ASME NQA 1 : 2015
Superseded
Superseded
A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.
View Superseded by
Quality Assurance Requirements for Nuclear Facility Applications (NQA-1 - 2015)
Available format(s)
Hardcopy , PDF
Superseded date
25-08-2021
Superseded by
Language(s)
English
Published date
01-01-2015
Publisher
Important note : All end users must be registered with an Account prior to user licenses being assigned.This Standard provides requirements and guidelines for the establishment and execution of quality assurance programs during siting, design, construction, operation and decommissioning of nuclear facilities. This Standard reflects industry experience and current understanding of the quality assurance requirements necessary to achieve safe, reliable, and efficient utilization of nuclear energy, and management and processing of radioactive materials. The Standard focuses on the achievement of results, emphasizes the role of the individual and line management in the achievement of quality, and fosters the application of these requirements in a manner consistent with the relative importance of the item or activity.
| DocumentType |
Standard
|
| ISBN |
9780791869567
|
| Pages |
316
|
| PublisherName |
American Society of Mechanical Engineers
|
| Status |
Superseded
|
| SupersededBy | |
| Supersedes |
| ASTM C 1065 : 2008 : R2015 | Standard Specification for Nuclear-Grade Zirconium Oxide Powder |
| ASTM D 7301 : 2011 | Standard Specification for Nuclear Graphite Suitable for Components Subjected to Low Neutron Irradiation Dose |
| ASTM C 1462 : 2000 : R2005 | Standard Specification for Uranium Metal Enriched to More than 15% and Less Than 20%<sup>235</sup> U |
| ASTM D 4286 : 2008 : R2015 | Standard Practice for Determining Coating Contractor Qualifications for Nuclear Powered Electric Generation Facilities |
| ASTM C 750 : 2009 | Standard Specification for Nuclear-Grade Boron Carbide Powder |
| BS EN 62765-1:2017 | Nuclear powers plants. Instrumentation and control important to safety. Management of ageing of sensors and transmitters Pressure transmitters |
| ASTM C 1615/C1615M : 2017 : REDLINE | Standard Guide for Mechanical Drive Systems for Remote Operation in Hot Cell Facilities |
| ASTM C 967 : 2013 : REDLINE | Standard Specification for Uranium Ore Concentrate |
| ANS 3.1-2014 | SELECTION, QUALIFICATION, AND TRAINING OF PERSONNEL FOR NUCLEAR POWER PLANTS |
| ASTM C 1217 : 2000 | Standard Guide for Design of Equipment for Processing Nuclear and Radioactive Materials |
| ASTM C 1065 : 2008 | Standard Specification for Nuclear-Grade Zirconium Oxide Powder |
| ASTM C 785 : 2008 | Standard Specification for Nuclear-Grade Aluminum Oxide Pellets |
| ASTM C 888 : 2003 : R2008 | Standard Specification for Nuclear-Grade Gadolinium Oxide (Gd<sub>2</sub>O<sub>3</sub>) Powder |
| ASTM D 3089 : 1997 : R2008 | Standard Practice for Determining the A-D Dimension of Aerosol Valve Dip Tubes |
| ASTM C 1188 : 2004 : R2011 | Standard Guide for Establishing a Quality Assurance Program for Uranium Conversion Facilities (Withdrawn 2017) |
