ML26078A158
| ML26078A158 | |
| Person / Time | |
|---|---|
| Issue date: | 03/19/2026 |
| From: | Bass J NRC/RES/DE |
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| Download: ML26078A158 (0) | |
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Minutes of February 24, 2026, Teleconference between NRC and ASME Management On February 24, 2026, U.S. Nuclear Regulatory Commission (NRC) staff and management met with representatives from the American Society of Mechanical Engineers (ASME) to discuss common areas of interest where effectiveness and efficiencies can be realized. The meeting covered priorities related to the ASME Boiler and Pressure Vessel Code (BPV Code),Section III, Section XI, ASME Operation and Maintenance of Nuclear Power Plants (OM Code), ASME Qualification of Active Mechanical Equipment Used in Nuclear Facilities (QME-1) Standard, Plant Systems Design Standard (PSD-1), and activities of the Joint Committee on Nuclear Risk Management (JCNRM). There were no regulatory decisions made during this meeting. The attendance list, agenda for the meeting, and the slides presented at the meeting are included in the Appendices of the meeting minutes.
Introduction and Opening Remarks Christian Araguas, the NRC Standards Executive, provided opening remarks. He explained the purpose of the meeting was to identify important actions and topics going forward. No regulatory decisions were to be made at this meeting.
Mr. Araguas discussed the anticipated NRC participation within ASME Codes and Standard (C&S) activities. He clarified that participation within standard development organization (SDO) activities is a priority for the NRC, and the NRC will continue to support high-priority C&S work.
Although, due to high scrutiny on travel, the number of staff able to travel may be reduced when compared to previous years. He emphasized the value of virtual options for Codes and Standards meetings.
Kate Hyam (ASME) discussed a memo titled Pause on Certain Standards Development Activities. This pause is only intended for non-safety related work. All non-editorial work will continue as usual.
Items of Importance - JCNRM Latonia Enos-Sylla (NRC) provided updates on the NRC Probabilistic Risk Assessment (PRA) standard priorities, Regulatory Guide (RG) 1.200 updated schedule, and RG 1.247. The seven NRC PRA standard priorities discussed are 1) Level 1 / Large Early Release Frequency (LERF),
- 2) Level 2, 3) Level 3, 4) Non-LWR, 5) Advanced LWR, 6) Low Power and Shutdown (LPSD), 7)
Multi-Unit. RG 1.200 is being updated. Staff positions related to PRA standards including Level 1/LERF and Level 2 have been drafted. Updates to the RG are anticipated to also address LPSD and Advanced light water reactors. RG 1.247, which provide PRA guidance for non-LWRs, is being updated considering recent developments in this area. No timeline currently exists for the publication of this RG.
The slides Latonia presented are included in Appendix C.
Status of 10 CFR 50.55a Rulemakings Aaron Kwok (NRC) discussed that the NRC staff are currently working on their review of the 2023 Edition of the ASME BPV Code for incorporation by reference in 10 CFR 50.55a. In addition, RGs 1.84, 1.147, and 1.192 and 1.193 which address various Code Cases are also being reviewed and updated as necessary.
The NRC published a direct final rule (DFR) amending its regulations in part 50 of title 10 of the
Code of Federal Regulations to incorporate by reference RG 1.262 that approved certain code cases published by the ASME. The effective date for this DFR was January 26, 2026.
The Nuclear Energy Institute (NEI) Petition for Rulemaking was discussed. This included a letter from NEI requesting that the NRC consider certain amendments to 10 CFR 50.55a, and approval of various code cases that are currently not approved. The letter was docketed as a petition under PRM-50-127. The NRC published a request for comment on this proposal and the comment period closed on 8/5/2025. Several comments were received. The NRC continues to consider this petition.
Update on Plant Systems Design Standard (PSD-1)
Ralpha Hill provided a status and overview on PSD-1. The standard is intended to reduce cost from the design stage through the life of a reactor. The focus of PSD-1 is on new plant design.
However, it can be used for the design of new capabilities being added to existing plants. It is a process-based standard which integrates systems engineering, risk-evaluations, and probabilistic design. The Standard was approved in January 2026 and will be available for purchase in the near term.
Current developments related to PSD-1 include a cloud-based application which has an anticipated release date in the second quarter of 2026. Example problems and trainings are being developed to familiarize the community with the Standard.
Preliminary applications and analyses of PSD-1 include a piloting implementation by Deep Fission and a 2026 ASME PVP paper which compares the PSD-1 and NuScale design processes.
Ralph noted that there will be interest in NRC endorsement of PSD-1 in the coming years.
A slide presented by Ralph Hill on PSD-1 is provided in Appendix D.
