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GB 15848-2009: Regulations for radiation and environment protection in uranium exploration
Status: Valid GB 15848: Evolution and historical versions
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Regulations for radiation and environment protection in uranium exploration
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GB 15848-2009
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| GB 15848-1995 | English | 559 |
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Regulations for radiation and environment protection in uranium geology
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Basic data | Standard ID | GB 15848-2009 (GB15848-2009) | | Description (Translated English) | Regulations for radiation and environment protection in uranium exploration | | Sector / Industry | National Standard | | Classification of Chinese Standard | F73 | | Classification of International Standard | 13.280 | | Word Count Estimation | 20,264 | | Date of Issue | 2009-05-06 | | Date of Implementation | 2010-02-01 | | Older Standard (superseded by this standard) | GB 15848-1995 | | Quoted Standard | GB 11215; GB 11806; GB 16297; GB 18871-2002 | | Regulation (derived from) | Announcement of Newly Approved National Standards No. 6, 2009 (No. 146 overall) | | Issuing agency(ies) | General Administration of Quality Supervision, Inspection and Quarantine of the People's Republic of China, Standardization Administration of the People's Republic of China | | Summary | This Chinese standard specifies requirements for uranium geological exploration work in radiation workers and the public dose constraint values ??, workplace radiation protection, occupational exposure management, environmental protection and emergency response requirements. This standard applies to the production of uranium geology, research and education sectors, containing natural radioactive substances in other geological departments can also be implemented by reference. | GB 15848-2009: Regulations for radiation and environment protection in uranium exploration---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.
Regulations for radiation and environment protection in uranium exploration
ICS 13.280
F73
National Standards of People's Republic of China
Replacing GB 15848-1995
Uranium exploration and radiation protection regulations on environmental protection
Posted 2009-05-06
2010-02-01 implementation
Administration of Quality Supervision, Inspection and Quarantine of People's Republic of China
Standardization Administration of China released
Foreword
All the technical contents of this standard is mandatory.
This standard replaces GB 15848-1995 "uranium radiation protection and environmental regulations."
The standards are compared with GB 15848-1995 mainly the following changes.
a) in accordance with applicable laws, regulations and standards are not consistent with the revised terms of the content of the original standard;
b) increase the training and emergency response content;
c) of the original section of the standard of a reasonable adjustment and consolidation.
The Standard Annexes A and B are normative appendix Appendix C is informative appendix.
The standard proposed by China National Nuclear Corporation.
This standard by the National Standardization Technical Committee on Nuclear Energy (SAC/TC58) centralized.
This standard was drafted. China Nuclear Industry Geological Bureau of Nuclear Industry Er ○ Ba brigade.
The main drafters of this standard. Gu Hua, Ding busy students, Zhang Junyi, Dai-Ming Shen, Xie Kaijing.
This standard replaces the standards previously issued as follows.
--- GB 15848-1995.
Uranium exploration and radiation protection regulations on environmental protection
1 Scope
This standard provides for uranium exploration in radiation workers and the public dose constraint value, workplace radiation protection, occupational
Illumination management, environmental protection and emergency requirements.
This standard applies to the production, research and education sectors uranium geology, and engage in other geological department containing natural radioactive substances can also refer to
carried out.
2 Normative references
The following documents contain provisions which, through reference in this standard and become the standard terms. For dated references, subsequent
Amendments (not including errata content) or revisions do not apply to this standard, however, encourage the parties to the agreement are based on research
Whether the latest versions of these documents. For undated reference documents, the latest versions apply to this standard.
GB 11215 General provisions Nuclear Radiation Environment Quality Evaluation
GB 11806 Regulations for the Safe Transport of Radioactive Substances
GB 16297 Air Pollutant Emission Standards
GB 18871-2002 ionizing radiation protection and safety of radiation sources basic standards
3 Terms
The following terms and definitions apply to this standard.
3.1
In order to search for and identify uranium resources, exploration and use various means to understand the geology of the ground, recognizing that uranium mineralization conditions and environment, integrated
Cooperative prospect of uranium mineralization, determine the favorable area, find uranium ore belt, proven uranium scale, find out the process of uranium-containing layer and the output capacity of the case.