| ASTM D 4286 : 2008 | Standard Practice for Determining Coating Contractor Qualifications for Nuclear Powered Electric Generation Facilities |
| ASTM C 1062 : 2000 | Standard Guide for Design, Fabrication, and Installation of Nuclear Fuel Dissolution Facilities |
| ANS 54.1-1989 | GENERAL SAFETY DESIGN CRITERIA FOR A LIQUID METAL REACTOR NUCLEAR POWER PLANT |
| UNI/TR 11510 : 2013 | Nuclear plants - Particular requirements for the application of UNI EN ISO 9001: 2008 in the nuclear field |
| ASTM C 852/C852M : 2017 : REDLINE | Standard Guide for Design Criteria for Plutonium Gloveboxes |
| ASTM C 1008 : 1999 : R2008 | Standard Specification for Sintered (Uranium-Plutonium) Dioxide<br> Pellets<span class='unicode'>—</span>Fast Reactor Fuel (Withdrawn 2014) |
| NFPA 804 : 2015 | FIRE PROTECTION FOR ADVANCED LIGHT WATER REACTOR ELECTRIC GENERATING PLANTS |
| CSA N286.7 : 2016 | QUALITY ASSURANCE OF ANALYTICAL, SCIENTIFIC, AND DESIGN COMPUTER PROGRAMS |
| ASTM C 1174 : 2017 : REDLINE | Standard Practice for Evaluation of the Long-Term Behavior of Materials Used in Engineered Barrier Systems (EBS) for Geological Disposal of High-Level Radioactive Waste |
| ISO 18075:2018 | Steady-state neutronics methods for power-reactor analysis |
| ASTM D 4069 : 1995 : R2014 | Standard Specification for Impregnated Activated Carbon Used to Remove Gaseous Radio-Iodines from Gas Streams |
| N286.10-16 | Configuration management for high energy reactor facilities |
| ANS 57.7-1988(R1997) | DESIGN CRITERIA FOR AN INDEPENDENT SPENT FUEL STORAGE INSTALLATION (WATER POOL TYPE) |
| ANS 51.1-1983(R1988) | NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY PRESSURIZED WATER REACTOR PLANTS |
| ANS 57.9-1992(R2000) | DESIGN CRITERIA FOR AN INDEPENDENT SPENT FUEL STORAGE INSTALLATION (DRY TYPE) |
| ASTM C 1725 : 2017 : REDLINE | Standard Guide for Hot Cell Specialized Support Equipment and Tools |
| ASTM C 788 : 2003 | Standard Specification for Nuclear-Grade Uranyl Nitrate Solution or Crystals |
| ASTM C 752 : 2013 : R2016 | Standard Specification for Nuclear-Grade Silver-Indium-Cadmium Alloy |
| ASTM C 833 : 2017 : REDLINE | Standard Specification for Sintered (Uranium-Plutonium) Dioxide Pellets for Light Water Reactors |
| ASTM C 1076 : 2009 : R2015 | Standard Specification for Nuclear Grade Hafnium Oxide Pellets |
| NFPA 804 : 2020 | FIRE PROTECTION FOR ADVANCED LIGHT WATER REACTOR ELECTRIC GENERATING PLANTS |
| ASTM E 2421 : 2015 : REDLINE | Standard Guide for Preparing Waste Management Plans for Decommissioning Nuclear Facilities |
| ASTM C 1068 : 2015 : REDLINE | Standard Guide for Qualification of Measurement Methods by a Laboratory Within the Nuclear Industry |
| ASTM A 826/A826M : 1995 | Standard Specification for Seamless Austenitic and Martensitic Stainless Steel Duct Tubes for Liquid Metal-Cooled Reactor Core Components |
| ASTM C 888 : 2003 : R2014 | Standard Specification for Nuclear-Grade Gadolinium Oxide (Gd<inf>2</inf>O<inf>3</inf >) Powder |
| ASTM C 992 : 2016 : REDLINE | Standard Specification for Boron-Based Neutron Absorbing Material Systems for Use in Nuclear Fuel Storage Racks in a Pool Environment |