Items of Importance - OM Code Thomas Scarbrough (NRC) provided updates on the NRC review and acceptance of the ASME OM-2-2024 Code for inservice testing (IST) programs in new and advanced reactors with water-cooled and non-water-cooled designs. The ASME OM-2-2024 Code allows more flexibility in condition monitoring of components than the ASME OM-1 Code. Currently, the NRC staff are preparing RG 1.220 to address acceptance of the ASME OM-2-2024 Code. Christian Araguas noted that this RG is implementing the direct final RG process which will allow for accelerated endorsement of the standard.
Thomas Scarbrough discussed some of the efforts which are currently being implemented within OM-1. These updates are intended to make OM-1 implementations more streamlined.
Mark Gowin noted that the OM-1 updates are on track to meet 2026 deadlines.
Items of Importance - QME-1 Standard Thomas Scarbrough provided updates on the NRC staff review of the new editions of the ASME QME-1 Standard for the qualification of mechanical equipment used in nuclear power facilities.
ASME has reformatted QME-1 to make the guidance more applicable for both water-cooled and
non-water-cooled reactors in the 2025 edition. The NRC staff are preparing Revision 5 to RG 1.100 to address the acceptability of both the 2023 edition and the new 2025 edition of the QME-1 Standard. The NRC staff plans to issue the proposed revision to RG 1.100 for public comment soon. It will go through the typical RG process.
Steve Norman added additional background on the QME code. He noted that the 2023 edition was issued on its normal 5-year schedule, but the 2025 edition was issued on an atypical timeline to address non-LWR considerations. He also noted that updates related to seismic considerations are a current area of interest. A task group was established with NRC participation for this purpose.
Items of Importance - NQA Spencer Daw discussed NEI 22-04, Utilization of ISO 9001 and Other Non-nuclear Suppliers for Safety-related Applications, and his concerns with the methodology. He noted that he sees an emphasis on quality program alignment over identifying safety features and characteristics.
Spencer Daw discussed an NQA-1 working group focused on developing implementation guidance for advanced reactors. Documentation developed by the group is anticipated to be published in Nuclear Technical Bulletins.
Tania Sandquist discussed clarification efforts within NQA-1. They have found that there is frequent misinterpretation of the NQA-1 requirements, so they are making significant revisions to clarify the language. Some of these clarifications will be present in the 2026 edition of NQA-
- 1.
Spencer Daw and Taunia Sandquist presented the slides in Appendix E.
Items of Importance - Section III Dale Matthews voiced that Code Case N-883, which provides guidance on construction of nuclear components before an owner is identified, is still a priority for the ASME. Christian Araguas responded that the NRC is aware of the importance of this Code Case and multiple staff are tracking its development. Dale Matthews also discussed Code Case N-907 and the NRCs review of it. Dale had concerns that the basis for not approving N-907 was not appropriate. John Honcharik (NRC) provided the NRC perspective on the CC and noted that the NRC staff did not have comments on the updated Code Case, N-907-1.
Items of Importance - Section XI Daniel Lamond discussed Code Case N-752, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems and asked if the NRC had any feedback on review of the Code Case. Jay Collins (NRC) noted that it is under review, but no additional details can be shared at this time.
Daniel Lamond noted that RG 1.262 endorses Code Cases with no limitations, but other RGs already document endorsed Code Cases. He asked how we ensure that people are able to find the information we need. Aaron Kwok provided a response for the NRC and stated that this is a new process that is still evolving. There are some potential solutions which the NRC has been discussing, but nothing has been finalized at this time. RG users may need to look at more than one RG to find the information they need.
Daniel Lamond noted that he is aware that RG 1.246 which endorsesSection XI Division 2 is being updated. Thomas Roberts asked if there was a timeline for publication of RG 1.246.
Greg Oberson (NRC) noted that this effort is a priority for the NRC, and we expect to have made significant progress by the summer, but there is currently no timeline which can be shared.
Daniel Lamond discussed a new Latin America International Working Group in ASME Section XI. They have been making significant progress recently and have been investigating considerations related to pressure tubes.
Thomas Roberts discussed an ASME Task Group on Section III/XI alignment. He stated that there are some implications related to Part 50 and 52 and requested NRC staff participation in the Task Group. Christian Araguas noted that Part 50 and 52 may be seeing significant changes in the coming years, but the NRC will certainly remain involved in high-priority topics in Code and Standards development.
Scheduling of Next NRC/ASME Management call, New Actions, Closing Comments Christian Araguas thanked all participants and provided brief closing remark discussing the importance of the information shared in this meeting.
The next NRC/ASME Management call is planned for August 25, 2026, from 2:00 - 4:00 p.m.
Adjourn The meeting adjourned at 3:30 PM.
