Radiation safety training criteria for industrial radiography: Recommendations of the National Council on Radiation Protection and Measurements (NCRP report ; no. 61)

NCRP REPORT No. 61

RADIATION SAFETY TRAINING CRITERIA FOR INDUSTRIAL RADIOGRAPHY Recommendations of the NATIONAL COUNCIL O N RADIATION PROTECTION AND MEASUREMENTS

Issued November 1,1978 First Reprinting April 30,1993 Second Reprinting January 15,1995 National Council on Radiation Protection and Measurements 7 9 l O WOODMONT AVENUE / WASHINGTON, D.C Z0014

Copyright O National Council on Radiation Protection and Measurements 1978

All rights reserved.Thie 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. Library of Congresa Catalog Card Number 78-61401 International Standard Book Number 0-913392-45-6

Preface This report is intended as a guide for training persons in the safe use of sources of radiation for industrial radiography. Industrial radiography personnel require continuing effective training in radiation safety principles and procedures in order to maintain routine exposures at a low level and to reduce accidental overexposures. Three phases of training are delineated in the repork initial training,on-the-job training,and periodic training. An outline of topics to be considered under each of the training categories, as well as recommendations relevant to the parti& category are presented. The Council has noted the adoption, by the 15th General Conference of Weights and Measures, of special names for some units of the Systeme International &Unit& (SI) used in the field of ionizing radiation. The gray (symbol Gy) has been adopted as the special name for the SI unit of absorbed doseJ absorbed dose indexJ h a J and specifi energy imp-. The becquerel (symbol Bq) has been adopted as the special name for the SI unit of activity (of a radionuclide). The gray equal one joule per kilogram, and the becquerel is equal to the second to the power of minus one. Since the transition &om the special units currently employed-rad and curie--to the new special names is expected to take some time, the Council has determined to continue, for the time being, the use of rad and curie. To convert from one set of units to the other, the following relationships pertain: 1rad = 0.01 J kg-' = 0.01 Gy 1curie 3.7 x 10lOs-'= 3.7 x 101° Bq (exactly).

The present report was prepared by Scientific Committee 42 on Industrial Applications of X Rays and Sealed Sources. Serving on the Committee during the preparation of this report were: FRPINK'LPAS-

JR. chairmm

Membets

NCRP Secretariat

HARRY I). ~~N

T H O M A s C. -ON

ROBERT B. SOCKY PAULL Z m c m

The Council wishes to express its appreciation to the members of iii

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/ PREFACE the Committee for the time and effort devoted to the preparation of this report. WARRENK.SINCLAIR President, NCRP Bethesda, Maryland May 1, 1978

Contents Preface . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . 1 Scope and Purpose . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 Philosophy . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1 General Statement . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2 The Need for Training Criteria . . . . . . . . . . . . . . . . . . . . . . 3 Personnel . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.2 Selection of Radiography Personnel . . . . . . . . . . . . . . . . . . 3.3 Personnel Training . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . APPENDIX A Dose Uniting Recommendations . . . . . . . . . . APPENDIX B Standards and Regulations relating to the Licensing and Use of Industrial Radiography Facilities and Equipment . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . References Cited . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . General References on Radiation Protection in Industrial Radiography . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . The NCRP . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . NCRP Publications . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Index . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

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1. Scope and Purpose This report is concerned with the training of industrial radiographers and is devoted principally to those aspects of training that wiU provide the means to minimixe radiation exposure of human beings. The report is intended as a guide for training persons in the safe use of sources of radiation for industrial radiography. The report should be applied with sound judgment to formulate a training program that is responsive to particular needs. Important considerations that should be reviewed in formulating an appropriate and responsible training program include management practices, the equipment to be used,and applicable regulatory requirements. F'rovision should be made for continuing training in both a r e M e r and an updating fashion. Continuing education joined with increasing experience provides the proper foundation for optimizing worker performance with respect to both productivity and safety.

2. Philosophy 2.1

General Statement

Industrial radiography is an indispensable tool for non-destructive testing.Its use, however, entails potential radiation exposure to people. Since such radiation exposure has the potential to be harmful, there is a need to limit radiation doses to people to a level at which the risk is believed to be acceptable to the individual and to society. Results of studies on the somatic and genetic effects of radiation are reviewed in other NCRP reports (NCRP, 1971). These results have been utilized in developing recommendations for limiting doses to occupationally exposed persons and to members of the general population (NCRP, 1975). Appendix A summarizes these recommendations. These dose limits do not include any dose received by an individual patient as a result of medical practices or from natural background. The NCRP recommendations are centered on the principle that the "lowest practicable" radiation level is the fundamental basis for establishing radiation standards, with due consideration being given to the risks and benefits associated with a given radiation exposure (NCRP, 1971). To attain the "lowest practicable" radiation doses, radiation workers must be properly trained in the procedures, practices, and use of equipment that will minimize radiation exposures. This Report is directed toward specifying the training necessary for industrial radiographers in order to better accomplish the objective of attaining "lowest practicable" radiation doses.

2.2

The Need for Training Criteria

Radiographers have one of the poorest radiation safety records of any industrial radiation workers. In a study of industrial radiation accidents, Catlin (1969) found that for 152 serious radiation accidents studied, the greatest frequency of accidents by work activity occurred among industrial radiographers. Catlin found that 39 percent of the accidents studied involved industrial radiographers. Of these, 76 per2

2.2

NEED FOR TFWNING CRITERZA

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cent were due to operator or procedural errors, such as failure to make radiation surveys, and 15 percent were due to equipment failures. In a more detailed study of radiography overexposures, Scott and Gallaher (Scott and Gallaher, 1972) evaluated accidents and hlgh dose incidents for the period June 1963 through December 1971. They found operator errors and management e m r s to be primary contributors to most accidental high exposures. In the case of operator errors, the most frequent error (40 percent) was failure to perform a radiation survey. Another major operator error (19 percent frequency) was inadequate radiation surveys. Management errors identified were inadequate records, use of unqualified personnel, failure to calibrate instruments regularly, and inadequate training programs. Although the majority of overexposures to industrial radiographers involve whole-body overexposures, a number of serious injuries have been associated with a relatively s m d number of cases of high exposure of the hands (McGuire and Brooks, 1976; Saenger, 1977). Scott and Gallaher (1972) do not identify inadequate training itself as being a major direct cause of radiation accidents. They do point out, however, that the failure to survey, which is a major cause of overexposure, is due in part to an inadequate awareness of the consequences or effects of radiation. They point out the need for training programs that emphasize the biological effects of radiation, personal safety, and the safety of others. It is clear that improved training could lead to improvement in many of the categories that Scott and Gallaher identify as contributing to overexposures. In a more recent analysis of radiation overexposures1 reported to the Nuclear Regulatory Commission from 1971 to 1976 (McGuire and Brooks, 1976), 113 of 3% overexposures, or 35 percent, involved industrial radiography. Of 50 overexposures requiring prompt notification, 29 of these, or 58 percent, involved industrial radiography. Of 12 overexposyres requiring immediate notification 11, or 92 percent, were industrial radiography incidents. Of the 52 causes given for industrial radiography overexposures, at least 34, or 65 percent, were due to operator error. The root cause was deduced to be poor training. A study of 698 reported incidents in Texas from 1970 to 1976 showed that 51 of 236, or 22 percent, of the overexposures under 3 rem and 80

' A reportable overexposure is any exposure in excess of the pertinent regulatory limit; overexposures may be categorized according to reporting requirements, whlch are based on the degree of exposure, e.g.: 1. Timely (30-day) notification - any overexposure a whole-body dose of 5 rern or more 2. Prompt (24-hour)notification a whole-body dose of 25 rem or more 3. Immediate notification