| ASTM C 1334 : 2005 | Standard Specification for Uranium Oxides with a <sup>235</sup>U Content of Less Than 5 % for Dissolution Prior to Conversion to Nuclear-Grade Uranium Dioxide |
| ASTM C 708 : 2016 : REDLINE | Standard Specification for Nuclear-Grade Beryllium Oxide Powder |
| ASTM C 1217 : 2000 : R2012 | Standard Guide for Design of Equipment for Processing Nuclear and Radioactive Materials |
| ASTM C 1334 : 2005 : R2010 | Standard Specification for Uranium Oxides with a <sup>235</sup>U Content of Less Than 5 % for Dissolution Prior to Conversion to Nuclear-Grade Uranium Dioxide |
| ASTM C 1008 : 1999 | Standard Specification for Sintered (Uranium-Plutonium) Dioxide Pellets-Fast Reactor Fuel |
| IEC 62765-1:2015 | Nuclear powers plants - Instrumentation and control important to safety - Management of ageing of sensors and transmitters - Part 1: Pressure transmitters |
| ASTM D 7301 : 2011 : R2015 | Standard Specification for Nuclear Graphite Suitable for Components Subjected to Low Neutron Irradiation Dose |
| ASTM C 1062 : 2000 : R2014 | Standard Guide for Design, Fabrication, and Installation of Nuclear Fuel Dissolution Facilities |
| ASME AG-1 : 2019 | CODE ON NUCLEAR AIR AND GAS TREATMENT |
| IEEE 308-2012 REDLINE | IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations |
| ASTM C 788 : 2003 : R2009 | Standard Specification for Nuclear-Grade Uranyl Nitrate Solution or Crystals |
| ASTM C 776 : 2017 : REDLINE | Standard Specification for Sintered Uranium Dioxide Pellets for Light Water Reactors |
| CSA N286.0.1 : 2014 | COMMENTARY ON N286-12, MANAGEMENT SYSTEM REQUIREMENTS FOR NUCLEAR FACILITIES |
| ACI 349M : 2013 | CODE REQUIREMENTS FOR NUCLEAR SAFETY-RELATED CONCRETE STRUCTURES AND COMMENTARY |
| ASTM C 888 : 2003 | Standard Specification for Nuclear-Grade Gadolinium Oxide (Gd<sub>2</sub>O<sub>3</sub>) Powder |
| ANS 58.6-1996(R2001) | CRITERIA FOR REMOTE SHUTDOWN FOR LIGHT WATER REACTORS |
| ANS 57.2-1983 | LIGHT WATER REACTOR SPENT FUEL STORAGE FACILITIES, REQUIREMENTS FOR, |
| ANS 4.5-80(R1986) | ACCIDENT MONITORING FUNCTIONS IN LIGHT-WATER-COOLED REACTORS, CRITERIA FOR |
| ANS 59.3-1992(R2002) | NUCLEAR SAFETY CRITERIA FOR CONTROL AIR SYSTEMS |
| ASTM C 996 : 2015 : REDLINE | Standard Specification for Uranium Hexafluoride Enriched to Less Than 5 % <sup> 235</sup>U |
| IEEE 603-2009 REDLINE | IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations |
| ASTM C 1031 : 2011 : R2016 | Standard Specification for Nuclear-Grade Aluminum Oxide Powder |
| IEC 63147:2017 | Criteria for accident monitoring instrumentation for nuclear power generating stations |
| ASTM C 1217 : 2000 : R2006 | Standard Guide for Design of Equipment for Processing Nuclear and Radioactive Materials |
| ASTM C 1334 : 2005 : R2016 : EDT 1 | Standard Specification for Uranium Oxides with a <sup>235</sup>U Content of Less Than 5 % for Dissolution Prior to Conversion to Nuclear-Grade Uranium Dioxide |
| ASTM C 922 : 2014 : REDLINE | Standard Specification for Sintered Gadolinium Oxide-Uranium Dioxide Pellets |