3.2
Underground exploration of uranium resources carried out prospecting operations.
3.3
Uranium content of uranium produced during geological exploration in more than one ten thousandth of uranium ore.
3.4
Uranium exploration generated during the waste rock (less than one ten thousandth grade uranium) and other solid wastes in general.
3.5
Radon concentration in air time integration. By showing the concentration of radon daughters by different units, exposure units are not the same.
When the concentration of radon daughters in J/m3 when the units of exposure expressed in J · h/m3.
3.6
(Radon progeny and
Radon (222Rn) daughters of complete decay of 210Pb (but not including 210Pb decay) and (220Rn) daughters of complete decay to stable
When 208Pb, the sum of α particles emitted energy in joules (J).
3.7
radon(
All radon or unit volume present in the air
All short-lived daughter atoms decay product mixture by any decay chains respectively
Decays to 210Pb (RaD) or total 208Pb α particles emitted during the energy in joules per cubic meter (J/m3).
3.8
Unit volume of air contained in the long-lived radionuclides α radioactive aerosol total α activity, in units of becquerels [Harrell] per cubic meter
(Bq/m3). Usually short-lived radon daughters by the analysis unit volume of total α activity obtained after complete decay.
4 General Provisions
4.1 Radiation protection should comply with the legitimacy of the practice, the risk of potential exposure and dose limiting restrictions, protection and security, optimization, and dose constraints
Principles potential exposure hazard constraints; environmental protection should implement environmental regulations promulgated by the state, standards, adhere to the "polluter pays" principle.
Environmental impact assessment should be carried out according to the law before 4.2 uranium exploration project construction.
4.3 uranium exploration project in radiation protection and environmental protection facilities with the main project should be designed, constructed and put into
use.
4.4 pipe uranium exploration units should set up regulatory agencies radiation protection and environmental protection, the development of the unit radiation protection and environmental protection
Management requirements and contingency plans, radiation protection monitoring. Engaged in uranium exploration personnel radiation safety, and environmental protection knowledge
Training, and regularly review assessment.
4.5 Uranium geological exploration unit protection and safety should develop an outline, which should include.
a) to determine the measures and resources to achieve the objectives of protection and safety needs, and ensure the correct implementation of these measures and the provision of these resources;
b) keep such measures and resources, regular review, and regularly verify protection and safety objectives are achieved;
c) Identification of any failure or defect protection and safety measures and resources, and take steps to correct it and prevent it from happening again;
d) according to protection and security needs, to make easy consultation and cooperation among the parties concerned arrangements;
e) Save fulfill the responsibilities of the record.
5 dose limiting
5.1 GB 18871-2002 comply with Appendix B of B. 1. The provisions relating to workers and the public dose constraint values.
5.2 engaged in uranium exploration career staff annual effective dose constraint value is not higher than 15mSv.
5.3 Pregnant women, nursing women may not engage in uranium exploration wells pit jobs, other jobs in the uranium effective dose constraint value of not more than
1mSv.
5.4 younger than 18 years old to accept the learning process involves radiation exposure employment training apprentices and younger than 18 years of age need to use
Students radioactive sources, should control its occupational exposure annual effective dose does not exceed 6mSv.
5.5 Practice with radiation exposure of members of the public about the critical groups are subjected dose estimates shall not exceed the following limits.
a) annual effective dose, 1mSv;
Under b) special case, if the average annual dose of five consecutive years does not exceed 1mSv, the effective dose of a single year can be increased
To 5mSv.
5.6 pit uranium geology, exploration wells so that the annual effective dose constraint value members of the public about the critical group of the subject should not exceed
Too 0.5mSv.
5.7 Radioactive staff engaged by both external beam and is irradiated within a variety of radionuclides, should satisfy 5.1 and formula (1)
Provisions.
HP
DL + j
I j, ing
I j, ing, L
+
I j, inh
I j, inh, L ≤
1 (1)
Where.
