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ANNEXURE LIST OF ABBREVIATIONS ACI&FS : Advisory Committee on Industrial & Fire Safety ACRS : Advisory Committee on Radiological Safety ACNS : Advisory Committee on Nuclear Safety ACOH : Advisory Committee on Occupational Health ACPSR : Advisory Committee for Project Safety Review ACPSR-FCF : Advisory Committee for Project Safety Review for Fuel Cycle Facilities AERB : Atomic Energy Regulatory Board AGFS : AERB Graduate Fellowship Scheme AGS : Annulus Gas System AHWR : Advanced Heavy Water Reactor ALARA : As Low As Reasonably Achievable AMD : Atomic Minerals Division ASME : American Society of Mechanical Engineers ANMPI : Association of Nuclear Medicine Physicians BARC : Bhabha Atomic Research Centre BDBA : Beyond Design Basis Accident BHAVINI : Bhartiya Nabhkiya Vidyut Nigam BIS : Bureau of Indian Standards BRIT : Board of Radiation and Isotope Technology CCE : Crank Case Exhaust C&I : Control & Instrumentation CCWP : Condenser Cooling Water Pump CDF : Core Damage Frequency CEP : Continued Education Program CESC : Civil Engineering Safety Committee CESCOP : Civil Engineering Safety Committee for Operating Plants CSP : Core Sub-assembly Plant CSRP : Committee for Safety Research Programmes CT : Computed Tomography CV CWMF DAE DBR DDG DFRP DG ECCS ECIL EE EMCCR EPR ESL FA FAC FBTR FFP FP FRP F.R. FRFCF GIS GLR GUI HDPE HEF HEP HRDD HWB HWP IAEA ICS IFSB IFTM IGCAR : Calandria Vault : Central Waste Management Facility : Department of Atomic Energy : Design Basis Report : Deputy Director General : Demonstration Fast Reactor Fuel Reprocessing Plant : Diesel Generator : Emergency Core Cooling System : Electronics Corporation of India Ltd : Equipment Erection : En-Masse Coolant Channel Replacement : European Pressurized Water Reactor : Environmental Survey Laboratory : Fuel Assembly : First Approach to Criticality : Fast Breeder Test Reactor : Fuel Fabrication Plant : Full Power : Fuel Reprocessing Plant : Frequency Rate : Fast Reactor Fuel Cycle Facility : Geographic Information System : Gross Load Rejection : Graphical User Interface : High Density Poly Ethylene : Head End Facility : Human Error Probability : Human Resource Development Division : Heavy Water Board : Heavy Water Plant : International Atomic Energy Agency : Inner Containment Structure : Interim Fuel sub-assembly Storage Building : Inclined Fuel Transfer Machine : Indira Gandhi Centre for Atomic Research 76
IGRPP IHX ILRT INES IPN IREL IRMRA IRS IRV ISI ISO ITER ITF IV &V IV & VC JHA LINAC KAPP KAPS KGS KK-NPP LCO LMC LOCA LTTM LWR MAPS MCNP MoU MV NAPS NDE NFC NLR NOC NPCIL NPP : Industrial Gamma Radiation Processing Plant : Intermediate Heat Exchanger : Integrated Leakage Rate Test : International Nuclear Event Scale : Input Processor Node : Indian Rare Earths Limited : Indian Rubber Manufacturers Research Association : Incident Reporting System : Instrumental Relief Valve : In-Service Inspection : International Organisation for Standardization : International Thermonuclear Experiment Reactor : Integral Test Facility : Independent Verification & Validation : Independent Verification and Validation Committee : Job Hazard Analysis : Linear Accelerator : Kakrapar Atomic Power Project : Kakrapar Atomic Power Station : Kaiga Generating Station : Kudankulam Nuclear Power Project : Limiting Condition for Operation : Lead Mini Cell : Loss of Coolant Accident : Low Trajectory Turbine Missile : Light Water Reactor : Madras Atomic Power Station : Monte Carlo N-Particle : Memorandum of Understanding : Main Vessel : Narora Atomic Power Station : Non-Destructive Examination : Nuclear Fuel Complex : Net Load Rejection : No-Objection Certificate : Nuclear Power Corporation of India Ltd. : Nuclear Power Plant NSSS NTC NZOSP OECD OGDHRS OLIC ONGC OPN OSCOM OSEE PC PDSC PEE PEFHI PFBR PHRS PHT PHWR PLDSC PPF PPP PSAR PSA PSD PSI PSHA PSS PSWP PWR QA QMS RAPP RAPS RB RCP R&D RI RPV RRCAT : Nuclear Steam Supply System : Nuclear Training