IAEA SAFETY STANDARDS History, Status, Structure, Contents by Stephen Evans, IAEA NSRW RIT School of Drafting Regulations Vienna, November 2012

Outline History and status of the IAEA Safety Standards Hierarchy and Structure of the SS’s General Safety Regulations Specific Safety Standards Safety Regulations and Guides Fundamental Safety Principles Reg'l WS on IAEA SSs and WENRA RLs 01-04 October 2012

History – IAEA statute Under Article III.A.6 of its Statute, the IAEA is authorized: “to establish or adopt, in consultation and, where appropriate, in collaboration with the competent organs of the United Nations and with the specialized agencies concerned, standards of safety for protection of health and minimization of danger to life and property.” In 1958, the IAEA published its first Safety Standard, Safety Series No. 1, Safe Handling of Radioisotopes. Over the years, some 200 publications have been issued in the Safety Series. Reg'l WS on IAEA SSs and WENRA RLs 01-04 October 2012

Historical milestones SS No. 15 Radioactive Waste Disposal into the Ground 1958 1961 1962 1965 Reg'l WS on IAEA SSs and WENRA RLs 01-04 October 2012

Historical milestones (cont.) SS No. 15 1974 1988 1996 2006 Reg'l WS on IAEA SSs and WENRA RLs 01-04 October 2012

Development From 1958 to 2006: “Bottom-up approach” 1996: Commission on Safety Standards (CSS) – standing body of senior governmental officials Committees: NUSSC, RASSC, WASSC, TRANSSC – standing bodies of senior experts From 2006: “Top down-approach” Safety Fundamentals (2006) Roadmap for the long term development of the Safety Requirements (2008) Reg'l WS on IAEA SSs and WENRA RLs 01-04 October 2012

The role and functions of CSS To provide guidance on the approach and strategy for establishing the Agency’s SSs To resolve issues raised by the committees To endorse the texts of the SF, SRs and SGs To provide general advice and guidance on SSs issues Reg'l WS on IAEA SSs and WENRA RLs 01-04 October 2012

Role and functions of the Committees To advise on the nuclear installation/radiation/ transport/waste safety programme for the development of the safety standards To recommend activities and areas for improvement to enhance the overall program To review reports on feedback from the Secretariat and NUSSC/RASSC/TRANSSC/ WASSC members on the application and use of the safety standards To review proposals for the development of relevant new standards and review and accept draft standards Reg'l WS on IAEA SSs and WENRA RLs 01-04 October 2012

Hierarchy Safety Fundamentals Safety Requirements Safety Guides Principles for protecting people and environment Requirements to be applied to meet the principles Safety Fundamentals Safety Requirements Recommended ways of meeting the requirements Safety Guides Technical documents Reg'l WS on IAEA SSs and WENRA RLs 01-04 October 2012

Relationship with National Legislation Reg'l WS on IAEA SSs and WENRA RLs 01-04 October 2012

Summary of Safety Standards Reg'l WS on IAEA SSs and WENRA RLs 01-04 October 2012

Other publications Reg'l WS on IAEA SSs and WENRA RLs 01-04 October 2012

Other publications (cont.) Reg'l WS on IAEA SSs and WENRA RLs 01-04 October 2012

Final Structure of Safety Standards Under development Reg'l WS on IAEA SSs and WENRA RLs 01-04 October 2012

Development of Safety Standards Developed and reviewed by IAEA staff and international experts In close consultation with Member States SF and SRs approved by the Board of Governors SGs are approved by IAEA DG Review periodicity is about 10 years Since 1996 more than 100 volumes published Reg'l WS on IAEA SSs and WENRA RLs 01-04 October 2012

http://www-ns.iaea.org/standards/ documents/general.asp General SRs http://www-ns.iaea.org/standards/ documents/general.asp Reg'l WS on IAEA SSs and WENRA RLs 01-04 October 2012

Facility/Activity Specific SSs Status of the SSs is available at http://www-ns.iaea.org/committees/ files/CSS/205/status.pdf Reg'l WS on IAEA SSs and WENRA RLs 01-04 October 2012

Nuclear Power Plants Specific Safety Requirements: Reg'l WS on IAEA SSs and WENRA RLs 01-04 October 2012

