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NSNI Priorities related to Advanced
Nuclear Plant Designs
Vesselina Ranguelova
Head, Safety Assessment Section
Division of Nuclear Installation Safety
Department of Nuclear Safety and Security
1
14th GIF-IAEA Interface Meeting, VIC, 8 July 2020
Outline
• Priorities 2020 and beyond
• Update of the NSNI Presentation for IAEA-
GIF 2019 meeting
– IAEA Safety Standards
– Small and Medium or Modular Reactors
(SMRs)
– New Design Safety Principles: Priorities
• Technical Safety
Review (TSR)
Services
• Conclusion
NSNI Priorities on Advanced
NPP: 2020 and beyond
• SMR Regulator’s Forum
• Review of current Safety Standards framework
• Launching SMR Technical Safety Reviews – Design/ Safety Assessment
• Application of SEED (Site and External Event Design) Safety Review
Services to innovative reactors
• Develop new safety framework for implementation of risk informed and
performance based methods considering site-installation interactions
• Preparing next Conference on topical Issues in Nuclear Safety:
Progressing from Evolutionary to Innovative Reactor Designs, 18-21 Oct
22
• Cooperation with NEA & GIF
• Holistic Technology Neutral Safety and Licensing Framework: safety goals-setting hierarchy of regulations and requirements
• TECDOC “Approach and Methodology for the Development of Regulatory Safety Requirements for the Design of Small Modular Reactors” – under preparation
• TECDOC “Framework for the application of site safety requirements considering the safety features of nuclear installations ” – under preparation
• Applicability of IAEA SS for siting and design of SMRs and Innovative Technologies:
– TECDOC on Applicability of Design Safety Requirements SSR-2/1 to SMRs ( under publication)
– TECDOC on Design Robustness of nuclear installations against external hazards (under publication)
– Review of specific systems design guides
• Safety & Security& Safeguards by design – is it possible?
• Launching SMR Technical Safety Reviews services – Review of Innovative Designs
• Application of SEED (Site and External Event Design) Safety Review Services to innovative reactors
• Cooperation with NEA WGRISK, IAGE, WGAMA, WGRNR,
GIF RSWG on application of IAEA safety standards to
Innovative technologies
Safety of Innovative Reactors : IAEA
Safety Standards
Safety of SMRs : SMR Regulators’ Forum
Members
• Canada
• China
• Finland
• France
• Republic of Korea
• Russian Federation
• Kingdom of Saudi Arabia
• United Kingdom
• United States of America
Observers
Euratom
OECD / NEA
Pilot Phase (2015-2017) with 3 WGs:
graded approach; defence in depth and
emergency planning arrangements
Phase 2 (2018-2020) with 3 new WGs:
licensing / design safety and safety analysis /
manufacturing, commissioning and operation
Phase 3 – beyond 2020: mutual recognition
of regulators’ assessment/Security by
design, interface with safety/organizational
stakeholders’ capabilities
Next SMR Forum meeting: 9-13 November
2020
Share SMR regulatory knowledge and
experience among members and other
stakeholders to facilitate international
cooperation among regulators performing
SMR-related assessments
Update of the NSNI
Presentation for IAEA-GIF
2019 meeting
Safety Standards Hierarchy
Global Reference
Point for a High Level
of Nuclear Safety
Design Safety
8
Safety objectives and
safety principles
Functional conditions
required for safety
Guidance on how to
fulfil the requirements
Safety Assessment
9
Safety objectives and
safety principles
Functional conditions
required for safety
Guidance on how to
fulfil the requirements
Involvement of Stakeholders
Participation by the different stakeholders (for example,
regulators, operators, designer and TSOs) during the
drafting and review phase is a long established practice10
IAEA Safety Standards: Applicability
• New Nuclear Power Plants
– Primarily to NPPs with water cooled reactors (land
based stationary)
• Nuclear Power Plants in operation
– It might not be practicable to entirely apply
– Expected: comparison made against current standards,
for example as part of the periodic safety review
• Other reactor types