| IEEE 317-2013 REDLINE | IEEE Standard for Electric Penetration Assemblies in Containment Structures for Nuclear Power Generating Stations |
| ANS 2.5-1984(R1990) | STANDARD FOR DETERMINING METEOROLOGICAL INFORMATION AT NUCLEAR POWER SITES |
| ANS 59.2-1985 | NUCLEAR POWER PLANTS - HVAC SYSTEMS LOCATED OUTSIDE PRIMARY CONTAINMENT, SAFETY CRITERIA FOR, |
| CSA N290.8 : 2015 | TECHNICAL SPECIFICATION REQUIREMENTS FOR NUCLEAR POWER PLANT COMPONENTS |
| ASTM D 7219 : 2008 | Standard Specification for Isotropic and Near-isotropic Nuclear Graphites |
| ASTM D 4069 : 1995 : R2003 | Standard Specification for Impregnated Activated Carbon Used to Remove Gaseous Radio-Iodines from Gas Streams |
| ASTM C 1462 : 2000 | Standard Specification for Uranium Metal Enriched to More than 15% and Less Than 20%<sup>235</sup> U |
| ASTM E 2230 : 2013 : REDLINE | Standard Practice for Thermal Qualification of Type B Packages for Radioactive Material |
| ASTM C 785 : 2008 : R2015 | Standard Specification for Nuclear-Grade Aluminum Oxide Pellets |
| ASME AG 1 : 2012 | CODE ON NUCLEAR AIR AND GAS TREATMENT |
| ASTM C 750 : 2009 : R2014 | Standard Specification for Nuclear-Grade Boron Carbide Powder |
| ASTM C 1533 : 2015 : REDLINE | Standard Guide for General Design Considerations for Hot Cell Equipment |
| ANS 40.35-1991 | VOLUME REDUCTION OF LOW-LEVEL RADIOACTIVE WASTE OR MIXED WASTE |
| ANS 52.1-83(R1988) | NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY BOILING WATER REACTOR PLANTS |
| ANS 56.6-1986 | VENTILATION SYSTEMS, PRESSURIZED WATER REACTOR CONTAINMENT |
| IEEE 497-2010 | IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations |
| BS 5882:1990 | Specification for a total quality assurance programme for nuclear installations |
| ASTM C 1462 : 2000 : R2008 | Standard Specification for Uranium Metal Enriched to More than 15 % and Less Than 20 % <sup> 235</sup>U |
| ASME PV CODE 11 : 2017 | BOILER AND PRESSURE VESSEL CODE - RULES FOR INSERVICE INSPECTION OF NUCLEAR POWER PLANT COMPONENTS |
| ASTM A 831/A831M : 1995 : R2000 | Standard Specification for Austenitic and Martensitic Stainless Steel Bars, Billets, and Forgings for Liquid Metal Cooled Reactor Core Components (Withdrawn 2005) |
| ASTM C 751 : 2016 : REDLINE | Standard Specification for Nuclear-Grade Boron Carbide Pellets |
| IEEE 730-2014 | IEEE Standard for Software Quality Assurance Processes |
| ASTM D 7219 : 2008 : R2014 | Standard Specification for Isotropic and Near-isotropic Nuclear Graphites |
| ASTM C 1062 : 2000 : R2008 | Standard Guide for Design, Fabrication, and Installation of Nuclear Fuel Dissolution Facilities |
| ASTM C 1066 : 2009 : R2015 | Standard Specification for Nuclear Grade Zirconium Oxide Pellets |
| ASTM C 1076 : 2009 | Standard Specification for Nuclear Grade Hafnium Oxide Pellets |
| EN 62765-1:2017 | Nuclear powers plants - Instrumentation and control important to safety - Management of ageing of sensors and transmitters - Part 1: Pressure transmitters |
| IEEE 420-2013 REDLINE | IEEE Standard for the Design and Qualification of Class 1E Control Boards, Panels, and Racks Used in Nuclear Power Generating Stations |
