NCRP report no 120 dose control at nuclear power plants

NCRP REPORT No 120 DOSE CONTROL AT NUCLEAR POWER PLANTS Recommendations of the NATIONAL COUNCIL O N RADIATION PROTECTION AND MEASUREMENTS Issued December 30, 1994 National Council on Radiation Protection and Measurements 7910 Woodmont Avenue / Bethesda, Maryland 20814-3095 LEGAI 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 &ay not infringe on privately owned rights; or (b) assumes any liability with respect to the use of, or for damages resulting from the use of any information, method or process disclosed in this Report, under the Civil Rights Act of 1964 Section 701 et seq as amended 42 U.S.C Section 2000e et seq (Title VII) or any other statutory or common law theory governing liability Library of Congress Cataloging-in-Publication Data National Council on Radiation Protection and Measurements Dose control at nuclear power plants recommendations of the National Council on Radiation Protection and Measurements p m.-(NCRP report ; no 120) "Issued December 1994." Includes bibliographical references and index ISBN 0-929600-39-8 Nuclear power plants-Safety measures Nuclear power plantsHealth aspects Radiation dosimetry Ionizing radiation-Safety measures Industrialsafety I Title 11 Series TK9152.N37 1994 621.48'35 dc20 94-40857 CIP Copyright National Council on Radiation Protection and Measurements 1994 All rights reserved This publication is protected by copyright No part of this publication may be reproduced in any form or by any means, including photocopying, or utilized by any information storage and retrieval system without written permission from the copyright owner, except for brief quotation in critical articles or reviews Contents Preface Introduction 1.1 Scope 1.2 Background 1.3 The ALARA Principle 1.4 Range of Applicability 1.5 Qualitative Aspects of ALARA 1.6 Quantitative Aspects of ALARA 1.7 Implementation Nuclear Power Dose Experience 2.1 Status of Nuclear Power Generation 2.2 Exposures in the United States 2.3 Goals for 1990 and 1995 2.4 Comparisons with Other Countries Quantitative Methods in Optimization 3.1 Introduction 3.2 Conceptual Approach 3.3 Valuation of Marginal Value of Dose Avoided 3.3.1 Valuations Based on Surveys and Past Practices 3.3.2 Impact of Required Crew Changes 3.3.3 Impact of Replacement Power Costs 3.3.4 Job-Specific Marginal Values of Dose Reduction : 3.4 Eqaluation of Options 3.4.1 Preliminary Screening of Options 3.4.2 Aggregating Present and Future Costs and Benefits 3.4.3 Present-Value Calculation 3.5 Comparison of Options 3.6 Sensitivity Analyses Management, Policy and Administration for an ALARA Program 4.1 Organization 4.2 Management Direction vi CONTENTS Corporate Policy Radiation Protection Manual Procedures Responsibilities Goals and Objectives 4.3 Training 4.3.1 Radiation Protection Technicians and Supervisors 4.3.2 Station Employees 4.3.3 Engineers 4.3.4 Managers and Supervisors 4.3.5 Examinations 4.3.6 Continuing Training 4.4 Monitoring Program Performance 4.4.1 Quantitative Indicators 4.4.2 Performance Monitoring 4.5 Assessment Dose Control Principles in Reactor D e s i m and Modification 5.1 Introduction 5.2 ALARA Principle in the Design Process 5.3 Design Dose Objectives 5.4 Design Responsibilities and Organizational Structure for Implementing the Dose Control Principles 5.5 Radiation Dose-Reduction Technology 5.5.1 Source Reduction Design Factors 5.5.1.1 Cobalt Source Reduction 5.5.1.2 System Chemistry and Metallurgy 5.5.1.3 System Decontamination 5.5.1.4 Fuel Integrity 5.5.2 System Integrity and Contamination 5.5.3 Time, Distance and Shielding 5.5.3.1 Plant and Equipment Reliability 5.5.3.2 Ease of Maintenance, Operation, Inspection and Access 5.5.4 System Layout 5.5.5 Remote Operation 5.5.6 Robotics 5.5.7 Shielding Operational Considerations 6.1 Introduction 6.2 Radioactive Source Reduction 4.2.1 4.2.2 4.2.3 4.2.4 4.2.5 CONTENTS Optimum pH Exclusion of Extraneous Materials Cobalt Reduction Hydrogen Water Chemistry and Zinc Injection in