GB/T 47648-2026General requirements for probabilistic safety assessment of nuclear power plants (English PDF)
核电厂概率安全评价总要求
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Issued by
SAMR; SAC
Level / Type
National · Recommended
Issue date
July 2, 2026
Implementation date
February 1, 2027
Scope
GB/T 47648-2026 is the English-translated version of 核电厂概率安全评价总要求.
GB/T 47648-2026 sets general requirements for probabilistic safety assessment (PSA) of nuclear power plants. It covers the objectives, indicators, scope and technical content of a PSA, and the chapters on analysis deal with internal events, external events and the analysis procedure.
Defined terms include accident sequence, common cause failure, core damage frequency, end state and event sequence. An informative appendix gives an example of PSA technical content for nuclear power plants.
It applies to probabilistic safety assessments of nuclear power plants, and assessments of other nuclear reactor facilities should be conducted with reference to it.
Issued on 2 July 2026 and applicable from 1 February 2027, it is a new standard and replaces no earlier edition.
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Document preview — GB/T 47648-2026
National Standard of the People's Republic of China
- ICS
- 27.120.20
- Classification
- F 65
Issued by: State Administration for Market Regulation; Standardization Administration of the PRC
Contents
- Preface
- 1 Scope
- 2 Normative References
- 3 Terms and Definitions
- 4 Abbreviations
- 5 General Rules
- 5.1 PSA Objectives
- 5.2 PSA Indicator
- 5.3 PSA Scope
- 5.4 PSA Technical Content
- 6.1 Internal Incident Analysis
- 6.2 External Event Analysis
- 6.3 Analysis Procedure
- Appendix A (Informative) Example of PSA Technology Content for Nuclear Power Plants
- References
Foreword
This document complies with the provisions of GB/T 1.1-2020 "Standardization Work Guidelines Part 1: Structure and Drafting Rules of Standardization Documents".
1 Scope
This document specifies the general requirements for conducting probabilistic safety assessments (PSAs) of nuclear power plants, including the purpose, indicators, scope, and techniques of PSAs.
This document applies to probabilistic safety assessments of nuclear power plants; probabilistic safety assessments of other nuclear reactor facilities should be conducted with reference to this document.
2 Normative references
The contents of the following documents, through normative references within the text, constitute essential provisions of this document. Dated citations are not included.
For references to documents, only the version corresponding to that date applies to this document; for undated references, the latest version (including all amendments) applies to this document.
NB/T 20037.1-2017RK - Level 1 Probabilistic Safety Assessment for Nuclear Power Plants - Part 1: General Requirements
NB/T 20445.1-2017 Level II Probabilistic Safety Assessment for Nuclear Power Plants - Part 1: General Requirements
3 Terms and Definitions
The terms and definitions defined in NB/T 20037.1-2017RK and NB/T 20445.1-2017, as well as the following terms and definitions, apply to this document.
3.1 Accident sequence
A sequence of events that leads to undesirable consequences, such as core damage.
3.2 Common cause failure
Common cause failure A failure caused by a single specific event or cause that results in the failure of two or more structures, systems or components.
3.3 Core damage frequency
The number of core damage events expected per unit time. correlation dependency The external requirements upon which an item depends to perform its function, and which are related to relevant events, which are caused by other events or chance occurrences.
Events are determined by them, influenced by them, or related to them. [Source: NB/T 20037.1-2017RK, 2.1.14]
3.5 Final state end state
A set of states at the end of an event sequence, which characterizes the impact of the event sequence on the power plant or the environment. [Source: NB/T 20037.1-2017RK, 2.1.15, with modifications]
3.6 Event sequence
Following the initial incident, a series of events (including system, functional, and operator responses) occur, resulting in success or failure, and ultimately, the situation is successfully mitigated.
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This preview omits tables, figures, formulas and parts of the technical clauses. The complete document — 15 pages — is available in the English PDF.
Referenced standards
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Related Standards
NB/T 20037.1-2017 — Level 1 probabilistic safety assessment for nuclear power plant applications - Part 1: General requirements
NB/T 20445.1-2017 — Level 2 probabilistic safety assessment for nuclear power plant applications - Part 1: General requirements
GB/T 7251.4-2026 — Low-voltage switchgear and controlgear assemblies - Part 4: Particular requirements for assemblies for construction sites (ACS)
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