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ASME PV CODE 3 NCA DIV 1&2 : 2017

Superseded

Superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

View Superseded by
superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

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

Available format(s)

Hardcopy

Superseded date

05-07-2019

Language(s)

English

Published date

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Superseded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
B620-14 (R2019) Highway tanks and TC portable tanks for the transportation of dangerous goods
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
B622-14 (R2019) Selection and use of highway tanks, TC portable tanks, and ton containers for the transportation of dangerous goods, Class 2
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

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