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of 179, or 45 percent, of the overexposures over 3 rem involved industrial radiography (Bailey et aL, 1976). The authors of this study concluded that most of the incidents in industrial radiography resulted from improper use of s w e y instruments, failure to survey, or disregard for procedures. Factors contributing to the opportunity for unsafe operations in industrial radiography include: 1. Presence of high energy penetrating radiations; 2. Hgh e d v i t y , x-ray output, or source activity; 3. Pemmel p r e m c e outside of confined areas; 4. Malfunction of radiographic equipment; 5. Field operations in remote areas resulting in limited supervision; 6. Imperfect understanding or concern by management regarding radiation safew, 7. Limited formal education and inadequate training of industrial

radiographers. The first three of the factors cited above are mandatory in the performance of many tests that are required by industry. High energy is required for the radiation to be transmitted through the specimen being inspected because specimens are normally constructed of thick and dense materials such a s steel. High emissivity is required to attain economically acceptable exposure times. Some radiography sources must be portable to permit use in field locations, since the items to be radiographed are frequently located in distant facilities (e.g., ships, cross-country pipelines, aircraft, off-shore oil production platforms, nuclear power plants) and cannot be readily moved'into shielded areas. The last three factors cited are related to human actions. Study of radiation accidents in industrial radiography indicates that the great majority of overexposures or radiation injuries are directly traceable to operator failure rather than to equipment problems. Thus, the most effectiveway of reducing accidents would seem to be to train employees to adhere to established and well-documented procedures, to exercise common sense and sound judgment, and to use the protective equipment and devices provided in the manner specified. 2.2.1

Industrial Organization

(a) The organization of industrial radiation safety programs should parallel that of the general work safety programs. Requirements for such a program are discussed elsewhere (MF,1969; HRN,1969; NBS, 1970). Briefly mmmarhd, the overall responsibility for safety in its broadest sense rests with highest management. However, responsibility

2.2 NEED FOR TRAINING CRITERIA

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for safety permeates every level of both line and staff organizations; and the ultimate responsibility for safety, in its narrowest sense, rests with each individual worker. The manager of an organization has the responsibility to protect both employees and the general public from unnecessary exposures to radiation sources being used and, therefore, shouM2have available a person knowledgeable in the basic principles of protection against radiation and radioactive materials. The manager shall assure that adequate training in radiation safety is provided for employees at the beginning of employment and at regular intervals thereafter, as necessary for the individual's own protection and the protection of others. Such training may also be needed for ancillary personnel, such as laborers who assist the radiographer, shipping and receiving clerks, material handlers, and janitorial staff. (b) Each organization using radiography sources shall appoint a qualified individual as the Radiation Protection Supervisor (RPS). The RPS shall be responsible to management for establishing and maintaining the radiation safety policies designated by management. The RPS should be involved in all phases of the training program for radiographers to ensure appropriateness and effectiveness. Additional responsibilities of the Radiation Protection Supervisor (RPS) are specified elsewhere (NCRP, 1968). (c) Radiographers shall be responsible at the job site for the safe utilization of radiography sources and shall be adequately trained to accomplish this assignment. Radiographers should be supervised to the extent necessary to ensure adequate performance. In addition, the radiographer shall adhere to radiation protection requirements to the satisfaction of the RPS. (dl When a major contractor subcontracts for radiographic work, the contract between the firmsshould clearly delineate responsibilities for radiation safety. For example, the radiographer should have responsibility and authority for designating exclusion areas, to be honored by all other contractor personnel at the job site. 2.2.2

Instructors of Radiography Personnel

Individuals selected to provide instructions in radiation safety to radiography personnel should be competent in a pertinent area of Recommendations throughout this report are expressed in tenns of shall and should. Shall indicates a recommendation that is necessary to meet the currently accepted standards of radiation protection. Should indicates an advisory mommendation that is to be applied when practicable.

science or engineering, e.g., health physics. Instructors shall have experience in the operation, handling, or use of radiation sources commensurate with the type and complexity of work anticipated to be performed by the students. The instructors shall know the characteristics of the radiation sources and know the types of hazards involved with these sources, including the handling of malfunctions of high level sources. They shall be familiar with the maximum permissible doses (NCRP,1971) and the dose limits. They shull be knowledgeable in the methods for lninimizing personnel exposures. They shall know the necessary techniques for personnel monitoring, radiation surveying, and how to interpret the results. They shall know the rules of the regulatory agencies concerned with the radiographers' activities.

3. Personnel 3.1

Introduction

The discussion of Section 2.2 leads to the conclusion that radiography personnel require effective training in radiation safety principles and procedures. Furthermore, such training must be on a continuing basis using periodic retraining programs. In this way radiographers can refresh and renew their understanding of radiation safety, and reaffirm the necessity for observing the applicable precautions and for following established procedures. Another reason retraining programs are needed is the fact that the rules and regulations pertaining to radiation safety tend to constantly change, becoming more detailed and generally more complex as more knowledge is gained on radiation effects. A more pragmatic reason for retraining prognuns is to introduce advances in equipment, techniques, and procedures.

3.2

Selection of Radiography Personnel

Selection and training of radiographers require a commitment on the part of management not only to the training of radiographers, but also to the selection of managers and supervisors who will be responsive to the need for such training. Within organizations that use radiography, managers should have sufficient knowledge of radiation hazards to enable them to understand the necessity of radiation safety training programs. Managers shall require that the supervisors and radiographers diligently and specifically implement training policies and procedures that have management approval. Individuals who have been selected as supervisors of radiographers shall have thorough knowledge of all company policies and procedures pertinent to their responsibilities in radiation safety. An individual who is to seme as a Radiation Protection Supervisor (RPS) must have a thorough knowledge of: (1) management policies; (2) company administrative and operating procedures; and (3) safety procedures that are related to protection against radiation exposures. 7

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Radiographers should have a minixnum educational background of a high school diploma or its equivalent. Because of the need to make simple mathematical calculations, radiographers should have mathematical ability equivalent to competence in basic high school algebra. Management should recognize that a person who fails to develop safe working habits or who has a past record of substandard performance on any assignment. Such a person should not be trained as a radiographer. A radiographer's physical condition should be compatible with job requirements, such as, strength to handle moderately heavy equipment or ciimb ladders. In some cases a radiographer m a y need the stamina to work long hours under adverse environmental conditions, including extreme heat, cold, dust, mud, rain, rough terrain, etc.

3.3 Personnel Training While training is a continuing process, it is convenient to recognize three distinct phases of training: initial, on-the-job, and periodic. Each is described below. This division into these phases should not imply that there should be any relaxation of the requirement to adopt improved methods for controlling radiation exposure as they are developed. As field conditions change, the radiographer, supenisor, and RPS shall make the necessary adjustments to equipment, operating procedures, and safety procedures to accomplish the assigned tasks and to continue the protection from unnecessary radiation exposures.

