Jump to:

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-2.18-202x, Evaluating Radionuclide Transport in Surface Water for Nuclear Power Sites (proposed new standard – title TBD)
  • ANS-2.32-202x, Guidance on the Selection and Evaluation of Remediation Methods for Subsurface Contamination (proposed new standard)
  • ANS-3.15-202x, Risk-Informing Critical Digital Assets (CDAs) for Nuclear Power Plant Systems (proposed new standard)
  • ANS-3.16-202x, Meteorological Aspects of Wildland Fire Response (proposed new standard – title TBD)
  • ANS-60.1-202x, Export Control Standard (proposed new standard – title TBD)

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 (R2012)]
  • ANS-2.21-202x, Criteria for Assessing Atmospheric Effects on the Ultimate Heat Sink [revision of ANSI/ANS-2.21-2012 (R2016)]
  • ANS-2.22-202x, Environmental Radiological Monitoring at Operating Nuclear Facilities (new standard) 1
  • ANS-2.26-202x, Categorization of Nuclear Facility Structures, Systems, and Components for Seismic Design [proposed revision of ANSI/ANS-2.26-2004 (R2017)]
  • ANS-3.13-202x, Nuclear Facility Reliability Assurance Program (RAP) Development (new standard)
  • ANS-2.34-202x, Characterization and Probabilistic Analysis of Volcanic Hazards (new standard)
  • ANS-2.35-202x, Guidelines for Estimating Present & Projecting Future Socioeconomic Impacts from Construction, Operations, and Decommissioning of Nuclear Facilities (new standard)
  • ANS-3.5.1-202x, Nuclear Power Plant Simulators for Use in Simulation Assisted Engineering and Non- Operator Training (new standard)
  • ANS-6.4.2-202x, Specification for Radiation Shielding Materials for Nuclear Facilities [revision of ANSI/ANS-6.4.2-2006 (R2016)]
  • 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 (R2018)]
  • ANS-8.7-202x, Nuclear Criticality Safety in the Storage of Fissile Materials [revision of ANSI/ANS-8.7- 1998 (R2017)]
  • ANS-8.12-202x, Nuclear Criticality Control and Safety of Plutonium-Uranium Fuel Mixtures Outside Reactors [revision of ANSI/ANS-8.12-1987 (R2016)]
  • ANS-8.20-202x, Nuclear Criticality Safety Training for Fissionable Materials Operations Outside Reactors [revision of ANSI/ANS-8.20-1991 (R2015)]
  • ANS-8.22-202x, Nuclear Criticality Safety Based on Limiting and Controlling Moderators [proposed revision of ANSI/ANS-8.22-1997 (R2016)]
  • ANS-8.26-202x, Criticality Safety Engineer Training and Qualification Program [revision of ANSI/ANS- 8.26-2007 (R2016)]
  • ANS-8.28-202x, Administrative Practices for the Use of Non-Destructive Assay Measurements for Nuclear Criticality Safety (new standard)
  • 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 (R2016)]
  • ANS-15.22-202x, Classification of Structures, Systems and Components for Research Reactors (new standard)
  • ANS-18.1-202x, "Radioactive Source Term for Normal Operation of Light Water Reactors" (revision of ANSI/ANS-18.1-2016)
  • ANS-19.3.4-202x, The Determination of Thermal Energy Deposition Rates in Nuclear Reactors [revision of ANSI/ANS-19.3.4-2002 (R2017)]
  • ANS-19.5-202x, Requirements for Reference Reactor Physics Measurements [new standard/supersedes ANS-19.5-1995 (W2005)]
  • ANS-20.2-202x, Nuclear Safety Design Criteria and Functional Performance Requirements for Liquid- Fuel Molten Salt Reactor Nuclear Power Plants (new standard)
  • ANS-30.1-202x, Integrating Risk and Performance Objectives into New Reactor Nuclear Safety Designs (new standard)
  • ANS-30.2-202x, Categorization and Classification of Structures, Systems, and Components for New Nuclear Power Plants (new standard)
  • ANS-30.3-202x, Light-Water Reactor Risk-Informed Performance-Based Design (new standard)
  • 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 [revision of ANSI/ANS-56.8- 2002 (R2016)]
  • ANS-57.2-202x, Design Requirements for Light Water Reactor Used Fuel Storage Facilities at Nuclear Power Plants [new standard/supersedes ANS-57.2-1983 (W1992)]
  • ANS-57.8-202x, Fuel Assembly Identification [revision of ANSI/ANS-57.8-1995 (R2017)]
  • 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-59.3-202x, Nuclear Safety Criteria for Control Air Systems [new standard/supersedes ANS-59.3- 1992 (W2012)]

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-2.27-202x, Criteria for Investigations of Nuclear Facility Sites for Seismic Hazard Assessments [revision of ANSI/ANS-2.27-2008 (R2016)]
  • ANS-2.29-202x, Probabilistic Seismic Hazard Analysis [revision of ANSI/ANS-2.29-2008 (R2016)]
  • ANS-3.14-202x, Process for Aging Management and Life Extension of Nonreactor Nuclear Facilities (new standard)
  • ANS-6.1.1-202x, Photon and Neutron Fluence-to-Dose Conversion Coefficients [new standard/supersedes ANS- 6.1.1-1991 (W2001)]
  • ANS-8.3-202x, Criticality Accident Alarm System [revision of ANSI/ANS-8.3-1997 (R2017)]
  • ANS-8.21-202x, 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 (R2017)]
  • ANS-51.10-202x, Auxiliary Feedwater System for Pressurized Water Reactors [revision of ANSI/ANS- 51.10-1991 (R2018)]
  • ANS-57.11-202x, Integrated Safety Assessments for Nonreactor Nuclear Facilities (new standard)

Recently Approved Standards

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

  • ANSI/ANS-2.8-2020, Probabilistic Evaluation of External Flood Hazards for Nuclear Facilities [new standard/supersedes ANS-2.8-1992 (W2002) – in production]
  • ANSI/ANS-3.5-2018, Nuclear Power Plant Simulators for Use in Operator Training and Examination (revision of ANSI/ANS-3.5-2009 – available for purchase)
  • ANSI/ANS-8.23-2019, Nuclear Criticality Accident Emergency Planning and Response [revision of ANSI/ANS-8.23-2007 (R2012) – available for purchase]
  • ANSI/ANS-16.1-2019, Measurement of the Leachability of Solidified Low-Level Radioactive Wastes by a Short-Term Test Procedure [revision of ANSI/ANS-16.1-2003 (R2017) – available for purchase]
  • ANSI/ANS-19.1-2019, Nuclear Data Sets for Reactor Design Calculations [revision of ANSI/ANS-19.1-2002 (R2011) – available for purchase]
  • ANSI/ANS-19.6.1-2019, Reload Startup Physics Tests for Pressurized Water Reactors [revision of ANSI/ANS-19.6.1-2011 (R2016) – available for purchase]
  • ANSI/ANS-54.1-2020, Nuclear Safety Criteria and Design Process for Sodium Fast Reactor Nuclear Power Plants [new standard/supersedes ANS-54.1-1989 (W1999) – in production]
  • ANSI/ANS-58.8-2019, Time Response Criteria for Manual Actions at Nuclear Power Plants [revision of ANSI/ANS-58.8-1994 (R2017) – available for purchase]

Last modified April 15, 2020, 6:13am CDT