CONTENTS GLOSSARY VII INTRODUCTION 1 1.1. General concepts 1 1.2. National policy in the nuclear field 2 1.3. National program corresponding to nuclear installations 2 1.4. Summary of the main subjects contained in the Report 3 1.4.1. Actions taken in the light of the Fukushima Daiichi Accident 4 1.4.1.1. External events 6 1.4.1.2. Loss of safety functions 6 1.4.1.3. Severe accident management 7 1.4.1.4. Emergency preparedness 7 1.4.2. Compliance with the principles of the Vienna Declaration 8 1.4.2.1. New design of nuclear power plants 8 1.4.2.2. Safety reviews for existing nuclear powers plants 9 1.4.2.2.1. Periodic Safety Review 9 1.4.2.2.2. Stress Test 10 1.4.2.2.3. Operating Experience Feedback 10 1.4.2.3. National requirements and standards 10 CHAPTER 2 – FOLLOW-UP FROM THE SEVENTH REVIEW MEETING 11 2.1. Challenge 1: The Regulatory Authority to prepare and host the IRRS Mission in 2018 11 2.2. Challenge 2: Salto Mission to Atucha I 11 2.3. Challenge 3: Resolution of issues with Atucha I and II RPV in-vessel retention and 12 external cooling arising from foro stress tests 2.4. Challenge 4: The Regulatory Authority to conduct licensing activities on CAREM 25 12 Small Modular Prototype Reactor under construction following principle 1 of the VDNS 2.5. Challenge 5: External Emergency Control Centre located far from Embalse NPP 13 2.6. Refurbishment activities of CNE 13 2.7. CNA I Life Extension Project 15 2.8. Implementation of the improvements arisen from stress tests 15 2.9. Programme of consolidation of safety culture 15 2.10.Normative framework review 16 2.11.Preparation of IAEA IRRS Mission 16 CHAPTER 3 – COMPLIANCE WITH ARTICLES OF THE CONVENTION 17 3.6. ARTICLE 6: EXISTING NUCLEAR POWER PLANTS 17 3.6.1. General 17 3.6.2. Existing Nuclear Power Plants in Argentina 17 3.6.3. Actions leading to safety improvements 18 3.6.3.1. Routine safety review 18 3.6.3.1.1. Documentation updating 18 3.6.3.1.2. Ageing Management Program 19 3.6.3.1.3. Operating experience 19 3.6.3.2. Specific safety review 20 3.6.4. Improvement activities 20 3.6.4.1. CNA I improvements 20 3.6.4.1.1. Construction of Dry Storage for spent fuel 20 3.6.4.1.2. Emergency control room 21 CONTENTS I 3.6.4.2. CNA II improvements 21 3.6.4.2.1. Review and improvement of emergency procedures 21 3.6.4.2.2. Alternative water sources 21 3.6.4.2.3. Reposition of light water to the primary system from 22 the volume control system 3.6.4.3. CNE improvements 22 3.6.4.3.1. Physical Protection System 22 3.6.4.3.2. Alternative water sources 22 3.6.4.3.3. Instrumentation & Control (I&C) 23 3.6.4.3.4. New systems providing redundancy during Refurbishment Outage 23 3.6.5. NPPs life extension 23 3.6.5.1. CNE life extension 23 3.6.5.2. CNA I life extension 28 3.6.6. Opinion concerning the operation continuity of nuclear installations 30 3.6.7. Compliance with the obligations imposed by the Convention 30 3.7. ARTICLE 7: LEGISLATIVE AND REGULATORY FRAMEWORK 31 3.7.1. National Legislative Framework 31 3.7.2. Normative Framework 32 3.7.2.1. Introduction 32 3.7.2.2. Compliance with the principles of Vienna Declaration on Nuclear Safety 34 3.7.2.3. Basic concepts 35 3.7.2.3.1. Deterministic and probabilistic aspects of the Regulatory Standards 35 3.7.2.3.2. Basic criteria of radiological and nuclear safety 36 3.7.3. Licensing System 36 3.7.3.1. General aspects 36 3.7.3.2. Licensing process 37 3.7.3.2.1. Nuclear power plant licensing 37 3.7.3.2.2. Periodic Safety Review and Renewals of License 38 3.7.3.2.3. Nuclear power plant personnel licensing 38 3.7.3.3. Regulatory inspections and audits 39 3.7.3.4. Regulatory actions 40 3.7.4. Sanctions Regime 40 3.7.5. Compliance with the obligations imposed by the Convention 41 3.8. ARTICLE 8: REGULATORY BODY 42 3.8.1. Functions and competence of the Regulatory Body 42 3.8.2. ARN organizational structure 43 3.8.3. ARN human resources 45 3.8.3.1. Resources assigned to the nuclear power plants regulatory control 47 3.8.3.1.1. General aspects 47 3.8.3.1.2. Human Resources assigned to operation control 48 3.8.3.1.3. Human