1. HARMONIZATION OF CODES AND STANDARDS
Session Name: Pumza Damba
Speaker Details: Functional Coordinator : Design Safety

2. 2nd NUCLEAR REGULATORY INFORMATION CONFERENCE
Presentation Outline
Introduction to CSWG
CSWG Harmonization Work
CSWG Harmonization Future Work
NNR and CSWG Work

3. Introduction to MDEP CSWG
2nd NUCLEAR REGULATORY INFORMATION CONFERENCE
Introduction to MDEP CSWG
MDEP established in Multinationa Design Evaluation Programme
Multinational initiative to leverage resources and knowledge of the national regulatory authorities tasked with the review of new nuclear power reactor designs.
Currently 16 countries participate in MDEP, which includes 6 design-specific working groups and 2 issue-specific working groups.
The NEA facilitates MDEP activities by providing technical secretariat services for the programme.
The MDEP Policy Group (PG) and the Steering Technical Committee (STC) oversee the programme.

4. Introduction to CSWG MDEP
2nd NUCLEAR REGULATORY INFORMATION CONFERENCE
Introduction to CSWG MDEP

5. Introduction to CSWG MDEP
2nd NUCLEAR REGULATORY INFORMATION CONFERENCE
Introduction to CSWG MDEP
The MDEP CSWG in existence since March 2008.
The CSWG’s primary, long-term goal is
To achieve international harmonisation of codes and standards for pressure-boundary components in nuclear power plants that are important to reactor safety.
By understanding the extent of similarities and differences

6. Introduction to CSWG MDEP
2nd NUCLEAR REGULATORY INFORMATION CONFERENCE
Introduction to CSWG MDEP
Harmonisation = Convergence + Reconciliation, where:
Convergence means establishing the same or equivalent code requirements in order to reduce the areas identified as “different,” and
Reconciliation means to accept differences in code requirements by justifying their acceptability

7. CSWG Harmonization Work
2nd NUCLEAR REGULATORY INFORMATION CONFERENCE
CSWG Harmonization Work
CSWG 1st Project - Class 1 Nuclear Power Plant Component Code Comparison -2008
SDO’s performed a comparison of own pressure-boundary codes and standards to identify the extent of similarities and differences in code requirements and the reasons for their differences.
SDO’s involved
ASME
AFCEN
CSA
JSME
KEA
NIKIET

8. CSWG Harmonization Work
2nd NUCLEAR REGULATORY INFORMATION CONFERENCE
CSWG Harmonization Work
Other Stakeholders
WNA – CORDEL
Nuclear industry recognised that standard designs will reduce the overall engineering and construction time vs non-standardised approach used in the past construction of NPP’s
Works in parallel and close interaction with the MDEP CSWG
SDOs’ Establishment of a Code-Convergence Board
The role of the Board is to work with stakeholders, (e.g., CORDEL, vendors, licensees, regulators, etc.) to identify potential areas of convergence.

9. CSWG Harmonization Work
2nd NUCLEAR REGULATORY INFORMATION CONFERENCE
CSWG Harmonization Work
Code Comparison Project Results

10. CSWG Harmonization Work
2nd NUCLEAR REGULATORY INFORMATION CONFERENCE
CSWG Harmonization Work
Code Comparison Project Results

11. CSWG Harmonization Work
2nd NUCLEAR REGULATORY INFORMATION CONFERENCE
CSWG Harmonization Work
MDEP Generic Common Position CP-CSWG-01
CSWG prepared a set of common positions for harmonising codes and standards used in the design and construction of pressure-boundary components in nuclear power plants.
Codes are living documents that evolve and need to be updated and reviewed in light of operating experience feedback and new developments.
Each code has been determined by each country to result in acceptably safe pressure boundary components when used in conjunction with that country's standard industry practice and regulations.

12. CSWG Harmonization Work
2nd NUCLEAR REGULATORY INFORMATION CONFERENCE
CSWG Harmonization Work
MDEP Generic Common Position CP-CSWG-01
Mixing different country’s code and standards requirements might be detrimental and should be carefully evaluated when attempted.
Codes are also highly dependent on cultural and philosophical factors and should be used within the context intended. Using codes outside this context, for example, using them in different countries, needs to be treated with caution and studied carefully.

13. CSWG Harmonization Work
2nd NUCLEAR REGULATORY INFORMATION CONFERENCE
CSWG Harmonization Work
MDEP Technical Report TR-CSWG-01
In pursuit of harmonisation this report documented the requirements of different MDEP regulator utilises on national or regional mechanical codes and standards in its safety reviews and licensing of new reactors.
CNSC
NNSA
STUK
ASN
NNR
CNSC, codes and standards become legal requirements and have the full force of law only if they are incorporated by reference into Licence as Licence Conditions.
CSA standards are the main source of accepted standards that CNSC usually refers in the regulatory practice
NNSA, after its foundation, started its own regulatory Codes and Guides system mainly based on those of IAEA. The Codes and Guides here correspond to Department Rules and Safety Guides
NNSA, in the early stage, generally accepted design and construction
standards of the country exporting the NPP with a prerequisite that the four regulatory Codes (siting, design, operation and quality assurance) issued by NNSA must be satisfied. The accepted standards
include RCC-M, ΠΗAЭ Γ and ASME etc.
ASME III is a primary minimum requirement for stress
analysis, but also other corresponding Codes may be deemed applicable if approved and applied in vendor’s country French RCC-M was applied to OL3 design. It was in some cases supplemented with e.g. ASME, ANSI,
KTA or EN
The 97/23/EC European directive defines essential safety requirements which have to be met by the equipment
The nuclear pressure equipment is regulated on the same basis as the conventional pressure equipment
The French regulatory specific order (December 12th 2005) determines additional requirements to take
into account the importance for safety of level 1 components and the importance of radioactive releases in case of failure of other components
The French regulation does not approve nor implement any code or standard. For example, the use of RCC-M code doesn’t imply that all essential safety requirements are met. The regulatory body must ensure that essential safety requirements are taken into account
The NNR Licensing Requirements require that the Nuclear Installations are designed, constructed and
operated in accordance with well-defined standards and rules.
The NNR does not specify the use of any specific design code or standard. There are also no specific design codes and standards developed in the Republic of South Africa for the safety of important components used in the South African nuclear industry.
The codes and standards must be justified in terms of application and must be applied consistently, without omission of conditions or embedded
requirements.

