Infrastructure and Methodologies for the Justification of Nuclear Power Programmes

Agustín Alonso is Emeritus Professor and Chair of Nuclear Technology at Madrid Polytechnic University, Spain, and serves on the IAEA’s International Nuclear Safety Advisory Group (INSAG).

"This book provides guidance on the principles on which appropriate radiation protection can be based. Readers from nuclear power industries would find the analysis of the environmental impacts of nuclear installations interesting." --Materials World

• Contributor contact detailsWoodhead Publishing Series in EnergyChapter 1: Overview of infrastructure and methodologies for the justification of nuclear power programmesAbstract:1.1 The past, current and future phases in the development of nuclear power1.2 The main factors shaping the deployment of nuclear power1.3 The bases for the development of nuclear power1.4 ConclusionPart I: Infrastructure of nuclear power programmesChapter 2: The lifecycle of a nuclear power plantAbstract:2.1 Introduction2.2 Overview of the complete nuclear fuel cycle2.3 Overview of the nuclear power plant lifecycle2.4 Requirements for new nuclear power plants2.5 Sources of further information and adviceChapter 3: The role of government in establishing the framework for nuclear power programmesAbstract:3.1 Introduction3.2 Role of government in the justification process3.3 International requirements3.4 Knowledge management3.5 Regulatory requirements3.6 New entrants3.7 Future trendsChapter 4: Regulatory requirements and practices in nuclear power programmesAbstract:4.1 Introduction4.2 Basic characteristics of regulatory organizations4.3 Creation, authority, responsibilities and competence of the regulatory body4.4 Development, functions and management system of the regulatory body4.5 Development of the regulatory framework and approaches4.6 The regulatory function: development of a regulatory pyramid4.7 Development of the licensing process and major regulatory activities during the licensing process4.8 The compliance function: verification and oversight during construction and operation4.9 The enforcement function4.10 Regulatory transparency and openness, and the relationship with the operating organization and other stakeholders4.11 Regulatory support and research4.12 Sources of further information and adviceChapter 5: Responsibilities of the nuclear operator in nuclear power programmesAbstract:5.1 Introduction5.2 The responsibilities of the nuclear operator5.3 The means to enact responsibilities and enhance leadership effectiveness5.4 Responsibilities of the operator in the lifecycle of a nuclear power plant5.5 Importance of organisations for safe operation5.6 Building and maintaining an operations organisation5.7 Monitoring and evaluating organisational effectiveness5.8 Maintaining organisations5.9 Basis for safe operation5.10 Engineering support and design authorityChapter 6: The need for human resources in nuclear power programmesAbstract:6.1 Introduction6.2 Human resource requirements of the nuclear stakeholders6.3 High-level nuclear education programmes6.4 Changing specialization requirements in the nuclear power plant lifecycle6.5 International experience6.6 Initial and sustained training programmes6.7 Sources of further information and adviceChapter 7: National technical capability development in nuclear power programmesAbstract:7.1 Introduction7.2 Establishing the foundation for national technical development7.3 Understanding the nuclear power plant (NPP) design7.4 National participation in siting7.5 National participation in design, equipment manufacture and construction7.6 Plant commissioning7.7 Plant operation7.8 Longer-term operation and management7.9 Decommissioning7.11 AcknowledgementsPart II: Justification of nuclear power programmesChapter 8: Application of the justification principle to nuclear power developmentAbstract:8.1 Introduction8.2 The ethics of the justification principle8.3 The justification process8.4 The terms of the justification equation8.5 The benefits of nuclear energy8.6 Risks and detriments of nuclear energy8.7 ConclusionsChapter 9: Available and advanced nuclear technologies for nuclear power programsAbstract:9.1 Introduction9.2 Classification of advanced nuclear reactors9.3 Key advances in