American Nuclear Society (ANS)

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What s New... American Nuclear Society (ANS) Project Initiation Notification System (PINS) ANS Standards Before work on a draft 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 completed a PINS form and are in approval process: ANS-2.31-201x, Standard for Estimating Extreme Precipitation at Nuclear Facility Sites (new ANS-3.2-201x, Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants (revision of ANSI/ANS-3.2-2006) ANS-3.4-201x, Medical Certification and Monitoring of Personnel Requiring Operator Licenses for Nuclear Power Plants (revision of ANSI/ANS-3.4-1996 (R2002) ANS-3.5-201x, Nuclear Power Plant Simulators for Use in Operator Training and Examination (revision of ANSI/ANS-3.5-2009) ANS-3.8.1-201x, Criteria for Radiological Emergency Response Functions and Organizations for Nuclear Facilities (revision of withdrawn standard ANSI/ANS-3.8.1-1995) ANS-3.8.2-201x, Criteria for Functional and Physical Characteristics of Radiological Emergency Response Facilities at Nuclear Facilities (revision of withdrawn standard ANSI/ANS-3.8.2-1995) ANS-3.8.3-201x, Criteria for Radiological Emergency Response Plans and Implementing Procedures and Maintaining Emergency Response Capability for Nuclear Facilities (revision and consolidation of withdrawn standards ANSI/ANS-3.8.3-1995 and ANSI/ANS-3.8.4-1995) ANS-3.8.6-201x, Criteria for the Conduct of Offsite Radiological Assessment for Emergency Response and Emergency Radiological Field Monitoring, Sampling and Analysis for Nuclear Facilities (revision and consolidation of withdrawn standards ANSI/ANS-3.8.5-1992 and ANSI/ANS-3.8.6-1995) ANS-3.8.7-201x, Criteria for Planning, Development, Conduct, and Evaluation of Drills and Exercises for Emergency Preparedness at Nuclear Facilities (revision of withdrawn standard ANSI/ANS-3.8.7-1998) ANS-6.4.3-201x, Gamma-Ray Attenuation Coefficients & Buildup Factors for Engineering Materials (revision of withdrawn standard ANSI/ANS-6.4.3-1991) ANS-8.20-201x, Nuclear Criticality Safety Training (revision of ANSI/ANS-8.20-1991; R1999; R2005) ANS-8.22-201x, Nuclear Criticality Safety Based on Limiting and Controlling Moderators (revision of ANSI/ANS-8.22-1997; R2006) ANS-8.25-201x, Development of Nuclear Criticality Safety Related Postings (new ANS-8.28-201x, Administrative Practices for the Use of Non-Destructive Assay Measurements for Nuclear Criticality Safety (new ANS-40.21-201x, Siting, Construction, and Operation of Commercial Low Level Radioactive Waste Burial Grounds (new