14. CSWG Harmonization Work
2nd NUCLEAR REGULATORY INFORMATION CONFERENCE
CSWG Harmonization Work
MDEP Technical Report TR-CSWG-03 – Fundamental Attributes
The fundamental attributes are the basic concepts underpinning the codes and standards to be considered in the design, materials, fabrication, installation, examination, testing and over-pressure protection requirements for pressure boundary components
Fundamental Attribute 1: Management/quality assurance system for the plant design and construction
Fundamental Attribute 2: Classification and Graded Approach based on safety significance
Fundamental Attribute 4: Design basis for items important to safety
shall specify the necessary capability, reliability and functionality for the relevant operational states, for accident conditions and for conditions arising from internal and external hazards,
For pressure boundary components, design loadings and service conditions shall be defined with appropriate design margins.

15. CSWG Harmonization Work
2nd NUCLEAR REGULATORY INFORMATION CONFERENCE
CSWG Harmonization Work
MDEP Technical Report TR-CSWG-03 – Fundamental Attributes
Fundamental Attribute 5: Provision for inspectability
Fundamental Attribute 6: Design by Analysis
stress analysis of a component to show that each stress limit defined for each stress category and each service level is satisfied when component is subjected to design basis loadings
The theory of failure on which the detail stress analysis is based, shall be identified.

16. CSWG Harmonization Work
2nd NUCLEAR REGULATORY INFORMATION CONFERENCE
CSWG Harmonization Work
MDEP Technical Report TR-CSWG-04 The essential performance guidelines
Provides qualitative performance descriptions of the rules and practices derived from nuclear pressure-boundary codes and standards
Identify common code aspects or requirements
Although differences between codes have been identified during code comparison, the basic structure and most essential requirements are shared by the different codes
The common areas cover the essential parts of the pressure boundary codes

17. CSWG Harmonization Work
2nd NUCLEAR REGULATORY INFORMATION CONFERENCE
CSWG Harmonization Work
MDEP Technical Report TR-CSWG-02 - Lessons Learnt on Achieving Harmonisation C &S
Regardless of the similarities and differences, the CSWG found that each pressure- boundary code produces a safe component design.
It should be also recognised that code-compliance in component design is just one aspect of the entire component design and construction process
The implementation of code requirements alone does not always provide a true representation of the component’s quality and safety without consideration of these philosophical and cultural factors.
The CSWG concludes that each country’s pressure-boundary code produces components of high quality when the code is used in conjunction with its country’s standard industry practice, is supplemented with industry guidance and regulatory requirements, and is implemented in a manner consistent with its cultural and philosophical factors

18. CSWG Harmonization Work
2nd NUCLEAR REGULATORY INFORMATION CONFERENCE
CSWG Harmonization Work
CSWG Current and Future
Continue sharing regulatory practices in using codes and sharing events in nuclear regulation with the purpose of minimizing differences in regulatory requirements
Continue engaging with the SDOs and the CORDEL CSTF on
• Code comparison
• Limiting further code divergence
• Code convergence

19. CSWG Harmonization Current Work
2nd NUCLEAR REGULATORY INFORMATION CONFERENCE
CSWG Harmonization Current Work
Continuous engagements with the SDO Convergence Board and CORDEL on relevant work products.
Report on Welding Qualification and Welding Quality Assurance
Certification of NDE Personnel
Non-Linear Analysis Design Rules, Part 1, Code Comparison and
Non-Linear Analysis Design Rules, Par 3 Benchmark

20. CSWG Harmonization Future Work
2nd NUCLEAR REGULATORY INFORMATION CONFERENCE
CSWG Harmonization Future Work
The proposed scope of work include codes & standards for NPP operation/maintenance and regulatory requirements:
Ageing management (e.g. Environmental Assisted Fatigue)
Challenges from Technological Innovation
Including a launched task on Codes and Standards Unified Framework for Qualification of Existing and New Manufacturing Techniques - Initial Sub-Case: Macro-segregation of carbon during ingot solidification
Codes & Standards for In-service Inspection
Assessment of the applicability and sufficiency of Codes & Standards for Advanced Reactors
Assessment of the applicability and sufficiency of Codes & Standards for Small Modular Reactors

21. 2nd NUCLEAR REGULATORY INFORMATION CONFERENCE
NNR and CSWG Work
The NNR has benefited greatly in the work carried out by CSWG
Code Comparisons
Fundamental Attributes as well as Essential Guideline reports
Incorporated some of the input in the NNR’s update of its regulatory framework.
SA as a country without own nuclear C&S stands to benefit and possibly influence futher harmonisation
Presence in the CSWG space will better inform SA of developments of C&S of possible vendor countries for SA possible future nuclear programs

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