3.3.1

Initial Training

Initial training is that training given to all prospective radiographers before they are assigned responsibilities as radiographers. The topi& that should be included in initial training are: I. FUNDAMENTALS OF RADLATION AND RADIATION PROTEC-

TION A. Structure of Matter 1. Elements, molecules, compounds 2. The atom a. Structure of the atom b. Isotopes and nuclides B. Radioactivity and Radiation 1. Natural (background)radiation and man-made radiation

3.3 PERSONNEL TRAINING

2. Nuclear reactions a. Nuclear fission (1)Chain reactions (2)Fissionproducts b. Activation of nuclides 3. Radioactive decay a. Types of decay b. Activity-the curie c. Fundamental decay law 4. Radiation producing devices a. X-ray production b. Neutron generators C. Nature and Consequences of Radiation Expome 1. Biological effects of radiation a. Types of effects (1) Somatic (2) Genetic b. RadiosensitiGty 2. Dose-effect relationships a. Classification of doses b. Effects of acute irradiation dose c. Chronic doses and late effects 3. Radiation quantities and units a. Exposure-roentgen b. Absorbed dose-rad c. Dose equivalent-rem d. Quality factor 4. Nature of radiation health problem a. External radiation b. Internal radiation contamination 5. Physical examinations a. Preoperational base-line data b. Exposure evaluations D. Radiation Hazard in Proper Perspective 1. Philosophy of radiation benefits and risks 2. Personnel exposures a. Background b. Man-made sources (1)Occupational exposure (2) Medical exposure 3. Radiation risk to radiographers 4. Maximum permissible doses for occupational workers a. Quarterly and annual dose limits b. Lifetime dose limits E. Control of Havvds from External Radiation Sources I. Time as a factor in radiation protection 2. Distance as a factor in radiation protection '

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3. Radiation attenuation and shielding a. Attenuation of alpha and beta particles and neutrons b. Attenuation of electromagnetic radiation attenuation (1) Linear attenuation coefficient (2) Hdf-value layers, tenth-value layers (3) Reduction factors F. Control of Hazards from Internal Radiation Sources 1. Control of contamination a. Modes of entry into the body: hgestion, Inhalation, Absorption b. Leak-testing of sources 2. Maximum permissible concentrations G. Measurement of Radiation 1. Basic concepts of radiation dosimetry a. Dose b. Dose rate 2. Personal monitoring devices a. Pocket dosimeters b. Badges: Film abd TLD 3. Survey meters a. Types (1) Ion chamber (2) Geiger counter (3) Solid state detectors b. Basic characteristics and lknitations 4. Instrument calibration 5. Radiography source standardization calculation a. Frequency of calibration b. Error analysis

II. FUNDAMENTALS OF RADIOGRAPHY A. Introduction to Radiography

1. The radiography process 2. Radiography applications 3. The radiograph

B. Elements of Radiography 1. Characteristics of radiation sources a. X-ray sources (1) Effects of voltage, current, and filtration on x-ray intensity b. Gamma-ray sources c. Neutron sources 2. Geometric principles 3. The specimen 4. Radiography film a. Film characteristic b. Chemical processing C. Radiography Techniques 1. Exposure calculations 2. Exposure arrangements

3.3 PERSONNEL TRAINING

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D. Interpretation of Radiographs 1. Concepts of interpretation 2. Metal discontinuities 3. Codes and specifications LICENSING AND REGULATION OF RADIOGRAPHY A. Requirements of Pertinent Federal and State Regulatory Agencies 1. Nuclear Regulatory Commission 2. Agreement states 3. Other bodies (e.g.. port authorities, cities, counties, etc.) B. X-Ray Machine Registration C. Radiography License for Using Radionuclide Sources 1. Requirements for a specific license to use by-product materials for radiography a. Conditions and control b. General considerations for protection against radiation c. Precautionary procedures and records required d. Qualifications and training of radiography personnel e. Organizational structure f. Operating procedures g. Internal inspection system h. Record systems D. Transportation of Radiography Sources 1. Federal and state regulations 2. International Atomic Energy Agency recommendations IV. RADIATION EMERGENCY PROCEDURES A. Types of Emergencies 1. Personnel overexposure 2. Equipment malfunctions 3. Lost sources 4. Exposures of non-radiography personnel B. Emergency Plans and Responses C. Reports and Follow-Up D. Case Histories

V. SUGGESTEDLABORATORYEXERCISES 1. Time and distance factors in radiation protection (inverse square law; time, distance, dose, and dose-rate relationships) 2. Radiography source calibration a. X ray b. Radionuclide 3. Survey meter calibration 4. Radiation attenuation 5. Radiation scattering 6. Radiography exposure techniques a. X ray b. Radionuclide 7. Leak testing sealed sources

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Approximately 80 hours of classroom and laboratory time shouM be devoted to initial training. No other duties shouZd be required of the trainee during this training so that time for study is available outside of the classroom. To become a radiographer, the trainee shall be required to demonstrate knowledge of the training material on a comprehensive written examination. Within the company files there shall be retained information on initial training examinations that includes: 1. The names of the individualswho took the examination, the date they took it, and grades scored on the examination. 2. The individual(s) responsible for administerbg the training course and

examination. 3. A COPY of the examination given (not necessarily the individual's test papers).

3.3.2

On-The-Job Training

In addition to completing "initial training," and before being given independent responsibilities, radiographers shall be given on-the-job training. In this phase of training, they shall be given instruction in the following topics, as they relate to radiography and radiation safety. A. Introduction-Purpose of On-The-Job Training B. Company Organization 1. Levels of authority 2. Degrees of responsibility C. Radiography Operating Procedures 1. Radiography equipment operating procedures 2. Safety equipment operating procedures D. Safetv Procedures 1. Radiography equipment 2: Personnel monitoring 3. S w e y procedures 4. Area layout and posting E. Emergency Procedures 1. Overexposures 2. Equipment malfunctions 3. Source damage 4. Lost sources F. Records Relating to Radiation Protection hogram 1. Personnel dose records 2. Receiving and shipping records 3. Quarterly inventory 4. Decay curves 5. Source utilization log

3.3 PERSONNEL TRAINING

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6. Leak test records 7. S o m e d q m d records 8. Survey meter calibrations 9. Area layout

The amount of time devoted to on-the-job training will be determined by the complexity of the company's programs and the learning rate of the radiographer. Special attention shall be given to emergency procedures. It is most important that the Radiation Protection Supervisor (RPS) and the supervisor observe the radiographer during this training phase. Responsibility for radiation protection shall not be given to radiographers until they have demonstrated that they can perform effectively and safely under actual field conditions. Examination of the radiography personnel to assure that the radiographer has sufficient knowledge of operating and safety procedures shall include a written or oral examination as well as direct observation of the radiographer under actual working conditions. "Retmhhg" shall be required where deficiencies are ascertained either from the examination results or from observation. Satisfactory completion of the onthe-job training and examination shall be documented. 3.3.3

Periodic Training

Periodic training shall be instituted either on a semi-annual basis or every time there is a substantive change in equipment, methods, procedures, regulations, or other factors affecting radiography. Training for radiographers should include the following pertinent topics: A. Introduction 1. Purpose--to review all conditions related to radiation protection B. Material to Review

3.

4. 5. 6. 7.

Company organization structure and responsibilities, including the responsibilities of the RPS Operating procedures Safety procedures a. Conventional safety programs b. Radiation safety programs Records Emergency procedures Internal inspection Transportation

The amount of time to be devoted to periodic training shall be related to the (1)new materials that have been added, (2) changes in older ~naterials,and (3) observation of the radiographer at work to

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determine whether deficiencies exist. The radiographer should pass an examination to assure that he continues to be competent to provide the required protection from radiation hazards. Examination of the radiography personnel shall include a written examination and observation of the radiographer in actual working situations by a qualified person who is not the regular supervisor. "Retraining" shall be required for any radiographer not performing adequately on the written examination or not performing acceptably during observation. Information on periodic training examinations shall be retained for each employee and this shall include: I. Names of the radiographers who took the examination, the date they took

it, and grades scored on the examination 2. Individual responsible for administering the examination 3. A copy of the examination (not necessarily the individual's test paper).

