The Role of Standards and Cer1fica1on in the Nuclear Power Industry - PowerPoint PPT Presentation

The Role of Standards and Cer1fica1on in the Nuclear Power Industry 15 th INPRO Dialog Forum on Sustainable Supply Chains for Advanced Nuclear Power Systems July 2-4, 2018 Allyson Byk Project Engineering Advisor ASME Nuclear Codes and Standards Europe Liaison

Agenda • ASME Background • History of Standards and Why They MaTer • ASME Nuclear Codes and Standards • ASME Conformity Assessment • ConsideraUons For Countries With Emerging Nuclear Programs

ASME at a Glance • ASME was founded in 1880 • 400 employees Offices : • 140,000 members with over 200 local secUons, 500 New York, NY student secUons in over 40 countries Washington DC • Develop standards and conformity assessment programs Fairfield, NJ for many industries including nuclear Houston, TX • ASME offers more than 200 courses and trains about Brussels 9,000 people each year Beijing • Publish mulUple technical journals and books New Delhi • Sponsor or co-sponsor many technical conferences

ASME Standards and Cer8fica8on Mission Develop the best, most applicable, codes, standards, and conformity assessment programs in the world, for the benefit of humanity. Involve the best and the brightest people from all around the world to develop, maintain, and promote the use of these ASME products and services world wide.

Background of ASME Codes & Standards • First standard issued in 1884 • Maintain approximately 500 published codes and standards, issuing between 75-100 annually • 700 total commiTees • Over 5500 volunteer commiTee members (SMEs) • Administer over 40 US Technical Advisory Groups to ISO

ASME Develops Codes & Standards for Many Industries Plumbing Authorized InspecUons Fossil Post ConstrucUon AutomoUve Gauges/Gaging Pressure Vessels Bioprocess Geometric Dimensioning & Tolerancing (GD&T) Pumps Blanks Rail TransportaUon HeaUng, VenUlaUng and Air-CondiUoning Boiler High Pressure Vessels/Systems CerUficaUon & AccreditaUon (C&A) Resistance Reinforced Thermo, PlasUc Corrosion Industrial Gas Chains Renewable/AlternaUve Energy Internal CombusUon Engine Chemical/Process Risk Analysis Keys & Keyseats Compressors Screw Threads Limits & Fits ComputaUonal/Analysis Steam Table Materials Steel Stacks CompuUng/InformaUon Science in Engineering Measurement Surface Quality Controls Medical/Health TesUng Conveyors Metal Products Sizes TexUle Engineering Cranes and Hoists Metric System Tools Design Noise Control and AcousUcs Turbines Elevators and Escalators Non-Personnel & Personnel Lijing Devices Valves Energy Efficiency NondestrucUve EvaluaUon/ExaminaUon Waste Engineering Drawing & Related PracUces Nuclear Water Management Environmental Operator QualificaUon and CerUficaUon Welding & Brazing Fasteners Performance Test Codes Fitness-For-Service Piping & Pipelines Figngs, Flanges & Gaskets Plant OperaUons

Brief History of Steam Power and the ASME Boiler and Pressure Vessel Code • Throughout the 1800’s, both boiler size and operaUng pressure conUnued to increase • By the 1890’s the number of boiler explosions was more than one per day, causing the loss of thousands of lives Example: • The Grover Shoe Factory boiler explosion on March 20, 1905 in Brockton, MassachuseTs

R. B. Grover & Company Shoe Factory Before the boiler explosion

R. B. Grover & Company Shoe Factory A@er Boiler Explosion

Why Standards MaPer It’s about protec.ng public health and safety • Following a number of explosions of this type, states began to develop their own boiler laws • This led to the development of different laws among the states • In response, ASME issued the first Boiler Code in 1914 • It provided for safe construcUon and promoted commerce through consistency of requirements

5000 psi 1600 psi P R E S S U R E 400 psi L 650 psi E V E L 500 psi

Why Standards MaPer It’s also about consistency of requirements

Without consistency of requirements you get this….. World Power Outlets

ASME Boiler & Pressure Vessel Code • Covers industrial and residenUal boilers, pressure vessels, nuclear reactor components, and transport tanks • Is Comprehensive - provides rules for materials, design, fabricaUon, examinaUon, inspecUon, tesUng, cerUficaUon, and pressure relief • Is Dynamic – evolves and changes to reflect new technology and industry needs • Includes a conformity assessment program wriTen into the code to assure compliance

