NSNI Priorities related to Advanced Nuclear Designs

Transcription

1 NSNI Priorities related to Advanced Nuclear Designs Cornelia Spitzer Section Head, Safety Assessment Section Division of Nuclear Installation Safety Department of Nuclear Safety and Security 12 th GIF-IAEA Interface Meeting,

2 Outline IAEA Safety Standards Technology-Neutral Safety Approach SMRs Study on the applicability of Design Safety Requirements for NPPs to SMRs TC Project RER2014 (Europe) SMR Regulators Forum Expanded design safety principles Technical Safety Review (TSR) 2

3 Safety Standards Hierarchy Global Reference Point for a High Level of Nuclear Safety 3

4 Safety Assessment Safety objectives and safety principles Functional conditions required for safety Guidance on how to fulfil the requirements Revised after the Fukushima Daiichi accident Main changes Margins to withstand external events and to avoid cliff-edge effects Multiple facilities / activities at one site Cases where resources are shared Human factors in accident conditions 4

5 Relevant Safety Guides Safety objectives and safety principles Functional conditions required for safety Guidance on how to fulfil the requirements 5

6 Design Safety Safety objectives and safety principles Functional conditions required for safety Guidance on how to fulfil the requirements To be implemented by the designer to fulfill the fundamental safety functions with the appropriate level of defence in depth To be used by the reviewer of the design (e.g. by the Regulatory Body) to assess the safety of the design 6

7 Relevant Safety Guides Safety objectives and safety principles Functional conditions required for safety Guidance on how to fulfil the requirements 7

8 Applicability Primarily applicable to new NPPs with water cooled reactors (land based, stationary) It might not be practicable to apply all the requirements to existing NPPs, already in operation Other reactor types: applicable with judgement, to determine how the requirements have to be considered in the design 8

9 Technical Documents IAEA TECDOC 1366 published in 2003 IAEA TECDOC 1570 published in

10 Key Issues Addressed Suitability of classical safety approach to innovative reactor designs Logical Framework to develop national safety requirements More risk-informed, less prescriptive Based on safety requirements established for LWRs Systematic evaluation of DiD implementation Systematic, logical and auditable design process Review of consistency with existing national safety framework 10

11 Proposed Approach DESIGN AND LICENSING RULES FOR CURRENT WATER REACTORS DESIGN AND LICENSING RULES FOR A GIVEN INNOVATIVE DESIGN MAIN PILLARS SAFETY OBJECTIVES FUNDAMENTAL SAFETY FUNCTIONS DEFENCE IN DEPTH NEW APPROACH - MORE RISK INFORMED - LESS PRESCRIPTIVE MAIN PILLARS MAIN PILLARS (New Approach) SAFETY QUANTITATIVE GOAL SAFETY GOAL FUNDAMENTAL SAFETY FUNCTIONS DEFENCE IN IN DEPTH (Enhanced) (Generalized) which includes probabilistic Technology neutral CRITICAL REVIEW Safety Requirements Requirements (General) Requirements (General) Requirements (Specific) Requirements (Specific) 1) Understanding: Safety Guides Recommendations for the Design -the rationale behind each requirement -the contribution of each requirement to defence in depth -whether the requirement is technology-neutral or technology-dependent Recommendations for the Design Technology dependent 2) Application of an Objective-ProvisionsTree 11

12 Study on Applicability (1/2) Designer s review of current practices on the applicability of Design Safety Requirements (SSR-2/1 Rev.1) to SMR technologies Light Water Reactor High Temperature Gas-Cooled Reactor Outcome will be considered on Preparation of a Technical Document Future IAEA Safety Standard review processes 12

13 Study on Applicability (2/2) Participation of representatives of 14 organizations from 8 Member States BWXT CGNPC CNEA CNNC Holtec IRSN INET JAEA KAERI NuScale Steenkampshraal Thorium Limited Rolls-Royce Westinghouse X-Energy SMR Regulators Forum representatives 13

14 TC Project RER2014 (Europe) Facilitating Capacity Building for SMRs Technology Developments Safety Assessment Licensing Utilization Several European countries recipient of TC Program Four workshops planned with respect to Nuclear Safety 14

15 SMR Regulators Forum Argentina Canada China Finland France Korea Russia Saudi Arabia United Kingdom United States 15

16 Objectives Share regulatory experience amongst forum members preparing to license SMRs Capture good practices and methods Interact with key stakeholders Provide inputs for consideration of IAEA in future activities 16

17 Forum s Activities Pilot Project: March 2015 to May 2017 Steering Committee and three Topical Working Groups (WGs): Graded Approach; DiD; Emergency Planning Zone Size Current phase New WGs: Licensing Issues; Design and Safety Analysis; Manufacturing, Commissioning and Operation First meeting held March

18 Priorities on SMRs Develop a project report on the Applicability of the Design Safety Requirements for NPPs to SMRs Preparation of an IAEA Technical Document on Safety Approaches to SMRs Implementation of regional and national workshops on SMRs according to TC Program Collaboration in activities related to SMR technology development and deployment 18

19 New Design Safety Principles Earlier Concept Operational States Design Basis Accident Conditions Beyond Design Basis (Accident Management) NO AOO DBAs (safety systems) BDBA Severe Accidents (core melting) SSR-2/1, 2012 Plant Design Envelope Operational States NO AOO DBAs (safety systems) Accident Conditions Safety features for sequences without significant fuel degradation DECs Safety features for accident with core melting Conditions practically eliminated 19

20 Priorities (1/2) Development of new 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 20

21 Priorities (2/2) 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 21

22 Technical Safety Review (TSR) The TSR incorporates IAEA safety assessment and design safety technical review services to address the needs of Member States at most stages of development and implementation of the nuclear power programme. TSR 22

23 Objectives Scope Independent evaluation of the plant safety assessment and design safety documentation Recommendations for enhancements to safety Assistance in following topics Safety of operating and new nuclear plant designs Safety Analysis Report Safety Requirements developed by regulatory authorities Safety assessments, also related to plant modifications Action taken to address emerging safety issues Periodic Safety Reviews 23

24 TSR Services Conducted Subject areas Design Safety (DS) Generic Reactor Safety (GRS) Safety Requirements (SR) Probabilistic Safety Assessment (PSA) Accident Management (AM) Periodic Safety Review (PSR) Audience: Regulatory Bodies, TSOs, Owners/Operators Duration: 3 9 months Technical Team: Lead by IAEA staff # experts: dependent on scope North America 1 Europe TSR Services* Asia and the Pacific 28 Africa 0 Latin America and the Caribbean 2 * total number of services to date 24

25 Prospect NSNI priorities Focused attention to encourage and provide assistance to Member States in the application of the IAEA safety standards Finalise revision of safety guides Development of associated technical documents Provision of tailored workshops, lectures and training Implementation of Technical Safety Review (TSR) services Particular actions ongoing and planned to support design safety considerations for new technologies GIF participation very welcome 25

26 Thank you for your kind attention! 26