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Approval of Proposed Standards Projects

Before work on a draft standard can begin, a Project Initiation Notification System (PINS) form must be approved and submitted to the American National Standards Institute (ANSI). The following projects have PINS forms in the development and/or approval process:

  • ANS-8.24-202x, Validation of Neutron Transport Methods for Nuclear Criticality Safety [revision of ANSI/ANS-8.24-2017 (R2023)
  • ANS-15.4-202x, Medical Certification and Monitoring of Personnel Requiring Operator Licenses for Research and Test Reactors [revision of ANSI/ANS-15.4-2016 (R2021)]
  • ANS-15.23-202x, Medical Certification and Monitoring of Personnel Requiring Operator Licenses for Research and Test Reactors (proposed new standard)

Drafts in Development

The following projects have approved PINS forms and are in development:

  • ANS-1-202x, Conduct of Critical Experiments [revision of ANSI/ANS-1-2000 (R2024)]
  • ANS-2.3-202x, Estimating Tornado, Hurricane, and Extreme Straight-Line Wind Characteristics at Nuclear Facility Sites [revision of ANSI/ANS-2.3-2011 (R2021)]
  • ANS-2.15-202x, Criteria for Modeling and Calculating Atmospheric Dispersion of Routine Radiological Releases from Nuclear Facilities [revision of ANSI/ANS-2.15-2013 (R2021)]
  • ANS-2.18-202x, Evaluating Radionuclide Transport in Surface Water for Nuclear Facilities (proposed new standard)
  • ANS-GD-2.22-202x, Environmental Radiological Monitoring at Operating Nuclear Facilities (proposed new guidance document)
  • ANS-2.26-202x, Categorization of Nuclear Facility Structures, Systems, and Components for Seismic Design [proposed revision of ANSI/ANS-2.26-2004 (R2021)]
  • ANS-2.32-202x, Remediation of Radioactive Contamination in the Subsurface at Nuclear Power Plants (proposed new standard)
  • ANS-2.34-202x, Characterization and Probabilistic Analysis of Volcanic Hazards (proposed new standard)
  • ANS-2.36-202x, Accident Analysis for Aircraft Crash into Reactor and Nonreactor Nuclear Facilities (proposed new standard)
  • ANS-3.5.1-202x, Nuclear Power Plant Simulators for Use in Simulation Assisted Engineering and Non-Operator Training (proposed new standard)
  • ANS-GD-3.8-202x, Guidance for Risk-Informing Emergency Preparedness Programs for Nuclear Facilities (proposed new guidance document)
  • ANS-3.13-202x, Nuclear Facility Reliability Assurance Program (RAP) Development (proposed new standard)
  • ANS-3.15-202x, Risk-Informing Critical Digital Assets (CDAs) for Nuclear Power Plant Systems (proposed new standard)
  • ANS-6.4-202x, Nuclear Analysis and Design of Concrete Radiation Shielding for Nuclear Power Plants [(revision of ANSI/ANS-6.4-2006 (R2021)]
  • ANS-6.4.2-202x, Specification for Radiation Shielding Materials for Nuclear Facilities [revision of ANSI/ANS-6.4.2-2006 (R2021)]
  • ANS-6.4.3-202x, Gamma-Ray Attenuation Coefficients & Buildup Factors for Engineering Materials [revision of ANS-6.4.3-1991 (W2001)]
  • ANS-8.1-202x, Nuclear Criticality Safety in Operations with Fissionable Materials Outside Reactors [revision of ANSI/ANS-8.1-2014 (R2023)]
  • ANS-8.12-202x, Nuclear Criticality Control and Safety of Plutonium-Uranium Fuel Mixtures Outside Reactors [revision of ANSI/ANS-8.12-1987 (R2021)]
  • ANS-8.19-202x, Administrative Practices for Nuclear Criticality Safety [revision of ANSI/ANS-8.19-2014 (R2024)]
  • ANS-8.22-202x, Nuclear Criticality Safety Based on Limiting and Controlling Moderators [proposed revision of ANSI/ANS-8.22-1997 (R2021)]
  • ANS-8.23-202x, Nuclear Criticality Accident Emergency Planning and Response [revision of ANSI/ANS-8.23-2019 (R2024)]
  • ANS-10.4-202x, Verification and Validation of Non-Safety-Related Scientific and Engineering Computer Programs for the Nuclear Industry [revision of ANSI/ANS-10.4-2008 (R2021)]
  • ANS-15.22-202x, Classification of Structures, Systems and Components for Research Reactors (new standard)
  • ANS-19.5-202x, Requirements for Reference Reactor Physics Measurements [new standard/supersedes ANS-19.5-1995 (W2005)]
  • ANS-20.3-202x, Oxygen Concentration Measurement in Molten Salt by Inert Gas Fusion Analysis (proposed new standard)
  • ANS-30.2-202x, Classification and Categorization of Structures, Systems, and Components for New Nuclear Power Plants (proposed new standard)
  • ANS-31.1-202x, Testing and Facilities for Space Nuclear Power and Propulsion Reactors (proposed new standard)
  • ANS-53.1-202x, Nuclear Safety Criteria for the Design of High Temperature Gas-Cooled Reactor Plants [proposed revision of ANSI/ANS-53.1-2011 (R2022)]
  • ANS-54.8-202x, Liquid Metal Fire Protection (proposed revision of ANSI/ANS-54.8-2025)
  • ANS-55.6-202x, Liquid Radioactive Waste Processing System for Light water Reactor Plants [proposed new standard/supersedes ANS-55.6-1993 (R2007) (W2017)]
  • ANS-56.2-202x, Containment Isolation Provisions for Fluid Systems [proposed new standard/supersedes ANS-56.2-1984 (W1999)]
  • ANS-56.8-202x, Containment System Leakage Testing Requirements [proposed revision of ANSI/ANS-56.8-2020 (R2025)]
  • ANS-57.9-202x, Design Criteria for an Independent Spent Fuel Storage Installation (Dry Type) [proposed new standard/supersedes ANS-57.9-1992 (R2000)(W2010)]
  • ANS-57.10-202x, Design Criteria for Consolidation of LWR Spent Fuel [revision of ANSI/ANS-57.10-1996 (R2021)]
  • ANS-57.11-202x, Integrated Safety Assessments for Nonreactor Nuclear Facilities (proposed new standard)
  • ANS-60.1-202x, Civilian Nuclear Export Controls (proposed new standard)
  • ASME/ANS RA-S-1.6-202x , Standard for Low Power and Shutdown Methodology for PRA Applications (proposed revision of trial-use standard ANS/ASME-58.22-2014)
  • ASME/ANS RA-S-1.7-202x, Trial Use Standard for Multi-Unit PRA (MUPRA) (proposed new trial-use standard)

