1. Introduction
1.1 General
1.1.1 This code specifies basic requirements for the quality assurance for on-land stationary thermal neutron reactor nuclear power plants.
1.1.2 The quality assurance principles specified in this code are applicable for both nuclear power plants and other nuclear facilities.
1.1.3 An overall quality assurance program for a nuclear power plant as well as separate programs for each constituent activity (e.g., siting, design, fabrication, construction, commissioning, operation and decommissioning) shall be properly developed and effectively implemented to ensure nuclear power plant safety. This code puts forward principles and objectives for the development and implementation of these programs. The principles to be followed for each type of program are the same.
1.1.4 It shall be noted that in performing a particular task (e.g., in siting, design, fabrication, construction, commissioning, operation and decommissioning) the major responsibility for achieving required quality rests with those assigned the task but not with the personnel responsible for verifying the quality.
1.1.5 Quality assurance program shall include the activities necessary for bringing items and service to the quality requirements, for ensuring by means of verification that the required quality has been achieved, and for collecting subjective evidence for the above mentioned activities.
1.1.6 Quality assurance is an essential part of “effective management”. Effective management contributes to the achievement of quality through thorough analysis of the tasks to be performed, identification of required skills, selection and training of appropriate personnel, use of appropriate equipment and procedures, creation of a satisfactory environment in which the activities are to be performed, and a clear recognition of the responsibility of those who are to undertake the tasks. Briefly speaking, a quality assurance program shall specify the requirements for and approach to all activities affecting quality, including verification that each task under verification has been properly verified and that necessary corrective action has been implemented. It shall also provide for the production of documentary evidence to demonstrate that required quality has been achieved.
1.1.7 The specific approaches adopted to implement this code, both at overall plant level and at the constituent activity level, may vary from organization to organization. However, at any case, the principles established in this code shall be followed and detailed implementation procedures shall be developed accordingly. It shall be recognized that a quality assurance program shall be precise and enable easy implementation while ensuring the integration of both technical and managerial activities.
1.2 Scope
This code specifies the principles and objectives for the development and implementation of a quality assurance program during siting, design, fabrication, construction, commissioning, operation and decommissioning in a nuclear power plant. These principles and objectives are applicable for all activities affecting the quality of items and services, such as design, procurement, fabrication, manufacture, handling, shipping, storage, cleaning, civil construction, installation, testing, commissioning, operation, inspection, maintenance, repair, refueling, modification and decommissioning. They are applicable by all the personnel responsible for the nuclear power plant, by plant designers, equipment suppliers, architect-engineers, plant constructors, plant operators, and other organizations participating in the activities affecting quality.
The safety guideline specified in Annex I serves as interpretation of and supplement to this code.
HAF 003-1991 Nuclear power plant safety requirements for quality assurance (English Version)
Standard No.
HAF 003-1991
Status
valid
Language
English
File Format
PDF
Word Count
9000 words
Price(USD)
270.0
Implemented on
1991-7-27
Delivery
via email in 1 business day
Detail of HAF 003-1991
Standard No.
HAF 003-1991
English Name
Nuclear power plant safety requirements for quality assurance
Chinese Name
核电厂质量保证安全规定
Chinese Classification
Professional Classification
HAD
ICS Classification
Issued by
National Nuclear Safety Administration
Issued on
1991-07-27
Implemented on
1991-7-27
Status
valid
Superseded by
Superseded on
Abolished on
Superseding
Language
English
File Format
PDF
Word Count
9000 words
Price(USD)
270.0
Keywords
HAF 003-1991, HAF/T 003-1991, HAFT 003-1991, HAF003-1991, HAF 003, HAF003, HAF/T003-1991, HAF/T 003, HAF/T003, HAFT003-1991, HAFT 003, HAFT003
Introduction of HAF 003-1991
1. Introduction
1.1 General
1.1.1 This code specifies basic requirements for the quality assurance for on-land stationary thermal neutron reactor nuclear power plants.
1.1.2 The quality assurance principles specified in this code are applicable for both nuclear power plants and other nuclear facilities.
1.1.3 An overall quality assurance program for a nuclear power plant as well as separate programs for each constituent activity (e.g., siting, design, fabrication, construction, commissioning, operation and decommissioning) shall be properly developed and effectively implemented to ensure nuclear power plant safety. This code puts forward principles and objectives for the development and implementation of these programs. The principles to be followed for each type of program are the same.
1.1.4 It shall be noted that in performing a particular task (e.g., in siting, design, fabrication, construction, commissioning, operation and decommissioning) the major responsibility for achieving required quality rests with those assigned the task but not with the personnel responsible for verifying the quality.
1.1.5 Quality assurance program shall include the activities necessary for bringing items and service to the quality requirements, for ensuring by means of verification that the required quality has been achieved, and for collecting subjective evidence for the above mentioned activities.
1.1.6 Quality assurance is an essential part of “effective management”. Effective management contributes to the achievement of quality through thorough analysis of the tasks to be performed, identification of required skills, selection and training of appropriate personnel, use of appropriate equipment and procedures, creation of a satisfactory environment in which the activities are to be performed, and a clear recognition of the responsibility of those who are to undertake the tasks. Briefly speaking, a quality assurance program shall specify the requirements for and approach to all activities affecting quality, including verification that each task under verification has been properly verified and that necessary corrective action has been implemented. It shall also provide for the production of documentary evidence to demonstrate that required quality has been achieved.
1.1.7 The specific approaches adopted to implement this code, both at overall plant level and at the constituent activity level, may vary from organization to organization. However, at any case, the principles established in this code shall be followed and detailed implementation procedures shall be developed accordingly. It shall be recognized that a quality assurance program shall be precise and enable easy implementation while ensuring the integration of both technical and managerial activities.
1.2 Scope
This code specifies the principles and objectives for the development and implementation of a quality assurance program during siting, design, fabrication, construction, commissioning, operation and decommissioning in a nuclear power plant. These principles and objectives are applicable for all activities affecting the quality of items and services, such as design, procurement, fabrication, manufacture, handling, shipping, storage, cleaning, civil construction, installation, testing, commissioning, operation, inspection, maintenance, repair, refueling, modification and decommissioning. They are applicable by all the personnel responsible for the nuclear power plant, by plant designers, equipment suppliers, architect-engineers, plant constructors, plant operators, and other organizations participating in the activities affecting quality.
The safety guideline specified in Annex I serves as interpretation of and supplement to this code.