Boiling Water Reactors 6.2.5 Hot Drain-Off of Feedwater Systems and Condensers Following Shutdown and Prior to Start-Up in Boiling Water Reactors 6.2.6 Ultra-Fine Filters for Letdown System 6.2.7 Oxygen Injection into Boiling Water Reactor Feedwater 6.2.8 Iron Controls in Boiling Water Reactors 6.3 Contamination Control 6.3.1 Proper Maintenance and Operations 6.3.2 Optimization of Plant Contamination Control 6.3.3 Protective Clothing andfor Respirator Optimization 6.3.4 Decontamination of Work Areas 6.3.5 Use of Tents Containment Bags and Glove Boxes 6.3.6 Use of Local Ventilation 6.3.7 Boiling Water Reactor Controlled Shutdowns 6.3.8 Pressurized Water Reactor Shutdown Chemistry 6.3.9 Decontamination of Primary System and Components 6.3.10 Fuel Cladding Integrity 6.4 External Exposure Control 6.4.1 External Exposure Control During Job Setup 6.4.1.1 Radiation Work Permit 6.4.1.2 Decontamination of Components 6.4.1.3 AleridAlarm Systems 6.4.1.4 Posting 6.4.1.5 Radiation and Airborne Radioactivity Monitoring 6.4.1.6 Temporary Shielding 6.4.1.7 Pre-Job Briefing 6.42 External Exposure Control During Work Activities 6.4.2.1 Job Supervisor 6.4.2.2 Radiation Protection Technician Coverage 6.2.1 6.2.2 6.2.3 6.2.4 viil / CONTENTS 6.4.2.3 Auxiliary Operators Routine Activities 92 Radiation Workers 92 Special Tooling and Robotics 93 Communications 93 Dose Tracking 93 6.4.3 Post-Job Activities 94 6.4.3.1 Dose Accounting 94 6.4.3.2 Post-Job Reviews 94 6.4.3.3 Documentation 94 6.4.3.4 ALARA Reports 94 6.5 Planning 95 6.5.1 General 95 6.5.2 Task Planning 95 6.5.2.1 Defining the Job Scope 96 6.5.2.2 Photos Video Tape and Video Mapping 96 6.5.2.3 Radiological Surveys 96 6.5.2.4 Pre-Job Inspections Dry Runs 97 6.5.2.5 Dose Estimates 97 6.5.3 Outage Coordination 97 6.5.3.1 Radiological Support Personnel 98 6.5.3.2 Schedule Considerations 98 6.5.3.3 Coordination of Outage Tasks 98 Appendix A Pre-Job ALARA Briefing 100 Appendix B Pre-Job ALARA Checklist 101 Appendix C ALARA Reviews-Graded Approach 103 References 104 The NCRP 115 NCRP Publications 123 Index 134 6.4.2.4 6.4.2.5 6.4.2.6 6.4.2.7 References ACAD (1991) The Objectives and Criteria for Accreditation of Training in the Nuclear Power Industry, ACAD 91-105 (National Academy for Nuclear Training, Atlanta, Georgia) AEC (1971) U.S Atomic Energy Commission "Light-water-cooled nuclear power reactors," Federal Register 35 FR 18385 (U.S Government Printing Office, Washington) AECB (1991).Atomic Energy Control Board, Advisory Committee on Radiation Protection Application of the ALARA Process in the Regulation of Nuclear Activities, Report No INFO-0387:AC-2 (National Technical Information Service, Springfield, Virginia) AIF (1980) Atomic Industrial Forum An Assessment of Engineering Techniques for Reducing Occupational Radiation Exposure a t Operating Nuclear Power Plants, prepared by AIF Subcommittee on Engineering Techniques for Reducing Occupational Exposures (Atomic Industrial Forum, Bethesda, Maryland) 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Nuclear Regulatory Commission NUREGI CR-3469, BNL-NUREG-51708, (National Technical Information Service, Springfield, Virginia) BAUM, J.W and KHAN, T.A (1992) "BNL ALARA center experience with an information exchange system on dose control at nuclear power plants," pages 270 to 282 in NEA Workshop on Work Management i n Occupational Dose Control (Organization for Economic Cooperation and Development, Nuclear Energy Agency, Paris) BAUM, J.W and MATTHEWS, G.R (1985).Compendium of Cost-Effectiveness Evaluations of Modifications for Dose Reduction at Nuclear Power Plants, U.S Nuclear Regulatory Commission NUREG/CR-4373 (National Technical Information Service, Springfield, Virginia) BAUM, J.W and SCHULT, D.A (1984) Occupational Dose Reduction at Nuclear P1ants:Annotated Bibliography of Selected Readings in Radiation Protection and RLARA, U.S Nuclear Regulatory Commission NUREGI CR-3469, BNL-NUREG-51708, (National Technical Information Service, Springfield, Virginia) BAUM, J.W and WEILANDICS, 