summary of results of the preparation consultants meeting …

Stewart Magruder

NRC/ USA

6th INPRO Dialogue Forum on Global Nuclear Energy Sustainability:

Licensing and Safety Issues for Small and Medium-sized

Nuclear Power Reactors (SMRs)

29 July - 2 August 2013

IAEA Headquarters, Vienna, Austria

Summary of Results of the Preparation

Consultants Meeting (CM)

Summary of Agenda

• Day 1 (17 December)

Opening and introductory presentation

MS presentations by technology holder countries on status of

deployment and licensing of SMRs


MS presentations on regulatory concerns and safety issues for

SMRs by technology user perspectives

Proposal of setting up an SMR Regulator’s Forum

Preparation of a Dialogue Forum


Preparation of a Dialogue Forum (continue)

Conclusion and recommendations

29 July-2 August 2013 6th IAEA INPRO Dialogue Forum on Licensing and Safety Issues 2

Participating Countries

Bangladesh

Canada

Finland

Indonesia

Kenya

Malaysia

Republic of Korea

Russian Federation

South Africa

Spain

United Kingdom

United States


Objectives of the CM

• Prepare a proposal to convene an INPRO Dialogue Forum (DF) in

2013 on licensing and regulatory aspects for SMRs.

Types of SMRs considered (power capacity, reactor types,

etc.)

Identification of detailed topics and issues

Forum structure and agenda

Organizational matters (dates, host country proposal, MSs to

be invited, funding options, etc.)

• Share experiences of SMR development, licensing and

deployment among MSs of TH and TU countries.

• Discuss possibility of setting up so-called an “International SMR

Regulator’s Forum” among MSs.

Proposal by the representative of USA: Its background and

necessity, objectives, roles and operation modal, etc.


Results achieved

• MS presentations to set context for discussion

• Presentations from IAEA staff

• Brainstorming on topics and format for DF

• Discussion of potential SMR Regulators Forum

• Produced draft prospectus for DF


Brainstorming Sessions

29 July-2 August 2013 6th IAEA INPRO Dialogue Forum on

Licensing and Safety Issues

6

Defence in Depth for SMR Designs 1 2 3 4 5 6 7 8 9 10 11 12 13 14 151. Technology proveness 10 5 10 10 9 6 8 6 10 1 3 10 10 10 10 7.9

2. Reliability of passive safety systems 10 5 10 10 8 10 10 6 10 10 10 10 9 5 8.8

3. Defence in depth 10 10 10 10 9 10 10 2 5 6 10 10 10 8.6

4. Flexibility in emergency planning requirements, accident response, application of graded approach (Cross-cutting with B and C) 8 10 5 10 9 8 8 2 10 10 10 10 10 10 10 8.7

5. Licensing (safety analyses) codes and methodologies (Cross-cutting with C) 9 8 5 9 7 10 7 7 10 10 3 10 10 10 3 7.9

6. Severe accident management 10 8 5 8 10 8 5 8 10 5 3 10 10 10 10 8.0

7. Siting issues for SMRs including transportable NPPs (Cross-cutting with B) 10 10 10 7 9 7 5 4 10 10 6 10 10 9 8 8.3

8. Safety goals 10 10 5 9 8 10 5 3 5 1 3 10 10 10 10 7.3

9. Non-conventional coolants 8 7 5 9 9 2 1 7 5 5 6 10 10 9 1 6.3

10. Long term maintenance free 8 8 5 8 10 2 1 8 10 10 6 10 10 10 1 7.1

11. New nuclear fuel issues (e.g. uranium nitride) (Cross-cutting with E) 5 7 5 8 9 8 1 7 1 10 3 10 9 8 1 6.1

12. Plant staffing (Cross-cutting with C and D) 7 7 5 6 10 7 10 9 10 10 6 10 9 10 7 8.2

13. R&D programmes (Cross-cutting with C) 5 7 5 9 7 7 10 6 5 5 3 10 10 3 6.6

14. Demonstration of innovative features (Cross-cutting with C) 10 8 5 9 5 7 5 7 10 10 10 7 9 10 10 8.1

15. Reactor stability 10 9 10 10 10 8 8 7 1 5 3 8 9 10 2 7.3

16. Reactor physics and thermal-hydraulics characteristics 10 7 5 9 5 8 6 6 1 5 3 10 10 10 2 6.5

17. Probabilistic Safety Assessment, reliability data (Cross-cutting with C) 8 7 5 7 6 9 5 6 10 5 6 10 10 8 1 6.9

18. Standardization of portion of design and safety classification (Cross-cutting with D) 7 7 5 8 7 9 10 3 10 5 10 7 10 7 10 7.7