Dose-Limiting MAXIMUM PERMISSIBLE DOSE EQUIVALENT FOR OCCUPATIONAL EXPOSURE Uniform whole body occupational exposure Prospective annual limit Retrospective annual limit Long term accumulation to age N years skin Hands Forearms Other organs, tissues, and organ systems Pregnant women DOSE LIMITS FOR THE PUBLIC, OR OCCASIONALLY EXPOSED INDIVIDUAZS Individual or Occasional Students

5 rern in any one Year 1G15 rem in any one year (N-18) x 5 rem 15 rern in any one year 75 rem in any one year (25/qtr) 30 rern in any one year (lO/qtr) 15 rern in any one year (5/qtr) 0.5 rern in gestation period to the embryo-fetus. 0.5 rem in any one Year 0.1 rem in any one Y*

POPULATION DOSE LIMITS Genetic

0.17 rem average per Y* 0.17 rern average per Year

Somatic EMERGENCY DOSE LIMITS--LJFE SAVING Individual (older than 45 years if possible) Hands and Forearms EMERGENCY DOSE LIMITS-LESS Individual Hands and Forearms

100 rern 200 rern more (300 rem, tad)

URGENT

25 rern 100 rem, total

'Taken Erom NCRP Report No. 39, Basic Radiation Protection Criteria (NCRP, 1971) which should be consulted for detailed information on maximum permissible dose and dose limits. 15

APPENDIX B

Standards and Regulations Relating to the Licensing and Use of Industrial Radiography Facilities and Equipment American Institute of Chemical Engineers (1968). Classification of Sealed Radwactiw Sources, ANSI N5.10-1!W3 (American National Standards Institute, New York). American National Standards Institute (1973). Manual of Good Safety Practices for Industrial Gamma Radiography. Proposed ANSI Standard N536. (American National Standards Institute, New York). Flora, D. H.. Miller, L. A. and Steiner, B. H. (1970). An Evalrratwn of the Compatibility and Uniformity of State Regulations for the Control of Radiation, BRH OR0 70-7 (U.S. Department of Health, Education, and Welfare, Bureau of Radiological Health, Rockville, Maryland). ICRU (1970). International Commission on Radiation Units and Measuements, Specification of High Activity Gamma-Ray Sources, ICRU Report 18 (International Commission on Radiation Units and Measurements, Washington, D.C.). International Organization for Standardization (1977). "Appmtus for Gamma Radwgraphy-Specification,'' International Standard IS0 3999-1977 (El (International Organization for Standardization, Geneva, Switzerland). National Bureau of Standards (1975). General Safety Standard for Installations Using Non-Medical X-Ray an2 Sealed Gamma-Ray Sources, National Bureau of Standards Handbook 114 (American National Standards Inst. Standard ANSI-N543-1974, U.S. Government Printing Office, Washington, D.C.). National Health and Medical Research Council (1968). Code of Practice for the Control and Safe Handling of Sealed Radioactive Sources Used in Industrial Radiography, (National Health and Medical Research Council, Canberra,Australia). U.S. Atomic Energy Commission (1967). AEC Licensing Guide, Industrial Radiography, (U.S. Atomic Energy Commission, Washington. D.C.).

STANDARDS AND REGULATIONS

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U.S. Nuclear Regulatory Commission (1974). "General Safety Standard for installations Using Non-Medical Sealed Gamma-Ray Sources," Regulatory Guide 6.5 (NRC Division of Document Control, Washington, D.C.). U.S. Nuclear Regulatory Commission (1975). Code of Federal Regulations, "Rules of General Applicability to Licensing of Byproduct Material," Title 10, Part 30, Code of Federal Regulations (10CFR30) (Superintendent of Documents, U.S.Government Printing Office, Washbgbn, D.C.). U.S. Nuclear Regulatory Commission (1975). "Licenses for Radiography and Radiation Safety Requirementsfor Radiographic Operations,"Title 10,Part 34, Code of Federal Regulations (10CFR34) (Superintendent of Documents. U.S. Government Printing Office, Washington, D.C.).

References Cited AIF (1969). Atomic Industrial Forum, Inc., Guide for Administratiw Practices in Radiation Monitoring, ANSI N13.2-1969 (American National Standards Institute, New York). Bailey, E. D., Stephenson, L. J. and Hamiter, F. R. (1976). Incident Report to the Texas Radiatwn Advisory Board (Texas Department of Health Resources, Division of Occupational Health and Radiation Control, Radiation Control Branch, Austin, Texas). Catlin, R. J. (1969). "Radiation accident experiences: Causes and lessons learned," page 437 in Handling of Radiation Accidents, IAEG Publication STI/PUB/229 (International Atomic Energy Agency, Vienna). HRN (1969). Handbook of Radioactive Nuclides, Wang, Y., Ed. (The Chemical Rubber Co., Cleveland, Ohio). McGuire, S. A. and Brooks, B. (1976). Private communication (US. Nuclear Regulatory Commission, Washington, D.C.). NBS (1970). National Bureau of Standards,Radiological Safety in the Design wad Operation of Particle Accelerators, National Bureau of Standards Handbook 107 (U.S. Government hinting M c e , Washington, D.C.). NCRP (1968). National Council on Radiation Protection and Measurements, Medical X-Ray and Gamma-Ray Protection for Energies Up to 10 MeV-Equipment Design curd Use, NCRP Report No. 33 (National Council on Radiation Protection and Measurements, Washington, D.C.). NCRP (1971). National Council on Radiation Protection and Measurements, Basic Radiatwn Protection Criteria, NCRP Report No. 39 (National Council on Radiation Protection and Measurements, Washington, D.C.). . NCRP (1975). National Council on Radiation Protection and Measurements, Review of the Current State of Radiation Protectwn Philosophy, NCRP Report No. 43 (National Council on Radiation Protection and Measurements, Washington, D.C.). Saenger, E. L. (1977). Private communication (Radioisotope Laboratory, Cincinnati General Hospital, Cincinnati, Ohio.). Scott, R. L. and Gallaher, R B. (1972). Radiography Incidents and Overexposures, Report ORNL-NSIC-53 (Nuclear Safety Information Center, Oak Ridge National Laboratory, Oak Ridge, Tennessee).

General References on Radiation Protection in Industrial Radiography Boggs, R. and Moore, T. (1967). "Health and Safety Aspects of Industrial Radiography," Am. Soc. Safety Engineers J. 12, 14. Frazier, P. M., Buchanan, C. R. and Morgan, G. W. (1954).Radiation Safety Using Industrial Radioisotopes, AECU 2967 (Office of Technical Services, U.S. Department of Commerce, Washington). Picker Industrial Division (1965). Radiation Safety Using Industrial Radioisotopes, T55-310 (Picker Corporation, Cleveland, Ohio). Richardson, H. D. (1968a). Industrial Radiography Instructor's Guide, OE84034 (US. Government Printing Office, Washington). Richardson, H. D. (1968b). Industrial Radiography Student Guide and Laboratory Exercises, 03-84035 (US. Government Printing Office, Washington). Richardson, H. D. (1968~).Industrial Radiography Manual, 03-84036 (US. Government Printing Office, Washington). Rockley, J. C. (1964). An Introduction to Industrial Radiography. (Butterworth, London). Unruh, C. M. (1969).Industrial Radiography Utilizing Byproduct Material, A Manual of Good Practice, BNWL-SA-2640 (Pacific Northwest Laboratory, Richland, Washington).