Projects at Ballot or Resolving Ballot Comments

Projects at ballot have completed drafts that have been issued for subcommittee or consensus committee ballot/concurrent public review. Before proceeding, all comments must be considered. Multiple ballots may be needed before a draft is approved. The following draft standards are in the process of approval/comment resolution:

  • ANS-2.35-202x, Guidelines for Estimating Present & Projecting Future Socioeconomic Impacts from Construction, Operations, and Decommissioning of Nuclear Facilities (proposed new standard)
  • ANS-15.11-202x, Radiation Protection at Research Reactors [revision of ANSI/ANS-15.11-2016 (R2021)]
  • ANS-GS-30.1-202x, Integrating Risk and Performance Objectives into New Reactor Nuclear Safety Designs (proposed new guidance standard)

Recently Approved Standards

The following new or revised standards have recently received ANSI approval:

  • ANSI/ANS-8.20-2025, Nuclear Criticality Safety Training for Fissionable Materials Operations Outside Reactors [revision of ANSI/ANS-8.20-1991 (R2020) - available for purchase]
  • ANSI/ANS-19.10-2025, Methods for Determining Neutron Fluence in BWR and PWR Pressure Vessel and Internals [revision of ANSI/ANS-19.10-2009 (R2021) - available for purchase]
  • ANSI/ANS-54.8-2025, Liquid Metal Fire Protection in LMR Plants [new standard/supersedes ANS-54.8-1988 (withdrawn) - available for purchase]
  • ANSI/ASME/ANS RA-S-1.3-2025, Standard for Radiological Accident Offsite Consequence Analysis (Level 3 PRA) to Support Nuclear Installation Application” (revision of trial-use standard ASME/ANS RA-S-1.3-2017 - available for purchase)

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What's New

For more details on any of the standards below, please contact standards.