HP --- throughout the year due to the irradiation of radiation personal dose equivalent units of mSv [Waters] (mSv);
DL --- corresponding effective dose of annual dose constraint value in units of mSv [Waters] (mSv);
I j, ing and I j, inh --- the same year ingestion or inhalation intake of radionuclides j, in units of becquerels [Harrell] (Bq);
I j, ing, L and I j, inh, L --- ingestion or inhalation of the radionuclide j constraint value of annual intake (ALI), in units of becquerels [Harrell] (Bq).
5.8 uranium exploration staff annual intake of radionuclides common constraint values in Appendix A, Table A. 1, the annual intake of other nuclides
Constraint value (ALI) in accordance with Appendix AA. 2 Chinese (A.1) is calculated.
5.9 pairs in the short-lived 222Rn or 220Rn progeny as the main hazards in the workplace, and their short-lived progeny α potential annual intake and photos
Injection quantity limit see Appendix A, Table A. 2.
6 Radiation Protection in the workplace
6.1 The main protection requirements in the workplace
6.1.1 radiation in the workplace should be a partition of 6.4 GB 18871-2002 requirements division, as far as possible in the field should be divided according to the construction and build
Was delimitation; uranium exploration tunnel, exploration wells, broken like radioactive dust and other workplaces zoned controlled area, other non-dust workplace plan
To oversee the area.
6.1.2 The new radiation in the workplace should select a plurality of candidate sites, a comprehensive evaluation, merit-based selection.
6.1.3 The new radiation in the workplace, should choose a lower population density, radioactive gas dilution and dispersion conditions better place, and should be set
In a region, according to local minimum frequency of wind direction, disposed upstream of a residential or other workplace.
6.1.4 radiation in the workplace and residential areas and drinking water source protection should be a certain distance, which limits the distance in Table 1. Within this distance
Area designated a restricted zone, the zone to deal with radioactive material regularly monitored.
6.1.5 Where the radioactive dust, aerosol in the workplace, its floors, walls and ceilings shall be used for building material can not easily be contaminated
Decoration materials, and strive to smooth; interior structure should be simple, to reduce the surface dust and easy to clean. Mineral analysis room, rooms and other pieces like sewage drain should be set up to access
Water pool.
6.1.6 Uranium samples should be stored in a special sample library, and let someone manage.
6.1.7 uranium ore processing chamber, Fusion and rooms should be equipped with exhaust gas treatment facilities, so that the exhaust gas after reaching the requirements of GB 16297 emissions.
Limit distance unit table 1 uranium radioactive workplace meters
Other places
Ore samples and models
Showroom
Crushed sample chamber, Fusion and room,
Ore processing chamber
Tunnel air vents, waste dumps,
Hydrometallurgical plant
Residential 3,050,500
Drinking water source 30 100 500
6.2 Dust drop radon
6.2.1 underground workplace, should be taken to "strengthen the mechanical ventilation and wet work, confined dust source radon, good personal protection, strengthen protection facilities management
Management and regular checks "and other comprehensive measures to make underground workplace air Rn-222 concentration is not more than 2.7kBq/m3, Rn-222 progeny α latent
Concentration can not be more than 5.4μJ/m
3, the dust concentration of not more than 2mg/m3.
6.2.2 Where the radioactive dust and harmful gases ground workplace, there should be ventilation device, the ventilation system should prevent backflow contamination.
6.2.3 underground ventilation requirements
6.2.3.1 inclined drift and deeper than 20m, shaft or shallow than 10m, patio over 5m, shall be mechanically ventilated. jobs
Surface should be used with forced ventilation, pressed into the duct from the end of the working face shall not exceed 10m, expenses lane roadway or turn driving deeper than 5m
When there should be a special ventilation.
6.2.3.2 When entering the tunnel work, should be ventilated so that the radon concentration inside the tunnel and its daughters to meet the requirements of 6.2.1, and not less ventilation time
In 15min. Pit stop when someone shall be ventilated.
