American Nuclear Society (ANS) News
Approval of Proposed Standards Projects (13)
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-2.10-201x, “Criteria for the Handling and Initial Evaluation of Records from Nuclear Power Plant Seismic Instrumentation” [proposed revision of ANSI/ANS-2.10-2003 (W2013)]
- ANS-2.18-201x, “Evaluating Radionuclide Transport in Surface Water for Nuclear Power Sites” (proposed new standard)
- ANS-2.27-201x, “Criteria for Investigations of Nuclear Facility Sites for Seismic Hazard Assessments” [proposed revision of ANSI/ANS-2.27-2008 (R2016)]
- ANS-2.29-201x, “Probabilistic Seismic Hazard Analysis” [proposed revision of ANSI/ANS-2.29-2008 (R2016)]
- ANS-2.33-201x, “Aquatic Ecological Surveys Required for Siting, Design, and Operation of Nuclear Power Plants” (formerly designated ANS-18.4) (proposed new standard – title TBD)
- ANS-2.34-201x, “Probabilistic Volcanic Hazard Assessment” (proposed new standard – titled TBD)
- ANS-3.15-201x, “Cybersecurity Standard” (proposed new standard – titled TBD)
- ANS-6.1.1-201x, “Neutron and Gamma-Ray Fluence-to-Dose Factors” [proposed revision of ANSI/ANS- 6.1.1-1991 (W2001)]
- ANS-8.1-201x, “Nuclear Criticality Safety in Operations with Fissionable Materials Outside Reactors” (proposed revision of ANSI/ANS-8.1-2014)
- ANS-15.22-201x, “Classification of Structures, Systems and Components for Research Reactors” (proposed new standard)
- ANS-16.1-201x, “Measurement of the Leachability of Solidified Low-Level Radioactive Wastes by a Short-Term Test Procedure” [proposed revision of ANSI/ANS-16.1-2003 (R2017)]
- ANS-56.1-201x, “Containment Hydrogen Control Standard” (proposed new standard – titled TBD)
- ANS-60.1-201x, “Export Control Standard” (proposed new standard – titled TBD)
Drafts in Development (29)
The following projects have approved PINS forms and are in development:
- ANS-2.6-201x, “Guidelines for Estimating Present & Projecting Future Population Distributions Surrounding Nuclear Facility Sites” (proposed new project)
- ANS-2.9-201x, “Evaluation of Ground Water Supply for Nuclear Facilities” [revision of withdrawn standard ANSI/ANS-2.9-1980 (R1989)]
- ANS-2.16-201x, “Criteria for Modeling Design-Basis Accidental Releases from Nuclear Facilities” (new standard)
- ANS-2.25-201x, “Surveys of Ecology Needed to License Nuclear Facilities” (new standard)
- ANS-3.8.10-201x, “Criteria for Modeling Real-Time Accidental Releases at Nuclear Facilities” (new standard)
- ANS-3.13-201x, “Nuclear Facility Reliability Assurance Program (RAP) Development” (new standard)
- ANS-3.14-201x, “Process for Aging Management and Life Extension of Nonreactor Nuclear Facilities” (new standard)
- ANS-6.4.2-201x, “Specification for Radiation Shielding Materials for Nuclear Facilities” (revision of ANSI/ANS-6.4.2-2006)
- ANS-6.4.3-201x, “Gamma-Ray Attenuation Coefficients & Buildup Factors for Engineering Materials” [revision of withdrawn standard ANSI/ANS-6.4.3-1991 (W2001)]
- ANS-8.7-201x, “Nuclear Criticality Safety in the Storage of Fissile Materials” [proposed revision of ANSI/ANS-8.7-1998 (R2007)]
- ANS-8.12-201x, “Nuclear Criticality Control and Safety of Plutonium-Uranium Fuel Mixtures Outside Reactors” [revision of ANSI/ANS-8.12-1987 (R2011)]
- ANS-8.23-201x, “Nuclear Criticality Accident Emergency Planning and Response” [proposed revision of ANSI/ANS-8.23-2007 (R2012)]
- ANS-8.24-201x, “Validation of Neutron Transport Methods for Nuclear Criticality Safety Calculations” [revision of ANSI/ANS-8.24-2007 (R2012)]
- ANS-8.26-201x, “Criticality Safety Engineer Training and Qualification Program” [revision of ANSI/ANS- 8.26-2007 (R2012)]
- ANS-8.28-201x, “Administrative Practices for the Use of Non-Destructive Assay Measurements for Nuclear Criticality Safety” (new standard)
- ANS-19.1-201x, “Nuclear Data Sets for Reactor Design Calculations” [revision of ANSI/ANS-19.1-2002 (R2011)]
- ANS-19.4-201x, “A Guide for Acquisition and Documentation of Reference Power Reactor Physics Measurements for Nuclear Analysis Verification” [proposed revision of withdrawn standard ANSI/ANS- 19.4-1976 (R2000) (W2010)]