Boiler and Pressure Vessel Code Sec8ons SecUon I - Power Boilers • Sec1on II - Materials • • Sec8on III - Rules for Construc8on of Nuclear Facility Components SecUon IV - HeaUng Boilers • Sec1on V - Nondestruc1ve Examina1on • SecUon VI - Recommended Rules for the Care and OperaUon of HeaUng Boilers • SecUon VII - Recommended Guidelines for the Care of Power Boilers • SecUon VIII Pressure Vessels • Sec1on IX - Welding and Brazing Qualifica1ons • SecUon X - Fiber-Reinforced PlasUc Pressure Vessels • • Sec8on XI - Rules for Inservice Inspec8on of Nuclear Power Plant Components • SecUon XII - Rules for the ConstrucUon and ConUnued Service of Transport Tanks • SecUon XIII – Overpressure ProtecUon (In development) 2017 Edi8on 12 Sec8ons / 31 Volumes / ~16,500 pages Updated every 2 years

Nuclear Codes and Standards

ASME Standards for Nuclear Construc8on Nuclear Codes • BPVC Sec8on III – Rules for ConstrucUon of Nuclear Facility Components • NQA-1 – Quality Assurance Requirements for Nuclear Facility ApplicaUons • BPVC Sec8on XI – Inservice InspecUon & TesUng Technical Reference Codes • BPVC Sec8on II – Materials • BPVC Sec8on V – NondestrucUve ExaminaUon • BPVC Sec8on IX – Welding & Brazing QualificaUons

ASME BPVC Sec8on III Rules for Construc1on of Nuclear Facility Components SecUon III establishes rules of safety relaUng only to pressure integrity , which governs the construc8on of boilers, pressure vessels, transport tanks, nuclear components and their supports .

ASME BPVC Sec8on III Rules for Construc1on of Nuclear Facility Components Subsec8on NCA: General Requirements for • Divisions 1 & 2 Division 1: Metallic vessels, heat exchangers, • storage tanks, piping systems, pumps, valves, core support structures, supports, and similar items. Division 2 : Code for Concrete Containments • Division 3: Containment Systems for • TransportaUon and Storage of Spent Nuclear Fuel and High-Level RadioacUve Material Division 4: Fusion Energy Devices (in development) • Division 5: High Temperature Reactors • Appendices • Sec8on III Code Cases •

Subsec8on NCA General Requirements for Divisions 1 & 2 • Referenced by and is an integral part of Division 1, SubsecUons NB through NG, and Division 2 of SecUon III • Covers quality assurance requirements, ASME product cer8fica8on marks, and authorized inspec8on for Class 1, 2, 3, MC, CS, and CC construc8on by referencing the requirements in NQA-1, Part I and supplemenUng them as necessary in NCA-4134 . • Includes a Glossary which defines selected terms used in SecUon III. The definiUons in this glossary prevail should a conflict exist elsewhere or in other documents referenced by SecUon III.

ASME BPVC Sec8on XI Rules for Inservice Inspec1on of Nuclear Power Plant Components • Preservice and inservice examinaUon – Mostly nondestrucUve (NDE) – IdenUfy degradaUon • EvaluaUon Standards • Repair/Replacement AcUviUes – Including modificaUons • Aging plant management

Quality Assurance Requirements for Nuclear Facility Applica8ons (NQA-1) • This Standard provides requirements and guidelines for the establishment and execu8on of quality assurance programs during siUng, design, construcUon, operaUon and decommissioning of nuclear faciliUes. • This Standard reflects industry experience and current understanding of the quality assurance requirements necessary to achieve safe, reliable, and efficient u8liza8on of nuclear energy, and management and processing of radioac8ve materials .

Quality Assurance Requirements for Nuclear Facility Applica8ons (NQA-1) • Part I – Requirements for Quality Assurance Programs for Nuclear FaciliUes • Part II – Quality Assurance Requirements for Nuclear Facility ApplicaUons • Part III - Nonmandatory Guidance on ImplemenUng Requirements of Part I and Part II • Part IV – Guidelines on the ApplicaUon and Use of the NQA-1 Standard

ASME Nuclear Codes & Standards • OM-1 - Code for OperaUon and Maintenance of Nuclear Power Plants • QME-1 - QualificaUon of AcUve Mechanical Equipment used in Nuclear Power Plants • RA-S - ProbabilisUc Risk Assessment for Nuclear Power Plant ApplicaUons (PRA) • AG-1 - Nuclear Air and Gas Treatment Requirements • Cranes for Nuclear FaciliUes

Conformity Assessment It’s all about quality • The recogniUon of a company’s or individual’s capability to fulfill the requirements of an ASME standard in order to advance public safety and facilitate internaUonal commerce. • Conformity Assessment, when properly applied, provides regulators and purchasers of products confidence that the products were manufactured in accordance with the applicable standard, regardless of where in the world they were manufactured