ML23251A057

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Session 1 - Importance of Standards, Opportunities for Participation and Collaboration
ML23251A057
Person / Time
Issue date: 09/13/2023
From: Robert Roche-Rivera
NRC/RES/DE
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Download: ML23251A057 (41)
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Importance of Standards, Opportunities for Participation and Collaboration Opening RemarksDivision Director, RES/DE by Michele Sampson, NRC Standards Executive;

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 USG NSSCET OBJECTIVES

Objective 1: Investment

Objective 2: Participation

Objective 3: Workforce

Objective 4: Integrity & Inclusivity CRITICAL AND EMERGING TECHNOLOGIES IDENTIFIED IN THE USG NSSCET

ARTIFICIAL INTELLIGENCE & COMMUNICATION & NETWORKING MACHINE LEARNING TECNOLOGIES

SEMICONDUCTORS BIOTECHNOLOGIES & MICROELECTRONICS

DIGITAL ID INFRASTRUCTURE & DISTRIBUTED QUANTUM INFORMATION LEDGER TECHNOLOGIES TECHNOLOGIES

RENEWABLE ENERGY GENERATION & STORAGE SPECIFIC CET APPLICATIONS

Automated & Connected Infrastructure Biobanking Smart cities, Internet of Things, and Involves the collection, storage, and other novel applications use of biological samples from individuals

Automated & Connected Transportation Electric Vehicles (EVs)

Autonomous vehicles, unmanned Standards to integrate EVs with the aircraft systems, automated subway electrical grid systems, smart cities, internet-of-things, and other possible applications

Critical Mineral Supply Chains Cybersecurity & Privacy Cross-cutting issues that are critical to Cross-cutting issues that are critical to enabling the development and enabling the development and deployment of emerging technologies deployment of emerging technologies and data security and data security USG NSSCET LINES OF EFFORT

Greater Investment in Pre-Participation in Standards Standardization Research Development Increase R&D funding for CETs Remove and prevent barriers to Support development of standards private sector participation that address risk, security, and Improve communication between resilience public and private sector Enhance USG representation and influence in international standards governance and leadership

Workforce Development Ensuring Integrity in Standards Development Educate and empower the new standards workforce Deepen standards cooperation withpartners and allies

Facilitate broad representation in standards development DEVELOPING A USG NSSCET IMPLEMENTATION PLAN

Communication and coordination information on standards.gov

NIST as point of Listening Sessions and additional stakeholder entry to engaging on engagement workshops the USG National Standards Strategy for NIST Visiting Committee on Advanced Technology Critical and Emerging Subcommittee on International Standards Technology Development

Request for Information on barriers to increased standards engagement (Sept 2023)

Advanced Reactors Codes and Standards Collaborative (ARCSC)

Frankie Pimentel-Sr. Project Manager, Engineering and Risk, NEI 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 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.

North American Advanced Reactors Codes & Standards Collaborative - Overall Process

Outreach/raise awareness (about overall initiative and status/ways to engage in SDOs standards development activities)

ARCSC Committee Membership includes SDOs, NEI, EPRI

SDO committees

AR developers

Industry (utilities/

operators, suppliers)

Regul ato rs

Research (national labs, academia)

ARCSC Workshop and Information Collection

  • Provide information - Developing a list of C&S related to Nuclear Advanced Reactors
  • Engage with the nuclear community to i de nt i f y and prioritize C&S gaps for advanced reactor designs Sur vey/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 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 Sur vey (in Development)

Attend Workshops to help us develop the Roadmap for Advanced Reactors Codes and Standards Participate at standards development meetings American Nuclear Society

U.S. Nuclear Regulatory Commission Standards Forum September 13, 2023

Andrew Sow der, Ph.D., CHP, ANS Standards Board Chair

©2023 American Nuclear Society ANS Standards - A Key Piece of the Nuclear SDO Pie

ANS Standards Committee (SC) responsiblefor 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 formedical purposes

Established in 1957 Produced earliest nuclear industrystandards

Accredited by American National StandardsInstitute (ANSI) in 1967

Maintains 88 current ANSI standards across8 Consensus Committees (CCs)

The ANS Standards Committee

Standards Board (governance)

Risk-informed, Multiple Principles and Policy Performance-based Committee (RP3C) Task Groups

Joint Large Light Nonreactor Nuclear Research and Safety &

Environmental Fuel, Waste & Committee on Water Nuclear Criticality Advanced Radiological

& Siting Decommissioning Nuclear Risk Reactors Facilities Safety Reactors Analyses Consensus Consensus Management Consensus Consensus Consensus Consensus Consensus Committee Committee (JCNRM)* Committee Committee Committee Committee Committee (ESCC) (FWDCC) Consensus (LLWRCC) (NRNFCC) (NCSCC) (RARCC) (SRACC)

Committee

Subcommittees

Working Groups

  • JCNRM is a joint ANS/ASME consensus committee.

Many Existing Applicable Standards (for ARs)

ANSI/ANS-30.3-2022 ANSI/ANS-54.1-2020 LWR Risk-Informed, Nuclear Safety Criteria Design Performance-Based Design Process for SFRs ANSI/ANS-53.1-2011ANSI/ASME/ANS RA-S-1.4-(R2021) 2021 Nuclear Design Process for MHCRs PRA Standard for Adv. non-LWRs How ANS Informs AR Standard Development

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 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!

