ML23251A057
| ML23251A057 | |
| Person / Time | |
|---|---|
| Issue date: | 09/13/2023 |
| From: | Robert Roche-Rivera NRC/RES/DE |
| To: | |
| References | |
| Download: ML23251A057 (41) | |
Text
Importance of Standards, Opportunities for Participation and Collaboration Opening Remarks by Michele Sampson, NRC Standards Executive; Division Director, RES/DE Session Chair: Meraj Rahimi, Branch Chief, RES/DE/RGPMB Panelists/Speakers:
Gordon Gillerman (NIST)
Frances Pimentel (NEI)
Andrew Sowder (ANS)
Tom Vogan (ASME)
Mark Bowman (IEEE)
USG NATIONAL STANDARDS STRATEGY FOR CRITICAL AND EMERGING TECHNOLOGY (USG NSSCET)
Gordon Gillerman Director Standards Coordination Office National Institute of Standards and Technology 2
Objective 2: Participation Objective 3: Workforce Objective 4: Integrity & Inclusivity Objective 1: Investment USG NSSCET OBJECTIVES 3
QUANTUM INFORMATION TECHNOLOGIES DIGITAL ID INFRASTRUCTURE & DISTRIBUTED LEDGER TECHNOLOGIES SEMICONDUCTORS
& MICROELECTRONICS BIOTECHNOLOGIES COMMUNICATION & NETWORKING TECNOLOGIES ARTIFICIAL INTELLIGENCE &
MACHINE LEARNING RENEWABLE ENERGY GENERATION & STORAGE CRITICAL AND EMERGING TECHNOLOGIES IDENTIFIED IN THE USG NSSCET 4
Automated & Connected Infrastructure Smart cities, Internet of Things, and other novel applications Automated & Connected Transportation Autonomous vehicles, unmanned aircraft systems, automated subway systems, smart cities, internet-of-things, and other possible applications Critical Mineral Supply Chains Cross-cutting issues that are critical to enabling the development and deployment of emerging technologies and data security Biobanking Involves the collection, storage, and use of biological samples from individuals Electric Vehicles (EVs)
Standards to integrate EVs with the electrical grid Cybersecurity & Privacy Cross-cutting issues that are critical to enabling the development and deployment of emerging technologies and data security SPECIFIC CET APPLICATIONS 5
Greater Investment in Pre-Standardization Research Participation in Standards Development Workforce Development Ensuring Integrity in Standards Development Increase R&D funding for CETs Support development of standards that address risk, security, and resilience Remove and prevent barriers to private sector participation Improve communication between public and private sector Enhance USG representation and influence in international standards governance and leadership Educate and empower the new standards workforce Deepen standards cooperation with partners and allies Facilitate broad representation in standards development USG NSSCET LINES OF EFFORT 6
Communication and coordination information on standards.gov NIST Visiting Committee on Advanced Technology Subcommittee on International Standards Development Listening Sessions and additional stakeholder engagement workshops Request for Information on barriers to increased standards engagement (Sept 2023)
NIST as point of entry to engaging on the USG National Standards Strategy for Critical and Emerging Technology DEVELOPING A USG NSSCET IMPLEMENTATION PLAN 7
Advanced Reactors Codes and Standards Collaborative (ARCSC)
Frankie Pimentel-Sr. Project Manager, Engineering and Risk, NEI 8
Advanced Reactors Codes and Standards Collaborative (ARCSC) Background
- NEI/EPRI North American Advanced Reactor Roadmap Nuclear Energy Institute (NEI) and Electric Power Research Institute (EPRI) in conjunction with industry partners have developed a roadmap that identifies key challenges, gaps and opportunities to be addressed to enable deployment of advanced reactors.
Advanced reactor designs and a new generation of nuclear reactor construction challenge the context and assumptions upon which current consensus Codes and Standards are based. Success will require a huge shift in Codes and Standards development and regulatory processes.
- Advanced Reactors Codes and Standards Collaborative established to realize the Codes and Standards building block of the Roadmap 9
Advanced Reactors Codes and Standards Collaborative Charter
- Mission: To ensure the development, alignment and timely availability of U.S., Canadian and international codes and standards needed to support large-scale advanced reactor deployment.
- Objectives:
- 1. Facilitate information sharing between SDOs and industry
- 2. Identify and gather advanced reactor developer standards needs
- 3. Inform and complement international and national C&S efforts (e.g., IAEA NHSI, WNA).
- 4. Align actions with the NEI/EPRI Advanced Reactor Roadmap Codes and Standards building block.