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Health Phys 64, 661-666 BENINSON, D and GONZALEZ, A.J (1981) "Optimization of nuclear safety systems," pages 449 to 455 in Proceedings of a n International Conference on Current Nuclear Power Plant Safety Issues, Volume 11, IAEASTIIPUB/566 (International Atomic Energy Agency, Vienna) BERGMANN, C.A and LAUDERMAN, E.I (1984) Cobalt Release from PWR Valves, EPRI NP-3445 (Electric Power Research Institute, Palo Alto, California) BERTHET, A., BOUSSARD, P., LOCHARD, J., BRISSAUD, A., ROLLIN, P and LEFAURE, C (1992) "Valems de r6f6rence de l'unit6 de dose collective professionnelle pour la mise en oeuvre de la politique "ALARA" dans les centrales nucleaires d'Electricit6 de France," Radioprotection 27,411-421 BESLU, P., ANTHONI, S., BRISSAUD, A., RIDOUX, P., CHEVALIER, C and SAURIN, P (1989).V e n d of plant radiation fields of French reactors: Analysis and perspectives," pages to in Water Chemistry of Nuclear Reactor Systems 5, (British Nuclear Energy Society, London) BOC (1989).U.S Bureau of Census Statistical Abstract of the United States, 1989, 109th ed (U.S Government Printing Office, Washington) BROOKS, B.G (1985) Occupational Radiation Exposure a t Commercial Nuclear Power Reactors 1983 Annual Report, U.S Nuclear Regulatory Commission NUREG-0713, (National Technical Information Service, Springfield, Virginia) CHARBONNEAU, S (1987) "Nuclear products and services," Nucl Eng 28, 121-126 CLARK, M.J., FLEISHMAN, A.B and WEBB, G.A.M (1981) Optimisation of the Radiological Protection of the Public, NRPB-R12O (National Radiological Protection Board, Chilton, Didcot, Oxon, United Kingdom) COHEN, J.J (1970) "Plowshare: New challenge for the health physicist," Health Phys 19, 633-639 COHEN, B.L (1980) "Society's valuation of life saving in radiation protection and other contexts," Health Phys 38, 33-51 COHEN, S.C., GOLDIN, D.J., GOLDIN, A.S and EDWARDS, D.W (1986) "Occupational radiation exposure implications of NRC-initiated multiplant actions," pages 269 to 279 in Proceedings ofASME IANS Bi-Annual Nuclear Power Conference: Safety and Reliability (American Society of Mechanical Engineers, New York) COMLEY, G.C.W and ROOFTHOOFT, R (1988)."Recent chemistry studies a t the Belgian PWRs, DOEL and DOEL 4," page in Proceedings of EPRI Seminar on PWR Water Chemistry and Radiation Field Control (Electric Power Research Institute, Palo Alto, California) CRAWFORD, G.S (1993) "Remote handling equipment aids Bruce," Nucl Eng Int 38,33-34 DIONNE, B.J and BAUM J.W (1985) Occupational Dose Reduction and ALARA a t Nuclear Power Plants: Study on High-Dose Jobs, Radwaste Handling, and AURA Incentives, U.S Nuclear Regulatory Commission REFERENCES 107 NUREGICR-4254, BNL-NUREG-51888 (Brookhaven National Laboratory, Upton, New York) DIONNE, B.J., MEINHOLD, C.B., KHAN TA and BAUM J.W (1990) Occupational Dose Reduction at Department of Energy Contractor Facilities: Study ofALARAPrograms-Status 1989 (Brookhaven National Laboratory, Upton, New York) DUBOURG, M (1985)."Designing for minimum man-rem," Nucl Eng Inter 60, 18 DUNSTER, H.J and MCLEAN, A.S (1970) "The use of risk estimates in setting and using basic radiation protection standards," Health Phys 19, 121-122 DUTTON, L.M.and KINNIBURGH, C.G (1990) "The control of occupational radiation exposure a t the first of a series of PWRs in the United Kingdom," pages 121to 132 in Proceedings of the International Workshop on New Developments in Occupational Dose Control and ALARA Implementation at Nuclear Power Plants and Similar Facilities, U.S Nuclear Regulatory Commission NUREGICP-0110, BNL-NUREG-52226 (National Technical Information Service, Springfield, Virginia) EICKELPASCH, N and LASCH, M (1986) "Investigations on transport and activation of corrosion products in the x 1300 MWel twin boiling water reactors of Gundremmingen," pages 55 to 58 in Proceedings of Water Chemistry of Nuclear Reactor Systems , (British Nuclear Energy Society, London) EPRI (1987) Electric Power Research Institute