Safety standards

☢️ IAEA Infrastructure Issue 2: Nuclear Safety Framework

Infrastructure Issue 2 requires establishment of a comprehensive nuclear safety regime based on international standards and IAEA Safety Fundamentals, ensuring that safety is the fundamental priority throughout the nuclear program. The safety framework must evolve across all three phases of the IAEA Milestones Approach to support licensing, construction, and operation.

🛡️ Core Safety Framework Components

• National nuclear safety policy and strategy
• Legal framework for nuclear safety based on international conventions
• Independent regulatory body with adequate authority and resources
• Safety standards and regulations aligned with IAEA Safety Standards
• Strong safety culture as organizational foundation
• Emergency preparedness and response capabilities

📅 Milestone 1 Expectation: National commitment to safety principles established; initial legal framework drafted; plans for regulatory independence defined.

📅 Milestone 2 Expectation: Regulatory body operational with published safety regulations; licensing processes initiated; emergency planning underway.

📅 Milestone 3 Expectation: Full regulatory capability demonstrated; construction permit issued; operating license preparation and oversight systems in place.

📈 Evolution Through Milestones

• Milestone 1: Commitment to IAEA safety principles; initial regulatory framework
• Milestone 2: Regulatory body operational; safety regulations published; site licensing underway
• Milestone 3: Full regulatory capability demonstrated; construction permit issued; operating license preparation

⚖️ Regulatory Independence

The regulatory body must be effectively independent from organizations promoting nuclear power and from utilities operating nuclear facilities. This independence is fundamental to maintaining public confidence and ensuring impartial safety oversight.

📅 Milestone 2 Expectation: Legal safeguards for regulatory independence enacted; budget and staffing secured.

📅 Milestone 3 Expectation: Independent oversight demonstrated through licensing decisions and inspection authority.

🌐 International Commitments

Countries typically join the Convention on Nuclear Safety and establish bilateral cooperation with experienced nuclear nations to build regulatory competence and align with global best practices.

📅 Milestone 1 Expectation: Accession to key international conventions initiated.

📅 Milestone 2 Expectation: International cooperation agreements signed; peer review missions planned.

📅 Milestone 3 Expectation: Participation in international safety reviews and conventions sustained.

🇺🇸 United States Nuclear Codes and Standards

The U.S. nuclear industry relies primarily on standards developed by the American Society of Mechanical Engineers (ASME) and the Institute of Electrical and Electronics Engineers (IEEE). These standards form the technical foundation for U.S. Nuclear Regulatory Commission (NRC) regulations and licensing requirements.

📘 ASME Boiler and Pressure Vessel Code (BPVC):

• Section III: Rules for Construction of Nuclear Facility Components
• Section XI: Rules for In-Service Inspection of Nuclear Power Plant Components
• Section V: Nondestructive Examination Methods
• Updated biennially with continuous improvement addenda

🛡️ ASME NQA-1 – Nuclear Quality Assurance:

• Defines requirements for quality assurance programs supporting nuclear facility design, construction, operation, and decommissioning
• Includes Part I (requirements), Part II (guidance), and Part III (nonmandatory appendices)
• Referenced in 10 CFR 50 Appendix B and widely adopted by NRC licensees and Department of Energy contractors
• Supports supplier qualification, document control, corrective actions, and software QA

📐 IEEE Nuclear Standards:

• IEEE 323: Qualification of Safety-Related Electrical Equipment
• IEEE 384: Criteria for Independence of Class 1E Equipment and Circuits
• IEEE 603: Requirements for Safety Systems in Nuclear Power Generating Stations
• IEEE 535: Qualification of Class 1E Vented Lead-Acid Storage Batteries
• IEEE 650: Qualification of Class 1E Battery Chargers, Inverters, and UPS Systems

🔋 Battery Standards Overview:

• IEEE 535 covers environmental and seismic qualification of vented lead-acid batteries used in safety-related systems
• IEEE 650 governs qualification of battery chargers, inverters, and UPS systems for Class 1E applications
• Referenced in NRC Regulatory Guide 1.210 and required for station blackout (SBO) and post-accident monitoring systems

✅ Supplier Qualification Pathways:

