What's New

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-31.1,-202x Standard for Testing and Facilities for Space Nuclear Power and Propulsion Reactors (proposed new standard)
• ANS-57.1-202x, Design Requirements for Light Water Reactor Fuel Handling Systems [proposed revision of ANSI/ANS-57.1-1992 (R2019)]
• ANS-57.10-202x, Design Criteria for Consolidation of LWR Spent Fuel [revision of ANSI/ANS-57.10-1996 (R2021)]

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

• ANS-1-202x, Conduct of Critical Experiments [revision of ANSI/ANS-1-2000 (R2019)]
• 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-2.22-202x, Environmental Radiological Monitoring at Operating Nuclear Facilities (proposed new guidance standard)
• 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-2.35-202x, Guidelines for Estimating Present & Projecting Future Socioeconomic Impacts from Construction, Operations, and Decommissioning of Nuclear Facilities (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-6.4.2-202x, 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-8.22-202x, Nuclear Criticality Safety Based on Limiting and Controlling Moderators [proposed revision of ANSI/ANS-8.22-1997 (R2021)]
• 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-19.10-202x, Methods for Determining Neutron Fluence in BWR and PWR Pressure Vessel and Internals [revision of ANSI/ANS-19.10-2009 (R2021)]
• ANS-30.2-202x, Classification and Categorization of Structures, Systems, and Components for New Nuclear Power Plants (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-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-57.2-202x, Design Requirements for Light Water Reactor Used Fuel Storage Facilities at Nuclear Power Plants [proposed new standard/supersedes ANS-57.2-1983 (W1992)]
• 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-60.1-202x, Civilian Nuclear Export Controls (proposed new standard)
• ASME/ANS RA-S-1.5-202x, Advanced Light Water Reactor (ALWR) PRA Standard (proposed new trial-use 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 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-3.11-202x, Determining Meteorological Data for Nuclear Facilities [revision of ANSI/ANS-3.11-2015 (R2020)]
• ANS-8.20-202x, Nuclear Criticality Safety Training for Fissionable Materials Operations Outside Reactors [revision of ANSI/ANS-8.20-1991 (R2020)]
• ANS-8.26-202x, Criticality Safety Engineer Training and Qualification Program [revision of ANSI/ANS- 8.26-2007 (R2022)]
• ANS-19.13-202x, Initial Fuel Loading and Startup Tests for FOAK Advanced Reactors (proposed new standard)
• ANS-GS-30.1-202x, Integrating Risk and Performance Objectives into New Reactor Nuclear Safety Designs (proposed new guidance standard)
• ANS-57.11-202x, Integrated Safety Assessments for Nonreactor Nuclear Facilities (proposed new standard)
• ASME/ANS RA-S-1.3-202x, 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)

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

• ANSI/ANS-8.21-2023, Use of Fixed Neutron Absorbers in Nuclear Facilities Outside Reactors [revision and consolidation of ANSI/ANS-8.21-1995 (R2019) and ANSI/ANS-8.5-1996 (R2022) - available for purchase]
• ANSI/ANS-8.28-2024, Administrative Practices for the Use of Nondestructive Assay Measurements for Nuclear Criticality Safety (new standard - available for purchase)
• ANSI/ANS-20.2-2023, Nuclear Safety Design Criteria and Functional Performance Requirements for Liquid- Fuel Molten Salt Reactor Nuclear Power Plants (new standard - available for purchase)
• ANSI/ASME/ANS RA-S-1.1-2024, Standard for Level 1/Large Early Release Frequency Probabilistic Risk Assessment for Nuclear Power Plant Applications (revision of ASME/ANS RA-S-1.1-2022 - available for purchase)
• ASME/ANS RA-S-1.2-2024, Severe Accident Progression and Radiological Release (Level 2) PRA Methodology to Support Nuclear Installation Applications (revision of trial-use standard ANS/ASME RA-S-1.2-2014 - available for purchase)