- Membership: Includes individuals from NEI, EPRI, standards development organizations (SDOs) including ASME, ANS, CSA, IEEE, ASCE Information and contributors will be solicited from DOE, WNA, IAEA, regulators, advanced reactor developers, nuclear suppliers and operators, research laboratories, and other stakeholders as appropriate.
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ARCSC Committee Membership includes SDOs, NEI, EPRI Outreach/raise awareness (about overall initiative and status/ways to engage in SDOs standards development activities)
SDO committees AR developers Industry (utilities/
operators, suppliers)
Regulators Research (national labs, academia)
North American Advanced Reactors Codes & Standards Collaborative - Overall Process 11
ARCSC Workshop and Information Collection
- Provide information - Developing a list of C&S related to Nuclear Advanced Reactors
- Engage with the nuclear community to identify and prioritize C&S gaps for advanced reactor designs Survey/Questionnaire (available soon)
Workshops - Next Workshop will be held November 30, 2023 in Washington D.C.
- Identify appropriate Standards Development Organization (SDO) to develop C&S to avoid duplication of efforts and expedite standards development.
Requests for grant and other funding to create new standards or expand existing standards 12
Future - Design Once, Build Everywhere
- Codes and Standards play a part in this goal.
- Worldwide acceptance of standards that address Advanced Reactor needs can support design and licensing.
- We need your input!
Advanced Reactor Codes and Standards Survey (in Development)
Attend Workshops to help us develop the Roadmap for Advanced Reactors Codes and Standards Participate at standards development meetings 13
American Nuclear Society U.S. Nuclear Regulatory Commission Standards Forum September 13, 2023 Andrew Sowder, Ph.D., CHP, ANS Standards Board Chair
©2023 American Nuclear Society 14
ANS Standards - A Key Piece of the Nuclear SDO Pie
ANS Standards Committee (SC) responsible for standards addressing the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology
But NOT for the application of radiation for medical purposes
Established in 1957
Produced earliest nuclear industry standards
Accredited by American National Standards Institute (ANSI) in 1967
Maintains 88 current ANSI standards across 8 Consensus Committees (CCs) 15
Standards Board (governance)
Environmental
& Siting Consensus Committee (ESCC)
Subcommittees Working Groups Fuel, Waste &
Decommissioning Consensus Committee (FWDCC)
Joint Committee on Nuclear Risk Management (JCNRM)*
Consensus Committee Large Light Water Reactors Consensus Committee (LLWRCC)
Nonreactor Nuclear Facilities Consensus Committee (NRNFCC)
Nuclear Criticality Safety Consensus Committee (NCSCC)
Research and Advanced Reactors Consensus Committee (RARCC)
Safety &
Radiological Analyses Consensus Committee (SRACC)
Risk-informed, Performance-based Principles and Policy Committee (RP3C)
Multiple Task Groups
- JCNRM is a joint ANS/ASME consensus committee.
The ANS Standards Committee 16
ANSI/ANS-30.3-2022 LWR Risk-Informed, Performance-Based Design Many Existing Applicable Standards (for ARs)
ANSI/ANS-53.1-2011 (R2021)
Nuclear Design Process for MHCRs ANSI/ANS-54.1-2020 Nuclear Safety Criteria Design Process for SFRs ANSI/ASME/ANS RA-S-1.4-2021 PRA Standard for Adv. non-LWRs 17
Leveraging direct engagement through the ANS structure
AR sessions at ANS national and topical meetings
ANS Advanced Reactor Working Group
RP3C Community of Practice seminars
Joint Committee on Nuclear Risk Management (with ASME)
Leveraging engagement with peer organizations and other entities
NEI, EPRI, USNIC
USDOE and USNRC
Other SDOs Leadership on Codes & Standards element under the North American Advanced Reactor Roadmap How ANS Informs AR Standard Development We need your help! What are gaps in standards for ARs? When are the standards needed? Volunteer for an ANS CC, subcommittee or working group!
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Integration and harmonization among nuclear SDOs to support AR community via timely development of relevant codes and standards
Owned and generated by industry, input from partners/stakeholders
Three pillars:
Regulatory efficiency
Project execution
Technology readiness
Codes & Standards development a key element under Technology Readiness
ANS - a foundational SDO on AR Roadmap development and execution Leadership on North American Advanced Reactor Roadmap 19
ANS Standards Board Leadership Andrew Sowder ANS Standards Board Chair asowder@epri.com Todd Anselmi ANS Standards Board Vice Chair todd.anselmi@inl.gov ANS Staff John Fabian ANS Director of Publications jfabian@ans.org Pat Schroeder ANS Standards Manager pschroeder@ans.org 555 N. Kensington Ave.
