ANS 51.1-1983(R1988)
Withdrawn
Withdrawn
A Withdrawn Standard is one, which is removed from sale, and its unique number can no longer be used. The Standard can be withdrawn and not replaced, or it can be withdrawn and replaced by a Standard with a different number.
NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY PRESSURIZED WATER REACTOR PLANTS
Available format(s)
Hardcopy , PDF
Withdrawn date
23-07-2013
Language(s)
English
Published date
01-01-1988
Publisher
Important note : Users cannot be edited or removed once added to your Multi user PDF.Describes the nuclear safety criteria and functional design requirements of systems, structures and components of PWR power plants. Maintenance operations and testing requirements are covered only to the extent that they affect design provisions.
| DocumentType |
Standard
|
| Pages |
204
|
| PublisherName |
American Nuclear Society
|
| Status |
Withdrawn
|
| Supersedes |
| ANS 58.8-1994(R2017) | TIME RESPONSE DESIGN CRITERIA FOR SAFETY-RELATED OPERATOR ACTIONS |
| ANS 55.4-1993(R2007) | GASEOUS RADIOACTIVE WASTE PROCESSING SYSTEMS FOR LIGHT WATER REACTOR PLANTS |
| ANS 56.6-1986 | VENTILATION SYSTEMS, PRESSURIZED WATER REACTOR CONTAINMENT |
| ANS 59.2-1985 | NUCLEAR POWER PLANTS - HVAC SYSTEMS LOCATED OUTSIDE PRIMARY CONTAINMENT, SAFETY CRITERIA FOR, |
| ASME QME 1 : 2017 | QUALIFICATION OF ACTIVE MECHANICAL EQUIPMENT USED IN NUCLEAR FACILITIES |
| IEEE DRAFT 379 : D5 2000 | DRAFT STANDARD APPLICATION OF THE SINGLE-FAILURE CRITERION TO NUCLEAR POWER GENERATING STATION SAFETY SYSTEMS |
| ANS 59.1-1986 | COOLING WATER SYSTEMS FOR LIGHT WATER REACTORS, NUCLEAR SAFETY RELATED, |
| ANS 56.2-1984(R1989) | NUCLEAR POWER PLANTS - CONTAINMENT ISOLATION PROVISIONS FOR FLUID SYSTEMS AFTER A LOCA |
| IEEE 7-4.3.2-2016 | IEEE Standard Criteria for Programmable Digital Devices in Safety Systems of Nuclear Power Generating Stations |
| ANS 55.6-1993(R2007)(W2017) | LIQUID RADIOACTIVE WASTE PROCESSING SYSTEM FOR LIGHT WATER REACTOR PLANTS |
| ANS 56.3-77(R1987) | OVERPRESSURE PROTECTION OF LOW-PRESSURE SYSTEMS CONNECTED TO THE REACTOR COOLANT PRESSURE BOUNDARY |
| IEEE 627-2010 | IEEE Standard for Qualification of Equipment Used in Nuclear Facilities |
| ANS 55.1-1992(R2017) | SOLID RADIOACTIVE WASTE PROCESSING SYSTEM FOR LIGHT-WATER-COOLED REACTOR PLANTS |
| IEEE DRAFT 603 : D7 JUN 96 | CRITERIA FOR SAFETY SYSTEMS FOR NUCLEAR POWER GENERATING STATIONS |
| ANS 57.2-1983 | LIGHT WATER REACTOR SPENT FUEL STORAGE FACILITIES, REQUIREMENTS FOR, |
| ANS 59.3-1992(R2002) | NUCLEAR SAFETY CRITERIA FOR CONTROL AIR SYSTEMS |
| ANS 56.4-1983(R1988) | PRESSURE AND TEMPERATURE TRANSIENT ANALYSIS FOR LIGHT WATER REACTOR CONTAINMENTS |
| IEEE 352-1987 | IEEE Guide for General Principles of Reliability Analysis of Nuclear Power Generating Station Safety Systems |
| ANS 59.1-1986 | COOLING WATER SYSTEMS FOR LIGHT WATER REACTORS, NUCLEAR SAFETY RELATED, |
| ACI 301 : 2016 | SPECIFICATIONS FOR STRUCTURAL CONCRETE |
| IEEE 577-2012 | IEEE Standard Requirements for Reliability Analysis in the Design and Operation of Safety Systems for Nuclear Power Generating Stations |
| ANS 2.12-1978 | NATURAL AND EXTERNAL MAN-MADE HAZARDS AT POWER REACTOR SITES, GUIDELINES FOR COMBINING, |