Guidelines for Permanent BWR Hydrogen Water Chemistry Installations-1987Revision, EPRI NP5283-SR-A (Electric Power Research Institute, Palo Alto, California) EPRI (1989) Electric Power Research Institute NOREM Wear Resistant, Iron-Based Hard Facing Alloys, EPRI NP-6466 (Electric Power Research Institute, Palo Alto, California) EPRI (1990a) Electric Power Research Institute Cobalt Reduction Guidelines, EPRI NP-6737 (Electric Power Research Institute, Palo Alto, California) EPRI (1990b) Electric Power Research Institute PWR Primary Water Chemistry Guidelines:Revision 2, EPRI NP-7077 (Electric Power Resea~ch Institute, Palo Alto, California) EPRI (1993a) Electric Power Research Institute Cobalt Reduction Guidelines Revision 1, EPRI-TR-103296(Electric Power Research Institute, Palo Alto, California) EPRI (1993b) Electric Power Research Institute PWR Primary Shutdown and Startup Chemistry, EPRI TR-101884 (Electric Power Research Institute, Palo Alto, California) EPRI (1993~).Electric Power Research Institute PWR Secondary Water Chemistry Guidelines-Revision 3, EPRI TR-102134 (Electric Power Research Institute, Palo Alto, California) EPRI (1993d) Electric Power Research Institute BWR Primary System Activity Transients During Plant Shutdowns, EPRI TR-103536 (Electric Power Research Institute, Palo Alto, California) Index Terms Links Cost-effective (Cont.): dose savings 73 modifications 44 Cost-effectiveness 38 analysis 42 equation 38 improvements 72 trade-offs 72 Costs health detriments 34 marginal 23 Costs per life saved 72 23 34 impact of crew changes of protection 42 31 34 inferred from various studies 31 marginal value of 34 summary 34 D Decision criteria 24 Decision process 24 Decommissioning 76 Decontamination 70 29 59 84 89 collective dose 84 of components 86 of work areas 85 primary system 86 87 techniques 87 89 Demineralizers 67 85 Design 57 60 89 64 This page has been reformatted by Knovel to provide easier navigation 67 Index Terms Links Design (Cont.): collective dose goal 60 considerations 74 filtration and cleanup systems 68 for ease of maintenance and operation 70 modifications 57 optimization 64 organizational structure 61 reference manuals 77 remote operation and robotics 75 responsibilities 61 space 68 72 76 70 system chemistry, metallurgy and decontamination 67 system layout 74 valving 70 Design dose objectives 60 advanced reactors 61 collective dose 60 cost-effective 61 ICRP recommendation 61 NCRP recommendation 60 public acceptability 60 Sweden 60 United Kingdom 60 United States 60 Discount rate 39 future dose savings 40 Discrete radioactive particles 88 Distance factors 72 This page has been reformatted by Knovel to provide easier navigation Index Terms Links Documentation 94 Dose control actions 18 25 57 24 37 44 57 62 67 73 25 implementation improvements 18 International Commission on Radiological Protection (ICRP) principles 57 reactor design modifications 57 techniques 20 Dose estimates 97 Dose limitation concepts 21 Dose rate controls 58 Dose reduction 100 cobalt reduction 24 during in-service inspection (ISI) 73 elimination/reduction of stable cobalt 67 evaluation of options 37 general actions 24 improved water chemistry 24 measures 100 metallurgy 67 modifications 44 research system chemistry technology Doses 57 67 62 13 This page has been reformatted by Knovel to provide easier navigation Index Terms Links Doses (Cont.): average dose per worker 11 boiling water reactors 13 collective 11 13 comparison with other countries 10 16 exceeding 50 mSv per year 15 pressurized water reactors 14 transient worker 10 Dose tracking 70 16 93 boiling water reactors with excess hydrogen 70 collective dose totals 93 radiotelemetric dosimeters 93 trigger points 93 Dry runs 97 E Electricity generated 11 Electropolishing 87 Equipment layout 75 Examinations 52 Exposure (see Doses) Exposure control 88 during job setup 88 during work 91 Exposure time reduction 58 F Filters 81 monitoring of 85 radiation levels on 81 85 This page has been reformatted by Knovel