La Grange Park, IL 60526 708-579-8269 (Pat) 20
ASME Advanced Reactor Standards Development Activity Tom Vogan ASME Senior Vice President and Chair of Council on Standards and Certification 21
ASME Facts and Figures Established in 1880 and headquartered in New York City, the American Society of Mechanical Engineers is a not-for-profit international society.
90,000+
Worldwide Membership 135+
Countries with ASME Members 25+
Conferences Conducted Annually 200+
Technical Courses &
Master Classes Offered Annually Offices: New York, NY; Washington, DC; Little Falls, NJ; Houston, TX; Beijing, China; and New Delhi, India 22
3 Coherence ASME is an international Standards Development Organization
- Accredited by ANSI
- Development process adheres to the principles and procedures outlined in the World Trade Organizations (WTO)
Agreement on Technical Barriers to Trade (TBT) for development of international standards Pressure Vessels, Piping, Nuclear Technologies, Elevators/Escalators, Cranes, Performance Testing, etc.
Engineers, Researchers, Government officials, etc.
enhancing public safety, health, and quality of life Setting the Standard 500+ Standards
& Products 6,500+ Dedicated Volunteers Used in 100+
Countries Transparency Openness Impartiality and Consensus Effectiveness and Relevance Development Dimension 23
ASME Nuclear Codes & Standards and SMR Activity 24
The Boiler & Pressure Vessel Codes (BPVC)
Construction Codes
BPVC I, Power Boilers
BPVC IV, Heating Boilers
BPVC VIII, Pressure Vessels
BPVC XII, Transport Tanks
Service Codes
BPVC II, Materials
BPVC V, Nondestructive Examination
BPVC IX, Welding, Brazing and Fusing
BPVC VI, Care and Operation of Heating Boilers
BPVC VII, Care of Power Boilers
BPVC XIII, Rules for Overpressure Protection
Nuclear Construction &
In-Service Inspection Codes
BPVC III, Construction of Nuclear Facility Components
BPVC XI, Nuclear In-service Inspection
Code Case Books
Boilers and Pressure Vessels
Nuclear Components 25
BPVC Section III - SMR Activity
- Section III is a technology neutral standard which can be applied to SMRs. The committee continuously works to evolve the standard to remain applicable to the advanced reactor needs.
- Section III Groups involved with AR activity
- Code Case development underway to support all advanced reactor types.
- Section III, Division 1 - Seismic Requirements in process of general update
- Section III, Division 4 - Fusion Devices published July 1, 2023
- Section III, Division 5 - High Temperature Reactors updated July 1, 2023
- Section III, Division 5 - Graphite Materials updated July 1, 2023 WG on Advanced Manufacturing TG on Division 5 Advanced Manufacturing Components TG on BPV III/XI Interface TG on Alt. Requirements for components comm ensurate with Safety &
Risk 26
Section III DIV. 1 Light Water SMR Construction of Nuclear Facility Components Division 2:
Concrete containment vessels with metallic liners Division 1: Metallic vessels, heat exchangers, storage tanks, piping systems, pumps, valves, core support structures,
- supports, and similar items.
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Section III DIV. 5 Liquid Metal SMR Construction of Nuclear Facility Components Division 2:
Concrete containment vessels with metallic liners Division 5: High temperature reactors providing rules suitable for construction of gas and liquid cooled reactors and are under a more active development to meet the evolving needs of our advanced reactor stakeholders 28
BPVC Section XI Nuclear Inservice Inspection
- Division 1: Inspection and Testing of Components of Light-Water-Cooled Plants
- Division 2: Reliability Integrity Management (RIM)
- A methodology to establish Inservice Inspection criteria independent of the SMR technology (e.g., Molten Salt, HTGR, Liquid Metal, etc.)
- Technology neutral - applicable to all reactor designs
- Alternative approach to current ISI activities, needed to accommodate new technologies.
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Qualification for Mechanical Equipment and Operations and Maintenance Standards The OM Code provides requirements for the operation and maintenance and Inservice Testing of nuclear power plant components.
QME provides the requirements and guidelines for the qualification of active mechanical equipment whose function is required to ensure the safe operation or safe shutdown of a nuclear facility.
ASME QME-1-2017 ASME OM-2022 The OM-2 Code will provide similar component testing rules as the current O&M Code.
It has been produced to address both regulatory and new reactor owner concerns that they have with utilizing current O&M Code rules with new nuclear facility designs.