Nuclear Power Plants (cont.) Specific Safety Guides to be discussed: Design of Emergency Power Systems for Nuclear Power Plants Safety Guide, NS-G-1.8 (2004) Design of the Reactor Coolant System and Associated Systems in Nuclear Power Plants Safety Guide, NS-G- 1.9 (2004) Design of Reactor Containment Systems for Nuclear Power Plants Safety Guide, NS-G-1.10 (2004) Design of the Reactor Core for Nuclear Power Plants Safety Guide, NS-G-1.12 (2005) Reg'l WS on IAEA SSs and WENRA RLs 01-04 October 2012

Nuclear Power Plants (cont.) Modifications to Nuclear Power Plants Safety Guide, NS-G-2.3 (2001) Maintenance, Surveillance and In-service Inspection in Nuclear Power Plants Safety Guide, NS-G-2.6 (2002) Commissioning for Nuclear Power Plants Safety Guide, NS-G-2.9 (2003) Licensing Process for Nuclear Installations Specific Safety Guide, SSG-12 (2010) Reg'l WS on IAEA SSs and WENRA RLs 01-04 October 2012

Current status of SSs Reg'l WS on IAEA SSs and WENRA RLs 01-04 October 2012

Recently published http://www-pub.iaea.org/MTCD/Publications/PDF/Pub1573_web.pdf Reg'l WS on IAEA SSs and WENRA RLs 01-04 October 2012

Safety Guide Review Plan (priorities)  NS-G-1.3 Instrumentation and Control Systems Important to Safety in Nuclear Power Plants (2002)  NS-G-1.8 Design of Emergency Power Systems for Nuclear Power Plants (2004)  NS-G-1.9 Design of the Reactor Coolant System and Associated Systems in Nuclear Power Plants (2004)  NS-G-1.4 Design of Fuel Handling and Storage Systems for Nuclear Power Plants (2003)  NS-G-1.10 Design of Reactor Containment Systems for Nuclear Power Plants (2004)  NS-G-1.7 Protection against Internal Fires and Explosions in the Design of Nuclear Power Plants (2004) NS-G-1.11 Protection against Internal Hazards other than Fires and Explosions in the Design of Nuclear Power Plants (2004)  SSG-2 Deterministic Safety Analysis for Nuclear Power Plants (2009)  NS-G-2.15 Severe Accident Management Programmes for Nuclear Power Plants (2009)  SSG-15 Storage of Spent Fuel (in publication)  GS-G-2.1 Arrangements for Preparedness for a Nuclear or Radiological Emergency (2007)  GSG-2 Criteria for Use in Preparedness and Response for a Nuclear or Radiological Emergency (2011)  WS-G-3.1 Remediation Process for Areas Affected by past activities and accidents (2007)  GS-G-1.1 Organization and staffing of the regulatory body for nuclear facility (2002)  GS-G-1.2 Review and assessment of nuclear facilities by the regulatory body (2002)  GS-G-1.3 Regulatory inspection of nuclear facilities and enforcement by the regulatory body (2002)  GS-G-1.4 Documentation for use in regulating nuclear facilities (2002) SSG-12 Licensing Process for Nuclear Installations (2010)  SSG-16 Establishing the Safety Infrastructure for a Nuclear Power Programme (2011) Reg'l WS on IAEA SSs and WENRA RLs 01-04 October 2012

Fundamental Safety Principles Principle 1: Responsibility for safety The prime responsibility for safety must rest with the person or organization responsible for facilities and activities that give rise to radiation risks. Authorization may be granted Prime responsibility is retained Responsibility for given activities in accordance with applicable safety objectives Responsibility for long term operation and wastes Reg'l WS on IAEA SSs and WENRA RLs 01-04 October 2012

Fundamental Safety Principles (cont.) Principle 2: Role of government An effective legal and governmental framework for safety, including an independent regulatory body, must be established and sustained. Framework to fulfil national responsibilities Arrangements to reduce radiation risks The RB has competence, resources; is effectively independent; informs and consults with interested parties; Reg'l WS on IAEA SSs and WENRA RLs 01-04 October 2012

Fundamental Safety Principles (cont.) Principle 3: Leadership and management for safety Effective leadership and management for safety must be established and sustained in organizations concerned with, and facilities and activities that give rise to, radiation risks. Leadership in safety matters at the highest level Safety culture integrated into the management system Accounting for human factor Graded approach to safety assessment Precursors to accident identified and analysed, feedback of OE Reg'l WS on IAEA SSs and WENRA RLs 01-04 October 2012

