ML22297A198
| ML22297A198 | |
| Person / Time | |
|---|---|
| Issue date: | 10/26/2022 |
| From: | Meraj Rahimi NRC/RES/DE/RGDB |
| To: | Louise Lund NRC/RES/DE |
| References | |
| Download: ML22297A198 (14) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 26, 2022 MEMORANDUM TO: Louise Lund, Director Division of Engineering Office of Nuclear Regulatory Research FROM: Meraj Rahimi, Branch Chief /RA/
Regulatory Guide and Programs Management Branch Division of Engineering Office of Nuclear Regulatory Research
SUBJECT:
SUMMARY
OF THE 2022 NRC STANDARDS FORUM On September 28, 2022, staff from the Office of Nuclear Regulatory Research (RES) and Office of Nuclear Reactor Regulation (NRR) held the 2022 U.S. Nuclear Regulatory Commission (NRC) Standards Forum.1 The purpose of the Standards Forum is to facilitate discussions on codes and standards (C&S) needs within the nuclear industry and explore how to collaborate in accelerating the development of C&S and the NRC's endorsement of these C&S in its regulations and regulatory guides. The focus of forum this year was on facilitating discussions on C&S that need to be updated or should be developed to support advanced reactor technologies. contains the Agenda for the Forum. Approximately 240 attendees joined the event, including participants from NRC staff, representatives from Standards Development Organizations (SDOs) such as American Nuclear Society (ANS), American Society of Mechanical Engineers (ASME), American Concrete Institute (ACI), American Society of Civil Engineers (ASCE), and Institute of Electrical and Electronics Engineers (IEEE), the Nuclear Energy Institute (NEI), Electric Power Research Institute (EPRI), representatives from the U.S.
Department of Energy (DOE), national laboratories, and academia representatives among others (see Enclosure 2 for the full list of attendees). The presentations from the meeting can be found at https://www.nrc.gov/about-nrc/regulatory/standards-dev/standards-forum/2022.html.
Summary The Standards Forum opened with remarks by Louise Lund, NRC Standards Executive, covering the purpose of the Standards Forum, an overview of the agenda, and prior internal and external C&S activities upon which the Standards Forum was built. This years event included six sessions.
CONTACT: Robert Roche-Rivera 301-415-8113 1
Public Meeting Notice: https://www.nrc.gov/pmns/mtg?do=details&Code=20220808
L. Lund These sessions covered initiatives being undertaken by industry in support of C&S; efforts by the NRC staff for streamlining the NRCs review and endorsement of C&S; perspectives from advanced reactors developers regarding their needs and priorities for C&S; perspectives from nuclear as well as aerospace industry representatives on the rapid qualification of advanced manufacturing technologies; research developments related to advanced constructions technologies; and discussions on recent and planned developments on a number of specific C&S. The discussions were valuable to understanding areas for further collaboration across SDOs and how the NRC and stakeholder groups can be more effective in developing, updating, and meeting the codes and standards needs. The following is a summary of the discussions in the sessions.
Session 1: Update on Industry Codes and Standards Initiatives Session 1 was moderated by Meraj Rahimi, Branch Chief of the Regulatory Guide and Programs Management Branch within the Division of Engineering (DE) in RES. The session included four presentations as follows:
- 1. Nuclear Standards Collaborative (NSC) and Integration of ANS Nuclear Standards Collaborative (NSC) into NEI-EPRI North American Advanced Reactor Roadmap (Donald Eggett, ANS and Andrew Sowder, EPRI)
- 2. ASME Standards Committee III Strategic Items Update and Proposal to Establish Alternate Requirements for Components Commensurate with Safety and Risk (Tom Basso, NEI and Rachel Romano, ASME)
- 3. Digital Twin Overview (Ben Holtzman, NEI)
- 4. IEEE NPEC Standards Update (Robert Konnik, IEEE NPEC)
The session opened with a combined presentation and discussion on the NSC and NEI-EPRI North American Advanced Reactor (NAAR) Roadmap. The NSC is a centralized industry led team aimed at coordinating and collaborating among SDOs to support the reactor designers, regulators, and other interested stakeholders in the development of industry standards and/or guidelines for advanced reactor designs. Its primary focus is on the integration and harmonization among all SDOs, and its objectives include the development of 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. Since the development of the NSC, NEI, and EPRI undertook an initiative to develop the NAAR roadmap. Given the complementary vision and strategic goals between the NSC and the NAAR roadmap, the broader stakeholder participation in the NAAR Roadmap, including international participation and engagement, the NSC will be merging with/transitioning to the NAAR Roadmap. The NAAR Roadmap focuses on four principal strategic elements (each one having a subset of additional elements), which include market demand, regulatory efficiency, technology readiness, and project execution. C&S for advanced reactors is included as key element within the technology readiness strategic element. The roadmap is anticipated to be issued by November 2022.