The new Code rules are tied directly to ASME qualification standards.
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ASME HARMONIZATION ACTIVITY 31
ASME & Nuclear Regulatory Commission
- ASME standards are cited in the NRC Regulations as well as Regulatory Guides.
Developing and amending regulations that licensees must meet Rulemaking Developing and revising guidance documents, such as regulatory guides Guidance Development Working with industry standards organizations to develop consensus standards associated with systems, equipment, or materials used by the nuclear industry so that these standards may be referenced in NRC regulations or guidance Standards Development ASME/NRC Management meeting is held twice a year to discuss high level priorities for the consensus committees Representation on all ASME consensus committees &
most subordinate committees at the technical working level 32
ASME International Activity
- SDO Convergence Board meets in conjunction with ASMEs Boiler Code Week and contains representation from various countries to align major requirements in the various standards.
- ASME and JSME have a close working relationship, meeting in conjunction with ASMEs Boiler Code Week.
- ASME has established numerous International Working Groups (IWGs) for various standards.
IWGs allow ASME to gain international perspective and obtain input on how our standards are being used.
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ASME Nuclear Conformity Assessment Programs
- N-type Certificates of Authorization - This allows Certificate Holders to certify and stamp newly constructed components, parts, and appurtenances used at a nuclear facility with the Certification Mark in accordance with Section III of the ASME BPVC.
- Quality System Certificates (QSC) issued by ASME verify the adequacy of a Material Organization's quality system program.
- NQA-1 Certification - Provides centralized, independent, third-party certification for quality assurance programs in conformance with the ASME NQA-1 standard, "Quality Assurance Requirements for Nuclear Facility Applications".
N - Vessels, pumps, valves, piping systems, storage tanks, core support structures, concrete containments, and transport packaging NA - Field installation and shop assembly of all items NPT - Parts, appurtenances, welded tubular products, and piping subassemblies NS - Supports NV - Pressure relief valves N3 - Transportation containments and storage containments OWN - Nuclear power plant owner 34
ASME Events 35
ASME Events Nuclear Engineering Division ICONE 31 International Conference on Nuclear Engineering - Planned for August 2024 (Location Pending)
ICEM 2023 International Conference on Environmental Remediation and Radioactive Waste Management Stuttgart, Germany, October 3-6, 2023 Nuclear Engineering Division SMR Conference - March 2024. EPRI Offices, Charlotte, NC.
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Mark Bowman Chair, IEEE Nuclear Power Engineering Committee NPEC Nuclear Power Engineering Committee 37
NPEC Nuclear Power Engineering Committee WHO WE ARE IEEE is the worlds largest technical professional organization dedicated to advancing technology for the benefit of humanity.
OUR SCOPE All nuclear power related technical and standards writing activities within the IEEE, including research, development, and advancement of nuclear engineering.
OUR COMMITTEE We are an international group of technical experts from nuclear utilities, power plants, equipment vendors, engineering companies, and regulators.
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NPEC Nuclear Power Engineering Committee OUR STANDARDS NPEC maintains 51 existing standards, 23 of those standards having full or partial NRC endorsement. NPEC standards are organized within these technical areas:
Equipment Qualification Operations/Maintenance/Aging/Testing/Reliability Auxiliary Power Systems Human Factors and Control Facilities Safety-Related Systems STANDARDS DEVELOPMENT NPEC has a total of 25 standards projects currently underway, including 5 new standards:
EMC Testing of Electrical and I&C Equipment Computer Based Displays for Monitoring & Control Application of the Single-Failure Criterion Classification of I&C and Electrical Systems Common Cause Failure Systems Analysis and Diversity 39
SIGNIFICANT ACTIVITIES Recent development/revision of several key nuclear power standards, including:
IEEE/IEC 387-63332, Diesel Generator Units Applied as Standby Power Sources IEEE Std-352, General Principles of Reliability Analysis IEEE Std-741, Protection of Class 1E Power Systems IEEE Std-1819, Risk-Informed Categorization and Treatment of Electrical Equipment IEEE Std-1205, Aging Effects on Electrical Equipment IEEE Std-1290 Motor Operated Valve Application, Protection, Control and Testing Coordination with NRC for Standards Endorsement Development of Joint-Logo Standards with IEC Participation in EPRI/NEI Advanced Reactor Codes and Standards (ARCS) Initiative NPEC Nuclear Power Engineering Committee 40
Learn More site.ieee.org/pes-npec/
NPEC Nuclear Power Engineering Committee 41