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!

V.Ranguelova@iaea.org

https://www-pub.iaea.org/books/IAEABooks/12286/Topical-Issues-in-

Nuclear-Installation-Safety49