Leadership on North American Advanced Reactor Roadmap

Integration and harmonizationamong nuclear SDOs to support AR community via timely development of relevant codes and standards Owned and generated by industryinput from partners/stakeholders,

Three pillars: Regulatory efficiency Project execution Technology readiness Codes & Standards development akey element under Technology Readiness ANS - a foundational SDO on ARRoadmap development and execution ANS Standards Board Leadership ANS Staff

Andrew Sow der John Fabian ANS Standards Board Chair ANS Director of Publications asowder@epri.com jfabian@ans.org

Todd Anselmi Pat Schroeder ANS Standards Board Vice Chair ANS Standards Manager todd.anselmi@inl.gov pschroeder@ans.org

555 N. Kensington Ave.

La Grange Park, IL 60526 708-579-8269 (Pat)

ASME Advanced Reactor Standards Development Ac t ivity

Tom Vogan ASME Senior Vice President and Chair of Council on Standards and Certification ASME Facts and Figures

Established in 1880 and headquartered in New York City, the American Society of Mechanical Engineers is a not -fo r-profit international society.

90,000+ 135+ 200+

Worldwide Countries with ASME Conferences Conducted Technical Courses &

Membership Members 25+AnnuallyMaster Classes Offered Annually

Offices: New York, NY; Washington, DC; Little Falls, NJ; Houston, TX; Beijing, China; and New Delhi, India Setting the Standard

Used in 100+ 500+ Standards 6,500+ Dedicated Countries & Products Volunteers

ASME is an international Pressure Vessels, Piping, Engineers, Researchers, Standards Development Nuclear Technologies, Government officials, etc.

Organization Elevators/Escalators, Cranes, enhancing public safety,

- Accredited by ANSI Performance Testing, etc. health, and quality of life

- Development process adheres to the principles and procedures outlined in the World Trade Transparency Impartiality and Coherence Organizations (WTO) Consensus Agreement on Technical Barriers to Trade (TBT) for development of Openness Effectiveness and Development international stan d ards Relevance Dimension

3 ASME Nucl ear Codes & Standards and SMR Activity The Boiler & Pressure Vessel Codes (BPVC)

Construction Codes Nuclear Construction &

BPVC I, Power Boilers In-Service Inspection Codes BPVC IV, Heating Boilers BPVC III, Construction of Nuclear Facility BPVC VIII, Pressure Vessels Components BPVC X, FRP Pressure Vessels BPVC XI, Nuclear In-service Inspection BPVC XII, Transport Tanks

Service Codes Code Case Books BPVC II, Materials BPVC V, Nondestructive Examination Boilers and Pressure Vessels BPVC IX, Welding, Brazing and Fusing Nuclear Components BPVC VI, Care and Operation of Heating Boilers BPVC VII, Care of Power Boilers BPVC XIII, Rules for Overpressure Protection BPVC Section III - SMR Activity

  • Section III is a technology neutral standard which can be applied to SMRs. The committeecontinuously works to evolve the standard to remain applicable to the advanced reactor needs.
  • Section III Groups involved with AR activity TG on Division 5 TG on Alt. Requirements WG on Advanced Advanced TG on BPV III/XI fo r components comm Manufacturing Manufacturing Interface ensurate with Safety &

Components Risk

  • 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 Section III DIV. 1 Light Water SMR Construction of Nuclear Facility Components

Division 1: Metallic vessels, heat exchangers, storage tanks, piping systems, pumps, valves, core support structures,

supports, and similar items.

Division 2:

C o n crete containment vessels with metallic linersSection III DIV. 5 Liquid Metal SMR Construction of Nuclear Facility Components

Division 5: High temperature reactors providing rules suitable fo r construction of gas and liquid cooled reactors and are under a more active development to meet the evolving needs of our advanced re a cto r stakeholders

Division 2:

C o n crete containment vessels with metallic liners BPVC Section XI Nuclear Inservice Inspection

  • Division 1: Inspection and Testing of Components of L i ght-Wa t e r-Cooled Plants
  • Division 2: Reliability Integrity Management (RIM)
  • A methodology to establish Inser vice Inspection criteria independent of the SMR technology (e. g., Molten Salt, HTGR, Liquid M eta l, etc. )
  • Technology neutral - applicable to all reactor designs
  • Alternative approach to current ISI activities, needed to accommodate new technologies.

Qualification for Mechanical Equipment and Operations and Maintenance Standards

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 QME provides the and new reactor owner requirements and concerns that they have guidelines for the The OM Code provides with utilizing current O&M qualification of active requirements for the Code rules with new mechanical equipment operation nuclear facility designs.

whose function is and maintenance and The new Code rules are tied directly to ASME required to ensure the Inservice Testing of qualification standards.

safe operation or safe nuclear power plant shutdown of a nuclear components.

facility.

A S ME H A R MONI ZAT I ONAC TIVITY ASME & Nuclear Regulatory Commission

  • ASME standards are cited in the NRC Regulations as well as Regulatory Guides.

Rulemaking Guidance Development Developing and amending Standards Developing and revising regulations that licensees guidance documents, such must meet Development as regulatory guides 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

Representation on ASME/NRC Management meeting is all ASME consensus committees & held twice a year to discuss high m o st subordinate committees at the l eve l priorities for technical working level the consensus committees 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.

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. N - Vessels, pumps, valves, piping systems, storage tanks, core suppor t structures, concrete containments, and transpor t packaging NA - Field installation and shop assembly of all items NPT - Par ts, appur tenances, welded tubular products, and piping subassemblies NS - Suppor ts NV - Pressure relief valves N3 - Transpor tation containments and storage containments OWN - Nuclear power plant owner
  • 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".

ASME Events 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.

NPEC Nuclear Power Engineering Committee

Mark Bowman

Chair, IEEE Nuclear Power Engineering Committee 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.

OUR STANDARDS NPEC NPEC maintains 51 existing standards, 23 of those Nuclear Power Engineering Committee 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 STANDARDS DEVELOPMENT
  • S a fe t y-Related Systems 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 NPEC Nuclear Power Engineering Committee 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

Learn More site.ieee.org/pes-npec/

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