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GB/T 44080-2024 English PDF

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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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GB/T 44080-2024English1079 Add to Cart 7 days [Need to translate] Management specification of reliability, availability, maintainability and safety(RAMS) for nuclear power plants Valid 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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