This presentation was followed by a combined presentation on ASME standards committee III strategic items update and proposal to establish alternate requirements for components commensurate with safety and risk. The 2023 priorities discussed included: increasing the value of Section III (including development of alternate rules for items commensurate with safety and risk; improving the interface between ASME Boiler and Pressure Vessel (BPV) Code
L. Lund Sections III and XI; and support for advanced manufacturing (including rules for high temperature service), amongst other. Regarding increasing the value of Section III, ASME is considering the development of alternative requirements based on component categorization, for example, based on the categorization process in NEI-18-04, Risk-Informed Performance-Based Technology-Inclusive Guidance for Non-Light Water Reactor Licensing Basis Development. The alternative requirements would use Section III rules developed specifically for nuclear applications as well as updated Section III requirements that align with typical industrial codes. The current focus areas for this effort include materials, fabrication, examination, and quality requirements. ASME and industry representatives plan on engaging in further discussions with the NRC via public meetings and workshops, amongst other.
Following the above-mentioned presentation, was a presentation covering an overview on Digital Twins. The presentation discussed efforts by ARPA-E and EPRI in this area. ARPA-E is working through the Generating Electricity Managed by Intelligent Nuclear Assets (GEMINA) program, whose goal is to lower plant operating costs through automation and autonomy. EPRI has developed a task force to identify the gaps and align on an implementation strategy for the digital twin applications in nuclear. The initial focus of the ongoing industry efforts is on modeling subcomponents and some specific components. The EPRI report (3002023904) titled, Program on Technology Innovation: Digital Twin Applications for Advanced Reactors, is anticipated to be publicly available in October 2022.
The session ended with a presentation that discussed the ongoing efforts for the update of IEEE Nuclear Power Engineering Committee (NPEC) standards. Many of the IEEE NPEC Standards are not specific to a reactor technology and many standards have been extended from nuclear power generation stations to nuclear facilities therefore enabling a broader applicability and use of the standards. IEEE NPEC is looking into changes that may be needed to support new reactor technologies. IEEE has received input from advanced reactor stakeholders regarding needed updates for IEEE/IEC 60780-323 IEC/IEEE International Standard -Nuclear facilities -
Electrical equipment important to safety -Qualification, and IEEE NPEC is initiating the efforts to revise this standard in the near term.
Session 2: Advanced Reactor Developers Perspectives on Codes and Standards Session 2 was moderated by Mark Richter, Technical Advisor at NEI. Opening remarks by Mark Richter included sharing perspectives on the role of C&S in support of the design and deployment of advanced reactor technologies. Mr. Richters remarks were followed by presentations from NuScale, TerraPower, and X-Energy representatives providing an overview of their reactor technologies and their perspectives on codes and standards needs and priorities to support their technologies. The following table provide a summary of the standards needs and priorities discussed in this session.
L. Lund Advanced Reactor Codes and Standards Needs/Priorities Developers ASME Section XI
- New rules for IWB IWB-3500 standards for application to austenitic vessel materials, dissimilar metal vessel material welds, and austenitic bolting material.