| IEEE 379-2014 | IEEE Standard for Application of the Single-Failure Criterion to Nuclear Power Generating Station Safety Systems |
| ACI 318 : 2014 | BUILDING CODE REQUIREMENTS FOR STRUCTURAL CONCRETE AND COMMENTARY |
| IEEE 383-2015 | IEEE Standard for Qualifying Electric Cables and Splices for Nuclear Facilities |
| ANS 55.1-1992(R2017) | SOLID RADIOACTIVE WASTE PROCESSING SYSTEM FOR LIGHT-WATER-COOLED REACTOR PLANTS |
| ANS 56.3-77(R1987) | OVERPRESSURE PROTECTION OF LOW-PRESSURE SYSTEMS CONNECTED TO THE REACTOR COOLANT PRESSURE BOUNDARY |
| ANS 58.4-1979 | TECHNICAL SPECIFICATIONS FOR NUCLEAR POWER STATIONS, CRITERIA FOR, |
| ANS 4.5-80(R1986) | ACCIDENT MONITORING FUNCTIONS IN LIGHT-WATER-COOLED REACTORS, CRITERIA FOR |
| IEEE 334 : 2007 | QUALIFYING CONTINUOUS DUTY CLASS 1E MOTORS FOR NUCLEAR POWER GENERATING STATIONS |
| IEEE 344-2013 | IEEE Standard for Seismic Qualification of Equipment for Nuclear Power Generating Stations |
| ANS 2.13-79(R1988) | EVALUATION OF SURFACE-WATER SUPPLIES FOR NUCLEAR POWER SITES |
| ANS 2.8-1992 | DETERMINING DESIGN BASIS FLOODING AT POWER REACTOR SITES |
| ANS 2.10-2003 | CRITERIA FOR THE HANDLING AND INITIAL EVALUATION OF RECORDS FROM NUCLEAR POWER PLANT SEISMIC INSTRUMENTATION |
| ANS 2.7-1982 | SURFACE FAULTING AT NUCLEAR POWER SITES, CRITERIA AND GUIDELINES FOR ASSESSING CAPABILITY FOR, |
| IEEE 279-1971 | IEEE Standard: Criteria for Protection Systems for Nuclear Power Generating Stations |
| ANS 58.2-1988 | DESIGN BASIS FOR PROTECTION OF LIGHT WATER NUCLEAR POWER PLANTS AGAINST THE EFFECTS OF POSTULATED PIPE RUPTURE |
| ANS 2.11-1978(R1990) | GUIDELINES FOR EVALUATING SITE-RELATED GEOTECHNICAL PARAMETERS AT NUCLEAR POWER SITES |
| IEEE 450-2010 REDLINE | IEEE Recommended Practice for Maintenance, Testing, and Replacement of Vented Lead-Acid Batteries for Stationary Applications |
| ACI 349 : 2013 | CODE REQUIREMENTS FOR NUCLEAR SAFETY-RELATED CONCRETE STRUCTURES AND COMMENTARY |
| ANS 58.9-2002(R2015) | SINGLE FAILURE CRITERIA FOR LWR SAFETY-RELATED FLUID SYSTEMS |
| ICC 2009 INTERNATIONAL BUILDING CODE : 2009 | INTERNATIONAL BUILDING CODE |
| ANS 2.9-80(R1989) | EVALUATION OF GROUND WATER SUPPLY FOR NUCLEAR POWER SITES |
| ASME NQA 1 : 2015 | Quality Assurance Requirements for Nuclear Facility Applications (NQA-1 - 2015) |
| ASTM E 185 : 2016 : REDLINE | Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels |
| ANS 3.3-1988 | SECURITY FOR NUCLEAR POWER PLANTS, |
| IEEE 352-1987 | IEEE Guide for General Principles of Reliability Analysis of Nuclear Power Generating Station Safety Systems |
| ASME PV CODE 11 : 2017 | BOILER AND PRESSURE VESSEL CODE - RULES FOR INSERVICE INSPECTION OF NUCLEAR POWER PLANT COMPONENTS |
| ANS 56.2-1984(R1989) | NUCLEAR POWER PLANTS - CONTAINMENT ISOLATION PROVISIONS FOR FLUID SYSTEMS AFTER A LOCA |
| IEEE 338-2012 | IEEE Standard for Criteria for the Periodic Surveillance Testing of Nuclear Power Generating Station Safety |
| IEEE 308-2012 REDLINE | IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations |
| AISC S326 : 1978 | SPECIFICATION FOR THE DESIGN, FABRICATION AND ERECTION OF STRUCTURAL STEEL FOR BUILDINGS (WITH COMMENTARY) |
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