• ASME N-Stamp Program: Certifies organizations to fabricate, assemble, and inspect nuclear components per Section III
• NQA-1 Audits: Suppliers are evaluated against ASME NQA-1 criteria for quality assurance and traceability
• Commercial Grade Dedication (CGD): Allows non-nuclear suppliers to be qualified for safety-related use through rigorous testing and documentation
• NRC Endorsement: NRC licensees may approve suppliers through procurement audits and performance history
• Department of Energy/NRC Shared Databases: Supplier performance and qualification records are maintained for oversight and benchmarking

⚖️ Regulatory Integration: NRC regulations — including 10 CFR 50 Appendix B and 10 CFR 50.55a — incorporate ASME and IEEE standards by reference, with specific regulatory positions and exceptions outlined in Regulatory Guides and NUREG documents.

🌍 Global Influence: ASME BPVC and NQA-1 are the most widely adopted nuclear codes internationally, serving as the technical basis for many national standards including KEPIC (Korea), RCC-M (France), and PNAE (Russia).

📚 Sources:
1. ASME Boiler and Pressure Vessel Code – Sections III, V, and XI
2. ASME NQA-1 – Nuclear Quality Assurance Standard
3. IEEE Standards Association – Nuclear Power Standards
4. NRC Regulatory Guide 1.210 – Qualification of Class 1E Battery Systems
5. NRC NUREG-1055 – Supplier Quality Assurance Practices
6. ASME N-Type Certificate Directory – Authorized Nuclear Component Manufacturers

🇨🇦 Canadian Nuclear Standards: CSA N-Series

Canada's nuclear regulatory framework is supported by the CSA N-series standards developed by the Canadian Standards Association (CSA) in collaboration with industry and the nuclear regulator, the Canadian Nuclear Safety Commission (CNSC). These standards provide comprehensive requirements for design, operation, safety, procurement, and environmental protection across nuclear facilities.

📘 Key CSA N-Series Standards:

• CSA N285.0: General Requirements for Pressure-Retaining Systems
• CSA N286: Management System Requirements for Nuclear Facilities
• CSA N286.7: Quality Assurance of Analytical, Scientific, and Design Computer Programs
• CSA N287: Concrete Containment Structures for Nuclear Power Plants
• CSA N288: Environmental Protection at Nuclear Facilities
• CSA N290: Requirements for Safety-Related Structures
• CSA N293: Fire Protection for Nuclear Power Plants

🛒 CSA N299 Series – Procurement and Supplier Quality:

• CSA N299.0: General Requirements for Nuclear-Related Procurement
• CSA N299.1–N299.4: Graded quality assurance levels for suppliers based on safety significance
• Applies to design, manufacturing, testing, and service providers supporting nuclear facilities

🔧 CANDU-Specific Standards: Many CSA standards incorporate requirements specific to CANDU reactor technology, including:

• Heavy water systems
• Pressure tube design
• Unique fuel handling and shutdown systems

📐 Key Non-Nuclear Standards Used in Nuclear Applications:

• CSA B51: Boiler, Pressure Vessel, and Pressure Piping Code
• CSA Z299 (legacy): Quality assurance program standards used prior to N299 adoption
• CSA C22 Series: Electrical standards referenced in nuclear facility design

⚖️ Regulatory Integration: CNSC regulatory documents reference CSA standards extensively, making them legally binding for Canadian nuclear facilities.

🌐 Global Deployment: CSA N-series standards are used in CANDU reactors worldwide — including India, Romania, Argentina, and China — and are recognized for technical excellence in pressure boundary integrity, aging management, and safety system reliability.

🇷🇺 Russian Nuclear Standards Framework

Russia’s nuclear industry operates under a multi-tiered standards system developed through decades of VVER reactor experience. These include:

📘 PNAE Series – Safety Rules and Regulations:

• PNAE G-7-002-86: Equipment and Piping of Nuclear Power Installations
• PNAE G-7-008-89: Strength Calculation Rules for Reactor Pressure Vessels
• PNAE G-5-40-97: Requirements for Full-Scope Simulators for NPP Control Room Operators

📐 GOST Series – State Standards for Nuclear Applications:

• GOST R 52857: Strength Analysis for Nuclear Power Plants
• GOST R 50.05.01: In-Service Inspection Requirements
• GOST R 51882-2002: Heat-Insulating Radioactivity-Resistant Products
• GOST R IEC 61500-2012: Safety I&C Data Communication Systems
• GOST R IEC 60964-2012: Control Room Design Requirements
• GOST R IEC 60880-2010: Software for Safety I&C Systems
• GOST R 50.05.20-2019: Monitoring Non-Destructive Metal Equipment and Pipelines

📗 NP Series – Federal Safety Rules:

• NP-001-15: General Safety Provisions for Nuclear Power Plants
• NP-002-15: Safe Management of Radioactive Waste
• NP-004-08: Operational Occurrence Investigation Procedures
• NP-005-16: Emergency Communication and Assistance Protocols
• NP-006-16: Safety Analysis Report Requirements for VVER Reactors
• NP-007-17: Safety Rules for Industry Reactor Decommissioning

🔐 Certification and Conformity Assessment:

• Governed by GOST R 50.05.x series and NP rules
• Includes conformity assessment systems for equipment, software, and operational procedures
• Certification performed by accredited bodies under supervision of Rostekhnadzor
• Methods include non-destructive testing (NDT), eddy current control, and documentation audits
• Required for domestic and imported safety-class components used in Russian nuclear facilities

🌐 Global Deployment: Russian standards are used in VVER reactor exports to Belarus, Bangladesh, Egypt, Turkey, Hungary, and other countries.

🇨🇳 Chinese Nuclear Regulatory Standards

China's nuclear industry operates under standards developed by the National Nuclear Safety Administration (NNSA) and the National Energy Administration. These are designated as HAF (nuclear safety regulations) and NB (nuclear industry standards), forming the backbone of China’s regulatory framework.

📘 HAF Series – Safety Regulations:

• HAF001: Safety Regulations for Nuclear Power Plants
• HAF002: Emergency Measures for Nuclear Accidents
• HAF003: Safety Regulations for Research Reactors
• HAF101: Site Selection Safety Regulations
• HAF102: Design Safety Regulations
• HAF103: Operation Safety Regulations
• HAF201: Quality Assurance for Nuclear Power Plants
• HAF202: Operation Safety for Research Reactors
• HAF301: Safety Regulations for Civil Nuclear Fuel Recycle Facilities
• HAF401: Radioactive Waste Safety Supervision
• HAF501: Nuclear Material Control Ordinance
• HAF601: Certification for Domestic Safety-Class Equipment Manufacturers
• HAF604: Certification for Imported Civil Nuclear Safety Equipment

🔐 HAF 604 Certification Overview:

• Mandatory for foreign suppliers of safety-related components used in Chinese nuclear power plants
• Covers design, manufacturing, and installation activities
• Separate certifications required for each responsible entity (e.g., designer vs. manufacturer)
• Valid for 5 years; renewal requires evidence of successful project completion in China
• Administered by NNSA under the “Supervision and Management Regulations for Imported Civilian Nuclear Equipment”
• Requires documentation, expert panel review, and confirmation of demand from Chinese end users

📐 NB Series – Industry Standards:

• NB/T 20007: Design and Construction Rules for Mechanical Equipment
• NB/T 20101: Materials for Nuclear Island Mechanical Equipment
• NB/T 47013: Non-Destructive Testing Methods
• NB/T 20001–20099: Welding, pressure vessels, piping, valves, and structural components
• NB/T 31001–31099: Electrical and I&C systems
• NB/T 32001–32099: Civil engineering and seismic design
• NB/T 33001–33099: Fire protection systems
• NB/T 34001–34099: Radiation protection and waste management

🌐 International Alignment: Chinese standards increasingly reference ASME, RCC-M, and IAEA frameworks while incorporating domestic reactor experience from CPR-1000, HPR-1000 (Hualong One), and CAP1400 designs.

🌍 Global Influence: As China expands nuclear exports to countries such as Pakistan, Argentina, and the UK, Chinese standards are gaining international recognition and acceptance.

🇰🇷 Korea Electric Power Industry Code (KEPIC)

KEPIC represents Korea's comprehensive nuclear standards framework, developed by the Korea Electric Association (KEA). It is based on ASME codes with Korean-specific adaptations and is endorsed by Korea's Nuclear Safety and Security Commission (NSSC).