– With judgement to determine how the requirements
have to be considered in developing the design
11
Emerging Topics
• To provide assistance to Member States in
areas such as SMRs, Floating Reactor
Technologies
– Conduct of projects to compile available safety
approaches and current understanding in the context
of IAEA Safety Standards
– Proposal and development of IAEA TECDOCs and
Safety Reports to reflect converging understanding
among stakeholders
– Proposal and development of IAEA Safety Standards
when necessary and if adequate knowledge in
Member States is available12
SMRs – Background
• More than 50 different designs for SMRs,
transportable and floating reactors in
development
• Number of Member States interested in SMRs
has increased over the past few years
• Convention on Nuclear Safety applies to any
civil land-based NPP, including SMRs
• Transport of radioactive material by sea is
governed by the International Convention for the
Safety of Life at Sea (SOLAS) and the
International Maritime Organization (IMO)13
SMRs – Claims
• Innovations
– Integral design / reduced number of DB initiators
– Largely inherently safe
– Passive safety systems / natural circulation
– Limited / no operator action in response to accident
scenarios (neither immediate nor delayed actions)
• Size
– Decreased radioactive inventory & site footprint
– Multi-module scalability – fit to capacity needs
– Factory fabrication – easy to deploy to remote sites
– Decreased on-site construction time14
SMRs – Challenges
• First-of-Kind for large number of different
designs
• Unproven technology
– Comprehensive analyses, simulations, and testing
needed to close knowledge gaps
• New design philosophy
• New materials
• New strategies for safety systems and safety features
• Lack of operational experience
• Regulatory processes
– Rules & Regulation, Safety Standards need to be
adapted, as appropriate 15
IAEA Documents
AGENCY CONSIDERS
• Development of Safety and Regulatory
Framework for New and Innovative
Technologies
AND PREPARES
• Proposal and development of new documents
16
• TECDOC on Applicability of IAEA Design Safety
Requirements to SMR Technologies Intended for
Near-term Deployment (in publication)
• 82 design safety requirements
30
8
52
74
0 10 20 30 40 50 60 70 80 90
HTGR
LWR
Changes or interpretation Applicable as is
5
Design safety requirements
17
5
Areas for potential
additional requirements
Applicability of SSR-2/1 (Rev1) to SMRs
• Inquiry phase: 19 organizations (10 Member States)
– Areva, BATAN, BWXT, CGNPC, CNEA, CNNC, Holtec,
INET, IRSN, JAEA, KAERI, NPIC, NuScale, STL,
Terrestrial Energy, USNC, Rolls-Royce, Westinghouse, X-
Energy
– SMR Regulators’ Forum representatives
• TECDOC development: Mainly CNEA, CNSC, NNSA,
IPPE, NPIC, EDF, JAEA, SEC-NRS, ONR, USNRC,
NuScale
• Two SMR technologies covered
– Light Water Reactors
– High Temperature Gas-cooled Reactors
18
IAEA TECDOC 1366
published in 2003
IAEA TECDOC 1570
published in 2007
19
Development of Regulatory Safety
Requirements for SMRs
• TECDOC on Approach and Methodology for the Development of
Regulatory Safety Requirements for the Design of Small Modular
Reactors (in preparation)
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
• Insights from TECDOC on Applicability of SSR-2/1 (Rev1) to SMRs
20
Requirements
(General)
Requirements
(Specific)
Recommendations
for the Design
Safety
Requirements
Safety Guides
DESIGN AND LICENSING
RULES FOR CURRENT
WATER REACTORS
Requirements
(General)
Requirements
(Specific)
Recommendations
for the Design
DESIGN AND LICENSING
RULES FOR A GIVEN
INNOVATIVE DESIGN
NEW APPROACH
- MORE “RISK” INFORMED
- LESS PRESCRIPTIVE
MAIN PILLARS (New Approach)
• SAFETY GOAL
•
• DEFENCE IN DEPTH (Generalized)
which includes probabilistic
MAIN PILLARS
• QUANTITATIVE SAFETY GOAL
• FUNDAMENTAL SAFETY FUNCTIONS
• DEFENCE IN DEPTH (Enhanced)
1) Understanding:
- the rationale behind each
requirement
- the contribution of each
requirement to defence in
depth
-whether the requirement
is technology-neutral or
technology-dependent
2) Application of an
Objective-ProvisionsTree
CRITICAL REVIEW
MAIN PILLARS
• SAFETY OBJECTIVES