6.2.3.3 to determine the amount of ventilation shall be met so that radon and its progeny in the roadway falls below the concentration limits required air flow.
6.2.3.4 Hang exhaust outlet should be located upwind side inlet minimum wind frequency, it should maintain a certain distance between the outlet and the inlet.
6.2.4 downhole seal radon reduction measures
6.2.4.1 The completed tunnel should be closed. To be closed tight and firm. As a result of the work need to enter the closed tunnel, shall be subject to protection management unit
Door agree, wear protective breathing apparatus and personal dosimeter, afterwards immediately re-sealed.
See sections 6.2.4.2 ore and fractured the main roadway should Arching or spraying anti-radon coating layer to reduce the precipitation of radon. And minimize
Ore residence time in the tunnel was not closed.
6.2.4.3 tunnel drains should be regularly cleaned to maintain water flow, high concentrations of radon underground water, should be set up dedicated pipe water directly into the pit outside
Wastewater treatment facilities.
6.2.4.4 trenches along veins should be designed in the veins outside. Construction-product ore and waste rock should be stacked separately.
6.2.5 Tunnel Excavation byproduct waste rock and ore processing
6.2.5.1 Tunnel Excavation waste rock produced should focus stacking and set below the retaining wall to prevent the waste rock by rain erosion loss.
6.2.5.2 byproduct of ore and waste rock pile should be separated, tunnel boring end-product of ore will promptly backfill into the tunnel.
6.3 surface contamination control
6.3.1 workplace (but not including underground workplace) table, equipment, walls, floors, roof surface and the staff work
Surface radioactive contamination control level clothes, underwear, etc. See Appendix B Table B. 1.
Workplace equipment, walls, floors, roofing appropriate decontamination measures, still exceeds Appendix B Table B. 1 The values listed, visualization
Fixity of pollution. After examination and administration department or the department authorized by the regulatory authorities to check it agrees, an appropriate increase in the level of control, but not exceeding attached
Appendix B Table B. 5 times the values listed in Table 1.
6.3.2 workplace equipment and supplies, after decontamination, to reduce their pollution levels in Appendix B Table B. 1. The values listed in the fiftieth
When one of the following, audited authorities or departments authorized by the regulatory authorities confirm consent, it can be used as common items to use.
6.4 Management of Radioactive Sources
6.4.1 should be engaged in activities using radioisotopes and radiation devices in accordance with the radiation safety license. Prohibited without a license or not
In accordance with the provisions of the license type and scope of activities in the use of radioisotopes and radiation devices.
6.4.2 The use of radioactive sources and waste should sign production unit of the imported radioactive sources radioactive sources return the contract.
6.4.3 The use of radioactive sources shall return the contract in accordance with radioactive waste, unused or abandoned radioactive sources within three months old
Radioactive surrender production units or return to the original exporter. Really can not be returned to production units or to return the original export side, sent a corresponding funding
Qualitative centralized storage of radioactive waste storage unit.
6.4.4 The use of radioactive sources shall be returned to the radioactive waste from the date of completion of activities within 20 days, the provincial environmental protection to the local
Administrative departments for the record.
6.4.5 radiation work unit shall establish a dedicated national standard radioactive source staging database staging library sources should meet the relevant requirements,
Set up special management, and regular inspections and monitoring.
6.4.6 radiation work unit shall establish the use of radioactive sources management system, including. procurement sources, storage, transfer, recipients, restitution,
Scrapped.
6.4.7 When the radiation work unit shall establish a ledger of radioisotopes and radiation apparatus, according radioisotopes radionuclide name, factory
Room and activity, name labels, coding, origin and destination, and radiation-emitting devices, models, ray type, category, purpose, origin and destination and other matters.
Radioisotopes and radiation ledger should be long-term preservation.
6.4.8 solid sealed radioactive sources should be installed in the lead tank, put together securely locked container, away from the surface of the container at any point 5cm agent
Amount equivalent rate should not exceed 2.5μSv/h, and placed in a safe and reliable source library.
6.4.9 sources should be checked regularly for leaks.