- New rules for Section XI, Mandatory Appendix VIII for application to austenitic vessel materials and dissimilar metal vessel material welds.
NuScale ASME O&M Code - Resolution of how to implement a single IST plan for multiple modules.
NRC endorsement of ANS 30.3, Light Water Reactor Risk Risk-Informed, Performance Performance-Based Design.
ASME BPV - Section III, Division 5, High Temperature Reactors, and Section XI, Division 2 (RIM), Appendix 7 TerraPower ASME OM-2 ASME QME-2 IEEE Standards 323 and 344 ASME BPV Section III, Division 5 for RPV and Metallic Internals and Graphite Structures X-Energy NRC final endorsement of Section III, Division 5 Session 3: Rapid Qualification of AMT Components - Is it Rocket Science?
Session 3 was moderated by Raj Iyengar, Branch Chief of the Reactor Engineering Branch within RES/DE, and Dirk Cairns-Gallimore, Lead for the Advanced Materials and Manufacturing Technologies Program within the Reactor Fleet and Advanced Reactor Deployment group in the DOE Office of Nuclear Energy. This session provided a panel discussion on various considerations on rapid qualification of components using advanced manufacturing technologies (AMT), while ensuring safe use of these components in service. Representatives from NASA, CEA, France, BWXT, and Relativity Space, shared their perspectives on the rapid qualification of AMT components including discussions of modeling and simulation, data analytics, and in-situ optimization, amongst other, to aid the qualification process. Furthermore, the first presentation in the session provided an overview of NASAs certification and qualification strategies for additively manufactured hardware per NASA-STD-6030, Additive Manufacturing Requirements for Spaceflight Systems, issued in April 2021. The second presentation covered, existing tools and processes for implementing new materials or new processes into French C&S and the approach for using those tools and processes to address the qualification of additively manufactured components. The third presentation covered predictive approaches used by BWXT to support the rapid and optimized design, manufacture, and qualification of nuclear products. The fourth presentation covered the use of AMT technologies by Relativity Space, for the successful and rapid production of large-scale metal structures. Further, the presentation covered current inspections and validation methods as well as efforts to enhance and transition to the use of in-situ monitoring for establishing the quality of the products being manufactured.
L. Lund Session 4: Regulatory Initiatives for Streamlining Code & Standards Endorsement Session 4 was moderated by Wendell Morton, Branch Chief of the Electrical Engineering Branch, within the Division of Engineering and External Hazards (DEX) in NRR. The session included three presentations as follows:
- 2. Information SECY-22-0075, Staff Requirements - SECY-21-0029 Inservice Testing and Inservice Inspection Program Rulemakings Update (David Rudland)
- 3. Regulatory Guidance Framework for IEEE Electrical Standards (Sheila Ray)
The first presentation in this session provided an update on the NRC staffs efforts to increase the frequency of endorsement of unconditionally approved Code Cases and streamline the ASME rulemaking process for code editions and conditionally approved code cases. The staff is working on plans to develop a dedicated 10 CFR 50.55a Office of Management and Budget (OMB) clearance and re-analyzing information collection impacts to develop guidance on when submission to OMB might not be required. The goal is to provide annual endorsement of unconditionally approved Code Cases while maintaining biannual endorsement of Code editions and conditionally approved Code Cases. This presentation was followed by a presentation on a summary of SECY-22-0075, Staff Requirements-SECY-21-0029 Inservice Testing and Inservice Inspection Program Rulemakings Update [NRC-2018-0291/3150-AK23]. SECY 0075 is an information SECY for the Commission, that explains deviations from SECY-21-0029 and how the staff plans to develop the proposed rule addressed in SECY-21-0029 regarding a rulemaking plan for extending the code of record (COR) interval for inservice testing (IST) and inservice inspection (ISI) programs. Three major changes include, combining two proposed rulemakings into one, making conforming changes to 10 CFR Part 50, Appendix J, and possible conforming and clarifying changes to address issues encountered during the development of the proposed rule. The session ended with a presentation that provided an update on the key regulatory guides that form part of the staffs regulatory guidance framework for IEEE electrical standards.