The NCRP The National Council on Radiation Protection and Measurements is a nonprofit corporation chartered by Congress in 1964 to: 1. Collect, analyze, develop, and disseminate in the public interest information and recommendations about (a) protection against radiation and (b) radiation measurements, quantities, and units, particularly those concerned with radiation protection; 2. Provide a means by which organkations concerned with the scientific and related aspects of radiation protection and of radiation quantities, units, and measurements may cooperate for effective utilization of their combined resources, and to stimulate the work of such organizations; 3. Develop basic concepts about radiation quantities, units, and measurements, about the application of these concepts, and about radiation protection; 4. Cooperate with the International Commission on Radiological Protection, the International Commission on Radiation Units and Measurements, and other national and international organizations, govenunental and private, concerned with radiation quantities, units, and measurements and with radiation protection. The Council is the successor to the unincorporated association of scientists known as the National Committee on Radiation Protection and Measurements and was formed to carry on the work begun by the Committee. The Council is made up of the members and the participants who serve on the fifty-eight Scientific Committees of the Council. The Scientific Committees, composed of experts having detailed knowledge and competence in the particular area of the Committee's interest, draft proposed recommendations. These are then submitted to the full membership of the Council for careful review and approved before being published. The following comprise the current officers and membership of the Council: President Vice President

T H E NCRP

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Secretory and Troaswer Assistant Secretary Assistant Treasurer

Members SEYMOURABRAHAMSON S. JAMESADEUTEIN ROY E. ALBERT FRANKH. A m JOHNA. AUXIER WILLIAMJ. BAIR VICTORP. BOND HAROLDS. B o r n ROBERTL. BRENT A. BERTRANDBRILL R ~ m o m F. BROWN WILLIAMW. BURR,JR. MELVINW. CARTER GEORGEW. CASARETP RANDALLS. CASWELL ARTHURB. CHILTON STEPHENF. CLEARY CYRILL.COMAR PATRICIAW. DURBIN MERRILEISENBUD %OMAS S. ELY BENJAMING. FERRIS ASHER J. RNKEL DONALDC. FLECKENSTEIN RCHARD F. FOSTER HYMERL ~ W U L ARTHUR H. GUDSTEIN ROBERTA. GOEPP BARRYB. GOLDBERG MARVINGOLDMAN ROBERT0. G~RSON DOUGLASGRAHN ARTHURW. GW ELLIS M. HALL JOHNH. HARLEY JOHNW. HEALY LOUIS H. HEMPLEMANN, JR. JOHNM. HESLEP Honoray Members

h u r u s r o ~S. TAYLOR, Honorcuy President PAULC. HODGES E ~ r H.n QUIMBY EDGARC. BARNES GEORGEV. LEROY JOHN H. RUST CARLB. BRAESTRUP KARLZ. MORGAN WALTERS. SNYDER A u m M. BRUES SHIELDS WARREN RUSSELL H. MORGAN FREDEFUCKP. COWAN HERBERT M. PARKER HAROW 0.WYCKOFF ROBLEYD. EVANS

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THE NCRP

Currently, the following Scientific Committees are actively engaged in formulating recommendations: SC-I: SC-3: SC-11: SC-16: SC-18: SC-23: SC-24: SC-25: SC-26: SC-32: SC-33: SC-34: SC-37:

SC-38: SC-39: SC-40: SC-41: SC-42: SC-44: SC-45: SC-46: SC-45: SC-48: SC-50: SC-51: SC-52: SC-53: SC-54: SC-55: SC-56: SC-57 SC-58

Basic Radiation Protection Criteria Medical X- and Gamma-Ray Protection Up to 1OMeV (Equipment Desgn and Use) Incineration of Radioactive Waste X-Ray Protection in Dental Ofiices Standards and Measurements of Radioactivity for Radiologid Use Radiation Hazards Resulting from the Release of Radionuclides into the Environment Radionuclides and labeled Organic Compounds Incorporated in Genetic Material Radiation Protection in the Use of SmaU Neutron Generators High Energy X-Ray Dosimetry A w t e r e d Radioactivity Dose Calculations Maximum Permissible Concentrations for Occupational and N o n h p a tional Exposures Procedures for the Management of Contaminated Persons Waste Disposal Microwaves Biological AspectP of Radiation Protection Criteria Radiation bsulting from Nuclear Power Generation Industrial Applications of X Rays and Sealed Sources Radiation Associated with Medical Examinations Radiation Fteceived by Radiation Employees Operational Radiation Safety Instrumentation for the Determination of Dose Equivalent Apportionment of Radiation Exposure Surface Contamination Rahation Protection in Pediatric Radiology and Nuclear Medicine Applied to Children Conceptual Basis of Calculations of Dose Distributions Biolwcal Effects and Exposure Criteria for Radiofrequency Electromagnetic Radiation Bioassay for Assessment of Control of Intake of Radionuclides Experimental Verification of Internal h i m e t r y Calculations Mammography Internal Emitter Standards Radioactivity in Water

In recognition of its responsibility to facilitate and stimulate cooperation among organizations concerned with the scientific and related aspects of radiation protection and measurement, the Council has created a category of NCRP Collaborating Organizations. Organizations or groups of organizations that are national or international in scope and are concerned with scientific problems involving radiation quantities, units, measurements and effects, or radiation protection may be admitted to collaborating status by the Council. The present

THE NCRP

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Collaborating Organizations with which the NCRP maintains liaison are as follows: American Academy of Dermatology American Association of Physicists in Medicine American College of Radiology American Dental Association American Industrial Hygiene Association American Insurance Association American Medical Association American Nuclear Society American Occupational Medical Association American Podiatry Association American Public Health Association American Radium Society American Roentgen Ray Society American Society of Radiologic Technologists Association of University Radiologists Atomic Industrial Fonun College of American Pathologists Defense Civil Preparedness Agency Genetics Society of America Health Physics Society National Bureau of Standards National Hectrical Manufacturers Association Radiation Research Society Radiological Society of North America Society of Nuclear Medicine United States Air Force United States Army United States Department of Energy United States Environmental Protection Agency United States Navy United States Nuclear Regulatory Commission United States Public Health Service

The NCRP has found its relationships with these organizations to be extremely valuable to continued progress in its program. TO all of these organizations the Council expresses its profound appreciation for their support. Initial funds for publication of NCRP reports were provided by a grant from 'the James Picker Foundation and for this the Council wishes to express its deep appreciation. The NCRP seeks to promulgate information and recommendations based on leading scientificjudgment on matters of radiation protection and measurement and to foster cooperation among organizations concerned with these matters. These efforts are intended to serve the public interest and the Council welcomes comments and suggestions on its reports or activities from those interested in its work.

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THE NCRP

The Council's activities are made possible by the voluntary contribution of the time and effort of its members and participants and the generous suppolt of the following organizations: Alfred P. Sloan Foundation Alliance of Amen& Insurers American Academy of Dental Radiology American Academy of Dermatology American Association of Physicists in Medicine American College of Radiology American College of Radiology Foundation American Dental hsociition American Industrial Hygiene Association American Insurance Association American Medical h i a t i o n American Nuclear Society American Occupational Medical Association American Osteopathic College of Radiology American Podiatry Association American Public Health Association American Ramurn Society American Roentgen Ray Society American Society of Radiologic Technologists American Veterinary Medical Association American Veterinary Radiology Society Association of University Radiologists Atomic Lndustrial Forum BaUelle Memorial Institute College of American Pathologists Defense Civil Preparedness Agency Edward Mallinckrodt, Jr. Foundation Electric Power Research Institute Genetics Society of America Health Physics Society James Picker Foundation National &sociation of Photographic Manufacturers National Bureau of Standards National Electrical Manufacturers Association Radiation Research Society Radiological Society of North America Society of Nuclear Medicine United States Department of Energy United States Environmental Protection Agency United States Navy United States Nuclear Regulatory Commission United States Public Health Service

NCRP Publications NCRP publications are distributed by the NCRP Publications OiEce. Idonnation on prices and how to order may be obtained by d m c t h g an inquiry to:

NCRP Publications 7910 Woodmont Avenue Suite 800 Bethesda, MD 20814-3095 The currently available publications are listed below. NCRP Reports No.