to provide easier navigation Index Terms Links Filters (Cont.): ventilation 85 Filtration and cleanup systems 68 Forward-pumped heater drains 85 Fuel cladding integrity 87 Fuel defects 88 Fuel failures 71 Fuel sipping 88 G Glove boxes 85 Goals 15 19 61 71 design 61 establishing 49 fuel element failures 71 quantitative indicators 54 types 49 48 H Heat stress 85 High-dose jobs 24 26 93 Hydrogen addition in boiling water reactors 70 80 86 Hydrogen peroxide addition prior to shutdown 67 Incident reviews 55 Inconel® 65 Indicators 53 Intergranular stress corrosion 70 Iron controls in boiling water reactors 81 73 This page has been reformatted by Knovel to provide easier navigation 54 Index Terms Links J Job planning 96 L Lead shielding problems 90 M Maintenance 73 accessibility 75 ease of 73 Management 46 Metallic ions 82 Miniature submarines 93 Mock-ups 97 75 99 53 Monetary value of dose avoided (see Value of dose avoided) Monitoring 54 airborne radioactivity 90 performance 54 radiation 90 90 N Net benefit Nuclear power generation 38 O Occupational doses Optimization (see also ALARA) 21 27 42 45 57 analysis 27 This page has been reformatted by Knovel to provide easier navigation 40 Index Terms Links Optimization (see also ALARA) (Cont.): comparison of options 42 criteria 24 discount factor 40 during decommissioning and disposal 59 during design 58 example 42 factors that require consideration 24 present-value calculation 40 publications 21 57 quantification process 21 58 review at design stage 59 Optimum pH 78 Organizational structures 46 Outage planning 97 42 45 58 62 Oxygen injection into boiling water reactor feedwater 81 P Passivation of surfaces 87 Performance 53 indicators 53 monitoring 53 54 pH control 70 78 optimum 78 Photos 96 Planning 95 Platforms 74 Posting 89 Post-job reviews 94 Pre-job planning 91 97 100 This page has been reformatted by Knovel to provide easier navigation 59 Index Terms Links ALARA briefing 100 ALARA check list 91 briefing 91 inspections 97 101 Present-value calculations 29 40 Procedures 47 94 radiation work permit Protective clothing health and safety trade-offs 100 48 84 84 Q Quick opening hatch for fuel transfer tube 42 R Radiation protection biological and conceptual bases goal manual 47 Radiation work permit 88 Radiation worker responsibilities 92 Radiological surveys 96 Recontamination 87 Reliability 72 Remote operation 75 Reports 94 Respirator optimization 84 Responsibilities 46 Review of ALARA—graded approach 47 48 61 103 Rework 83 Risk 34 Robotics 75 93 This page has been reformatted by Knovel to provide easier navigation 91 Index Terms Links Root causes 55 Scaffolding 74 Secondary system chemistry in pressurized water reactors 83 Sensitivity analyses 45 Shielding 72 dose during installation and removal 90 guidelines 72 inventory 90 safety concerns 90 Shot peening 73 Shutdown chemistry 85 pressurized water reactor 86 shutdown rate for boiling water reactor 85 Source reduction 76 64 78 cobalt 64 79 design factors 64 exclusion of extraneous materials 79 nickel 82 shutdown and startup procedures 80 Space 99 Special tooling 93 Staff qualifications 46 Stainless steel 65 Steam generator design and maintenance 73 Stellite ® 65 Surface finish effect on dose rates 70 Surface pretreatment 68 System layout 74 90 70 This page has been reformatted by Knovel to provide easier navigation Index Terms Links T Task reviews of historical information 96 Technician coverage 92 Tents 85 Time reductions 72 Tools 93 Training accreditation 49 managers, supervisors and engineers 51 49 93 21 radiation protection technicians and supervisors station employees 50 51 U Ultra-fine filters 80 Ultrasonic testing 88 V Value of dose avoided adjusted for inflation 30 adjusted for new risk estimates 30 ALARA levels for effluents 31 alpha (α) value 29 based on past practices 29 based on surveys 29 cost of avoiding limits 29 factors considered 37 for high-dose jobs 34 for low-dose jobs 34 marginal values 29 This page has been reformatted by Knovel to provide easier