Session 5: Recent and Planned Developments and Updates in Codes and Standards, Part 1 Session 5 was moderated by Angela Buford, Branch Chief of the Vessels and Internals Branch, within the Division of New and Renewed Licenses in NRR. The session included five presentations as follows:
- 1. Research and Advanced Reactor Consensus Committee (RARCC), 2022 Activities (George Flanagan, ANS)
- 2. ANS-30.3 -2022, Light-Water Reactor Risk-Informed, Performance-based Design (Kent Welter, ANS)
- 4. ASME QME-2 Qualification of Mechanical Equipment and ASME OM-2 Operation and Maintenance of Nuclear Power Plants (Steven Unikewicz, ASME)
- 5. ASME Section III Seismic Design Steering Group - Introduction (Timothy Adams, ASME)
The session opened with a presentation on ongoing efforts being pursued by the ANS RARCC for updating and or developing new standards for research and advanced reactors. RARCC has two subcommittees namely, the research and test reactor subcommittee which currently
L. Lund has 10 standards or projects in development, and the advanced reactors subcommittee with currently has five standards or projects in development. The discussion focused on the following advanced reactor standards:
- ANS-53.1-2011 (R2021), Nuclear Safety Design Process for Modular Helium- Cooled Reactor Plants - The standard was reaffirmed in October 2021. A revision is being initiated with focus on making the standard more inclusive of other high temperature gas reactor types.
- ANS-54.1-2020, Nuclear Safety Criteria and Design Process for Sodium Fast Reactor Nuclear Power Plants - The standard was approved in 2020 and remains current. The scope covers all sodium fast reactor nuclear power plants, irrespective of level of power production and energy end use. It also applies to configurations in which there are one or more reactor units (modules) on a site.
- ANS-20.2-202x, Nuclear Safety Design Criteria and Functional Performance Requirements for Liquid-Fuel, Molten-Salt Reactor Nuclear Power Plants - New standard in development. The standard provides design criteria for liquid-fuel, molten-salt reactors (MSRs); definitions of MSR terminology; it describes safety considerations for MSRs; and provides an MSR focused description of a risk-informed design process.
The standard was issued for formal ballot to the RARCC and parallel public review in August 2022.
- ANS-GS-30.1-202x, Integrating Risk and Performance Objectives into New Reactor Nuclear Safety Designs - The ANS Standards Board directed ANS-30.1 to be converted from a requirements standard to a guidance standard. The draft guidance standard is expected to be issued for review before the end of 2022.
- ANS-30.2, Classification and Categorization of Structures, Systems, and Components for New Nuclear Power Plants - New standard in development. Draft anticipated by August 2023 to begin subcommittee review.
The second presentation in this session provided an overview of the ANS standard ANS-30.3, Light Water Reactor Risk-Informed, Performance-Based Design. This standard was issued in July 2022. As discussed during the presentation, the purpose of this standard is to provide requirements for the incorporation of risk-informed, performance-based (RIPB) principles and methods into the nuclear safety design of new commercial light water reactors (LWRs). It establishes a minimum set of requirements to appropriately combine deterministic, probabilistic, and performance-based methods during design development. The ANS Standards Board has requested NRCs endorsement of this standard.
The third presentation in this session covered an update on the ASME Standard on Plant Systems Design (PSD). Per the discussion during this presentation, the PSD standard incorporates and integrates systems engineering, hazard and risk evaluation, and probabilistic design methods into traditional design processes; and provides detailed process and guidance on how to perform and integrate industry and regulatory concepts such as defense-in-depth, safety significance, and risk-informed and performance-based concepts into a design process.