Drafts in Development The following projects have approved PINS forms and are in development: ANS-2.2-201x, Earthquake Instrumentation Criteria for Nuclear Power Plants (revision of ANSI/ANS-2.2-2002) ANS-2.9-201x, Evaluation of Ground Water Supply for Nuclear Facilities (revision of withdrawn standard ANSI/ANS-2.9-1980; R1989) ANS-2.15-201x, Criteria for Modeling and Calculating Atmospheric Transport of Routine Releases from Nuclear Facilities (new ANS-2.16-201x, Criteria for Modeling Design-Basis Accidental Releases from Nuclear Facilities (new ANS-2.25-201x, Surveys of Ecology Needed to License Nuclear Facilities (revision of withdrawn standard ANSI/ANS-2.25-1982; R1989) ANS-2.30-201x, Assessing Capability for Surface Faulting at Nuclear Facilities (new ANS-3.1-201x, Selection, Qualification, and Training of Personnel for Nuclear Power Plants (revision of withdrawn standard ANSI/ANS-3.1-1993; R1999) ANS-3.8.10-201x, Criteria for Modeling Real-Time Accidental Releases at Nuclear Facilities (new ANS-5.1-201x, Decay Heat Power in Light Water Reactors (revision of ANSI/ANS-5.1-2005) ANS-6.1.2-201x, Neutron and Gamma-Ray Cross Sections for Nuclear Radiation Protection Calculations for Nuclear Power Plants (revision of ANSI/ANS-6.1.2-1999; R2009) ANS-8.1-201x, Nuclear Criticality Safety in Operations with Fissionable Materials Outside Reactors (revision of ANSI/ANS-8.1-1998; R2007) ANS-8.3-201x, Criticality Accident Alarm System (revision of ANSI/ANS-8.3-1997; R2003) ANS-8.10-201x, Criteria for Nuclear Criticality Safety Controls in Operations with Shielding and Confinement (revision of ANSI/ANS-8.10-1983; R2005) ANS-8.12-201x, Nuclear Criticality Control and Safety of Plutonium-Uranium Fuel Mixtures Outside Reactors (revision of ANSI/ANS-8.12-1987; R1993; R2002) ANS-8.15-201x, Nuclear Criticality Control of Special Actinide Elements (revision of ANSI/ANS-8.15-1981; R2005) ANS-8.19-201x, Administrative Practices for Nuclear Criticality Safety (revision of ANSI/ANS-8.19-2005) ANS-8.21-201x, Use of Fixed Neutron Absorbers in Nuclear Facilities Outside Reactors (revision of ANSI/ANS-8.21-1995; R2001 and consolidation and revision of ANSI/ANS-8.5-1996; R2002; R2007) ANS-10.7-201x, Non-Real Time, High Integrity Software for the Nuclear Industry (new 2

ANS-15.2-201x, Quality Control for Plate-Type Uranium-Aluminum Fuel Elements (revision of ANSI/ANS- 15.2-1999; R2009) ANS-15.8-201x, Quality Assurance Program Requirements for Research Reactors (revision of ANSI/ANS-15.8-1995; R2005) ANS-15.17-201x, Fire Protection Program Criteria for Research Reactors (revision of ANSI/ANS-15.17-1981; R2000) ANS-15.19-201x, Shipment and Receipt of Special Nuclear Material (SNM) by Research Reactors (revision of withdrawn standard ANSI/ANS-15.19-1991) ANS-15.21-201x, Format and Content for Safety Analysis Reports for Research Reactors (revision of ANSI/ANS-15.21-1996; R2006) ANS-18.1-201x, Radioactive Source Term for Normal Operation of Light Water Reactors (revision of withdrawn standard ANSI/ANS-18.1-1999) ANS-19.1-201x, Nuclear Data Sets for Reactor Design Calculations (revision of ANSI/ANS-19.1-2002) ANS-19.3-201x, Steady-State Neutronics Methods for Power-Reactor Analysis (revision of ANSI/ANS- 19.3-2005) ANS-19.6.1-201x, Reload Startup Physics Tests for Pressurized Water Reactors (revision of ANSI/ANS- 19.6.1-2005) ANS-19.9-201x, Delayed Neutron Parameters for Light Water Reactors (new 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; R2002) ANS-19.12-201x, Nuclear Data for Isotope Production Calculations for Medical and Other Applications (new ANS-51.10-201x, Auxiliary Feedwater System for Pressurized Water Reactors (revision of ANSI/ANS- 51.10-1991; R2008) 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) ANS-56.8-201x, Containment System Leakage Testing Requirements (revision of ANSI/ANS-56.8-2002) ANS-58.8-201x, Time Response Design Criteria for Safety-Related Operator Actions (revision of ANSI/ANS-58.8-1994; R2008) ANS-58.16-201x, Safety and Pressure Integrity Classification for Non-Reactor Nuclear Facilities (new ANS/ASME-58.24-201x, Severe Accident Progression and Radiological Release (Level 2) PRA Methodology to Support Nuclear Installation Applications (new ANS/ASME-58.25-201x, Standard for Radiological Accident Offsite Consequence Analysis (Level 3 PRA) to Support Nuclear Installation Applications (new 3