Centre : New Zirconium Oxide and Sponge Plant : Organisation for Economic Cooperation & Development : Operational Grade Decay Heat Removal System : Official Language Implementation Committee : Oil and Natural Gas Commission : Output Processor Node : Orissa Sand Complex : Off-site Emergency Exercises : Primary Containment : Project Design Safety Committee : Plant Emergency Exercises : Preventive Efforts and Fire Hazard Index : Prototype Fast Breeder Reactor : Passive Heat Removal System : Primary Heat Transport : Pressurized Heavy Water Reactor : Pre-Licensing Design Safety Committee : Process Plant Facility : Primary Pressurising Plant : Preliminary Safety Analysis Report : Probabilistic Safety Analysis : Pulse Safety Device : Pre-Service Inspection : Probabilistic Seismic Hazard Analysis : Primary Shutdown System : Process Sea Water Pump : Pressurized Water Reactor : Quality Assurance : Quality Manual System : Rajasthan Atomic Power Project : Rajasthan Atomic Power Station : Reactor Building : Reactor Coolant Pump : Research and Development : Regulatory Inspection : Reactor Pressure Vessel : Raja Ramanna Centre for Advanced Technology 77
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ATOMIC ENERGY REGULATORY BOARD The
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THE FUNCTIONS OF THE ATOMIC ENERGY
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3.2.2 Shipments Approved 27 3.2.3 R
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CHAPTER 10 PUBLIC INFORMATION 61 10
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INDEX TO FIGURES Figure Title Page
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1.2 ORGANISATION CHART OF AERB ATOM
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Mumbai. For Uranium Corporation of
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CHAPTER 2 SAFETY SURVEILLANCE OF NU
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out and clearances were issued in s
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● ● ● PFBR related pipe trenc
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Some of the important observations/
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● ● PFBR ● ● DFRP ● ● T
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Load Capacity (ULC) of the Inner Co
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2.2.9 Licensing of Operating Staff
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to explore the possibility of repla
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● ● ● ● ● ● ● Cause f
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CHAPTER 3 SAFETY SURVEILLANCE OF RA
Page 36 and 37: Table-3.4: Licences / NOC Issued A.
Page 38 and 39: for the loading/ replenishment of C
Page 40 and 41: gauge device. The device has adequa
Page 42 and 43: In order to enhance industrial safe
Page 44 and 45: ● ● ● ● ● ● Individual
Page 46 and 47: Fig 4.2: Distribution of Man-days L
Page 48 and 49: CHAPTER 5 ENVIRONMENTAL SAFETY AND
Page 50: - - - Note: Limits for release of A
Page 53 and 54: 5.3 OCCUPATIONAL HEALTH AND SAFETY
Page 55 and 56: CHAPTER 7 DEVELOPMENT OF SAFETY DOC
Page 57 and 58: Part-2 of the Analysis: The mass of
Page 59 and 60: provisions of AERB safety standard
Page 61 and 62: 8.2 SAFETY REVIEW OF NUCLEAR POWER
Page 63 and 64: inventory. A report on the above an
Page 65 and 66: Fig. 9.2: Aerial Extents of Water B
Page 67 and 68: Fig. 9.5: Subsurface Characterizati
Page 69 and 70: Fig. 9.7: Ground Water Classificati
Page 71 and 72: CHAPTER 10 PUBLIC INFORMATION 10.1
Page 73 and 74: CHAPTER 11 INTERNATIONAL COOPERATIO
Page 75 and 76: Inauguration of INSAG Meeting in Pr
Page 77 and 78: 12.5 AERB COLLOQUIA l l l l Followi
Page 79 and 80: Table 13.2: Research Projects Renew
Page 81 and 82: l l l Compliance Assurance for the
Page 83 and 84: CHAPTER 15 GENERAL 15.1 IMPLEMENTAT
Page 85: l l l l l l l l S.K.Pradhan, R.S.Ra
Page 89 and 90: INTERNATIONAL NUCLEAR EVENT SCALE (
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