The fourth presentation provided a discussion regarding ongoing efforts within ASME for developing QME-2 and OM-2 standards related to the qualification of mechanical equipment
L. Lund and operation and maintenance of nuclear power plants, respectively, for new and advanced reactor technologies. The intent for QME-2 is to be a function-based standard for pumps, valves, and dynamic restraints. The goal is to focus on the qualification (e.g., seismic and environmental qualification) of required/safety functions of the mechanical equipment. The standard is also intended to implement a risk-informed and graded approach to qualification and form the baseline for the IST per OM-2. A draft of the QME-2 standard is anticipated for 2023.
Consistent with the intent of the OM Code, OM-2 will focus on ensuring operational readiness, detection of degradation, and trend results so that a component can be reworked before failure.
Moreover, consistent with QME-2, the focus of IST per OM-2 is intended to be a component function. Rather than having the standard establish the scope of IST components, the standard intends to establish that the designer and regulator should define what would be in the scope of IST. Additionally, in OM-2, IST is intended to be independent of plant mode. A first final draft of OM-2 is anticipated for December 2022 and the final OM-2 is anticipated to be issued during 2024.
The fifth presentation provided an overview of the ASMEsSection III Seismic Design Steering Group and its roadmap for implementing changes to the seismic design rules and guidance.
The presentation provided a listing of 15 main items/topics for areas in need of update and additional items that the committee is considering based on review comments. The roadmap considered input from advanced reactor stakeholders. The steering committee for the roadmap anticipates getting ASME Section III approval of the roadmap by the end of 2022. The items to be updated per the roadmap are anticipated to be implemented in the 2025 and future editions of the ASME code.
Session 6: Recent and Planned Developments and Updates in Codes and Standards, Part 2 Session 6 was moderated by Madhumita Sircar, Senior Structural Engineer, in RES/DE. It included five presentations as follows:
- 1. NRIC Program & ACT Overview (Christy Williams, NRIC)
- 2. Planned Updated Code Provisions for Steel-Plate Composite Construction for the New Edition of the AISC N690 (Ronald Janowiak, AISC)
- 4. Modernization of the ASME Section III, Div. 2 Code (John McLean, ASME)
This session opened with a presentation that provided an overview on the Advanced Construction Technology (ACT) initiative under the National Reactor Innovation Center (NRIC) program. The objectives of the ACT initiative are to significantly reduce costs and schedule for nuclear power builds and demonstrate, in partnership with industry, technologies to enable commercial advanced nuclear by 2030. The demonstrations technologies addressed by the initiative include:
- Vertical shaft excavation techniques
- Steel Bricks system
- State-of-the-art digital twin replica
- Advanced condition and performance monitoring techniques The second presentation provided a discussion regarding the ongoing effort to update the provisions for steel-plate composite construction in AISC N690, Specification for Safety-
L. Lund Related Steel Structures for Nuclear Facilities. The anticipated updates include clarification and elimination/relaxation of certain limitations, including but not limited to, clarifying the applicability of the existing provisions to slabs and foundations and new requirements for maximum tie-bar spacing, new/revised provisions based on recent research such as permitting concrete contribution to out-of-plane shear strength to be based on 2 fc, and other changes that take into consideration current industry trends and needs such as specifying limits for accident and service temperature exposures, among others.
The third presentation in the session provided a discussion on potential updates under consideration for ASCE 4, Seismic Analysis of Safety Related Structures, and ASCE 43, Seismic Design Criteria for Structures, Systems, and Components, in Nuclear Facilities.
Specifically, theres an effort to merge these two standards into a single standard. Furthermore, the next update is intended to eliminate content in the domain of other SDOs (e.g., risk assessment [ANS], piping systems and supports [ASME]), in addition to limit state D (essentially elastic behavior), providing a pathway for limit states B (moderate permanent distortion) and C (limited permanent distortion), and ensure that the standard supports DOE best practices, among others.
The fourth presentation provided a discussion on efforts being undertaken by ASME for the modernization of ASME Section III, Division 2 (Code for Concrete Containment). These modernization efforts include improved guidance for impulsive and impactive loading, harmonization of design provisions for containment structures and non-containment nuclear structures, new provisions for fiber reinforced concrete to enhance concrete tensile capacity and resistance to impulsive/impactive loading, and Code Case or new Code for steel plate concrete composite construction, among others.
