Volume 2 - Atomic Energy Regulatory Board

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FOREWORD Activities concerning establishment and utilisation of nuclear facilities and use of radioactive sources are to be carried out in India in accordance with the provisions of the Atomic Energy Act, 1962. In pursuance of the objective of ensuring safety of members of the public and occupational workers as well as protection of the environment, the atomic energy regulatory board (AERB) has been entrusted with the responsibility of laying down safety standards and enforcing rules and regulations for such activities. The Board, therefore, has undertaken a programme of developing safety standards, codes and related guides and manuals for the purpose. While some of these documents cover aspects such as siting, design, construction, operation, quality assurance and decommissioning of nuclear and radiation facilities, other documents cover regulatory aspects of these facilities. Safety codes and standards are formulated on the basis of nationally and internationally accepted safety criteria for design, construction and operation of specific equipment, systems, structures and components of nuclear and radiation facilities. Safety codes establish the objectives and set requirements that shall be fulfilled to provide adequate assurance for safety. Safety guides elaborate various requirements and furnish approaches for their implementation. Safety manuals deal with specific topics and contain detailed scientific and technical information on the subject. These documents are prepared by experts in the relevant fields and are extensively reviewed by advisory committees of the Board before they are published. The documents are revised when necessary, in the light of experience and feedback from users as well as new developments in the field. AERB issued a safety code on ‘Regulation of Nuclear and Radiation Facilities’ (AERB/ SC/G) to spell out the requirements/obligations to be met by a nuclear or radiation facility for the issue of regulatory Consent at every stage. This safety guide apprises the details of the regulatory requirements for setting up the radiation facility. such as consenting process, the stages requiring consent, wherever applicable documents to be submitted and the nature and extent of review. The guide also gives information on methods of review and assessment adopted by AERB. Consistent with the accepted practice, ‘shall’ and ‘should’ are used in the guide to distinguish between a firm requirement and a desirable option respectively. Appendices are an integral part of the document, whereas annexures, bibliography and list of participants are included to provide further information that might be helpful to the user. Approaches for implementation different to those set out in the guide may be acceptable, if they provide comparable assurance against undue risk to the health and safety of the occupational workers and the general public, and protection of the environment. For aspects not covered in this guide, applicable national and international standards, codes and guides acceptable to AERB should be followed. Non-radiological aspects i
such as industrial safety and environmental protection are not explicitly considered in this guide. Industrial safety shall be ensured by compliance with the applicable provisions of the Factories Act, 1948 and the Atomic Energy (Factories) Rules, 1996. The guide has been prepared by AERB staff. It has been reviewed by experts and the Advisory Committee on Preparation of Code and Guides and on Governmental Organisation for Nuclear and Radiation Facilities (ACCGORN). AERB wishes to thank all individuals and organisations who have prepared and reviewed the draft and helped in its finalisation. The list of experts, who have participated in this task, along with their affiliations, is included for information. (S. S. Bajaj) Chairman, AERB ii
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GUIDE NO. AERB/RF/SG/G-3 (Vol. 2 of
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4. Performance of Safety System/Int
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APPENDIX-3D-I & II (Refer section 3
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APPENDIX-3D-III (Refer section 3.7.
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APPENDIX-3E (Refer section 3.2.2.5
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APPENDIX-3F (Refer sections 3.2.2.3
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1.6 Non-conformance Control and Cor
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and that of product specifications.
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4. Hazard Assessment (a) (b) (c) (d
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(h) 4. Safety Analysis (a) (b) (c)
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APPENDIX-4C (Refer section 3.3.4) F
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APPENDIX-4F (Refer section 3.3.2 to
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established which includes the arra
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conditions adverse to quality, such
Page 29 and 30: B.3.2 (d) report (ATR), and radiati
Page 31 and 32: for review and disposition of non-c
Page 33 and 34: Leakage radiation and other paramet
Page 35 and 36: - Dose rate profiles anticipated at
Page 37 and 38: other action to be taken (e.g. Ozon
Page 39 and 40: APPENDIX-5D (Refer section 3.4.1.4)
Page 41 and 42: (c) (d) (e) (f) (g) (h) (i) (j) Fac
Page 43 and 44: (b) Structural design: Seismic and
Page 45 and 46: 20. Pre-operational radiation surve
Page 47 and 48: APPENDIX-5E (Refer section 3.4.1.4)
Page 49 and 50: APPENDIX-5F (Refer section 3.4.1.3,
Page 51 and 52: A.3.2 A.3.3 control of documents sh
Page 53 and 54: A.7. for review and disposition of
Page 55 and 56: B.3.2 (b) (c) (d) Document release
Page 57 and 58: for review and disposition of non-c
Page 59 and 60: (c) (d) (iii) (iv) (v) (vi) (vii) (
Page 61 and 62: APPENDIX-6B (Refer section 3.4.3.3)
Page 65 and 66: - Prevention of accidental fall of
Page 67 and 68: - Type of detectors used and their
Page 69 and 70: APPENDIX-6D (Refer section 3.4.3.4)
Page 73 and 74: - Prevention of accidental fall of
Page 75 and 76: - Type of detectors used and their
Page 77 and 78: Provisions including adequate finan
Page 79: Price Order for this guide should b
Page 83 and 84: Betatron An electron accelerator in
Page 85 and 86: Manufacture, possess, store, use, t
Page 87 and 88: adioactive substances and has an ac
Page 89 and 90: Treatment Simulation Methods by whi
Page 91 and 92: CONTENTS FOREWORD .................
