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Session 1 - Update on Industry Codes and Standards Initiatives
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Issue date:	09/28/2022
From:	Meraj Rahimi, Robert Roche-Rivera; NRC/RES/DE/RGDB
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Update on Industry Codes and Standards Initiatives Moderator: Meraj Rahimi, Branch Chief, RES/DE/RGPMB Panelists/Speakers:

Donald Eggett (ANS)

Andrew Sowder (EPRI)

Tom Basso (NEI)

Rachel Romano (ASME)

Ben Holtzman (NEI)

Robert Konnik (IEEE)

ANS Nuclear Standards Collaborative (NSC) to Support Advanced Reactor Standards Needs NRC Standards Forum September 28, 2022 Donald R. Eggett, Chair Andrew Sowder, Vice-Chair ANS Standards Board 2

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Background===

Multiple reports have been issued and workshops held identifying the need for standards for the advanced reactor community. Some of these have included:

From 2015 to 2017, the NRC and the U.S. Department of Energy (DOE) co-hosted three Advanced Reactor Workshops. The NRC has transitioned from workshop format to more frequent periodic stakeholder meetings.

NRC Standards Forum on advanced reactors (September 2017)

ORNL/SR-2017/520, Assessment of Applicability of Standards Endorsed by Regulatory Guides to Sodium Fast Reactors (September 2017)

ANS/NRC Workshop to Develop a Strategic Vision for Advanced Reactor Standards (May 2018)

NEI 19-03 (Rev. 1), Advanced Reactor Codes and Standards Needs Assessment (March 2020)

ANS/NEI Advanced Reactor Codes and Standards Workshop (June 2020)

NRC Standards Forum emphasized need for better industry coordination (October 2020).

NRC Standards Forum (September 2021) aimed the discussion at collaborating/accelerating development of C&Ss and NRC endorsement of such in its regulations and reg guides.

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ANS/EPRI Joint Nuclear Standards Collaborative Proposal ANS proposed a Nuclear Standards Collaborative (NSC) in 2021 with ASME/EPRI in mind. EPRI has since committed to full engagement.

a centralized industry led team to ensure there is coordination and collaboration among standards This proposal parallels the development organizations focus of NRCs Forums:

(SDOs) to support the reactor designers, aims to identify regulators, and other standards needs for stakeholders the nuclear industry to develop industry that are not currently standards and/or being addressed by guidelines in support of the standards development designers advanced organizations (SDOs) such reactor designs. as ASTM, ASME, ACI,ANS, IEEE, etc.

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Focus of NSC Primary focus is on the integration and harmonization among all SDOs to support advanced reactor designers on the needs for developing such standards. Though the focus will be on advanced reactors, nonreactor nuclear facilities and current operating reactors may be given some consideration relative to their prioritized needs for consensus standards or industry guidelines.

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Objectives of NSC Develop appropriate interrogatories, agendas, and other actions necessary to facilitate strategies and action plans that support the development of codes, standards, and other guidance that foster licensing, design, construction, and operation of advanced reactors. Specific actions include:

Establish a list of advanced reactor needs using existing industry resources.

Solicit additional standards needed from Nuclear Standards Collaborative members based on users prioritization.

Compile a list of all standards currently being developed or revised and planned by SDOs and other stakeholders that will support advanced reactor initiatives.

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Objectives of NSC (Contd)

Develop a roadmap for advanced reactor standards needs across all participative SDOs based on above gathered information.

Develop a recommended list of standards development priorities with associated targeted milestones from this roadmap.

Develop plans that are optimal in meeting the needs of developers/designers and stakeholder organizations. Formats may include virtual, face-to-face, or hybrid meetings and the structuring of semi-annual international forums with the mission of assembling stakeholders to obtain their input, comments, priorities, and challenges.

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Envisioned NSC Organization ANS EPRI AISC ACI NSC to be governed by a steering committee.

ASCE ASME ANS Standards Board Chair, EPRI senior manager to lead the ASTM AWS steering committee.

Membership to be comprised of core HPS Designers group industry members, working independently but with support of the DOE INMM NSC, ANS and EPRI leadership to drive achievement of timely needed prioritized IEEE standards by the designers based on an NEI industry consensus.

ISA NRC NFPA International NIRMA Vendors 8

Transitioning from NSC to North America Advanced Reactor Roadmap What is the NAAR Roadmap?

Industry initiative sponsored by NEI and EPRI A shared vision among industry stakeholders Owned and generated by industry, input from partners/stakeholders Four pillars to success

Market Demand

Regulatory Efficiency

Technology Readiness

Project Execution Why Transition from NSC to NAAR Roadmap Complementary in vision and strategic goals Broadens stakeholders International participation & engagement (CNS, IAEA, WNA, others)

Envisioned SDO-led committee for accelerating C&S development gets elevated visibility 9

Benefits to Transition and Participation Improve the identification and prioritization of needed standards through engagement, input and collaboration with industry stakeholders.

Determine which subject matter is best covered by standards vs.

other industry documents (guidelines).

Incentivize the harmonization of integrated codes & standards and collaborative SDO activities.