technology9.4 Advanced nuclear reactor designs9.5 Non-electrical applications9.6 Sources of further information and adviceChapter 10: Nuclear safety in nuclear power programsAbstract:10.1 IntroductionChapter 11: Radiation protection in nuclear power programmesAbstract:11.1 Introduction11.2 Radiation doses11.3 Biological effects of radiation11.4 Attributability of risks and potential health effects to nuclear power plants (NPPs)11.5 Radiation protection paradigm11.6 Potential exposures11.7 Radiation safety standards11.8 Occupational protection at nuclear power plants (NPPs)11.9 Public protection at nuclear power plants (NPPs): controlling discharges into the environmentChapter 12: Emergency planning in nuclear power programmesAbstract:12.1 Introduction12.2 Need for emergency planning as the last barrier of defence and mitigation of the radiological consequences of potential accidents12.3 International conventions and standards on emergency planning12.4 Responsible organizations12.5 Emergency management12.6 Emergency drills and exercises12.7 Emergency coordination centresChapter 13: Non-proliferation safeguards in nuclear power programmesAbstract:13.1 Introduction13.2 Nuclear Non-Proliferation Treaty (NPT)13.3 International Atomic Energy Agency (IAEA) and international safeguards13.4 Non-proliferation responsibilities13.5 Transparency during a nuclear renaissance13.6 Sources of further information and adviceChapter 14: Spent fuel and radioactive waste management in nuclear power programmesAbstract:14.1 Introduction14.2 Policies and strategies for management of spent fuel and radioactive waste14.3 Radioactive waste from nuclear power production14.4 Management systems for spent nuclear fuel14.5 Management of low- and intermediate-level waste14.6 ConclusionsChapter 15: The economics of nuclear power: past, present and future aspectsAbstract:15.1 Introduction15.2 Economics today and tomorrow15.3 Levelized cost of electricity generation15.4 Risks and uncertainties15.5 ConclusionsChapter 16: Social impacts and public perception of nuclear powerAbstract:16.1 Introduction16.2 Social impacts at both national and local levels16.3 Public perception of nuclear power16.4 ConclusionChapter 17: Environmental impacts and assessment in nuclear power programmesAbstract:17.1 Introduction17.2 Environmental protection17.3 Environmental Impact Assessment (EIA)17.4 Land planning for new nuclear17.5 Key controls on environmental impacts17.6 Overlap with other regulatory controls17.7 Conclusions17.8 Future trendsPart III: Development of nuclear power programmesChapter 18: Site selection and evaluation for nuclear power plants (NPPs)Abstract:18.1 Introduction18.2 Schematic approach to site selection18.3 Basic safety principles applicable to nuclear power plant (NPP) siting18.4 International Atomic Energy Agency (IAEA) requirements and safety guides on nuclear power plant siting18.5 Consideration of the feasibility of an emergency plan18.6 Demographic requirements and site parameters developed and applied by the United States Nuclear Regulatory CommissionChapter 19: Bid invitation in nuclear power plant procurementAbstract:19.1 Introduction19.2 Contracting approach and bid invitation specifications19.3 Basis for preparation of the bid invitation specifi cations19.4 Purpose, structure and contents19.5 Letter of invitation19.6 Instructions to bidders19.7 Scope of supply19.8 Technical requirements19.9 Project implementation19.10 Technical data sheets19.11 Draft contract19.12 Commercial conditions19.13 Financing requirementsChapter 20: Licensing for nuclear power plant siting, construction and operationAbstract:20.1 Introduction20.2 The need for licensing20.3 Licensing application and supporting technical documents20.4 Safety review of licensing applications and license requirements20.5 Licensee activities during design, construction, commissioning, operation and decommissioning20.6 Regulatory compliance during design, construction, commissioning and operation20.7 Licensing of a country’s first nuclear power plant20.8 Acknowledgements20.10 Appendix: Examples of licensing systemsChapter 21: Quality assurance during design, construction and operation of nuclear power plantsAbstract:21.1 Introduction21.2 Definitions21.3 Quality assurance criteria21.4 Quality