| IEEE 628-2011 | IEEE Standard Criteria for the Design, Installation, and Qualification of Raceway Systems for Class 1E Circuits for Nuclear Power Generating Stations |
| ANS 54.2-1985 | DESIGN BASES FOR FACILITIES FOR LMFBR SPENT FUEL STORAGE IN LIQUID METAL OUTSIDE THE PRIMARY COOLANT BOUNDARY, |
| ASTM C 1334 : 2005 : EDT 1 | Standard Specification for Uranium Oxides with a <sup>235</sup>U Content of Less Than 5 % for Dissolution Prior to Conversion to Nuclear-Grade Uranium Dioxide |
| ANS 2.7-1982 | SURFACE FAULTING AT NUCLEAR POWER SITES, CRITERIA AND GUIDELINES FOR ASSESSING CAPABILITY FOR, |
| ANS 59.1-1986 | COOLING WATER SYSTEMS FOR LIGHT WATER REACTORS, NUCLEAR SAFETY RELATED, |
| ASTM C 788 : 2003 : R2015 | Standard Specification for Nuclear-Grade Uranyl Nitrate Solution or Crystals |
| ASTM C 752 : 2013 | Standard Specification for Nuclear-Grade Silver-Indium-Cadmium Alloy |
| ASTM D 3843 : 2016 : REDLINE | Standard Practice for Quality Assurance for Protective Coatings Applied to Nuclear Facilities |
| ASTM C 784 : 2016 : REDLINE | Standard Specification for Nuclear-Grade Aluminum Oxide-Boron Carbide Composite Pellets |
| BS IEC 63147:2017 | Criteria for accident monitoring instrumentation for nuclear power generating stations |
| ASTM C 1031 : 2011 | Standard Specification for Nuclear-Grade Aluminum Oxide Powder |
| ASTM C 1066 : 2009 | Standard Specification for Nuclear Grade Zirconium Oxide Pellets |
| ASTM C 1188 : 2004 | Standard Guide for Establishing a Quality Assurance Program for Uranium Conversion Facilities |
| ASTM D 4069 : 1995 : R2008 | Standard Specification for Impregnated Activated Carbon Used to Remove Gaseous Radio-Iodines from Gas Streams |
| ASTM C 1462 : 2000 : R2013 | Standard Specification for Uranium Metal Enriched to More than 15 % and Less Than 20 % 235U |
| UFC 4-024-01 : 2008 | UNIFIED FACILITIES CRITERIA - SECURITY ENGINEERING: PROCEDURES FOR DESIGNING AIRBORNE CHEMICAL, BIOLOGICAL, AND RADIOLOGICAL PROTECTION FOR BUILDINGS |
| ASME STP-NU-015 : 2008 | A GUIDE TO AMERICAN CRANE STANDARDS FOR ELECTRIC OVERHEAD TRAVELING CRANES, HOISTS, AND RELATED EQUIPMENT FOR NUCLEAR FACILITIES |
| IEEE 690-2004 | IEEE Standard for the Design and Installation of Cable Systems for Class 1E Circuits in Nuclear Power Generating Stations |
| ANSI/NIRMA CM 1.0 : 2007 | GUIDELINES FOR CONFIGURATION MANAGEMENT OF NUCLEAR FACILITIES |
| ASME PTB 12 : 2017 | GUIDELINES FOR ADDRESSING DATA GAPS AND RECORDKEEPING FOR ASME B31.4, B31.8 AND B31.8S FOR PIPELINE INTEGRITY MANAGEMENT |
| ASCE/SEI 4 16 : 2017 | SEISMIC ANALYSIS OF SAFETY - RELATED NUCLEAR STRUCTURES |
| ASCE/SEI 49 12 : 2012 | WIND TUNNEL TESTING FOR BUILDINGS AND OTHER STRUCTURES |
| DIN 6789-3:1990-09 | SYSTEMATIC ARRANGEMENT OF DOCUMENTS; REVISIONS OF DOCUMENTS AND ITEMS; GENERAL REQUIREMENTS |
| ASME NUM 1 : 2009 | RULES FOR CONSTRUCTION OF CRANES, MONORAILS, AND HOISTS (WITH BRIDGE OR TROLLEY OR HOIST OF THE UNDERHUNG TYPE) |
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