APPENDIX A: ATTENDANCE NRC Participants Aaron Kwok Angie Buford Bruce Lin Christian Araguas Darrell Dunn Eric Reichelt Greg Oberson George Thomas Gurjendra Bedi Ian Tseng Jay Collins Jeff Whited Jeffery Wood Jen Whitman John Bozga John Honcharik Joseph Bass Kaihwa Hsu Kamal Manoly Latonia Enos-Sylla Matthew Hiser Matthew Mitchell Nicholas Hansing Raj Iyengar Ravi Penmetsa Robert Tregoning Russell Felts Stephen Cumblidge Steven Levitus Stewart Bailey Tania Martinez Navedo Thomas Scarbrough Travis Tate Yamir Diaz-Castillo Yuken Wong
Other Participants Adam Maslowski Annemarie Appleton Augi Cardillo Chris Cantrell Dale Matthews Derek Walker Daniel Lamond Edward Renaud Kate Hyam Kent Olson Mark Allen Gowin Mark Richter Maury A Pressburger Ralph Hill Spencer L. Daw Steve Norman Taunia Jean Sandquist Tim Stuhldreher Thomas J. Vogan Tom Roberts
APPENDIX B: AGENDA NRC/ASME Management Meeting Date:
Tuesday, February 24, 2026 Time:
2:00 pm - 4:00 pm EDT, Virtual Meeting via Teams (Note: Phone participants are requested to send an email to joseph.bass@nrc.gov to be included on the roster of participants.)
Purpose:
To establish at the management level:
(a) A common understanding between NRC and ASME of the needs of the NRC as a stakeholder in its use of the ASME Boiler and Pressure Vessel (BPV) Code and the ASME Operation and Maintenance of Nuclear Power Plants (OM Code).
(b) A communication pathway between NRC and ASME with respect to mission, objectives, or issues that may impact implementation of the ASME BPV Code and the ASME OM Code in the U.S.
nuclear industry.
Time Topic Presenter(s) 2:00 Introductions/Opening Remarks Memo - Pause on Certain Standards Development Activities Christian Araguas, NRC Kate Hyam, ASME 2:10 Items of Importance - JCNRM NRC-PRA standard priorities RG 1.200 updated schedule RG 1.247 Latonia Enos-Sylla, NRC 2:20 Status of 10 CFR 50.55a Rulemakings Proposed rule: Approval of the 2023 Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code and Code Cases, Revision 41 Staff is developing proposed rule.
IBRs the 2023 ASME BPV Code and updates RGs 1.84, 1.147, and 1.192 with acceptable code cases.
Direct final rule: Approval of American Society of Mechanical Engineers Unconditioned Code Cases Confirmation of effective date was Aaron Kwok, NRC Nicole Fields, NRC
published on 1/27/2026 (91 FR 3359).
No significant adverse comments were received.
NEI Petition for Rulemaking (PRM)
Letter from NEI requesting that the NRC consider amendments to 10 CFR 50.55a and inclusion of various code cases in RG 1.84 Docketed as PRM-50-127; Request for comment published on 6/6/2025 (90 FR 24083)
Comment period closed on 8/5/2025.
Staff continues to review the petition.
2:40 Update on Plant systems Design Standard (PSD-1)
PSD-1 is published We are developing A cloud application A detailed example problem training Deep Fission is piloting implementation A comparison of PSD-1 and NuScale design processes has been performed and will be published as a paper for PVP 2026 Results are very positive with recommendations where each can be improved as a result of the comparison Ralph Hill, ASME 2:55 Items of Importance - OM Code NRC preparing new RG to accept OM-2 Code with any appropriate conditions ASME OM-1 Code project updates Thomas Scarbrough, NRC Mark Gowin, ASME 3:05 Items of Importance - QME-1 Standard ASME has issued QME-1-2023 and QME 2025 NRC preparing proposed Revision 5 to RG 1.100 for public comment.
Thomas Scarbrough, NRC Steve Norman, ASME 3:15 Items of Importance - NQA NEI 22-04 NQA 2026 Taunia Sandquist, ASME Spencer Daw, ASME 3:25 Items of Importance - Section III Status update on Code Case N-883-1 RG 1.87 Revision Dale Matthews, ASME Joseph Bass, NRC Christian Araguas, NRC
3:35 Items of Importance - Section XI Latest Status on CC N-752 Approval LTP for Current RG Series Unconditionally Approved CCs (RG 1.262 impact)
RG 1.246 Revision Plans (i.e., BPV XI Div 2 and CC N-934 / N-954)
New Section XI Latin America IWG Status TG III/XI Alignment Initiative Update Daniel Lamond, GSE Solutions 3:45 Other Updates All 3:50 Scheduling of Next NRC/ASME Management call, New Actions, Closing Comments All 3:55 Adjourn All
APPENDIX C: JCNRM STATUS
APPENDIX D: PSD-1 STATUS
APPENDIX E: NQA STATUS