19. Condition monitoring of plant’s equipment 10 6 5 8 7 8 10 8 10 5 6 7 10 8 1 7.3

20. Control room operation (human factor engineering, man-machine interface) 9 6 5 6 7 7 8 9 10 10 6 5 9 8 2 7.1

21. Instrumentations and controls, increased use of automation (Cross-cutting with C) 6 7 5 8 7 7 8 10 10 5 3 10 10 9 1 7.1

22. Incorporations of lessons-learned from the Fukushima accident 10 10 5 8 6 8 10 5 5 5 10 10 10 10 8 8.0

23. Maintainability 8 7 10 10 8 7 1 5 10 5 6 10 10 10 1 7.2

24. Environmental qualification of systems and components 8 7 5 10 5 7 6 5 10 5 3 8 9 9 1 6.5

25. Safety culture (Cross-cutting with E) 10 10 5 7 3 2 5 2 5 1 6 1 9 10 1 5.1

26. Source term calculation (Cross-cutting with B and C) 4 7 5 7 5 2 1 2 5 10 3 1 9 9 10 5.3

27. Spent fuel management (Cross-cutting with B and E) 9 10 5 9 7 8 1 4 1 1 3 10 10 8 1 5.8

28. Spent fuel pool cooling and monitoring (Cross-cutting with C) 7 8 10 9 7 7 1 4 1 1 3 10 10 8 1 5.8

29. Transportation of fuelled-NPPs (modules) fits A – E. 7 8 5 9 9 7 10 6 10 10 3 7 10 10 10 8.1

30. Constructability & Decommissioning 6 9 5 8 5 7 5 5 5 5 3 7 7 10 1 5.9

31. Quality Assurance (QA for long-lead items, timing & location). (Cross-cutting with D) 9 8 5 8 5 7 5 6 5 1 3 1 8 8 1 5.3

GRADING from PARTICIPATING MEMBER STATES

Follow up work

A. Defence in Depth for SMR Designs

1. Technology proveness

2. Reliability of passive safety systems

3. Defence in depth

4. Flexibility in emergency planning requirements, accident response, application of

graded approach (Cross-cutting with B and C)

5. Licensing (safety analyses) codes and methodologies (Cross-cutting with C)

6. Severe accident management

7. Siting issues for SMRs including transportable NPPs (Cross-cutting with B)

8. Safety goals

9. Non-conventional coolants

10. Long term maintenance free

11. New nuclear fuel issues (e.g. uranium nitride) (Cross-cutting with E)

12. Plant staffing (Cross-cutting with C and D)

13. R&D programmes (Cross-cutting with C)

14. Demonstration of innovative features (Cross-cutting with C)

15. Reactor stability

16. Reactor physics and thermal-hydraulics characteristics

17. Probabilistic Safety Assessment, reliability data (Cross-cutting with C)

18. Standardization of portion of design and safety classification (Cross-cutting with D)

19. Condition monitoring of plant’s equipment

20. Control room operation (human factor engineering, man-machine interface)

21. Instrumentations and controls, increased use of automation (Cross-cutting with C)

22. Incorporations of lessons-learned from the Fukushima accident

23. Maintainability

24. Environmental qualification of systems and components

25. Safety culture (Cross-cutting with E)

26. Source term calculation (Cross-cutting with B and C)

27. Spent fuel management (Cross-cutting with B and E)

28. Spent fuel pool cooling and monitoring (Cross-cutting with C)

29. Transportation of fuelled-NPPs (modules) fits A – E.

30. Constructability & Decommissioning

31. Quality Assurance (QA for long-lead items, timing & location). (Cross-cutting with D)

A. Site and Siting Considerations of SMRs

1. Flexibility in emergency planning requirements, accident response, application of

graded approach (Cross-cutting with A and C)

2. Siting issues for SMRs including transportable NPPs (Cross-cutting with A)

3. Site lacking in infrastructure (Cross-cutting with D)

4. Environmental impact (Cross-cutting with D and E)

5. Source term calculation (Cross-cutting with A and C)

6. Spent fuel management (Cross-cutting with A and E)

7. Transportation of fuelled-NPPs (modules) – fits A – E.

8. Safeguardability (Cross-cutting with D and E)


Category of Key Issues to be prioritized in the planned Dialogue Forum: •Defence in Depth for SMR Designs

•Site and Siting Considerations of SMRs •Application of Graded Approach in Regulatory and Licensing Process

•Legal and Regulatory Framework of SMRs

•Public participation in novel SMR concepts

Discussion of Draft Prospectus for DF

• Agreed on objectives and outputs

• Agreed on location and date

• Agreed on participants

• Drafted prospectus during the CM


summary of results of the preparation consultants meeting …

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