a Symposium held May 29, 1996 (1997) NCRP PUBLICATIONS / 145 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 levi is ion Receivers, Interim Statement of the National Council on Radiation Protection and Measurements (1968) Specifiation of Units ofNatural 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) The Probability That a Particular Malignancy May Have Been Caused by a Specified Irradiation (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) Index Access controls 45-47, 59 audible signals 46 barriers 46 external exposure controls 45 interlock 46 internal exposure controls 59 pre-startup notification 46 run-safe switches 46 visual signals 46 Access control systems 47 effective dose category 47 Accident investigations 21 Administrative controls 6,43, 49,57 Air monitoring 56.66-69 criteria for surveys 67 internal dose assessment 68 objectives 68 ALARA (as low as reasonably achievable) 2,3,5-11, 12,18, 26,40,43-44, 52,55, 61,81 administrative controls applicability of cost-benefit analysis collective effective dose 11 cost-benefit approach documentation 11 external exposure controls 43-44, 52 facility design 26 management commitment and policy 12 monetary value of avoided dose 9-10 occupational dose records 55 occupational exposures 11 public exposure 11,81 screening for ALAFtA assessment 11 social and economic factors use of collective effective dose Alarm systems 45-47,59 area monitors 46 audible signals 46 criticality accident 47 effective dose category 47 external exposure controls 45 internal exposure controls 59 pre-startup notification 46 visual signals 46 Area monitoring 53 external exposure controls 53 Area surveys 19 Audits 20,22 Bioassay 56, 62-66, 71 direct bioassay 63-65 dose assessment 65,66 indirect bioassay 64,65 Calibration 98 facility 98 frequency 98 Collective effective dose ALARA Contamination controls 56 Contamination control programs 57-59 engineering controls 58 Contamination surveys 69 Cost-benefit analysis ALARA Criticality accident 51 personal monitoring 51 Criticality safety 36 facility design 36 Decontamination of equipment 76 waste 76 Detriment social factors INDEX / stochastic health effects Dose records 54,71,72 external exposure controls 54 internal exposure controls 71, 72 Emergency plan 108-113 development 108,109 equipment 110 implementing procedures 109 key individuals 109,110 plan evaluation 112,113 Emergency procedures 17 Emergency response 22 Engineering controls 42,43,49, 58,61 ALARA 61 external exposure controls 43 internal exposure controls 58 Environmental monitoring 82-93 documentation 92,93 dose assessment 91-92 measurement methods 90-91 operational monitoring 89-90 preoperational monitoring 88-89,90 purposes 87,88 quality assurance 92-93 screening models 88 Exposure limits External dosimetry 17 External exposure controls 42-55 access controls 45-47 access control systems 46-47 administrative dose guidelines 43 ALARA 43,44 alarm systems 45-47 area monitoring 53 dose assessment 51 dose records 54 engineering controls 43,49 facility design 42 personal dosimetry 42 personal monitoring 49-51 147 protective clothing 53 radiation safety procedures 48-49 radiation surveys 51 radiation work permits (RWP) 43,48-49 shielding 44 Facility design 26-37.42 air cleaning devices 33 criticality safety 36 economic considerations 28 equipment and system design 29 exhaust vents 33 facility layout 28 fume hoods 34 gloved boxes 34 instrumentation and access control systems 36 monitoring and surveillance equipment 29-30 personal decontamination 29 power reactors 27 public or commercial access 28 radiation-producing equipment 27 radioactive material 27 radioactive waste management 35 shielding 30 site selection 26-28 ventilation 32 waste management 29 waste processing facilities 27 Fume hoods 34-35 Glwed boxes 3435,41 training 41 Incident investigations 21 Instrumentation 94-107 accuracy acceptance criteria 101 calibration 96-98 etchable track detectors 105 film 105 148 / INDEX Geiger-Miiller counters 102, 104,105 instrument specification 95 ionization chamber 102,104, 105 liquid drop (bubble) detectors 104 maintenance 98-99 measurement accuracy 99 measurement uncertainty 100 pulse counting instruments 102 radioactive contamination 103 records 106,107 scintillation detectors 102,105 selection of instrument for various applications 100 semiconductor surface barrier 105 short-term stability 101 superheated liquid drop (bubble) detectors 105 thermoluminescent detectors (TLD)104 uncertainties 97 use categories 99 Interlocks 43 Internal dosimetry 