Page 93 and 94: 3.3.8 Lead Time for Submission/Avai
Page 95 and 96: 3.8.3 Construction ................
Page 97 and 98: 3.15.2 Procurement and Registration
Page 99 and 100: FUNCTIONAL PERFORMANCE OF SAFETY SY
Page 101 and 102: APPENDIX-5E (Refer section 3.4.1.4)
Page 103 and 104: GAMMA RADIATION PROCESSING FACILITY
Page 105 and 106: FACILITY FOR RADIATION TECHNOLOGY (
Page 107 and 108: ANNEXURE-33b APPLICATION FOR PROCUR
Page 109 and 110: BIOMEDICAL RESEARCH STUDIES ON HUMA
Page 111 and 112: ANNEXURE-59 APPLICATION FOR NO (3.1
Page 113 and 114: VOLUME - 2
Page 115 and 116: tools should conform to the relevan
Page 117 and 118: (c) (d) (ii) (iii) (iv) (v) (vi) (v
Page 119 and 120: APPENDIX-2B (Refer section 3.2.1.3)
Page 121 and 122: - Overhead water storage tank detai
Page 123 and 124: - Ozone concentration (maximum) ant
Page 125 and 126: APPPENDIX-2C (Refer section 3.2.1.4
Page 127 and 128: 1. SAFETY SYSTEMS/INTERLOCKS (CONTD
Page 129 and 130: 2. AREA/ZONE MONITORS S. No. 1. 2.
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3. EMERGENCY WATER LEVEL SENSOR (CO
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5 (i) SEARCH OPERATION - 1 (Hydraul
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S. No. 1. 2. 3. 4. 5. 6. Audio / Co
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the design, statement declaring com
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- Gravity/accidental fall of rack i
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5. Design Basis Accident Analysis A
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h. Quantity of activity : —— PB
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APPENDIX-2E (Refer section 3.2.1.4)
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F. EMERGENCY PLANNING AND PROCEDURE
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(g) (h) 1.2 Organisation The need t
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(i) (ii) (iii) 1.3 Interfaces Ensur
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(iii) (iv) (v) (vi) All constructio
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Standards to which the accelerator
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(b) Accelerator facility (c ) Elect
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15. Details of Disposal Procedures
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Details of beam energy and current
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(h) Laboratory, workshops, stores e
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(i) (ii) (iii) (iv) (v) (vi) During
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4. Documentation Detail Design Deta
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8. Normal and Emergency Operation P
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4. Performance of Safety System/Int
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APPENDIX-3D-I & II (Refer section 3
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APPENDIX-3D-III (Refer section 3.7.
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APPENDIX-3E (Refer section 3.2.2.5
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APPENDIX-3F (Refer sections 3.2.2.3
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1.6 Non-conformance Control and Cor
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and that of product specifications.
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4. Hazard Assessment (a) (b) (c) (d
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(h) 4. Safety Analysis (a) (b) (c)
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APPENDIX-4C (Refer section 3.3.4) F
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APPENDIX-4F (Refer section 3.3.2 to
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established which includes the arra
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conditions adverse to quality, such
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B.3.2 (d) report (ATR), and radiati
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for review and disposition of non-c
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Leakage radiation and other paramet
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- Dose rate profiles anticipated at
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other action to be taken (e.g. Ozon
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APPENDIX-5D (Refer section 3.4.1.4)
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(c) (d) (e) (f) (g) (h) (i) (j) Fac
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(b) Structural design: Seismic and
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20. Pre-operational radiation surve
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APPENDIX-5E (Refer section 3.4.1.4)
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APPENDIX-5F (Refer section 3.4.1.3,
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A.3.2 A.3.3 control of documents sh
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A.7. for review and disposition of
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B.3.2 (b) (c) (d) Document release
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for review and disposition of non-c
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(c) (d) (iii) (iv) (v) (vi) (vii) (
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APPENDIX-6B (Refer section 3.4.3.3)
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- Prevention of accidental fall of
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- Type of detectors used and their
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APPENDIX-6D (Refer section 3.4.3.4)
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- Prevention of accidental fall of
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- Type of detectors used and their
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Provisions including adequate finan
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(b) Contamination monitoring - On l
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1.3 Organisation The responsible or
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(ii) (iii) 1.4 Interfaces Ensuring
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1.6 Accident statistics should be m
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adiation zone monitors and radiatio
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(APPENDIX 8C-I, 8C-II, 8C-III AND 8
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2. Pre-patient/post-patient collima
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APPENDIX-8C-I (Refer section 3.6.3)
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C.3 Measurement of Timer Linearity
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Tolerance : ± 20% of the quoted va
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(a) Shift in the edges of the radia
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6. LINEARITY OF TIMER Operating par
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(c) (d) Recommended performance sta
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TABLE 3 : HVT AS A FUNCTION OF FILT
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2.5 Locking facility of the compres
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6. ACCELERATING VOLTAGE Result : Se
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Result : Coefficient of linearity f
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APPENDIX-8E (Refer section 3.6.3 )
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(THIS IS THE ONLY APPENDIX FOR INDU
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APPENDIX-10 (Refer section 3.18.1)
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APPENDIX-10 (CONTD.) (Refer section
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Containing Radioactive Substances
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LIST OF PARTICIPANTS DRAFT DOCUMENT
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ADVISORY COMMITTEE ON PREPARATION O
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PROVISIONAL LIST OF CODES, GUIDES A
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Volume 2 - Atomic Energy Regulatory Board

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