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GB 27742-2011 (GB27742-2011)

GB 27742-2011_English: PDF (GB27742-2011)
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GB 27742-2011English130 Add to Cart 0--9 seconds. Auto-delivery Activity concentration for material not requiring radiological regulation Valid GB 27742-2011

BASIC DATA
Standard ID GB 27742-2011 (GB27742-2011)
Description (Translated English) Activity concentration for material not requiring radiological regulation
Sector / Industry National Standard
Classification of Chinese Standard F70
Classification of International Standard 17.240
Word Count Estimation 15,179
Date of Issue 2011-12-30
Date of Implementation 2012-12-01
Quoted Standard GB 17567-2009; GB 18871-2002
Drafting Organization Nuclear Industry Standardization Institute
Administrative Organization National Standardization Technical Committee of Nuclear Energy
Regulation (derived from) Announcement of Newly Approved National Standards No. 22 of 2011
Proposing organization China National Nuclear Corporation
Issuing agency(ies) Administration of Quality Supervision, Inspection and Quarantine of People's Republic of China; Standardization Administration of China
Summary This Chinese standard specifies the radiation protection regulation may be exempted from the material activity concentration of radionuclides. This standard applies to large quantities (greater than 1 ton) of material production operations, trade, landfill or recycling and other activities, but does not apply to the following: food, water, animal feed and animal feed for food or any substance, radon (radon concentration in air action level optimization see GB 18871-2002 Appendix H), transport material (standard management of transport), has approved the practice of the resulting liquid and airborne effluent (they belong to the approval of emissions range), environment (including soil at the site) of the radioactive residues.

Standards related to: GB 27742-2011

GB 27742-2011
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
GB 18871-2002 Basic standards for protection against ionizing radiation and
for the safety of radiation sources
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.
3.5
radiation, the additional criterion is. the effective dose possibly caused by this
kind of low probability events shall not exceed 1 mSv/a, at the same time the
exemption regulation criterion of equivalent dose to the skin is also assumed
as 50 mSv/a.
Note. The irradiation scenarios, ways, main relevant parameters taken into
account when deducing regulation-exempted concentration for artificial
radionuclides are shown in Appendix A.
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
5.4.1 Materials containing different natural radionuclides
For materials containing different mixtures of natural radionuclides, it shall be
required that each active concentration for natural radionuclides shall meet the
requirements of relevant values listed in Table B.1.
5.4.2 Mixture of artificial radionuclides
For materials containing various of mixtures of artificial radionuclides, it shall
be required that the sum of RATIOES of each activity concentration for artificial
radionuclides AND the respective regulation-exempted concentration values
shall be less than 1, that is meeting the requirements of formula (1).
management.
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.
6.5 Steel, aluminum, nickel and copper with minor contamination
For the recycle and reuse of steel, aluminum, nickel and copper with minor
radioactive contamination, it has already be specified in GB 17567-2009 that
the clearance level of artificial radionuclides that can be melted and reused
can be seen as regulation-exempted declared value. For other radionuclides
regulation-exempted concentrations (including natural radionuclides) that are
not given in GB 17567 -2009, it can be implemented by referring to this
Standard.
6.6 Small amount of material (less than 1 ton)
For cases of small amount (less than 1 ton) material, it shall be implemented
according to the exemption concentration given in the Appendix A of 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.
7.2 Under the premise of ensuring that the active concentration for material
shall not exceed the regulation-exempted concentration value of this Standard,
it can adopt some indirect methods, including conducting on-site screening
and measurement of γ dose rate of radioactive-contaminated materials, the
method of determining the relationship between the different nuclides content
according to appropriate derivation, the method of inquiring traceable
allowed without the consent of the regulatory authorities.
7.7 After the radioactive content in material meets the requirements of this
Standard, it shall also meet the requirements of relevant national standards in
other aspects (for example, chemical, biological toxicity, etc.).
Appendix A
(Informative)
The irradiation scenarios, ways, main relevant parameters considered when deriving regulation-exempted concentration
for artificial radionuclides
Table A.1 The irradiation scenarios and relevant ways
Irradiation scenarios Description Individual being exposed Relevant irradiation ways
WL
Staff at the landfill or other utilities
(except melting plant)
Working staff
External irradiation at landfill;
Inhaled internal irradiation at landfill;
polluted materials ingested directly
WF Staff in the melting plant Working staff
External irradiation from equipment or waste
iron heap in melting plant;
Inhaled internal irradiation in melting plant;
polluted materials ingested directly
WO Other staff (such as truck driver) Working staff
External irradiation from equipment or materials
loaded by truck
RL-C
Residents near landfill or other
utilities
1-year-old ~ 2-year-old children Inhaled internal irradiation near landfill or other
utilities;
Ingested internal Irradiation of food growin...
...