• FUNDAMENTAL SAFETY FUNCTIONS
• DEFENCE IN DEPTH
•
•
•
Proposed Approach
21
Graded Approach
• Development of IAEA TECDOC
Application of Graded Approach in Regulating
Nuclear Power Plants, Research Reactors and
Fuel Cycle Facilities
• Covering all regulatory functions and types of
nuclear installations
• Documenting Member States’ practices &
possible generic methodologies22
Scope
• Regulatory Functions
– Framework: Development of regulations and guides
Safety margins
– Authorization of facilities and activities
– Review and assessment of facilities and activities
– Inspection of facilities and activities
– Enforcement
– Communication and consultation with interested
parties
23
Safety Report on safety analysis and
assessment of SMRs
• Application of IAEA safety standards on safety
analysis to SMRs– Consideration of applicable safety requirements
– Defence in depth
– Deterministic Safety Analysis (SSG-2 (Rev. 1))
– Probabilistic Safety Assessment (SSG-3 for PSA Level 1
and SSG-4 for PSA Level 2)
– Considerations on safety classification
• SMR technologies– General and specific considerations
• Technical Meeting held in November 2019– Draft safety report in preparation
24
CRP on EPZ for SMR Deployment
• CRP I3 1029: Development of Approaches,
Methodologies and Criteria for Determining the
Technical Basis for Emergency Planning Zone
for Small Modular Reactor Deployment
• Overall Expected Outcome
– Definition of consistent approaches, methodologies,
criteria to determine need for off-site EPR, including
EPZ/D size, for SMR deployment
– Includes identification of technology specific factors for
different SMRs that may influence
• source term and timing of release
• possible sequences to be considered for emergency classification
system25
CRP Participating Countries
• Under Research
Agreement:
– China
– United Kingdom
– Japan
– Finland
– Netherlands (representing
EC through JRC-Petten)
– Pakistan
– Saudi Arabia (with Republic
of Korea)
– Canada
– USA
26
• Under Research
Contract:
– Indonesia
– Tunisia
– Israel
– China
– Argentina
Current Status
• RCM-1, Vienna, May 2018; main outcome
– Presentation of objectives and scope of the planned research to be conducted by each participant entity
– Definition of Table of Contents of the CRP Report
• RCM-2, Beijing, China, 27-31 May 2019
– Discussion and exchange of progress made by participants and way forward
• RCM-3 dates scheduled to take place in August 2020.
• Project to be completed by February 2021. Timeline could need to be reconsidered owing to pandemics. To be discussed in RCM-3
27
SMR Regulators’ Forum
Members
• Canada
• China
• Finland
• France
• Republic of Korea
• Russian Federation
• Kingdom of Saudi Arabia
• United Kingdom
• United States of America
Observers
• European Union
• OECD / NEA
28
Objectives
• Share SMR regulatory knowledge and
experience among members and other
stakeholders to
– Facilitate efficient, robust and thorough regulatory
decisions
– Encourage enhanced nuclear safety
– Facilitate international cooperation among regulators
performing SMR-related assessments
• Identify / discuss common safety issues that may
challenge regulatory reviews and, if possible,
recommend common approaches for resolution29
Procedure
• Pilot Phase (2015-2017) with 3 WGs: graded approach; defence in
depth and emergency planning arrangements
• Phase 2 (2018-2020) with 3 new WGs: licensing / design safety and
safety analysis / manufacturing, commissioning and operation
• Phase 3 – beyond 2020: mutual recognition of regulators’
assessment/Security by design, interface with safety/organizational
stakeholders’ capabilities
• Next SMR Forum meeting : 9-13 November 2020
• Self funded; IAEA’s secretariat to facilitate meeting
• Several workshops held for embarking countries to share information
and experience on nuclear regulation and licensing approaches
30
New Design Safety Principles
31
NO AOO DBAs
(safety systems)
Operational States Accident Conditions
Design BasisBeyond Design Basis
(Accident Management)
Severe Accidents
(core melting)
DECs
NO AOODBAs
(safety systems)
Operational States Accident Conditions
Plant Design Envelope
SSR-2/1, 2012