Fundamental Safety Principles (cont.) Principle 4: Justification of facilities and activities Facilities and activities that give rise to radiation risks must yield an overall benefit. Benefits must outweigh the radiation risk Risk/benefit decisions taken on state or regulatory body levels Justification of medical radiation exposure in the benefit of the patient Reg'l WS on IAEA SSs and WENRA RLs 01-04 October 2012

Fundamental Safety Principles (cont.) Principle 5: Optimization of protection Protection must be optimized to provide the highest level of safety that can reasonably be achieved To provide the highest level of safety that can reasonably be achieved (ALARA) For this all normal, abnormal and accident conditions must be assessed (in graded approach) Judgement of the relative significance of various factors Resources devoted and measures commensurate with the magnitude of the radiation risk Reg'l WS on IAEA SSs and WENRA RLs 01-04 October 2012

Fundamental Safety Principles (cont.) Principle 6: Limitation of risks to individuals Measures for controlling radiation risks must ensure that no individual bears an unacceptable risk of harm Doses and radiation risks controlled within specified limits Optimization of protection and limitation of doses go together Reg'l WS on IAEA SSs and WENRA RLs 01-04 October 2012

Fundamental Safety Principles (cont.) Principle 7: Protection of present and future generations People and the environment, present and future, must be protected against radiation risks Radiation risk across borders and for long time To protect the entire ecosystem Waste management without undue burden on the future generations Reg'l WS on IAEA SSs and WENRA RLs 01-04 October 2012

Fundamental Safety Principles (cont.) Principle 8: Prevention of accidents All practical efforts must be made to prevent and mitigate nuclear or radiation accidents Ensure that the likelihood of accident with harmful consequences be extremely low Defence in depth concept to prevent and mitigate Developing accident management procedures Reg'l WS on IAEA SSs and WENRA RLs 01-04 October 2012

Fundamental Safety Principles (cont.) Principle 9: Emergency preparedness and response Arrangements must be made for emergency preparedness and response for nuclear or radiation incidents Effective response at all levels Ensure that the risk is minor Mitigate consequences Proper arrangements in advance Consider all reasonably foreseeable events Reg'l WS on IAEA SSs and WENRA RLs 01-04 October 2012

Fundamental Safety Principles (cont.) Principle 10: Protective actions to reduce existing or unregulated radiation risks Protective actions to reduce existing or unregulated radiation risks must be justified and optimized Radiation risks in situations other than in regulated facilities and activities Protective actions are justified if they yield sufficient benefit to outweigh radiation risks Optimized to result the greatest reasonably achievable benefit Reg'l WS on IAEA SSs and WENRA RLs 01-04 October 2012

Review of compliance with SSs Integrated Regulatory Review Service (IRRS) to peer review the host country’s nuclear and radiation safety regulatory regime against the IAEA Safety Standards Modular review by international experts (15-20) Core regulatory activities Modules Mission report with Recommendations, Suggestions, Good Practices (findings) Reg'l WS on IAEA SSs and WENRA RLs 01-04 October 2012

What is an IRRS mission for? IRRS is meant to provide an opportunity for continuous improvement for the host RB through self-assessment and through peer review by an international expert team a review of the technical and policy issues relevant for the host country an opportunity to share and exchange experience and discuss issues with international experts a contribution to the harmonization of regulatory approaches among Member States Reg'l WS on IAEA SSs and WENRA RLs 01-04 October 2012

What is not an IRRS mission for? The IRRS missions are NOT meant to inspect regulatory or operator activity in the host country form any judgment on the host country regulatory regime or practice to provide comparison among Member States Therefore the number of findings is in no way a measure of the status of the regulatory body. Comparisons of such numbers between IRRS reports from different countries should not be attempted. Reg'l WS on IAEA SSs and WENRA RLs 01-04 October 2012

IRRS Missions to date IRRS Modules Reg'l WS on IAEA SSs and WENRA RLs 01-04 October 2012

IRRS mission sites (2006 – 2012) Reg'l WS on IAEA SSs and WENRA RLs 01-04 October 2012

Inviting a mission Regulatory bodies in the region are highly encouraged to invite IRRS missions Invitation is to be addressed to the DDG for Nuclear Safety and Security of IAEA Reg'l WS on IAEA SSs and WENRA RLs 01-04 October 2012

THANK YOU FOR YOUR ATTENTION Ivan Lux, IAEA NSNI RAS, i.lux@iaea.org Reg'l WS on IAEA SSs and WENRA RLs 01-04 October 2012