The fifth and last presentation in this session, provided a discussion on upcoming updates for several publications under the ACI Technical Committee 349, Concrete Nuclear Structures.
The updates under consideration include updates to load and load combinations, updated provisions for 80,000 psi rebar, new commentary referencing ASME Section III Division 2, and major changes in impulsive and impactive loading provisions, amongst other. The presentation also discussed new business items being considered by the committee including introduction of changes to ACI-349 in response to NEI 19-03, Rev 1, "Advanced Reactor Codes and Standards Needs Assessment," such as reassessing temperature limits for structural concrete.
Additionally, the committee is considering updates related to anchorage of embedment plates using groups of reinforcing bars, design for combined forces, moments, and shears, interaction of in-plane and out-of-plane shear, high strength materials, and 3D printed materials, among others.
The 2022 Standards Forum ended with closing remarks by Louise Lund, NRC Standards Executive. The Forum facilitated the sharing of information and perspectives with ongoing standards related efforts as well as needs for further standards development and updates.
Specific areas undergoing revisions and updates across multiple standards were highlighted as well as pathways for incorporation of new materials, methods, and technologies into multiple standards. The discussions also covered ongoing research that is anticipated to inform future standards updates and identified opportunities and areas for further coordination and collaboration across SDOs. Further, the discussions covered NRC efforts to streamline the endorsement of standards in NRC Regulations and Regulatory Guides. The discussions during the Forum are expected to lead to standards with wide ranging support that are more easily utilized by the NRC and licensees.
L. Lund
SUBJECT:
SUMMARY
OF THE 2022 NRC STANDARDS FORUM DATE:
It is anticipated that the next NRC Standards Forum will be scheduled for Fall 2023.
Enclosures:
Enclosure 1: 2022 Standards Forum Agenda Enclosure 2: 2022 Standards Forum List of Attendees DISTRIBUTION:
A. Buford, NRR R. Iyengar, RES W. Morton, NRR R. Gascot Lozada, RES S. Ray, NRR M. Rolon Acevedo, RES D. Rudland, NRR M. Sircar, RES K. Song, NRR I. Tseng, NRR ADAMS Accession Package No.: ML22266A199 OFFICE RES/DE/RGPMB RES/DE/RGPMB RES/DE/RGPMB NAME R. Roche-Rivera B. Curran M. Rahimi w/comments DATE 10/25/2022 10/26/2022 10/26/2022 OFFICIAL RECORD COPY
U.S. NUCLEAR REGULATORY COMMISSION 2022 NRC Standards Forum Wednesday, September 28, 2022, 10:00 AM to 05:15 PM ET Agenda Time Topic Speaker Louise Lund 10:00 - Welcome, logistics, introductions, and objectives Robert 10:05 Roche NRC Donald Eggett, ANS Update on Industry Codes and Standards Initiatives and Andrew Sowder, Moderator: Meraj Rahimi (NRC)
- 1. Nuclear Standards Collaborative (NSC) and Integration Tom Basso, of ANS Nuclear Standards Collaborative (NSC) into NEI- NEI and EPRI North American Advanced Reactor Roadmap Rachel 10:05 -
(Donald Eggett, ANS and Andrew Sowder, EPRI) Romano, 11:20
- 2. ASME Standards Committee III Strategic Items Update ASME and Proposal to Establish Alternate Requirements for Components Commensurate with Safety and Risk (Tom Ben Basso, NEI and Rachel Romano, ASME) Holtzman,
- 3. Digital Twin Overview (Ben Holtzman, NEI) NEI
- 4. IEEE NPEC Standards Update (Robert Konnik, IEEE Robert NPEC)
Konnik, IEEE NPEC Mark Richter, NEI Advanced Reactor Developers Perspectives on Codes and Standards J.J. Arthur, NuScale Moderator: Mark Richter (NEI) 11:20 -
Steven 12:00
- Perspectives from: Unikewicz, o NuScale (J.J. Arthur) TerraPower o TerraPower (Steven Unikewicz) o X-Energy (Timothy Lucas) Timothy Lucas, X-Energy 12:00 -
Lunch Break 12:45 Enclosure 1
Time Topic Speaker Rapid Qualification of AMT Components - Is it Rocket Richard W.