📘 KEPIC Code Categories:

• KEPIC-MN: Mechanical components for nuclear facilities (based on ASME Section III)
• KEPIC-EN: Electrical and I&C systems for nuclear applications
• KEPIC-QN: Quality assurance requirements for nuclear facilities
• KEPIC-SN: In-service inspection rules (based on ASME Section XI)
• KEPIC-CN: Civil engineering and structural design for nuclear installations
• KEPIC-RN: Reactor systems and components
• KEPIC-NM: Materials used in nuclear mechanical components
• KEPIC-IS: Safety-related instrumentation systems
• KEPIC-IE: Electrical equipment and installation standards
• KEPIC-FN: Fire protection systems for nuclear facilities

🛠️ Development Approach: KEPIC began as a Korean-language translation of ASME codes but has evolved to incorporate:

• Korean operational experience and regulatory feedback
• Domestic material specifications and fabrication practices
• Design innovations from Korean reactor development (e.g., OPR-1000, APR-1400)

🌐 Global Deployment: KEPIC is used for Korean-designed reactors exported to the UAE (Barakah Nuclear Power Plant) and is being considered for other international projects.

⚖️ Regulatory Endorsement: KEPIC is officially recognized by Korea's Nuclear Safety and Security Commission (NSSC) as the approved standard for nuclear component design and construction in South Korea.

🎓 KEPIC Certification Program:

• Validates organizations and personnel performing nuclear safety-related activities per KEPIC requirements
• Ensures quality assurance capability through audits and evaluations by KEA-approved examination teams
• Registered professional engineers certify design documents and specifications
• Authorized inspectors verify compliance during fabrication and construction stages, including welding, NDE, and hydrotesting
• Certification stamps are applied to nameplates and documents to confirm KEPIC compliance
• Reduces reliance on foreign certification programs and lowers acquisition costs

The program acts as a third-party validation mechanism—independent of regulators and operators—to enhance safety and reliability across Korea’s nuclear fleet.

🇫🇷 French Nuclear Standards

France’s nuclear regulatory framework is built on the Règles de Conception et de Construction (RCC) standards, developed by AFCEN (French Association for Design, Construction and In-service Inspection Rules for Nuclear Island Components). These codes cover mechanical, electrical, civil, fire protection, and inspection domains across power reactors, research facilities, and advanced systems.

🔩 RCC-M (Mechanical Components)

• Equivalent to ASME Section III for mechanical components
• Covers design, materials, fabrication, inspection, and testing
• Used extensively in PWR construction worldwide (e.g., EPR reactors)
• Includes specific requirements for French reactor designs

🔌RCC-E (Electrical and I&C Components)

• Standards for electrical and instrumentation & control equipment qualification
• Covers design, manufacturing, and testing requirements
• Includes environmental and seismic qualification criteria
• Supports aging management for safety-related electrical equipment

🛠️ RCC-C (Electrical and I&C Manufacturing)

• Focuses on manufacturing and quality assurance for electrical and I&C components
• Complements RCC-E by detailing fabrication and inspection processes

🔬RCC-MRx (Advanced and Research Reactors)

• Applies to high-temperature reactors, sodium-cooled fast reactors, and research facilities
• Includes rules for non-standard materials and complex thermal-mechanical behaviour

🏗️ RCC-CW (Civil Works)

• Covers design and construction of nuclear civil structures (e.g., reactor buildings, foundations)
• Includes seismic, geotechnical, and structural integrity requirements

🔥 RCC-F (Fire Protection)

• Defines fire protection design, equipment qualification, and performance criteria
• Supports defence-in-depth and regulatory compliance for fire safety systems

🔍 RSE-M (In-Service Inspection)

• Specifies inspection rules for mechanical components during operation
• Supports ageing management, defect monitoring, and regulatory reporting

RCC standards are recognized by nuclear regulators worldwide and are specified for many international reactor projects including Finnish Olkiluoto 3, French Flamanville 3, and UK Hinkley Point C.

Key Differences from ASME: RCC-M includes more stringent fracture mechanics requirements and material specifications tailored to European steel grades. RCC-MRx and RCC-CW address advanced reactor and civil design needs not covered by ASME.