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Approval of Proposed Standards Projects

Before work on a draft standard can begin, a Project Initiation Notification System (PINS) form must be approved and submitted to the American National Standards Institute (ANSI). The following projects have PINS forms in the development and/or approval process:

  • ANS-8.24-202x, Validation of Neutron Transport Methods for Nuclear Criticality Safety [revision of ANSI/ANS-8.24-2017 (R2023)
  • ANS-15.4-202x, Medical Certification and Monitoring of Personnel Requiring Operator Licenses for Research and Test Reactors [revision of ANSI/ANS-15.4-2016 (R2021)]
  • ANS-15.23-202x, Medical Certification and Monitoring of Personnel Requiring Operator Licenses for Research and Test Reactors (proposed new standard)

Drafts in Development

The following projects have approved PINS forms and are in development:

  • ANS-1-202x, Conduct of Critical Experiments [revision of ANSI/ANS-1-2000 (R2024)]
  • ANS-2.3-202x, Estimating Tornado, Hurricane, and Extreme Straight-Line Wind Characteristics at Nuclear Facility Sites [revision of ANSI/ANS-2.3-2011 (R2021)]
  • ANS-2.15-202x, Criteria for Modeling and Calculating Atmospheric Dispersion of Routine Radiological Releases from Nuclear Facilities [revision of ANSI/ANS-2.15-2013 (R2021)]
  • ANS-2.18-202x, Evaluating Radionuclide Transport in Surface Water for Nuclear Facilities (proposed new standard)
  • ANS-GD-2.22-202x, Environmental Radiological Monitoring at Operating Nuclear Facilities (proposed new guidance document)
  • ANS-2.26-202x, Categorization of Nuclear Facility Structures, Systems, and Components for Seismic Design [proposed revision of ANSI/ANS-2.26-2004 (R2021)]
  • ANS-2.32-202x, Remediation of Radioactive Contamination in the Subsurface at Nuclear Power Plants (proposed new standard)
  • ANS-2.34-202x, Characterization and Probabilistic Analysis of Volcanic Hazards (proposed new standard)
  • ANS-2.36-202x, Accident Analysis for Aircraft Crash into Reactor and Nonreactor Nuclear Facilities (proposed new standard)
  • ANS-3.5.1-202x, Nuclear Power Plant Simulators for Use in Simulation Assisted Engineering and Non-Operator Training (proposed new standard)
  • ANS-GD-3.8-202x, Guidance for Risk-Informing Emergency Preparedness Programs for Nuclear Facilities (proposed new guidance document)
  • ANS-3.13-202x, Nuclear Facility Reliability Assurance Program (RAP) Development (proposed new standard)
  • ANS-3.15-202x, Risk-Informing Critical Digital Assets (CDAs) for Nuclear Power Plant Systems (proposed new standard)
  • ANS-6.4-202x, Nuclear Analysis and Design of Concrete Radiation Shielding for Nuclear Power Plants [(revision of ANSI/ANS-6.4-2006 (R2021)]
  • ANS-6.4.2-202x, Specification for Radiation Shielding Materials for Nuclear Facilities [revision of ANSI/ANS-6.4.2-2006 (R2021)]
  • ANS-6.4.3-202x, Gamma-Ray Attenuation Coefficients & Buildup Factors for Engineering Materials [revision of ANS-6.4.3-1991 (W2001)]
  • ANS-8.1-202x, Nuclear Criticality Safety in Operations with Fissionable Materials Outside Reactors [revision of ANSI/ANS-8.1-2014 (R2023)]
  • ANS-8.12-202x, Nuclear Criticality Control and Safety of Plutonium-Uranium Fuel Mixtures Outside Reactors [revision of ANSI/ANS-8.12-1987 (R2021)]
  • ANS-8.19-202x, Administrative Practices for Nuclear Criticality Safety [revision of ANSI/ANS-8.19-2014 (R2024)]
  • ANS-8.22-202x, Nuclear Criticality Safety Based on Limiting and Controlling Moderators [proposed revision of ANSI/ANS-8.22-1997 (R2021)]
  • ANS-8.23-202x, Nuclear Criticality Accident Emergency Planning and Response (revision of ANSI/ANS-8.23-2019)
  • ANS-10.4-202x, Verification and Validation of Non-Safety-Related Scientific and Engineering Computer Programs for the Nuclear Industry [revision of ANSI/ANS-10.4-2008 (R2021)]
  • ANS-15.22-202x, Classification of Structures, Systems and Components for Research Reactors (new standard)
  • ANS-19.5-202x, Requirements for Reference Reactor Physics Measurements [new standard/supersedes ANS-19.5-1995 (W2005)]
  • ANS-20.3-202x, Oxygen Concentration Measurement in Molten Salt by Inert Gas Fusion Analysis (proposed new standard)
  • ANS-30.2-202x, Classification and Categorization of Structures, Systems, and Components for New Nuclear Power Plants (proposed new standard)
  • ANS-31.1-202x, Testing and Facilities for Space Nuclear Power and Propulsion Reactors (proposed new standard)
  • ANS-53.1-202x, Nuclear Safety Criteria for the Design of High Temperature Gas-Cooled Reactor Plants [proposed revision of ANSI/ANS-53.1-2011 (R2022)]
  • ANS-54.8-202x, Liquid Metal Fire Protection (proposed revision of ANSI/ANS-54.8-2025)
  • ANS-55.6-202x, Liquid Radioactive Waste Processing System for Light water Reactor Plants [proposed new standard/supersedes ANS-55.6-1993 (R2007) (W2017)]
  • ANS-56.2-202x, Containment Isolation Provisions for Fluid Systems [proposed new standard/supersedes ANS-56.2-1984 (W1999)]
  • ANS-56.8-202x), Containment System Leakage Testing Requirements [proposed revision of ANSI/ANS-56.8-2020 (R2025)]
  • ANS-57.9-202x, Design Criteria for an Independent Spent Fuel Storage Installation (Dry Type) [proposed new standard/supersedes ANS-57.9-1992 (R2000)(W2010)]
  • ANS-57.10-202x, Design Criteria for Consolidation of LWR Spent Fuel [revision of ANSI/ANS-57.10-1996 (R2021)]
  • ANS-57.11-202x, Integrated Safety Assessments for Nonreactor Nuclear Facilities (proposed new standard)
  • ANS-60.1-202x, Civilian Nuclear Export Controls (proposed new standard)
  • ASME/ANS RA-S-1.6-202x , Standard for Low Power and Shutdown Methodology for PRA Applications (proposed revision of trial-use standard ANS/ASME-58.22-2014)
  • ASME/ANS RA-S-1.7-202x, Trial Use Standard for Multi-Unit PRA (MUPRA) (proposed new trial-use standard)

