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GB/T 44080-2024: Management specification of reliability, availability, maintainability and safety(RAMS) for nuclear power plants
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Management specification of reliability, availability, maintainability and safety(RAMS) for nuclear power plants
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GB/T 44080-2024
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Basic data | Standard ID | GB/T 44080-2024 (GB/T44080-2024) | | Description (Translated English) | Management specification of reliability, availability, maintainability and safety(RAMS) for nuclear power plants | | Sector / Industry | National Standard (Recommended) | | Classification of Chinese Standard | F63 | | Classification of International Standard | 27.120.20 | | Word Count Estimation | 54,522 | | Date of Issue | 2024-05-28 | | Date of Implementation | 2024-05-28 | | Issuing agency(ies) | State Administration for Market Regulation, China National Standardization Administration | GB/T 44080-2024: Management specification of reliability, availability, maintainability and safety(RAMS) for nuclear power plants
---This is a DRAFT version for illustration, not a final translation. Full copy of true-PDF in English version (including equations, symbols, images, flow-chart, tables, and figures etc.) will be manually/carefully translated upon your order.
ICS 27:120:20
CCSF63
National Standards of People's Republic of China
Nuclear power plant reliability, availability, maintainability and
Security Management Specifications
Released on 2024-05-28
2024-05-28 Implementation
State Administration for Market Regulation
The National Standardization Administration issued
Table of Contents
Preface III
Introduction IV
1 Scope 1
2 Normative references 1
3 Terms and Definitions 1
4 Abbreviations 2
5 General Requirements for RAMS in Nuclear Power Plants 2
6 RAMS Management of Nuclear Power Plants Based on Life Cycle 6
7 RAMS life cycle management specifications for each stage 8
Appendix A (Informative) RAMS Specification Example 25
Appendix B (Informative) RAMS Outline 30
Appendix C (Informative) Examples of Nuclear Power Plant Parameters 33
Appendix D (Informative) RAMS tasks at each stage of the nuclear power plant life cycle 35
Appendix E (Informative) Risk Analysis and Evaluation 38
Appendix F (Informative) Examples of Some Risk Acceptance Criteria 40
References 44
Foreword
This document is in accordance with the provisions of GB/T 1:1-2020 "Guidelines for standardization work Part 1: Structure and drafting rules for standardization documents"
Drafting:
Please note that some of the contents of this document may involve patents: The issuing organization of this document does not assume the responsibility for identifying patents:
This document was proposed and coordinated by the National Nuclear Energy Standardization Technical Committee (SAC/TC58):
This document was drafted by: Tsinghua University, Shanghai Nuclear Engineering Research and Design Institute Co:, Ltd:, China General Nuclear Power Engineering Co:, Ltd:, China National Nuclear Corporation
Operation Service Technology Co:, Ltd:, China Nuclear Power Engineering Co:, Ltd:, Beijing Institute of Petrochemical Technology, China Nuclear Energy Technology Co:, Ltd:, Shenzhen Zhongguang
Nuclear Engineering Design Co:, Ltd:, Nuclear Power Operation Research (Shanghai) Co:, Ltd:, and Nuclear Industry Standardization Institute:
The main drafters of this document are: Li Zhizhong, Zhang Renyou, Hu Juntao, Duan Feng, Zhong Zhimin, Xu Zhixin, Yu Guangwei, Tian Xiufeng, Liu Zhaopeng,
Tong Jiejuan, Liu Tao, Zhao Jun, She Manrong, Zhang Bing, Sun Feng, Wang Xin, Ling Shiqing, Du Dongxiao, Deng Ruiyuan, Wu Feifei, Liu Shangyuan:
Introduction
This document divides the life cycle of a nuclear power plant into the following 5 major stages and 14 minor stages:
a) Design:
1) Concept design (including site selection);
2) Definition and application conditions of nuclear power plants;
3) Risk analysis;
4) Determination of nuclear power plant demand;
5) Nuclear power plant demand allocation;
6) Detailed design:
b) Construction:
1) Manufacturing;
2) Construction and installation:
c) Debugging:
1) Nuclear power plant confirmation;
2) Acceptance inspection of nuclear power plants:
d) Operation and supervision management:
1) Operation and maintenance;
2) Performance tracking;
3) Transformation:
e) Decommissioning: Decommissioning and final disposal:
Based on the above stage division, this document provides the reliability, availability, maintainability and safety tasks of each stage of the nuclear power plant life cycle:
Objectives, requirements, inputs, results and verification tasks provide guidance for the systematic management of the entire process of nuclear power plants, but also emphasize the operation of nuclear power plants:
Based on the applicability of the contents of this document to specific nuclear power plants and taking into account the special needs of specific nuclear power plants, the unit shall evaluate how to apply it to specific
In addition, the requirements of this document only involve reliability, availability, maintainability and safety, which need to be applicable in accordance with GB/T 19001:
The required quality management system is implemented with the support of the required quality management system:
Nuclear power plant reliability, availability, maintainability and
Security Management Specifications
1 Scope
This document specifies the implementation of a coherent whole process management of reliability, availability, maintainability and safety throughout the life cycle of a nuclear power plant:
Methods and requirements:
This document is applicable to RAMS management at all stages of the life cycle of nuclear power plants:
2 Normative references
The contents of the following documents constitute the essential clauses of this document through normative references in this document:
For referenced documents without a date, only the version corresponding to that date applies to this document; for referenced documents without a date, the latest version (including all amendments) applies to
This document:
GB/T 2900:99 Credibility of electrical terminology
HAF103-2022 Safety regulations for commissioning and operation of nuclear power plants
3 Terms and definitions
The terms and definitions defined in GB/T 2900:99 and the following apply to this document:
3:1
Audit
A systematic, independent, documented process for obtaining records, statements of fact, or other relevant information and evaluating them objectively to determine
The extent to which specified needs are met:
[Source: ISO /IEC TR29110-1:2016, 3:7]
3:2
Hazard
An essential quality or condition that may result in harm or destruction:
[Source: ISO /IEC /IEEE24765:2017,3:1787-1]
3:3
Hazard Log
A document that records all safety management activities, hazards identified, decisions made, and solutions taken:
Note: Hazard logs are also called security logs:
3:4
Mission Profile
A description of the expected ranges and variations of parameters such as power, reactivity, temperature, pressure, flow, etc: during the mission of a nuclear power plant:
3:5
Resource support
All resources arranged and organized to operate and maintain a product at the required life cycle cost and specified availability level:
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