Science? Russell, NASA Moderators: Raj Iyengar (NRC) and Dirk Cairns-Gallimore (DOE-NE) Thierry Lebarbe, 12:45 -
- NASAs Certification and Qualification Strategies for CEA, France 1:45 Additively Manufactured Hardware (Richard W. Russell, NASA) Matt
- Predictive Technologies and Nuclear Product Qualification (Matt LeVasseur, BWXT) Josh Brost,
- Perspectives from Relativity (Josh Brost, Relativity) Relativity Regulatory Initiatives for Streamlining Code & Standards Endorsement Ian Tseng Moderator: Wendell Morton (NRC)
David 1:45 -
- Information SECY-22-0075, Staff Requirements -
SECY-21-0029 Inservice Testing and Inservice Sheila Ray Inspection Program Rulemakings Update (David Rudland) NRC
- Regulatory Guidance Framework for IEEE Electrical Standards (Sheila Ray)
George Recent and Planned Developments and Updates in Codes Flanagan, and Standards Part 1 ANS Moderator: Angela Buford (NRC)
Kent Welter,
- 1. Research and Advanced Reactor Consensus Committee ANS (RARCC), 2022 Activities (George Flanagan, ANS)
Ralph Hill, 2:15 - 2. ANS-30.3 -2022, Light-Water Reactor Risk-Informed, ASME 3:40 Performance-based Design (Kent Welter, ANS)
- 4. ASME QME-2 Qualification of Mechanical Equipment ASME and ASME OM-2 Operation and Maintenance of Nuclear Power Plants (Steven Unikewicz, ASME) Timothy
- 5. ASME Section III Seismic Design Steering Group - Adams, Introduction (Timothy Adams, ASME) ASME Time Topic Speaker 3:40 -
Break 3:50 Christy Williams, NRIC Recent and Planned Developments and Updates in Codes and Standards Part 2 Ronald Janowiak, Moderator: Madhumita Sircar (NRC)
- 1. NRIC Program & ACT Overview (Christy Williams, Andrew NRIC)
Whittaker,
- 2. Planned Updated Code Provisions for Steel-Plate 3:50 - ASCE Composite Construction for the New Edition of the AISC 5:10 N690 (Ronald Janowiak, AISC)
John
- 4. Modernization of the ASME Section III, Div. 2 Code (John McLean, ASME)
Madhumita
- 5. ACI Technical Committee 349, Concrete Nuclear Sircar, NRC Structures (Madhumita Sircar, NRC and Carlos and Cantarero Leal, ACI)
Carlos Cantarero Leal, ACI 5:10 -
Summary of key takeaways and closing remarks NRC 5:15 U.S. NUCLEAR REGULATORY COMMISSION NRC Standards Forum List of Attendees September 28, 2022 NRC Participant List Name Name Name Ben Adams Amy Hull Dogan Seber Reed Anzalone Ata Istar Madhumita Sircar Meg Audrain Raj Iyengar Alex Siwy Stewart Bailey Ian Jung Frederick Sock Courtney Banks Joshua Kaizer Kyle Song Antonio Barrett Kamal Manoly Jim Steckel Gurjendra Bedi William Kennedy Steve Jones Michael Benson Bruce Lin Gabe Taylor Angie Buford Louise Lund George Thomas Jesse Carlson Shah Malik Ian Tseng Alexander Chereskin John Matrachisia Lucieann Vechioli Feliciano Christopher Cook John McKirgan Dan Widrevitz Stephen Cumblidge Kenn Miller John Wise Bridget Curran Wendell