Projects at Ballot (or resolving ballot comments) The following drafts and standards are at one of the many levels of review, reaffirmation, revision, or approval: ANS-2.3-201x, Estimating Tornado, Hurricane, and Extreme Straight Line Wind Characteristics at Nuclear Facility Sites (revision of withdrawn standard ANSI/ANS-2.3-1983) ANS-2.17-201x, Evaluation of Subsurface Radionuclide Transport at Commercial Nuclear Power Production Facilities (revision of withdrawn standard ANSI/ANS-2.17-1980; R1989) ANS-2.21-201x, Criteria for Assessing Atmospheric Effects on the Ultimate Heat Sink (new ANSI/ANS-3.11-2005 (R201x), Determining Meteorological Information at Nuclear Facilities (reaffirmation) ANS-5.4-201x, Method for Calculating the Fractional Release of Volatile Fission Products from Oxide Fuel (revision of withdrawn standard ANSI/ANS-5.4-1982) ANS-19.6.1-201x, Reload Startup Physics Tests for Pressurized Water Reactors (revision of ANSI/ANS- 19.6.1-2005) ANS-41.5-201x, Verification and Validation of Radiological Data for Use in Waste Management and Environmental Remediation (new ANS-53.1-201x, Nuclear Safety Criteria and Safety Design Process for Modular Helium-Cooled Reactor Plants (new ANS-58.14-201x, Safety and Pressure Integrity Classification Criteria for Light Water Reactors (revision of withdrawn standard ANSI/ANS-58.14-1993) ANS-58.22-201x, Low Power and Shutdown PRA Methodology (new ANS Recently Approved Standards The following new or revised standards have recently received ANSI approval: ANSI/ANS-2.23-2002 (R2009), Nuclear Plant Response to an Earthquake (reaffirmation approved 6/15/09 available for purchase) ANSI/ANS-2.26-2004 (R2010), Categorization of Nuclear Facility Structures, Systems, and Components for Seismic Design (reaffirmation of ANSI/ANS-2.26-2004 available for purchase) ANSI/ANS-3.5-2009, Nuclear Power Plant Simulators for Use in Operator Training and Examination (revision of withdrawn standard ANSI/ANS-3.5-1998; W2008 approved 9/4/2009 available for purchase) ANSI/ANS-6.1.2-1999 (R2009), Neutron and Gamma-Ray Cross Sections for Nuclear Radiation Protection Calculations for Nuclear Power Plants (reaffirmation approved 2/23/2009 available for purchase) ANSI/ANS-8.17-2004 (R2009), Criticality Safety Criteria for the Handling, Storage and Transportation of LWR Fuel Outside Reactors (reaffirmation approved 9/14/09 available for purchase) 4

ANSI/ANS-10.2-2009 (R2009), Portability of Scientific and Engineering Software (reaffirmation approved 8/14/09 available for purchase) ANSI/ANS-14.1-2004 (R2009), Operation of Fast Pulse Reactors (reaffirmation approved 10/27/09 available for purchase) ANSI/ANS-15.2-1999 (R2009), Quality Control for Plate-Type Uranium-Aluminum Fuel Elements (reaffirmation approved 3/23/09 available for purchase) ANSI/ANS-15.11-2009, Radiation Protection at Research Reactors (revision of ANSI/ANS-15.11-1993; R2004 approved 10/8/09 available for purchase) ANSI/ANS-19.10-2009, Methods for Determining Neutron Fluence in BWR and PWR Pressure Vessel and Reactor Internals (new standard approved 2/24/09 available for purchase) ANSI/ANS-40.37-2009, Mobile Radioactive Waste Processing Systems (revision of withdrawn standard ANSI/ANS-40.37-1993; W2004 approved 11/20/09 available for purchase) ANSI/ANS-55.1-1992 (R2009), Solid Radioactive Waste Processing System for Light-Water-Cooled Reactor Plants (reaffirmation approved 6/15/09 available for purchase) ANSI/ANS-58.9-2002 (R2009), Single Failure Criteria for Light Water Reactor Safety-Related Fluid Systems (reaffirmation approved 2/24/2009 available for purchase) Contact standards@ans.org for more details on any of the above standards. Updated 10/15/2010 5