Title Control and Removal of Radioactive Contamination in hboratories (1951) Mazimum Pennksible Body Burdens and Maximum Permissible Concenkcrtions of Radionuclides in Air and in (1959)[Includes AddenWaterfor O c c u ~ n c ri?hposure l d u m 1 issued in August 19631 Measurement of N e m n Flus and Spectra for Physical and Biological Applications (1960) Measurement ofAbsorbedDose ofNeutmns, and ofMixt2lm.s of Nerctrons and Gamma Rays (1961) Stopping Powers for Use with Cavity Chambers (1961) Safe Handling of Radia&ve Materids (1964) Radiation Protection in Educati~nalInstituti~ns(1966) Dentcrl X-Ray Pmtection (1970) Radiation Protection in Veterinary Medicine (1970) Precautions i n the Management o f Patients Who Have Received Thempeufic Amounts of R&nuclides (1970) Protection Against Nerrtron Radktbn (1971)

41

Specificadion of Gamma-Ray Bmchythempy So(1974) Radiological Factors Affecting Decision-Making i n a Nrrclew Attack (1974) Krypton-85 in the A t m o s p h e r e - A c c u m ~ n lBiologrml Signif;cancel and Control Technology (1975)

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NCRP PUBLICATIONS

Alpha-Emitting Particles in Lungs (1975) Tritium Measurement Techniques (1976) Structuml ShieldingDesign and Evalzmhn for Medical Use of X Rays and Gamma Rays of E m g i e s Up to 10 MeV (1976) Environmental Radiation Measwvments (1976) Radiation ~&tecttonDesign Guiclelines for 0.1-100 MeV Particle Accekmtor Facilities (1977) Cesium-137from theEnvironment to Man: MMetcrbolism and Dose (1977) Medial Radiation Exposum of Pregrurnt and Potentidly Pregnant Women (1977) Protection of the Thyroid Gland in the Event of Releases of Radioiadine (1977) Instrumentation and Monitoring Methuds for Radiution Protection (1978) A Handbook of Radioactivity Measurements Procedures, 2nd ed. (1985) Operationul Radiation Safzty Pmgmm (1978) Physical, Chemiwl, and Bwlogrccrl Properties of Rcrdiocerium Relevant to Radiation Protection Guidelines (1978) Radiation Safety Training Criteria for Industrid Racliogmphy (1978) Tritium in the Environment (1979) Tritium and Other Radionuclide Labeled Organic Compounds Imrpomted in Genetic Materid (1979) Influence of Dose and Its Distribution in Time on DoseResponse Relutbmhips for Low-LET Radiations (1980) Management of Persons Accidentally Contaminated with Radiomlides (1980) Radiofrequency Electromagnetic Fields-Pro,~erties, Quantities and Units, Biophysical Interaction, and Measwements (1981) Radiation Pmtection in P e M Radiblogy (1981) Dosimetry ofX-Ray and Gamrmz-RayBeam for Radiation Thempy in the Energy Range 10 keV to 50 MeV (1981) Nuclear Medicine-Factom Infhncing the Choice and Use of Radionuclides in Diagnosis and Thaupy (1982) Opemtiunal Radiation Safety--Tminirrg (1983) Radiation Protection and Measurement for Low-Voltage Neutron Generators (1983) Protection in Nuclear Medicine and Ultrasound Dicrgrwstic Procedwes in Children (1983)

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Biological Effects of Ultmsound: Mechanisms and Clinical Implications (1983) Iodine-129: Evaluation of Releases from Nuclear Power Generaabn (1983) Radiolo@ Assessment: Predicting the T m p o r t , Bioaccumulation, and Uptake by Man of Radionuclides Relecrsed to the Environment (1984) Exposures from the Uranium Series with Emphasis on Radon and Its Daughters (1984) Evaluation of Occupational and Envitonmental Exposures toRadon and RadonDaughters in the United States (1984) Neutron Contamination from Medical Etectron Accelemtors (1984) Induction of Thyroid Cancer by Ionizing Rcrdiafion (1985) Carbon-14 in the Environment (1985) SZ Units in Radicrtion h t e c t i o n and Measurements (1985) The Experimental Basis fir Absorbed-Dose C-ns in M e d i d Uses of Radionuelides (1985) General Concepts fir the Dosimetry of Internally Deposited Radionuclides (1985) Mammgmphy-A User's Guide (1986) Biol0gzea.l Effects and Exposure Criteriu for Radio/kquency Electromagnetic Fieids (1986) Use of Bioassay Procedures fir Assessment of Znternal Radionuclide Deposition (1987) Radiutbn A l u m and Access Control Systems (1986) Genetic Effects from internally Deposited Radionuclides (1987) Neptunium: R a d s n Protection Guidelines (1988) Public Radiation Expsm from N u c k r Power Germation in the United States (1987) Ionizing Radiation Exposure of the Population of the United States (1987) Exposure of the Populdion in the United Sand C a d from Natwal Background Radiation (1987) R a d i d o n Exposure of the U S . Pop-n from Consumer Products and MisoeUaneolrs Sources (1987) Comparative Carcinogenicity of Ionizing Radiation and Chemicals (1989) Measurement of Radon and Radon Daughters in Air (1988) Guidunce on Radiaabn Received in Space Actwides (1989) Qlraliiy Assumnce for Diagmstic Imaging (1988) Exposure of the U S . Poplllation from Diagnostic Medid Radiation (1989)

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NCRP PUBLICATIONS

Exposure of the U S . Population from Occupational Radiation (1989) Medical X-Ray, Electmn Beam and Gantmu-RayPtbtWion for Energies Up to 50 MeV (Equipment Design, Performance curd Use) (1989) Control of Radon in Houses (1989) TheRelutiue Bwb& Effectiveness of Radiations ofDifirent Quality (1990) Radiation Protection for Medical and Allied Health Personnel (1989) Limit for Exposwe to W o t Parti&sn on the Skin (1989) I m p l e m e m n of the Principle of As Low As R e a s o d l y Achievable (ALMA) for Medial and Dental Personnel (1990) Conceptual Basis for Calculations o f Absorbed-Dose DistributiQns (1991) Effects of Ionizing Radiution on Aqucctic Orgcurisms (1991) Som Aspects of Strontium Radiobiology (1991) Developing Radiation EmergencyPlans f o r d c a d . , Medical or Industrial Facilities (1991) Cdibmfion ofSu~eylnstmrnentsUsed inRadiation Pmtection for tk Assessment of Ionizing Radiation Fie& and Radioactive Surface Co&zmination (1991) Exposcrre Criteriafor MeDiqmstic Ultmsowrd.I. Criteria Based on T h e d Meclumisms (1992) Maintaining Radiation Pmtection Recotds (1992) Risk Estimates for Radiation Protection (1993) Li-n of E-sure Ionizing Rad&.tion (1993) Research Needs for Radiation Pivtxtion (1993) Radiation Protection i n the Mineral Extraction Industry (1993) A PnrcticalGuide to the Determination of Human Eqwsure to R a d i o ~ u e & Fie& (1993) Binders for NCRP reports are available. Two sizesmake it possible to collect into small binders the "oldseries" ofreporb(NCRP Reports Nos. 830) and into largebindersthe more recentpublications(NCRP Reports Nos. 32-119). Each binder will accommodate from five to seven reports. The binders carry the identification WCRP 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. Volume II.