Resources assigned to commissioning control 49 3.8.3.1.4. Human Resources assigned to construction, refurbishment control 49 3.8.3.1.5. ARN personnel qualification 49 3.8.4. Quality Management System in the Regulatory Body 50 3.8.4.1. Process approach improvement 51 3.8.4.2. Measurement, assessment and improvement 51 3.8.4.3. Certification and accreditation 52 3.8.4.4. Documentation requirements 52 3.8.4.5. Satisfaction of stakeholders 53 3.8.4.6. Continuous improvement 53 3.8.5. Communications with the stakeholders 53 II CONTENTS 3.8.6. Financial resources 54 3.8.7. Relationship with other organizations 56 3.8.8. Compliance with the obligations imposed by the Convention 58 3.9. ARTICLE 9: RESPONSIBILITY OF THE LICENSEE HOLDER 59 3.9.1. Background 59 3.9.2. Licensee and Primary Responsible 59 3.9.3. Communication with the public 60 3.9.3.1. Communication campaigns 60 3.9.3.2. Relations with the media 60 3.9.3.3. Digital communication 61 3.9.3.4. Relations with the community 61 3.9.3.5. Plant tours 61 3.9.3.6. Communication to environmental authorities 61 3.9.3.7. Communications to others government organizations 62 3.9.4. Regulatory control on the fulfilment of the Licencee Responsibilities 62 3.9.5. Compliance with the obligations imposed by the Convention 62 3.10. ARTICLE 10: PRIORITY TO SAFETY 63 3.10.1. General Regime 63 3.10.2. Specific actions 65 3.10.2.1. Safety policy 65 3.10.2.2. Safety culture and its development 65 3.10.2.3. Commitment to safety 66 3.10.2.4. Management attitudes towards safety 66 3.10.2.5. Personnel motivation 66 3.10.2.6. Voluntary activities and good practices related to safety 67 3.10.3. Compliance with the obligations imposed by the Convention 63 3.11. ARTICLE 11: HUMAN AND FINANCIAL RESOURCES OF THE LICENSEE 68 3.11.1. Introduction 68 3.11.2. Electrical generation and economics 69 3.11.2.1. Total electrical generation period 2016 - 2018 69 3.11.2.2. Nuclear generation 2016, 2017, 2018 70 3.11.2.3. Human Resources 71 3.11.2.4. Current expenses 2016, 2017, 2018 72 3.11.3. Compliance with the obligations imposed by the Convention 73 3.12. ARTICLE 12: HUMAN FACTORS 74 3.12.1. System to detect, correct and prevent human errors 74 3.12.1.1. Human corrective actions in CNA I 75 3.12.1.2. Human corrective actions in CNA II 77 3.12.1.3. Human corrective actions in CNE 77 3.12.1.3.1. Error prevention techniques 78 3.12.1.3.2. Management in the field 79 3.12.1.3.3. Self-assessment 79 3.12.2. Management and institutional aspects 79 3.12.3. Human Reliability Analysis (HRA) 80 3.12.4. Progress in human factors 80 3.12.5. Compliance with the obligations imposed by the Convention 81 3.13. ARTICLE 13: QUALITY ASSURANCE 82 3.13.1. Introduction 82 3.13.2. Quality System 82 3.13.2.1. Quality supervision of external suppliers related to operation, refurbishment 83 and construction of NPPs. CONTENTS III 3.13.3. Quality Management Program of the CAREM Project 84 3.13.3.1. Quality supervision of external suppliers related to design and construction 85 of CAREM project 3.13.4. Compliance with the obligations imposed by the Convention 85 3.14. ARTICLE 14: ASSESSMENT AND VERIFICATION OF SAFETY 88 3.14.1. Introduction 88 3.14.2. Ageing 88 3.14.2.1. CNA I Reactor Pressure Vessel 88 3.14.2.2. CNE testing of safety related components 92 3.14.3. Safety assessment 93 3.14.3.1. Deterministic assessments 93 3.14.3.1.1. Safety Analysis Upgrading 94 3.14.3.1.2. Post Fukushima analysis 94 3.14.3.1.3. Accident Management and Severe Accident Management Program 94 3.14.3.1.3.1. CNA I 96 3.14.3.1.3.2. CNA II 98 3.14.3.1.3.3. CNE 101 3.14.3.1.3.4. Others strategies proposal 101 3.14.3.1.3.5. Development of Instructions and Guidelines 102 3.14.3.1.4. CAREM Deterministic Safety Assessment 105 3.14.3.2. Probabilistic Safety Assessment 105 3.14.3.2.1. CNA I Probabilistic Safety Assessment applications 105 3.14.3.2.2. CNA II Probabilistic Safety Assessment applications 107 3.14.3.2.3. CNE Probabilistic Safety Assessment applications 109 3.14.3.2.4. CAREM Probabilistic Safety Assessment applications 110 3.14.3.3.