navigation 29 Index Terms Links ALARA levels for effluents (Cont.): near dose limits objective health detriment 29 radiation protection costs 29 replacement power costs 35 various countries and organizations 32 Valve maintenance 83 Ventilation 85 Video uses 75 93 96 80 86 W Water chemistry guidelines 67 Willingness to pay 33 Z Zinc injection 67 in boiling water reactors 67 research 80 This page has been reformatted by Knovel to provide easier navigation APPENDIX A Pre-Job ALAR,A Briefing (Example of type of information presented) Description: Basic Sequence: Radiological Condition: General description of task Stepby-step outline of the entire job The expected andlor historical radiological conditions (dose rate, contamination level, airborne radioactivity, type of radiation) Major sources of radiation and how conditions are expected to change with each portion of the job Industry lessons learned if appropriate Dose Reduction Measures: Shielding,training, etc., as appropriate Location of low-dose waiting areas within the work area Listing of protective requirements and ALARA controls on the RWP Questions l Comments: Allow time for suggestions, questions and comments APPENDIX B Pre-Job ALARA Checklist (Example of types of information and items to be considered) Procedure Preparation job procedure prepared unnecessary work deleted radiation hold points identified tool lists developedldedicated tools/tool boxes special tools considered remote or robotic equipment/tools/surveillance prefabrication considered human factors considered "lessons learned" reviewed repetitive tasks practiced in the lowest dose-rate area first other Setup Preparation access to and exit from work area planned -services provided -lighting -breathing air -welding -staging -instrument/tool air -electric -heating/cooling -ventilation -other communication provided -headset -walkie-talkie -TV camera/monitor -other radiation monitors to be set up -area monitors radioactive gas -alarm considerations Worker Preparation experienced workers selected special training/photos/drawings/video tapes available rehearsal mock-up training workers exposures reviewed use of fewer workers evaluated Exposure Controls allow for decay following facility shutdown decontaminate equipment flushing or filling equipment move equipment to low-dose rate area work equipment underwater temporary shielding of equipment temporary shielding of work area permanent shielding posting of hot spots and low-dose rate waiting areas other Contamination Controls floor covering (absorbent paper, herculite) contamination curbing or kick plate fence off contaminated area glove boxesltents portable ventilation blower vacuum cleaner decontaminate areaiequipment other APPENDIX C ALARA ReviewsGraded Approach (Example program) Category Dose Estimate Review 500 person-mSv Note: In all categories, the dose-reduction techniques should be considered by the work group performing the task The ALARA reviews serve as independent reviews by radiation protection professionals By radiation protection technician as part of RWP preparation By radiation protection technician and radiation protection supervisor By radiation protection supervisor and engineer responsible for ALARA planning Dose estimate and planned dose reduction techniques to be documented in a pre-job report to management In addition to the above, review by plant management or ALARA committee ... Congress Cataloging-in-Publication Data National Council on Radiation Protection and Measurements Dose control at nuclear power plants recommendations of the National Council on Radiation Protection... Radiation, NCRP Report No 17, out of print NCRP (1978).National Council on Radiation Protection and Measurements Operational Radiation Safety Program, NCRP Report No 59 (National Council on Radiation... an operational radiation safety program, and NCRP Report No 71 (NCRP, 1983) which gives additional guidance on operational radiation safety training In Report No 101 (NCRP, 1989), the NCRP summarized