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GB 27742-2011 PDF English

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GB 27742-2011: Activity concentration for material not requiring radiological regulation
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GB 27742-2011: Activity concentration for material not requiring radiological regulation

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ICS 17.240 F 70 GB National Standard of the People’s Republic of China Active concentration for material not requiring radiological regulation Issued on. DECEMBER 30, 2011 Implemented on. DECEMBER 1, 2012 Issued by. General Administration of Quality Supervision, Inspection and Quarantine; Standardization Administration Committee.

Table of Contents

Foreword... 3 1 Scope... 4 2 Normative references... 4 3 Terms and definitions... 5 4 Determination basis of regulation-exempted concentration... 6 5 Regulation-exempted concentration value... 7 6 Application of regulation-exempted concentration... 8 7 Verification of meeting regulation-exempted concentration values... 10 Appendix A... 13 Appendix B... 18

Foreword

The contents of Chapter 4, Chapter 5, Chapter 6, 7.1, 7.4, 7.5, 7.7 of this Standard are mandatory, the rest are recommended. This Standard is formulated by referring to IAEA safety guide “Application of the Concepts of Exclusion, Exemption and Clearance” (No. RS-G-1.7), and combining the actual situations in China. The Appendix A of this Standard is informative, the Appendix B is nominative. This Standard was proposed by National Nuclear Corporation. This Standard shall be administered by National Standardization Technical Committee of Nuclear Energy (SAC/TC 58). Main drafting organization of this Standard. Institute of Nuclear Industry Standardization. Main drafter of this Standard. Xia Yihua. Active concentration for material not requiring radiological regulation

1 Scope

This Standard specifies the active concentration for material not requiring radiological regulation (hereinafter referred to as regulation-exempted concentration). This Standard applies to activities such as production operation, trade, landfill or recycle of large amount (more than 1 ton) material. However, it does not apply to the following conditions. - Food, water, animal feed and any substances used in food or animal feed; - Radon in the air (optimized action level of radon concentration in the air is shown in Appendix H of GB 18871-2002); - Material in transporting (managed according to transportation standard); - Liquid and gas effluents generated by approved practice (they belong to the scope of approved emission); - Radioactive residues in the environment (including field soil).

2 Normative references

The provisions in following documents become the provisions of this Standard through reference in this Standard. For dated references, the subsequent amendments (excluding corrections) or revisions do not apply to this Standard, however, parties who reach an agreement based on this Standard are encouraged to study if the latest versions of these documents are applicable. For undated references, the latest edition of the referenced document applies. GB 17567-2009 Clearance levels for recycle and reuse of steel, aluminum, nickel and copper from nuclear facilities

3 Terms and definitions

The following terms and definitions apply to this Standard. 3.1 Material The collective term of substances and materials, including large amount of solid raw materials, auxiliary materials or materials intend to be deposed involved in the activities such as production operation, trade, recycle and landfill disposal. 3.2 Natural radionuclides The radionuclides that is naturally existed in the earth with significant amount. It mainly refers to the native radionuclides 235U, 238U, 232Th and theirs decay daughter. 3.3 Exclusion Outside the application scope of standard, it specifically refers to those irradiation situations that can not control the irradiation size and possibility through implementing the requirements of this Standard, such as the irradiation caused by 40K in human body and the cosmic ray reaching to the earth's surface. 3.4 Exemption The practice and the source in practice that comply with the specified exemption requirements and levels, and they are exempted from regulatory requirements after agreed by the regulatory authorities.

4 Determination basis of regulation‐exempted concentration

4.1 Determination basis of regulation-exempted concentration for natural radionuclides 4.2 Determination basis of regulation-exempted concentration for artificial radionuclides For materials containing artificial radionuclides, the criterion to determine whether it can be exempted from radiological regulation is. the individual effective dose caused by them is at the magnitude of 10 μSv/a, or less. 5 Regulation‐exempted concentration value 5.1 Regulation-exempted concentration value of natural radionuclides The regulation-exempted concentration value of natural radionuclides is shown in Table B.1. 5.2 Regulation-exempted concentration value of artificial radionuclides The regulation-exempted concentration value of artificial radionuclides is shown in Table B.2. 5.3 Regulation-exempted concentration value of inert gas For inert gas, USE the exemption concentration for artificial radionuclides given in Appendix A of GB 18871-2002 as regulation-exempted concentration. 5.4 Materials containing various of radionuclides 6 Application of regulation‐exempted concentration 6.1 Natural radionuclides 6.1.1 Under the premise that the legitimacy of activity of regulation-exempted declaration is confirmed, any activity of which the active concentration for natural radionuclides is less than or equal to the values listed in Table B.1, is usually not required to conduct radiological regulation. 6.2 Artificial radionuclides For the material in which the active concentration for artificial radionuclide is not greater than the value listed in Table B.2, after approved by regulatory authorities, the operation and use of this kind of material can be exempted from regulation, that is these exempted and cleared materials can be exempted from entering the practice protection system, unless the regulatory authorities put forward special requirements to some special cases or special uses. 6.3 Dose assessment 6.3.1 When it is determined that it is necessary to conduct dose assessment, the dose criterion for regulatory authorities to determine whether it can be exempted from regulation is. 6.3.2 For the situation of which the activity concentration exceeds the value listed in Table B.1 and Table B.2, it is required to evaluate case-by-case according to optimization principle. Based on the irradiation (or potential irradiation) amount indicated in assessment results, it shall decide to put forward radiological regulation requirements corresponding to the dangerous level. 6.4 Material and equipment with contaminated surfaces For those materials or equipment only with contaminated surfaces, they shall be executed according to the specifications of B 2.2 in GB 18871-2002.

7 Verification of meeting regulation‐exempted concentration values

7.1 The basic and direct verification methods are to conduct laboratory analysis of activity concentration to representative samples, it shall establish and adopt qualified verification process for activity concentration value. 7.3 For the material only containing γ radionuclides, or the material in which the relationship between its γ radioactivity level and the content of different nuclides is clear, it is very convenient to adopt on-site screen of γ dose rate. 7.4 Regulatory authorities shall verify the sampling and measurement methods, the quality assurance requirements of instrument configuration and verification adopted by the application organization. 7.5 Before conducting the measurement of material, it shall classify different kinds of materials, so as to let the composition and sources of same kind of material remain close. When conducting direct measurement or sample concentration analysis, tit shall ensure the representativeness of measurement condition and sampling samples. ......
Source: Above contents are excerpted from the full-copy PDF -- translated/reviewed by: www.ChineseStandard.net / Wayne Zheng et al.


      

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