Projects at Ballot or Resolving Ballot Comments

Projects at ballot have completed drafts that have been issued for subcommittee or consensus committee ballot/concurrent public review. Before proceeding, all comments must be considered. Multiple ballots may be needed before a draft is approved. The following draft standards are in the process of approval/comment resolution:

  • ANS-2.35-202x, Guidelines for Estimating Present & Projecting Future Socioeconomic Impacts from Construction, Operations, and Decommissioning of Nuclear Facilities (proposed new standard)
  • ANS-15.11-202x, Radiation Protection at Research Reactors [revision of ANSI/ANS-15.11-2016 (R2021)]
  • ANS-GS-30.1-202x, Integrating Risk and Performance Objectives into New Reactor Nuclear Safety Designs (proposed new guidance standard)

Recently Approved Standards

The following new or revised standards have recently received ANSI approval:

  • ANSI/ANS-8.20-2025, Nuclear Criticality Safety Training for Fissionable Materials Operations Outside Reactors [revision of ANSI/ANS-8.20-1991 (R2020) - available for purchase]
  • ANSI/ANS-19.10-2025, Methods for Determining Neutron Fluence in BWR and PWR Pressure Vessel and Internals [revision of ANSI/ANS-19.10-2009 (R2021) - available for purchase]
  • ANSI/ANS-54.8-2025, Liquid Metal Fire Protection in LMR Plants [new standard/supersedes ANS-54.8-1988 (withdrawn) - available for purchase]
  • ANSI/ASME/ANS RA-S-1.3-2025, Standard for Radiological Accident Offsite Consequence Analysis (Level 3 PRA) to Support Nuclear Installation Application” (revision of trial-use standard ASME/ANS RA-S-1.3-2017 - available for purchase)

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Last modified October 6, 2025, 7:57pm CDT