ASME PV CODE 3 NCA DIV 1&2 : 2017
Superseded
A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.
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BPVC Section III-Rules for Constructions of Nuclear Facility Components BOILER AND PRESSURE VESSEL CODE - RULES FOR THE CONSTRUCTION OF NUCLEAR FACILITY COMPONENTS - GENERAL REQUIREMENTS FOR DIVISION 1 AND DIVISION 2
Hardcopy
05-07-2019
English
01-07-2017
List of Sections
Foreword
Statement of Policy on the Use of the Certification Mark and
Code Authorization in Advertising
Statement of Policy on the Use of ASME Marking to Identify
Manufactured Items
Submittal of Technical Inquiries to the Boiler and Pressure
Vessel Standards Committees
Personnel
The American Concrete Institute
Organization of Section III
Summary of Changes
List of Changes in Record Number Order
Cross-Referencing and Stylistic Changes in the Boiler and
Pressure Vessel Code
Article NCA-1000 - Scope of Section III
Article NCA-2000 - Classification of Components and Supports
Article NCA-3000 - Responsibilities and Duties
Article NCA-4000 - Quality Assurance Requirements
Article NCA-5000 - Authorized Inspection
Article NCA-7000 - Reference Standards
Article NCA-8000 - Certificates, Nameplates, Certification Mark,
and Data Reports
Article NCA-9000 - Glossary
The rules of this Section constitute requirements for the design, construction, stamping, and overpressure protection of items used in nuclear power plants and other nuclear facilities.
| DocumentType |
Standard
|
| Pages |
121
|
| PublisherName |
American Society of Mechanical Engineers
|
| Status |
Superseded
|
| SupersededBy | |
| Supersedes |
| ASME AG-1 : 2019 | CODE ON NUCLEAR AIR AND GAS TREATMENT |
| ASME AG 1 : 2012 | CODE ON NUCLEAR AIR AND GAS TREATMENT |
| ANS 52.1-83(R1988) | NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY BOILING WATER REACTOR PLANTS |
| IEEE 497-2010 | IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations |
| CSA N285.8 : 2015 | TECHNICAL REQUIREMENTS FOR IN-SERVICE EVALUATION OF ZIRCONIUM ALLOY PRESSURE TUBES IN CANDU REACTORS |
| BS 7910:2005 | Guide to methods for assessing the acceptability of flaws in metallic structures |
| IEC 63147:2017 | Criteria for accident monitoring instrumentation for nuclear power generating stations |
| ASTM A 358/A358M : 2015 : REDLINE | Standard Specification for Electric-Fusion-Welded Austenitic Chromium-Nickel Stainless Steel Pipe for High-Temperature Service and General Applications |
| BS IEC 63147:2017 | Criteria for accident monitoring instrumentation for nuclear power generating stations |
| ASME PV CODE 3 NH DIV 1 : 2015 | BOILER AND PRESSURE VESSEL CODE - RULES FOR THE CONSTRUCTION OF NUCLEAR FACILITY COMPONENTS - CLASS 1 COMPONENTS IN ELEVATED TEMPERATURE SERVICE |
| API 941 REDLINE : 2008 | STEELS FOR HYDROGEN SERVICE AT ELEVATED TEMPERATURES AND PRESSURES IN PETROLEUM REFINERIES AND PETROCHEMICAL PLANTS |
| ASCE/SEI 4 16 : 2017 | SEISMIC ANALYSIS OF SAFETY - RELATED NUCLEAR STRUCTURES |
| ASME PTB 8 : 2014 | Procurement Guidelines for Metallic Materials (PTB-8 - 2014) |
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