NCRP Reports Nos. 8,22 NCRP Reports Nos. 23,25,27,30

NCRP PUBLTCATIONS

Volume ID. Volume n7. Volume V. Volume VI. Volume VII. Volume Vm. Volume M. Volume X. Volume XI. Volume XTI. Volume Xm. Volume XIV. Volume XV. Volume XVI. Volume XVLI. Volume XVIII. Volume XM. Volume XX. Volume XXL Volume XXII. Volume XXIII.

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NCRP Reports Nos. 32,35,36,37 NCRP Reports Nos. 38,40,41 NCRP Reports Nos. 42,44,46 NCRP Reports Nos. 47,49,50,51 NCRP Reports Nos. 52,53,54,55, 57 NCRP Report No. 58 NCRP Reports Nos. 59,60,61,62, 63 NCRP Reports Nos. 64,65,66,67 NCRP Reports Nos. 68,69,70,71, 72 NCRP Reports Nos. 73,74, 75,76 NCRP Reports Nos. 77,78,79,80 NCRP Reports Nos. 81,82,83,84,85 NCRP Reports Nos. 86,87,88,89 NCRP Reports Nos. 90,91,92,93 NCRP Reports Nos. 94,95,96,97 NCRP Reports Nos. 98,99,100 NCRP Reports Nos. 101, 102,103, 104 NCRP Reports Nos. 105,106,107,108 NCRP Reports Nos. 109, 110,111 NCRP Reports Nos. 112,113,114 NCRP Reports Nos. 115, 116,117,118

(Titles of the individual reports contained in each volume are given above.)

No. 1 2

3

4

5 6

NCRP Commentaries Title Krypton-85 in the Atmosphere-With Specific Reference to tkPublic Health Signihnce of the Proposed Controlled Release at T h Mile Ishnd (1980) Pndiminary Evaluation of Critericrfor the Disposal of T m wanic Contaminated Waste (1982) Screening Techniques for Determining Compliance with Enuimnmentcrl Standurds-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 Signiiicmce of the Pmposed Relecrse of Trsated Waste Waters at Three Mile Island (1987) Review of the Publiwtion, Living Without Landfills (1989) Radon Exposure of the U.S.Population-Status o f the Problem (1991)

Misadministnation of Radimctiw Material in MedicineScientificBackground (1991) Uncedinty in NCRP Scteening Models R e l . to A t m spheric Transport, Deposition and Uptuke by Humans (1993)

Proceedings of the Annual Meeting No. 1

Title

Perceptions of Risk, Proceedings of the Fifteenth Annual Meeting held on March 1415, 1979 (including Taylor Lecture No. 3) (1980) CTiticcrl Issues in Settrettrng Radiation Dose Limits,b c e d ings of the Seventeenth Annual Meeting held on April 89, 1981 (including Taylor Lecture No. 5 ) (1982) Radiation Protection and New Medical Diagnostic Approaches, Proceedingsof the Eighteenth Annual Meeting held on April 6 7 , 1982 (including Taylor Ledure No. 6 ) (1983) Environmental Radioactivity, Proceedings of the Nineteenth Annual Meeting held on April 67,1983 (including Taylor Lecture No. 7) (1983) Some Issues Impomrat in Developing Basic Radiation Protection RecomndQtions, Proceedings of the Twentieth Annual Meeting held on April 4-5,1984 (includingTaylor Lecture No. 8) (1985) Radioactive Waste,Pmmdmgs of the Twenty-first Annual Meeting held on April 3-4,1985 (includingTaylor Ledure No. 9 ) (1986) Nonionizing E l s c t m Radiatiom ~ and Uttms~und, Fkmdhgs of the Twenty-second Annual Meeting held on April 2-3, 1986 (including Taylor Lecture No. 10) (1988) New Dosimetry at Himhima and Nagasaki andIts Implicationsfor Risk Esa'matzs, h c e e d b p of the Twenty-thkd Annual Meeting held on April &9,1987 (including Taylor Lecture No. 11)(1988) Radon, Pmmdmgs of the Twenty-fourth Annual Meeting held on March 30-31,1988 (including Taylor Lecture No. 12) (1989) RadiationPmtection Toaky-TheNCRP atsixty Years,Proceedings of the Twenty-mh Annual Meeting held on April 5-6, 1989 (includmg Taylor Lecture No. 13) (1990)

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Health and Ecological Impliedions of Radiocrcfively Contaminated Environments, Proceedings of the Twentysixth Annual Meeting held on April 45,1990 (including Taylor Lecture No. 14) (1991) Genes, Cancer and Radi&tion Protedion, Proceedings of the Twenty-seventh Annual Meeting held on April 3-4,1991 (including Taylor Lecture No. 15) (1992) Radiation Protection in Medicine, Pmxe&gs of the Twentyeighth Annual Meeting held on April 1-2,1992 (including Taylor Lecture No.16) (1993)

No. 1

Lauriston S. Taylor Lectmes Title TheSquares oftheNcrtuml Numbers inRadiation Pmtection by Herbert M.Parker (1977) Why be Quantitative about Radiation Risk Estimates? by Sir Edward Pochin (1978) Radiahon ~ 4 o n c e p t and s Trade Off5! by Hymer L F'riedell(1979) [Available also in Perceptions of Risk, see above] From "QuantityofRadiation"0Uzd "Dose" tb ?Exposure" and "Absorbed Dose"-An Historical Review b y Harold 0. Wyckoff (1980) How Well Can We Assess Genetic Risk? Not Very by James F. Crow (1981)[Available also in Criticd Issues in Settiag Radziztion Dose Limits, see above] Ethics, Trade-offs and Medical Radiation by Eugene L. Saenger (1982) [Available also in Radiation Protection and New M e W Diagnostic Approaches, see above] The Human Environment-Past, Present and Future b y Meml Eisenbud (1983) [Available also in E l u t i m n d R a d b c t i d y , see above] Limitation and Assessment in Radiation Protection by Harald H. Rossi (1984) [Available also in Some Issttes Important in Developing Basic Radiation Pmtection Recommendations, see above] Truth (and Beauty) in Radidon Measurement by John H. Harley (1985) [Available also in R a d h d v e Waste, see above] Biological Effects o f Non-ionizing Radiations: Cellular Properties and I&mctbns by Hennan P. Schwan (1987) [Available also in Nonionizing Electromagnettc Radiations and Vltmsound, see above]

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NCRP PUBLICATIONS

How to be Quantitative abollt Rudidzbn Risk Estimates by Seymour Jablon (1988) [Available also in New Dosimetry at Hiroshima and Nagasaki and its Implicatisns for Risk Estimates, see above] How SMe is Safe Enough? by Bo Lindell(1988) [Available also in Radon, see above] Radiobiology and Radiation Protection: The Past Century and Prospects for the Future by Arthur C. Upton (1989) [Available also in Radiation Protection Toduy,see abovel Radiation Protection and the Internal Emitter Saga by 3. Newel1 StaMard (1990) [Available also in Health and Ecological Implications of Radiwctiwly Contami~ted Environmnts, see abovel When is a Dose Not aDose? by Victor P. Bond (1992) [Available also in Genes, Cancer and R4di4tion Protection, see abovel Dose and Risk in Dkgmstx Radiology: How Big? How Little? by Edward W. Webster (1992)tAvailablealso in Radicrtion Protection in Medicine, see abovel Science, Radialion Protection and the NCRP by Warren K. Sinclair (1993)

S p p o h Proceedings The Control of Exposum of thePublic to Ionizing Radiation in the Event of AccidentorAttuck,Ikcehgs of a S - p sium held April 27-29, 1981 (1982)