BDBA
Earlier Concept
Safety features for
sequences without
significant fuel
degradation
Safety features for
accident with core
melting
Conditions
practically
eliminated
Priorities (1/3)
• Finalise & publish revision of 4 safety assessment
and design safety guides, including DS 508 on:
Assessment of the Application of General
Requirements for Design of Nuclear Power Plants
• Safety reports – Implementation of Accident Management Programmes in Nuclear
Power Plants
– Human Reliability Analysis for Nuclear Installations
– Safety Aspects of Using Smart Digital Devices in Nuclear Safety
Systems
– Safety Assessment and Safety Analysis for Small Modular Reactors
(SMRs)
32
Priorities (2/3)
• Technical documents in preparation
– Commercial NPPs• Level 1 Probabilistic Safety Assessment for Nuclear Power Plants with Candu-
Type reactors
• Experience in applying the new IAEA Design Safety Principles to new Nuclear
Power Plants
• Current Knowledge and Path Forward for the Licensing of Advanced Nuclear
Fuels for LWRs
• Current Approaches in Member States to analysis of design extension conditions
for new nuclear power plants
– SMRs and other innovative technologies• Applicability of Design Safety Requirements to Small Modular Reactor (SMR)
Technologies Intended for Near-term Deployment (under publication)
• Approach and Methodology for the Development of Regulatory Safety
Requirements for the Design of Small Modular Reactors
• Application of NPP design safety guides to SMR technologies
33
Priorities (3/3)
• Technical documents– Use of Safety Analysis Methods to Support Nuclear Security
Considerations and Decision Making.
– Accident Management for Advanced Reactors.
• Conduct projects and develop reports – Use of Passive Safety Features in Nuclear Power Plant Designs and
their Safety Assessment.
– Development of Methodology for Aggregation of Various Risk
Contributors for Nuclear Facilities.
– Multiunit PSA Methodology ( under publication).
34
Documents recently published (1/2)
• Safety Guides– Design of the Reactor Coolant System and Associated Systems in
Nuclear Power Plants – SSG-56.
– Design of Reactor Containment and Associated Systems for Nuclear
Power Plants – SSG-53.
– Accident Management Programmes for Nuclear Power Plants –
SSG-54.
– Design of the Reactor Core for Nuclear Power Plants – SSG-52.
– Human Factors Engineering in Nuclear Power Plants – SSG-51.
– Deterministic Safety Analysis for Nuclear Power Plants – SSG 2
(Rev.1).
- Format and Content of Safety Analysis Reports for NPPs – SSG-61
35
Documents recently published (2/2)
• TECDOCs– In-Vessel Melt Retention and Ex-Vessel Corium Cooling – Summary
of a Technical Meeting – TECDOC-1906.
– Considerations on Performing Integrated Risk Informed Decision
making – TECDOC 1909.
– Experiences in Implementing Safety Improvements at Existing
Nuclear Power Plants - TECDOC 1894.
– Hierarchical Structure of Safety Goals for Nuclear Installations –
TECDOC 1874.
• Service Series– TECHNICAL SAFETY REVIEW (TSR) SERVICE GUIDELINES –
SVS-41.
36
Major Meetings (1/3)
• (Virtual Event) Technical Meeting on Accident Management
for Advanced Reactors, 31 August -04 September 2020.
• (Virtual Event) Technical Meeting on the Application of the
New IAEA Principles for Design Safety of New Nuclear
Power Plants, 07-11 September 2020.
• Technical Meeting on the Enhancement of Methods,
Approaches and Tools for Development and Application of
Probabilistic Safety Assessments, 29 September - 02
October 2020, Vienna, Austria.
• Technical Meeting on Experience in Application of Level 2
Probabilistic Safety Assessment (PSA) for NPPs, 04-07 May
2021, Vienna, Austria.
37
Major Meetings (2/3)
• Technical Meeting on the Evaluation of Defence in Depth
in the Framework of Periodic Safety Review Programme,
18-21 May 2021, Ceske Budejovice, Czech Republic.
• Technical Meeting on Use of Probabilistic Safety
Assessment for Security Purposes, 10-14 October 2021,
Vienna, Austria.
• Technical Meeting on the Applicability of IAEA Safety
Standards and Status of Knowledge for the Licensing of
Advanced Fuels for Light Water Reactors, 18-22 October
2021, Vienna, Austria.