assurance during design21.5 Quality assurance during construction21.6 Quality assurance during commissioning21.7 Quality assurance during operation21.8 Assessment21.9 Human resources21.10 Sources of further information and advice21.12 Appendix: list of abbreviations and acronyms.Chapter 22: Commissioning of nuclear power plants (NPPs)Abstract:22.1 Introduction22.2 Codes, standards and other requirements for the commissioning of nuclear power plants (NPPs)22.3 Commissioning programme and stages of commissioning22.4 Pre-operational tests22.5 Nuclear commissioning22.6 Roles and responsibilities during commissioning22.7 Commissioning organization and management22.8 Commissioning procedures22.9 Test procedures22.10 Qualification requirements for commissioning personnel and other human factors22.11 Safety management and development of a safety culture22.12 Recording and analysis of tests22.13 Documentation22.14 International experienceChapter 23: Operational safety of nuclear power plantsAbstract:23.1 Introduction23.2 International Atomic Energy Agency (IAEA) requirements for nuclear power plant (NPP) operation23.3 Management, organization and administration of nuclear power plants (NPPs)23.4 Training and qualification23.5 Operations23.6 Maintenance23.7 Technical support23.8 Operational experience feedback (OEF)23.9 Radiation protection23.10 Chemistry23.11 Emergency planning and preparedness23.12 Operational Safety Review Team (OSART)23.13 Sources of further information and adviceChapter 24: Decommissioning of nuclear power plants (NPPs)Abstract:24.1 Introduction24.2 Brief history of the development of decommissioning24.3 Development of decommissioning cost- estimating methodologies24.4 Development of long-term planning for decommissioning24.5 Decommissioning technologies and research and development24.6 Overview of the decommissioning phase of a nuclear power plant (NPP) lifecycle24.7 Management of decommissioning waste and the recycling of materials24.8 International experience24.9 Sources of further information and advicePart IV: AppendicesAppendix 1: The justification test for new nuclear power development: United Kingdom experienceAbstract:A1.1 International Commission on Radiological Protection (ICRP) and originsA1.2 European Atomic Energy Community (Euratom) legislation and European Court of Justice and UK case law on justificationA1.3 UK regulationsA1.4 Application of justification test to nuclear new build proposalsA1.5 ConclusionsAppendix 2: Nuclear safety culture: management, assessment and improvement of individual behaviourAbstract:A2.1 IntroductionA2.2 DefinitionsA2.3 The organizationA2.4 Assessing the stage of developmentof safety cultureA2.5 Identifying the lack of safety cultureA2.6 Improvement of safety cultureA2.7 ConclusionAppendix 3: Nuclear installation safety: International Atomic Energy Agency (IAEA) training programmes, materials and resourcesAbstract:A3.1 Background and introductionA3.2 Building competence and effectiveness of trainingA3.3 Training of leaders for safety, emerging regulatorsA3.4 Challenges for building sustainable competence systemsA3.5 IAEA training materials and related resourcesA3.6 IAEA training resources on the WebA3.7 The IAEA interdepartmental group on training and Web-based training resourcesA3.8 Regional cooperation, knowledge networks and harmonized approach to training managementA3.9 Conclusions and recommendations for efficient and sustainable training systems to build competenceA3.10 AcknowledgementsA3.12 List of abbreviations and acronymsA3.13 Annex: Four quadrants competencies model based on TECDOC 1254 and SARCoN guidelinesAppendix 4: Simulator training for nuclear power plant control room personnelAbstract:A4.1 Reasons for simulator trainingA4.2 Deciding who should be trained in full-scope simulatorsA4.3 Operating scenarios for trainingA4.4 Competencies to be acquiredA4.5 Defining good simulator trainingA4.6 Requirements for simulatorsA4.7 Other applications for training simulatorsA4.8 ConclusionAppendix 5: Multinational Design Evaluation Programme (MDEP): multilateral cooperation in nuclear regulation and new reactor designAbstract:A5.1 IntroductionA5.2 Programme goals and outcomesA5.3 Programme implementationA5.4 Current activitiesA5.5 Interim resultsA5.6 Future trendsIndex