Expedite standards development through an industry process for funding and possible trial use.

Standards that better meet design goals, challenges and development timelines, and provide a path to efficient regulatory approval.

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Benefits to Participation (Contd)

SDOs will realize benefits as follows:

Integral part of recommendations to ensure prioritization of timely needed standards to better plan for and allocate limited supporting resources.

Ensure standards are relevant and support industry objectives.

Increased participation of advanced reactor developers/vendors standards development.

Develop more harmonized and better-quality standards through collaboration

Establish better collaboration with industry 11

Envisioned New SDO-led C&S Organization ANS CNS ASME WNA IAEA NEI EPRI SDO-Led Advanced Reactor Codes and Standards Workshop: Planning Meeting, IEEE ASTM December 1, 2022, EPRI Office, Washington, D.C. ACI AISC Discussion on the formation of a SDO-led Vendors Designers organization in the interest of accelerating the need for consensus standards.

DOE NRC AWS ASCE ISA HPS Utilities 12

Summary: What This Transition Does NAAR Roadmap: A multi-organization campaign dedicated to accelerating the development of industry consensus standards for advanced nuclear energy systems.

Guiding principle: Greater use in determining industry consensus standards, where needed, in the NRC licensing and regulatory processes Expands involvement through U.S. and international participation incentivizes harmonization of C&Ss 13

Integration of ANS Nuclear Standards Collaborative (NSC) into NEI-EPRI North American Advanced Reactor Roadmap 14

Advanced Reactor Roadmap Phase 1:

North America 15

Strategic Framework 16

Strategic Elements Codes and Standards for advanced reactors included as a key element within Roadmap 17

Role of Nuclear Standards Collaborative

ANS Nuclear Standards Collaborative fully compatible with Roadmap

Provides the issue ownership for coordinated actions among SDOs

Accountability to industry executives via Roadmap offers path to priority and resources needed to enable AR commercialization 18

Connectivity to Industry Executives

1. SDOs own C&S Codes & Standards coordination and action Element 2. Informed by AR industry gaps/needs Nuclear Standards Collaborative 3. Resourcing from (SDOs) industry to meet gaps/needs 19

Advanced Reactor Standards Needs QUESTIONS/COMMENTS 20

21 Standards Committee III Strategic Items Update NRC Standards Forum September 28th, 2022 Tom Basso Section III Executive Strategic Advisory Council 22

Section III Strategic Priorities

Strategic priorities focus resources

Developed by the Section III Leadership

- Input from industry stakeholders

Items of Strategic Importance

- Targets actionable goals for each Code Edition

- Guides long-term development

Managed by the Executive Committee 23

2023 Edition Strategic Priorities

SI-2023-01 Increasing Value of Section III

- Objective is to align value with safety

Modify requirements that add little or no value independent of risk

Develop alternate rules for items commensurate with safety and risk

SI-2023-02 Improve Section III/XI Interface

- Objective is to align and modify requirements to improve the transition from construction to in-service inspection

SI-2023-03 Support for Advanced Manufacturing

- Objective to support the use of Advanced Manufacturing

Provide General Requirements (e.g., QA, process qualification)

Provide rules for high temperature service (Division 5) 24

2023 Edition Strategic Priories

SI-2023-04 Development of Seismic Action Plan

- Objective is to develop a road map to modernize and coordinate the develop of seismic design rules

Nearing completion of a roadmap

Transition to the Execution Phase for 2025 Code Edition

SI-2023-05 Implementation of Fatigue Action Plan

- Objective is to execute the fatigue action plan developed 2018

Accomplished majority original plan

Expecting to close out this item with the 2023 Edition

SI-2023-06 NCA Rewrite

- Objective is to complete the NCA rewrite Phase III

Expecting to close out this item with the 2023 Edition 25

2025 Edition Strategic Priorities

Currently developing priorities for 2025 Edition

Expecting carry overs from 2023

- Increasing the value of Section III

- Improving the Section III/XI interface

- Advanced Manufacturing

Candidates for 2025 Edition

- Transition to implementation of Seismic Action Plan

- Support for advanced reactors with a focus on:

Design rules for High Temperature Service

Materials for High Temperature Service 26

Proposal to Establish Alternate Requirements for Components Commensurate with Safety and Risk NRC Standards Forum September 28, 2022 Rachel Romano, MPR Associates 27

Problem Statement Summary

Section III is developing alternative requirements commensurate with an items contribution to safety and risk (e.g., NEI 18-04)

- Results in increased value for construction

- Aligned with the design needs of advanced reactors

Current available options to construct such items:

- Construct to requirements of Section III

- Construct to industrial codes and as necessary, apply additional requirements ASME Section III Industrial Codes + Additional Requirements Rules well suited for nuclear Value commensurate with items applications contribution to safety and risk Value may not be commensurate Industrial design rules not well with items contribution to safety suited for nuclear application and risk 28

Proposed Solution

Provide a new construction option commensurate with an items contribution to safety and risk via alternative requirements within Section III that:

Uses design rules developed specifically for nuclear applications AlignsSection III construction requirements with typical industrial codes Technical Basis:

- Nuclear design rules are already used in nuclear applications

- Construction of low safety significant items to industrial code requirements is already permitted (e.g., 10CFR50.69) 29

Focus Areas

Materials, Fabrication, and Examination Requirements

- Code revisions for alternate material procurement

- Code Case to permit alternate methods for NDE and testing

Quality Requirements

- Subsection NCA revision for alternate quality requirements Alt. Material Code Case NCA Revision Code Revisions

C&S Connect *Before 2025 Code *2025 Code Edition Record No.22-979 Edition

2023 Code Edition 30

Regulatory Strategy

Reason for a Regulatory Strategy

- Unique approaches

- Stakeholder needs

- Broader and more frequent engagement

Strategy

- NRC Drop-ins

- Public Meetings or Workshops

White papers

- Apply various regulatory options

Expedited endorsement 31

Questions?

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Backup Slide 33

Alternate Requirements Code Case Evolution 34

Digital Twin Overview NRC Standards Forum Ben Holtzman Nuclear Energy Institute September 28th, 2022

The Next Step of Nuclear Innovation Various Applications

What If Analysis

Inform Design Activities

Current Industry

Next Steps A Rose by Any Other Name...

One Small Step New tools but existing regulatory framework

Questions?

IEEE NPEC Standards Update Robert Konnik IEEE NPEC Secretary 40

Overview NPEC (Nuclear Power Engineering Committee) has 50 Standards with about 28 currently in revision NPEC's principal subcommittees cover:

Equipment Qualification; Operating, Aging, Maintenance, Testing and Reliability; Auxiliary Power; Human Factors and Control Facilities; Safety Related Systems IEEE Standards are updated on a 10-year cycle to keep them current Many standards are in revision for 3 to 6 years Many standards are not specific to reactor technology and standards have been extended from Nuclear Power Generating Stations to Nuclear Facilities Consequences of New Reactor Technology on NPEC Standards is Being Reviewed 41

Select Standards In Revision IEEE/IEC 60780-323 IEC/IEEE International Standard - Nuclear facilities --

Electrical equipment important to safety - Qualification is starting a revision There has been some discussion with new reactor vendors on possible updates IEEE 383 Standard for Qualifying Electric Cables and Splices for Nuclear Facilities is being readied for Ballot Over the last couple of revisions, there have been updates to address some issues raised because of passive reactors (such as submergence) as well as lessoned learned over the last 50 years This is a test standard, so advanced reactors may not require any changes to the test methodology: Note these standards do not include Test Profiles IEEE 1682 IEEE Standard for Qualifying Fiber Optic Cables, Connections, and Optical Fiber Splices for Use in Safety Systems in Nuclear Power Generating Stations was developed in 2011 to address new reactors and control systems This standard is in ballot now with some updates based on experience gained since the initial revision 42

Additional Standards IEEE 2425 Standard for Electromagnetic Compatibility Testing of Electrical and Instrumentation and Control Equipment at Nuclear Power Generating Stations and Other Nuclear Facilities is a new standard being developed that should be in ballot soon In SC2 a new subcommittee has been formed for the IEEE/IEC 62582 standards on condition monitoring. These have been developed in the last decade and many are now being revised.

IEEE 1205 IEEE Guide for Assessing, Monitoring, and Mitigating Aging Effects on Electrical Equipment Used in Nuclear Power Generating Stations and Other Nuclear Facilities in Revision IEEE 317 IEEE Standard for Electric Penetration Assemblies in Containment Structures for Nuclear Power Generating Stations in Revision 43

In Ballot IEEE 338 IEEE Standard for Criteria for the Periodic Surveillance Testing of Nuclear Power Generating Station Safety Systems in Ballot IEEE 334 IEEE Standard for Qualifying Continuous Duty Class 1E Motors for Nuclear Power Generating Stations in Ballot IEEE 420 IEEE Standard for the Design and Qualification of Class 1E Control Boards, Panels, and Racks Used in Nuclear Power Generating Stations in Ballot IEEE/IEC 62582 Series on Condition Monitoring IEC/IEEE International Standard - Nuclear power plants - Instrumentation and control important to safety - Electrical equipment condition monitoring methods Part 2: Indenter measurements in Ballot Part 3: Elongation at break in Ballot Part 4: Oxidation induction techniques in Ballot Note, Part 1: General in Draft 44

Published in 2022 IEEE 577-2022 IEEE Standard Requirements for Reliability Analysis in the Design and Operation of Safety Systems for Nuclear Power Generating Stations and Other Nuclear Facilities IEEE 741-2022 IEEE Standard for Criteria for the Protection of Class 1E Power Systems and Equipment in Nuclear Power Generating Stations IEEE 765-2022 IEEE Standard for Preferred Power Supply (PPS) for Nuclear Power Generating Stations (NPGS)

IEEE 1786-2022 IEEE Guide for Human Factors Applications of Computerized Operating Procedure Systems (COPS) at Nuclear Power Generating Stations and Other Nuclear Facilities 45

QUESTIONS 46

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