Morton Yuken Wong Robert Davis Christopher Nellis Jim Xu Matthew Dennis Khoi Nguyen On Yee David Desaulniers Jinsuo Nie David Dijamco Noah Parquette Carolyn Fairbanks Hanh Phan Ismael Garcia Stephen Philpott Stanley Gardocki Jose Pires Ramon Gascot Lozada Jeff Poehler Matthew Gordon Andrew Prinaris Tyler Hammock Meraj Rahimi Nicholas Hansing Sheila Ray Michelle Hayes Wendy Reed Todd Hilsmeier Robert Roche-Rivera Matthew Hiser Marcos Rolon Acevedo John Honcharik David Rudland Kaihwa Hsu Michele Sampson Enclosure 2
List of Participants from the Public Name Name Name Name Timothy Adams Kurt Edsinger Ron Lippy Rachel Romano Marc Albert Don Eggett Leigh Lloveras Tom Ruggiero Lisa Anderson George Flanagan John William Lockaby Richard W. Russell Charlie Angelilli Melissa Franco DeLeah Lockridge Frank Schaaf Todd M. Anselmi Maria Luisa Garcia Heras Larisa Logan Pat Schroeder Michael Archer J Andrew Garcia Thomas R. Loomis Farshid Shahrokhi Robert Armistead Jim Gleason Tim Lucas Ting-Leung Sham J.J. Arthur Mark Allen Gowin Heramb P. Mahajan Todd Sherman Kenneth Baker Frederic F. Grant Daniel Mann Neal Simmons Ken Balkey Matt Gratias Oliver Martinez Adam Smith Thomas Basso John Grimes Adam Maslowski Thomas F. Solinsky Osama Bedair Daryl L. Harmon Steve McCracken Andrew Sowder Richard A.
Randy Belles Kurt Harris John B. McLean Stadtlander Jana Bergman Ralph Hill Bob McReynolds Adam Stein Bruce Balkcom Bevard David Holcomb Helen A. Mearns Kerry E. Sutton Jake Blanchard Benjamin Holtzman Ricardo A. Medina Benjamin Sutton Joshua Brost Kate Hyam Daniel Miro-Quesada Mark Svajger Melanie H. Brown Richard E. Jacob Vanessa Mitchell Mohamed M. Talaat Frederick Brust R. Jacobson Mark Moenssens Russell Thames Matthew D. Bucknor Ron Janowiak Luis Moreschi David Thompson Rob Burg Boris Jeremic Sandra Morgan Nassia Tzelepi Dirk Cairns-Gallimore Boughman, Jim Shawn P. Moylan Steve Unikewicz Carlos Cantarero Leal Joey Michael Muhlheim Patrick A. Vallejos Riccardo Cappa Scott M. Jones Javeed Munshi Tom Vogan Augi Cardillo Narasimha Prasad Kadambi Patrick Murray Yanli Wang Gene Carpenter Bob Kalantari Kyle J. Noel Shen Wang Justin Cassamassino Matt Keene Farhang Ostadan Kent Welter Suresh Channarasappa Austin Charles Keller Coco Paul Jie Wen Yiren Chen Robert Konnik Ben Pellereau Andrew Whittaker Vinod Chugh Elliott Korb Petesch Christy M. Williams Frankie Chui Daniel Lamond Frances Pimentel Joe Wishard James Cirilli Hilary Lane Edward L. Pleins Zia Zafir Keith A. Consani Eric Lantz Maury A. Pressburger Kai Zhang Bill Corwin Laudenat Mark A Pyne Allan Coutts Thierry Lebarbé Steven Reed Ramon Cruz Sue Lesica Weiju Ren Larry Cunningham Matthew P LeVasseur John Richards Paul Donavin Meimei Li Mark Richter Siavash Dorvash Jared S. Liebowitz Kevin Robb Arthur C. Eberhardt Mark Linn Tom Roberts