- ANS-19.5-201x, “Requirements for Reference Reactor Physics Measurements” [revision of withdrawn standard ANSI/ANS-19.5-1995 (W2005)]
- ANS-19.6.1-201x, “Reload Startup Physics Tests for Pressurized Water Reactors” (proposed revision of ANSI/ANS-19.6.1-2011)
- ANS-19.11-201x, “Calculation and Measurement of the Moderator Temperature Coefficient of Reactivity for Water Moderated Power Reactors” [revision of ANSI/ANS-19.11-1997 (R2011)]
- ANS-20.1-201x, “Nuclear Safety Criteria and Design Criteria for Fluoride Salt-Cooled High-Temperature Reactor Nuclear Power Plants” (new standard)
- ANS-20.2-201x, “Nuclear Safety Design Criteria and Functional Performance Requirements for LiquidFuel Molten Salt Reactor Nuclear Power Plants” (proposed new project)
- ANS-30.1-201x, “Integration of Risk-Informed, Performance-Based Principles and Methods into Nuclear Safety Design for Nuclear Power Plants” (new standard)
- ANS-30.2-201x, “Categorization and Classification of Structures, Systems, and Components for New Nuclear Power Plants” (proposed new project)
- ANS-54.1-201x, “Nuclear Safety Criteria and Design Process for Liquid-Metal-Cooled Nuclear Power Plants” [revision of withdrawn standard ANSI/ANS-54.1-1989 (W1999)]
- ANS-56.8-201x, “Containment System Leakage Testing Requirements” [revision of ANSI/ANS-56.8- 2002 (R2011)]
- ANS-57.2-201x, “Design Requirements for Light Water Reactor Used Fuel Storage Facilities at Nuclear Power Plants” [revision of withdrawn standard ANSI/ANS-57.2-1983 (W1992)]
- ANS-57.11-201x, “Integrated Safety Assessments for Nonreactor Nuclear Facilities” (new standard)
- ANS-58.8-201x, “Time Response Design Criteria for Safety-Related Operator Actions” [revision of ANSI/ANS-58.8-1994 (R2008)]
Projects at Ballot or Resolving Ballot Comments (7)
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-2.8-201x, “Probabilistic Evaluation of External Flood Hazards for Nuclear Facilities” [revision of withdrawn standard ANSI/ANS-2.8-1992 (W2002)]
- ANS-3.5-201x, “Nuclear Power Plant Simulators for Use in Operator Training and Examination” (revision of ANSI/ANS-3.5-2009)
- ANS-8.3-201x, “Criticality Accident Alarm System” [revision of ANSI/ANS-8.3-1997 (R2012)]
- ANS-8.20-201x, “Nuclear Criticality Safety Training for Fissionable Materials Operations Outside Reactors” [revision of ANSI/ANS-8.20-1991 (R2005)]
- ANS-8.21-201x, “Use of Fixed Neutron Absorbers in Nuclear Facilities Outside Reactors” [revision and consolidation of ANSI/ANS-8.21-1995 (R2011) and ANSI/ANS-8.5-1996 (R2011)]
- ANS-51.10-201x, “Auxiliary Feedwater System for Pressurized Water Reactors” [revision of ANSI/ANS- 51.10-1991 (R2008)]
- ANS-57.3-201x, “Design Requirements for New Fuel Storage Facilities at Light Water Reactor Plants” [revision of withdrawn standard ANSI/ANS-57.3-1983 (W1993)]
ANS Recently Approved Standards
The following new or revised standards have recently received ANSI approval:
- ANSI/ANS-2.2-2016, “Earthquake Instrumentation Criteria for Nuclear Power Plants” (revision of withdrawn standard ANSI/ANS-2.2-2002 – available for purchase)
- ANSI/ANS-2.23-2016, “Nuclear Plant Response to an Earthquake” [revision of ANSI/ANS-2.23-2002 (R2009) – available for purchase]
- ANSI/ANS-15.4-2016, “Selection and Training of Personnel for Research Reactors” (revision of ANSI/ANS-15.4-2007 – available for purchase)
- ANSI/ANS-15.11-2016, “Radiation Protection at Research Reactors” (revision of ANSI/ANS-15.11-2009 – available for purchase)
- ANSI/ANS-18.1-2016, “Radioactive Source Term for Normal Operation of Light Water Reactors” [revision of withdrawn standard ANSI/ANS-18.1-1999 (W2009) – available for purchase]
Joint ANS/ASME Trial-Use Standards
- ASME/ANS RA-S-1.2-2014, “Severe Accident Progression and Radiological Release (Level 2) PRA Standard for Nuclear Power Plant Applications for Light Water Reactors (LWRs)” (trial-use standard – available for purchase)
- ASME/ANS RA-S-1.4-2013, “Probabilistic Risk Assessment Standard for Advanced Non-LWR Nuclear Power Plants,” (trial-use standard – available for purchase)
- ANS/ASME-58.22-2014, “Requirements for Low Power and Shutdown Probabilistic Risk Assessment” (trial-use standard – available for purchase)
Read more at www.ans.org