Implementation of Vienna Declaration on Nuclear Safety - IAEA Activities

IAEA Activities Related to Implementation of the Provisions of the Vienna Declaration on Nuclear Safety Division of Nuclear Installation Safety Department of Nuclear Safety and Security IAEA 1

Background: 7th Review Meeting of CNS Summary Report of the 7th Review Meeting Report of the President of the Review Meeting, Annex III Paragraph 24: .The Contracting Parties further noted that the Agency continues to reflect the principles of the CNS in its relevant documentsand requested the Secretariat of the Agency to brief about these on the next Organisational Meeting.. 2

Background: Vienna Declaration Objective: Principles for the implementation of the objective of the Convention on Nuclear Safety to prevent accidents and mitigate radiological consequences Adopted by the Contracting Parties (CPs) to the CNS at a Diplomatic Conference held on 9.02.2015 at the IAEA Headquarters 3

Background: Principles of Vienna Declaration New nuclear power plants are to be designed, sited, and constructed, consistent with the objective of preventing accidents in the commissioning and operation and, , mitigating possible releases of radionuclides causing long-term off site contamination and avoiding early radioactive releases or radioactive releases large enough to require long-term protective measures and actions. Comprehensive and systematic safety assessments are to be carried out periodically and regularly for existing installations throughout their lifetime in order to identify safety improvements that are oriented to meet the above objective. Reasonably practicable or achievable safety improvements are to be implemented in a timely manner. National requirements and regulations for addressing this objective throughout the lifetime of nuclear power plants are to take into account the relevant IAEA Safety Standards and, as appropriate, other good practices as identified inter alia in the Review Meetings of the CNS. 4

IAEA Roles and Responsibilities Legal Instruments Provision of secretarial support to the Convention on Nuclear Safety (CNS) within its mandate and responsibilities, as necessary Safety Standards Support the CPs within its statutory mandate in relation to nuclear safety and the CNS consideration of MSs needs (GC resolution) development int l Safety Standards and supporting their implementation associated technical documents organisation of technical meetings 5

Safety Standards VDNS (1/2) Commission on Safety Standards confirmed: .technical elements of the VDNS already well reflected in the relevant IAEA Safety Requirements IAEA Safety Guides provide associated recommendations (under revision/well advanced) IAEA TECDOCs provide further support IAEA Safety Review Services and Peer Review Missions provide for implementation of IAEA Safety Standards VDNS principles implicitly addressed 6

Safety Standards VDNS (2/2) Revised IAEA Safety Standards for design primarily applicable to new NPPs as far as reasonably practicable or achievable, also applicable to safety re-evaluation of existing NPPs Comprehensive and systematic safety assessments to be carried out for existing installations throughout their lifetime addressed in the context of the Fundamental Safety Principles (specifically no 3.16) further elaborated in IAEA Safety Guide on Periodic Safety Reviews 7

New Design Safety Principles Earlier Concept Beyond Design Basis (Accident Management) Design Basis Operational States Accident Conditions Severe Accidents (core melting) DBAs BDBA NO AOO (safety systems) SSR-2/1, 2012 Plant Design Envelope Operational States AccidentConditions Conditions practically eliminated DECs DBAs Safety features for sequences without significant fuel degradation NO AOO Safety features for accident with core melting (safety systems) 8

Updated Safety Demonstration Plant Design Envelope Operational States AccidentConditions Large or Early Releases DECs DBAs Safety features for sequences without significant fuel degradation NO AOO Safety features for accident with core melting (safety systems) Large Fast Reactivity Excursion Component Failure HPME MCCI Operational Criteria Acceptance Criteria H2 Detonation Cont'ment Bypass Acceptance Criteria Acceptance Criteria Acceptance criteria < large & < early release 9

Resolutions of 61st General Conference Resolution 52 Recalls the outcomes of the 7th Review Meeting of the Contracting Parties to the CNS, further recalls the adoption by consensus of the Vienna Declaration on Nuclear Safety at the CNS Diplomatic Conference of February 2015, and encourages all Member States to contribute to the realization of its principles including through the implementation of the relevant provisions of this Resolution. Resolution 53 Requests the Secretariat, in consultation with Member States, to facilitate information exchange between interested Member States, including through a Technical Meeting (TM), to share experience on implementing safety improvements at existing nuclear power plants. 10

Information Exchange 2017 IAEA International Conference Topical Issues in Nuclear Installation Safety: Safety Demonstration of Advanced Water Cooled Nuclear Power Plants, 6 9 June 2017, Vienna Key output Member States to share experiences and practical approaches on application of new design safety principles and evaluation of new design features safety improvements for existing NPPs IAEA to provide fora information exchange; and to assist Member States in application of Safety Standards Organisation of a Technical Meeting (see GC 53) Share Experience on Implementing Safety Improvements at Existing Nuclear Power Plants; IAEA Headquarters, Vienna, Austria,11 14 June 2018 11

IAEA Priorities Development of Safety Guide Assessment of the Application of General Requirements for Design of Nuclear Power Plants Development of TECDOCs Developing Design Criteria for Diverse Actuation Systems for Nuclear Power Plants Current Approaches in Member States to the Analysis of Design Extension Conditions for New Nuclear Power Plants Experiences on implementing safety improvements at existing nuclear power plants: approaches and strategies aiming at minimising radioactive releases in the event of a nuclear accident (2nd CS: IAEA Headquarters, Vienna, Austria, 10 13 April 2018) Development of Reports In-Vessel Melt Retention and Ex-Vessel Corium Cooling Summary of a Technical Meeting Use of Passive Safety Features in Nuclear Power Plant Designs and their Safety Assessment 12

Thank you for your kind attention! G.Rzentkowski@iaea.org 13