NCRP Statements No. 1

Title "Blood Counts, Statement of the National Committee on Radiation Protection," Radiology 63,428 (1954) "Statements on IKaximum Permissible Dose h m Television Receivers and Mnnimum 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-RayPrvtection Standwds for Home Television Receivers, Interim Statement of the NafiohcJ Couccil on Radiation Protection and Mecrsurements (1968) Speciftation of UnitsofNatuml Umniumand Ntrucrl Thorium, Statement of the National Council on Rcrdiation Protection and Measwements, (1973)

NCRP PUBLICATIONS

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NCRP Statement on Dose Limit for Neutrons (1980) Control of Air Emissions of Radionuclides (1984) The Probability That a Particuhu Malignunq May Have Been Caused by a Specified Irradiation (1992)

Other Docaments The following documents of the NCRP were published outside of the NCRP Report, Commentary and Statement series: Somatic Radiaabn Dose for the Geneml Populution, Report of the Ad Hoc Committee of the National Council on Radiation F'rotection and Measurements, 6May 1959,Science, February 19,1960,Vol. 131,No. 3399, pages 482-486 Dose Effect Modifying Factors I n Radiation Protection, Report of Subcommittee M 4 (Relative Biological Effectiveness) of the National Council on Radiation Protection and Measurements, Report BNL 50073 Cl'471)(1967) Brookhaven National Laboratory (National Technical Information Service Sp@eld, Virginia) The following documents are now superseded andlor out of print:

NCRP Reports No.

Title X-Ray Pm&hbn (1931)[ S p m d e d by NCRP Report NO. 31 Radium PIbtedion (1934)[Supemeded by NCRP Repart No. 41 X-Ray Prdedion (1936)[Supemdedby NCRP Report No. 61 Radiwn Protection (1938)[!hpmded by NCRP Repat NO.131 Safe Handing of Radiouctive Luminous Compound (1941) [Out of Print] Mediccrl 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 Recommendationsfor WasteDisposal ofPhphorus32 and Iodine-131 for Medical Users (1951)[Out of Printl Radiological Monitoring Methm2.s and Instruments (1952) [Superseded by NCRP Report No. 571 Maximum Permissible Amounts of Radioisotopes in the Human Body and Mazimum Permissible Concentmtbns in Air and Wafer (1953)[Superseded by NCRP Report No. 221 Recommendations for the Disposal of Carbon-14 Wastes (1953)[Supmded by NCRP Report No. 811

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NCRP PUBLICATIONS

Protection Against Radiati~nsWrn Radium,Cobait-60and Cesium-137 (1954)[Superseded by NCRP Report No. 241 Pfotmtion Against Betatron-Synchrotron Radiations Up to 100 Million Eledron Volts (1954)[Superseded by NCRP Report No. 511 Safe Handing of Cadizwrs Containing Radioactive Isotopes (1953)[Superseded by NCRP Report No. 211 Radioactive-Waste Disposal i n the Ocean (1954)[Out of Print] Permissible Dose fmm External Sources of Ionizing Radiation (1954)i n c l u w Maximum Permissible E x p o s u ~ t sa Man, Addendum to Nationcrl Bursau of Standards Handb k 59 (1958)[Superseded by NCRP Report No. 391 X-Ray M n (1955)[Supemded by NCRP Report No. 261 Regulation of R adiation Exposure by Legislative Means (1955)[Out of Print] Protection Against Neutron Radiation Up to30 MiUion E k trvn Volts (1957)[Supersededby NCRP Report No.381 Safe Handling of Bodies Containing Radbactiw Isotopes (1958)[Superseded by NCRP Report No. 373 Protection Against Radiations Nrn Sealed Gamma Sources (1960)[Suprseded by NCRP Reports No. 33,34 and 401 Medical X-Ray Protection U p to Three Million Volts (1961) lSuperseded by NCRP Reports No. 33,34,35 and 361 A M a n d of Radioactivity P m h (1961)[Superseded by NCRP Report No. 581 Exposure to Rcrditrtion in an Emqgency (1962)[Superseded by NCRP Report No. 421 Shielding for High-Energy Electron Accelerator Imtullatiom (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 Gammu-RayPmtedion f0rEnergi.e~U p to 10 MeV--Stmctuml ShieZding Des* and Ev&luation Handbook (1970)[Supersededby NCRP Report No. 491 Bask Radiation Protection C e r i a (1971)[Superseded by NCRP Report No. 911 Review ofthe Current State of R a d i d o n Pmtection Philasophy (1975)[Superseded by NCRP Report No. 911 Natwcrl BacKgn,und Raaktibn in the Un&d States (1975) [Superseded by NCRP Report No. 9-41 Radiation Protection for Medioal and Allied Health Personnel (1976)[Superseded by NCRP Report No. 1051

NCRPPUBLICATIONS

53

56 58 66 91

No. 2

1

35

Review ofNCRP Rocliation DoseLimit forEmblyo and Fetus in Occ-dZy-Exposed Women (1977) [Outof Print] Ra&&bn-firn C o n s w m r Md ~ MiscelIrmeous So(1977) [Slzperseded by NCRP Report No. 951 A Handbook of Radioactivity Measurements Procedures, 1st ed. (1978) [Superseded by NCRP Report No. 58, 2nd ed.1 Mamnwgmphy (1980) [Out of Print] Recoon L i d f6TExpsm toIonizing Rudiuth (1987) [Supersededby NCRP Report No. 1161

Title Quuntitdve Risk in S t a m Settiag, Proceedings of the

kcteenth Annual Meeting held on April 23,1980 [Out of Print]

Index Dose limits, i. 15 emergency. 15 individual. 15 population, 15

radiation surveying. 6 superviuors. 7 qualifications, 7 responsibilities. 5 selecting, 7

Emergency procedures, 13 Examinations, 13 Initial Training, 14 On the job training, 14 Periodic training. 14 Exposures to radiation, 6 methods to control, 6

P e r s o ~ emonitoring, l 6 Procedures, 7 administrative, 7 management, 7 operating, 7 l=.gulatory. 7 safety, 7

industrial organization. 4.5

Radiation accidenq 2,3.4 em& 2 equipment failure, 2 management, 2 operator, 2 e.posures, 2 factors contributing, 3 safety, 2 Radiation s w e y s , 6 Regulations and regulatory agencies, 6,17 licensing, 17 radiographer's activities, 6

line organization,5 management, 4 staff organization. 5 responsibility. 5 protection h m radiation, 5 protection from radioactive material. 5 worker's responsibility, 5 Instructors, 5 qualilications, 6 academic, 5 experience, 6 personnel, 5,7,8, 13 managers, 7 qualifications, 7 responsibiities, 7 radiation protection supervisors, 7 examinations, 13 qualifications. 7 responsibilities, 5 training involvement. 5 radiographers, 5, 7 qualifications, 7 academic. 8 physical, 8 responsibility,5

Standards,listed, 17 'Raining criteria, need for, 2 contributing factors, 4 equipment failures. 2 management errors, 2 m h b k e exposure, 1 operator errors, 2 personnel safety, 3 procedural e m , 2 radiation accidents. 2 radiography overexpomms, 2 . 3 whole body, 3 hand, 3 radiation surveys, failure, 2 safety of others, 3

supervised,5 training, 7 workmg conditions, 8

37

Training in radiation safety,1,s. 6, 12-14 examinatians. 12, 14 oral, 13 practical, 13 Written. 12.13, 14 malfunctions, 6 minimize radiation nposure. 1 phases of training . initial.8.9.10, 11, 12 on the job, 8,12, 13

periodic, 8, IS, 14 persunnel, 5 ancillary. 5 radiographers, 5 pmtection. 5 individuals, 5 radiographers. 5 responsibilities, 5 time, IS