• Technical Meeting on the Utilization of the IAEA Safety
Guidance for Nuclear Power Plants Design in Small
Modular Reactor Technologies, 18-22 October 2021,
Vienna, Austria.38
Major Meetings (3/3)
• Technical Meeting on Experience and Feedback from
Technical Safety Review (TSR) Peer Reviews, 22-26
October 2021, Vienna, Austria.
• Training Workshop on the Development of Severe Accident
Management Guidelines Using the IAEA's Severe Accident
Management Guideline Development Toolkit, 19-23 October
2020 & 06-10 December 2021, Vienna, Austria.
• Joint IAEA-NEA Workshop on the Current Implementation
Status of Measures to Manage Open Phase Conditions in
Electrical Power Systems of Nuclear Power Plants, 27-30
October 2020, Vienna, Austria.
• Workshop on Safety Assessment for Embarking Countries,
14-18 June 2020, location TBD.
39
Upcoming International Conferences
• International Conference on One Decade of Strengthening
Nuclear Safety After The Fukushima Daiichi Accident
– Date: 22-26 February 2021
– Location: Vienna, Austria
• International Conference on Topical Issues in Nuclear
Installation Safety: Progressing from Evolutionary to
Innovative Reactor Designs
– Date: 18-22 October 2022
– Location: Vienna
40
Future activities – Safety/Security interface
• IAEA General Conference on safety-security interface:
– GC(63)/RES/7. 6) Requests the Secretariat, while recognizing the
distinction between nuclear safety and nuclear security, to continue
facilitating in close cooperation with Member States a coordination
process to address their interfaces in a timely manner, and
encourages the Agency to develop safety and security
publications, ensure consistency and to foster culture accordingly;
41
• Developing a Technical Report on the
Use of Safety Analysis Methods for
Nuclear Security Considerations and
Decision Making
– Scope includes: PSA and DSA, potential SA
applications for nuclear security (VAI, DBT,
etc.)
Technical Safety Review (TSR)
The TSR Peer Reviews
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.
43
TSR
Review Services Conducted
(1/2) 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: 6 – 9 months
Technical Team: Lead by IAEA
staff
# experts: dependent on scope45
* total number of services to date
North America 1
Africa 2
Europe 79
Latin America and
the Caribbean 2
Asia and the
Pacific 29113 TSR
Services*
46
TSR Ongoing and Inquired
Number Subject AreaMember
StateStatus
1 Periodic Safety Review (PSR)Czech
RepublicCompleted Q1 2018
2 Design Safety (DS) Bangladesh Completed Q2 2018
3 Safety Requirements (SR) Saudi Arabia Completed Q1 2019
4 Safety Requirements (SR) Egypt Completed Q3 2019
5 Safety Requirements (SR) Nigeria Completed Q1 2020
6 Design Safety (DS) HungaryRequest Follow-up Meeting
(Q1 2020)
7 Design Safety (DS) Turkey Formal request received
8 Probabilistic Safety Assessment (PSA) Turkey Formal request received
9 Probabilistic Safety Assessment (PSA) Mexico Formal request received
10 Generic Reactor Safety (GRS) UK Interest expressed (meeting)
11 Accident Management (AM) Pakistan Interest expressed (meeting)
12 Safety Requirements (SR) Saudi Arabia Interest expressed (meeting)
13 Generic Reactor Safety (GRS) France/Japan Interest expressed (email)
Conclusion (1/2)
• Focused attention to encourage and provide
assistance to Member States in the application
of the IAEA safety standards
– Complete revision of safety guides
– Development of associated technical documents
and safety reports
– Continuation of CRP on Emergency Planning Zone
for Small Modular Reactor Deployment
– Provision of tailored workshops, lectures and
training
– Collaboration in activities related to technology
development and deployment47
Conclusion (2/2)
• Implementation of Technical Safety Review
(TSR) services
• Particular actions ongoing and planned to
support design safety considerations for new
technologies
• GIF participation in IAEA activities very
welcome to effectively feed the development
and/or necessary launch of IAEA documents
• IAEA pleased to cooperate in defined areas,
such as reviewing consistency of GIF
documents with IAEA safety standards48
Thank you for your kind attention!
https://www-pub.iaea.org/books/IAEABooks/12286/Topical-Issues-in-
Nuclear-Installation-Safety49