ML25084A235
| ML25084A235 | |
| Person / Time | |
|---|---|
| Site: | Nuclear Energy Institute |
| Issue date: | 03/12/2025 |
| From: | Uhle J Nuclear Energy Institute |
| To: | NRC/NRR/DANU |
| References | |
| Download: ML25084A235 (7) | |
Text
©2025 Nuclear Energy Institute NRC RIC - Session W14 Dr. Jennifer Uhle, NEI March 12, 2025 Efficient Development of Risk-informed Codes &
Standards for New Reactors
©2025 Nuclear Energy Institute 2 Enhanced safety, new materials & fabrication methods, & needed pace of deployment necessitate heightened focus on codes and standards (C&S)
Key NRC & industry actions
Participation in the development of new C&Ss
Expedited endorsement of critical Code Cases (CCs )
Use of risk insights to enable safety & cost effectiveness Need for New and Modernized Codes & Standards NRC & industry support for C&Ss is critical for enabling efficient &
timely deployment of new reactors
©2025 Nuclear Energy Institute 3 Manufacturing of components without an owner is restricted ASME III permits it for valves, pumps
& supports < 4 in.
Code Case N-883 removes size limit w/ requirements NRC concern: no jurisdiction without licensee as owner What is the safety issue here?
Resolution needed to enable deployment NRC Endorsement of ASME III Code Case N-883 Courtesy of the U.S. Department of Energy
©2025 Nuclear Energy Institute 4 ASME,Section III, Div 5, CC N-940 Alternative Rules for Construction of Class A Components for High Temperature Reactors Section uses a risk-informed approach NRC limitations on this CC limit its benefit & increase cost with no safety benefit Support for Risk-Informed, Performance-Based ASME III Division 5 Code Case N-940
©2025 Nuclear Energy Institute 5 Sec. III requires RT for construction inspection (CI)
Pre-service inspection requires UT CC permit UT vs. RT for CI UT is just as effective as RT but easier
& no dose Sec. III criteria different than Sec. XI -
unnecessary repair can sensitize for SCC CC improves safety & efficiency Acceptance of UT in Lieu of RT for Construction and Pre-Service Inspections Image from NRC.gov - ML13162A146
©2025 Nuclear Energy Institute 6 High-quality and high-reliability options among non-nuclear Civil/Structural codes are Risk-informed Performance-based, High reliability for many critical buildings in high seismicity areas Enhanced safety of advanced reactor designs, should permit flexibility Efficient and Effective Civil/Structural Codes for Advanced Reactors Image created using Dall_E
©2025 Nuclear Energy Institute 7 C&Ss that are risk-informed and leverage technological advancements Key priorities include ASME III Code Case N-883 component manufacturing components prior to specifying the owner/licensee ASME III Division 5 Code Case N-940 UT in lieu of RT for initial construction inspection &
pre-service inspection Civil/structural codes that recognize modern civil structural quality & enhance safety of advanced reactors Codes and Standards for Advanced Reactors NRC & industry support for C&Ss is critical for enabling efficient &
timely deployment of new reactors