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GB/T 41577-2022Operational intervention levels for nuclear power plant emergencies (English PDF)

核电厂应急操作干预水平

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Issued by

SAMR; SAC

Level / Type

National · Recommended

Issue date

July 11, 2022

Implementation date

February 1, 2023

Scope

GB/T 41577-2022 is the English-translated version of 核电厂应急操作干预水平.

GB/T 41577-2022 sets out how operational intervention levels are established and corrected for a reactor emergency at a nuclear power plant. It is written for pressurized water reactors, and other reactor types may take it as a reference.

It explains what the levels are for, the types of level, the default values of OIL1 to OIL9 and what each of them means, and how initial values are determined. It then gives the correction methods for OIL1 and OIL2, for OIL4, for OIL6 and OIL7 and for OIL8 and OIL9.

Four annexes add the dose action levels for acute exposure, the generic optimized intervention and action levels for emergency exposure situations, and the conversion factors for inhaled dose rate and for deposition dose.

It cites GB 18871-2002, was issued on 11 July 2022 and has applied since 1 February 2023.

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Document preview — GB/T 41577-2022

National Standard of the People's Republic of China

ICS: 27.120
Classification: F 70

Issued by: State Administration for Market Regulation; Standardization Administration of the PRC

Preface
1 Scope
2 Normative references
3 Terms and Definitions
4 Operational Intervention Level Application Purpose
5 Establishment of Operational Intervention Levels
5.1 Type of operational intervention levels
5.2 Default values for operational intervention levels
5.3 Description of default values for operational intervention levels
5.3.1 Description of OIL1
5.3.2 Description of OIL2
5.3.3 Description of OIL3
5.3.4 Description of OIL4
5.3.5 Description of OIL5
5.3.6 Description of OIL6
5.3.7 Description of OIL7
5.3.8 Description of OIL8
5.3.9 Description of OIL9
5.4 Determination of initial values for operational intervention levels
6 Operational Intervention Level Correction
6.1 General requirements
6.2 OIL1 and OIL2 corrections
6.3 OIL4 Amendment
6.4 OIL6 and OIL7 corrections
6.5 OIL8 and OIL9 Correction
Appendix A (Normative) Dose Action Levels for Acute Exposure
Appendix B (normative) Generic optimized intervention levels and action levels in emergency exposure situations
Appendix C (Informative) Inhaled dose rate conversion factor
Appendix D (informative) Deposition dose and deposition dose rate conversion factor
Reference

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 of Standardization Documents" drafted.

1 Scope

This document specifies the methodology for establishing and correcting operational intervention levels under reactor emergency conditions.

This document applies to pressurized water reactors, other types of reactors can also be used for reference.

2 Normative references

The contents of the following documents constitute essential provisions of this document through normative references in the text. Among them, dated citations documents, only the version corresponding to that date applies to this document; for undated references, the latest edition (including all amendments) applies to this document.

GB 18871-2002 Basic standard for ionizing radiation protection and radiation source safety

3 Terms and Definitions

The following terms and definitions apply to this document.

3.1 Intervention level

The preventable dose level established for an emergency exposure situation or a continuous exposure situation.

NOTE: When reaching this preventable dose level, consider taking appropriate protective or remedial actions. [Source: GB 18871-2002, J6.10, with modifications]

3.2 Action level

In the case of continuous exposure or emergency exposure, the dose level or activity concentration level at which remedial action or protective action is taken into account. [Source: GB 18871-2002, J6.11, with modifications]

3.3 Operational intervention level

The value derived from the corresponding generic intervention level or generic action level.

NOTE: Operational intervention levels are quantities that can be directly compared with instrumental measurements or laboratory analyses, such as ambient dose equivalents in radioactive plumes rate, radionuclide concentration, etc.

3.4 Preventable dose

The dose reduced by taking protective action, that is, the dose expected to be received if protective action is taken and the dose not taking protective action the difference between the doses expected to be received under the circumstances. [Source: GB 18871-2002, J6.9]

3.5 Covert sheltering

Emergency protection measures for personnel staying (or entering) indoors, closing doors, windows and ventilation systems.

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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

Normative references

GB 18871-2002Basic Standards for Protection Against Ionizing Radiation and for the Safety of Radiation Sources

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