17 Internal exposure controls 56-72 air monitoring 56 access controls 59 alarm systems 59 bioassay 56,62-65 contamination controls 56 contamination control programs 57-59 dose assessments 56,65-66, 68-69 dose records 71-72 engineering controls 58,61 limits 57 monitoring and surveillance program 66-69 personal monitoring 56,62,65 protective clothing 70 protective equipment and devices 69-71 radiation safety procedures 61 radiation safety program 60 radiation work permits (RWP) 60-61 respiratory protection 56,70 Limitation Limits 4,30,43,57 external exposure controls 43 facility design 30 internal exposure controls 57 summary of limits Justification Management commitment and policy 12-13 ALARA 12 budgetary support 12 goals of the radiation safety program 12 Radiation Safety Officer (RSO) 13 worker training 13 Monetary value of avoided dose 9,lO ALARA 9.10 Monitoring and surveillance program 66-69,83-90 airborne radioactivity 66-69, 84-85 emergency 83-84.90 environmental 87-90 internal dose assessment 68-69 liquid effluent 86 solid waste 86-87 Negligible individual dose 4,9 Occupational dose records 55 ALARA 55 Occupational exposure 4,42 limit Occupational medicine 23 Off-site exposures 82-86 airborne effluents 84-85 INDEX / determining the need for monitoring 83 liquid effluents 86 sampling frequency 85 screening models 83 solid waste 86 techniques for control 82 Operating procedures 42 149 goals 18 incident investigations 21 personal monitoring 19 program audits 20 surveillance 19 surveys 19,20 Radiation emergencies 40,41, 108-113 classification of emergencies 110-111 Personal decontamination 29 Personal dosimetry 42,49 Personal monitoring 19,22, 49-51,56,62-65 bioassay 62-65 criticality accident 51 dose assessment 51 dosimeter devices 50 external radiation dosimetry 49 internal exposure controls 62 radiation surveys 51 Protective clothing 17,42,53,70 Protective equipment and devices 69-71 containment systems 69 internal exposure controls 70-71 protective clothing 70 respiratory protection 70 Public exposure 4,81-93 environmental monitoring 87, 88 limit solid waste 87 standards 81 Quality assurance 18-22,92-93 accident investigations 21 area surveys 19 audits 22 corrective actions 22 deficiency tracking 22 definition 18 environmental monitoring 92-93 emergency plan 108 practical considerations 111 restoration and recovery 111 training 40,41 Radiation Safety Committee (RSC) 13-16,18,22 Radiation safety manual 15-16 Radiation Safety Officer (RSO) 13,14,15,18,19,21,22,23 authority 14 qualification 14 responsibility 14 Radiation safety procedures 15, 16-17,48-49,60-61 Radiation surveys 17.51-52 documentation 52 nonroutine 52 routine 52 shielding 52 Radiation work permits (RWP) 43,48-49,60,61 Radiological accident 33 Records 54-55,71-72,79,93, 106-107 environmental monitoring 93 external exposures 54-55 instrumentation 106-107 internal exposures 71-72 waste 79 Records management 23 Respiratory protection 17,41, 56,67,70 Respiratory protective equipment 32.41 training 41 Responsibilities 17-19 management 18-19 150 / INDEX Radiation Safety Committee (RSC) 18 Radiation Safety Officer (RSO) 18-19 worker 17 Shielding 30-32,52 dose limit 30 facility design 30 materials 31 radiation surveys 52 Site selection 26-27 facility design 27 power reactors 27 radiation-producing equipment 27 radioactive material 27 waste processing facilities 27 Surveys 19,22 Training 22,38-41,75,112-113 design of a general training Program 39 general principles 38 gloved box 41 radiation emergencies 40-41, 112-113 respiratory protection equipment 41 specific training requirements 41 waste minimization 75 Ventilation 32-35 air cleaning devices 33 exhaust vents 33 facility design 32 radiological accident 33 Waste 73-79,86 classifying 76-77 collecting 76-77 disposal 78 minimizing 74-76 mixed wastes 73,75-76 records 79,86 recycling 79 storage 78 sorting 76-77 volume reduction 77 Waste management 22,29 Worker qualifications 17 ... include, NCRP Report No 71, Operational Radiation Safety- Training (NCRP, 1983a); NCRP Report No 88, Radiation Alarms and Access Control Systems (NCRP, 1986) ;NCRP Report No 105 ,Radiation Protection... 1991b); NCRP Report No 114, Maintaining Radiation Protection Records (NCRF', 1992); NCRP Report No 118, Radiation Protection i n the Mineral Extraction Industry (NCRP, 1993a); NCRP Report NO 120,... Preface NCRP Report No 59, Operational Radiation Safety Program, was published in 1978 That report provided the philosophy, basic principles and requirements for a radiation safety program In