6.4.10 transfer of radioactive sources, should be put in a container of radioactive sources in compliance with protection requirements, and prohibited carry by public transport.
6.4.11 If radioactive source is lost, damaged, the unit should immediately start emergency plan, and to take measures in a timely manner to the local environmental protection department
report.
6.4.12 When using sealed radioactive sources, should try to shorten the exposure time and the expansion of the operating distance, and take measures to shield.
6.5 Transport Safety
6.5.1 transporting ore, ore and rock cores, etc., must have anti-spill, anti-dust measures. Shipment of ore, ore and rock cores vehicles with
After decontamination should be carefully cleaned.
6.5.2 Railway Transport performed in the relevant provisions of GB 11806.
6.5.3 Staff dose in transport requirements
a) an effective amount of a year can not exceed 1mSv, without using a special way of working, we do not have detailed monitoring, dose formulation
Measuring Program and save personal records;
B) When the year is expected to be the effective dose between 1mSv ~ 5mSv, monitoring or individual monitoring shall be formulated by the workplace
Dose assessment program and save the relevant records;
c) the effective dose expected to be a year when more than 5mSv, individual monitoring should be carried out. When individual monitoring or workplace monitoring
, Should keep relevant records.
7 occupational exposure management
7.1 General requirements
7.1.1 uranium exploration units should be set radiation safety authorities and with technical management personnel.
7.1.2 uranium exploration units should develop and implement regulations and procedures for the control and management of occupational exposure unit, ensure workers
The level of protection and security for staff and other personnel in line with GB 18871 requirements.
7.1.3 should strengthen protection and security training and cultural awareness cultivation, improve staff and associated personnel rules established by Cheng
Understanding and awareness of the program and the implementation of protection and safety regulations. All training records should be archived properly kept.
7.1.4 The monitoring system should be established in accordance with the requirements of the regulatory authorities and the appointment of the person in charge of radiation protection for all work involving occupational exposure be
Adequate oversight and to take reasonable steps to ensure that obtain various rules, procedures, protection and compliance with safety regulations and so on.
7.1.5 All staff should be provided.
a) they have suffered occupational exposure (including normal exposure and potential exposure) the circumstances and the possible health effects;
b) appropriate protection and safety training and guidance;
c) their actions on the protection and information security sense.
7.1.6 Female workers should be possible to enter the controlled area and supervised areas of work include the following information.
a) risks to pregnant women is irradiated embryos and fetuses;
b) the importance of female staff notification unit radiation management as soon as possible after pregnancy;
c) the baby through breast-feeding ingestion of radioactive material danger.
7.2 Personal protection and sanitation
7.2.1 The control area should be established showers, changing rooms and rooms Bao Jianxiang.
7.2.2 According to the actual need for staff to provide suitable, adequate and comply with the relevant standard personal protective equipment, such as various types of protective clothing, protective
Aprons, protective gloves, protective masks and respiratory protective equipment, etc., and should make them understand that they use protective equipment performance and use,
The incoming radiation in the workplace, should wear protective equipment.
7.2.3 Do not eat in the workplace radiation, drinking, smoking and storing food; before eating radiation workers should wash their hands, gargle. Used
Protective equipment should be cleaned regularly, can not bring back living area.
7.3 Monitoring and evaluation of occupational exposure
7.3.1 Individual Dose Monitoring and Evaluation
7.3.1.1 personal dose monitoring and evaluation of the implementation of GB 18871-2002 in accordance with the provisions of 6.6.2.
7.3.1.2 uranium underground operations, ore crushing, high-grade ore and other model making annual intake may exceed the annual dose limit
Radiation workers 5mSv/a should be carried out within the individual radiation dose monitoring and skin, pollution monitoring garment.
7.3.1.3 Calibration radioactive leak detection personnel engaged in uranium ore grade of greater than two hundred locations in pitting operations personnel and others
Irradiation dose may exceed the annual dose limit 5mSv/a radiation workers should be external irradiation individual dose monitoring.
7.3.1.4 occur Losing Radioactive Source, Exposed personnel dose response of tracking; when broken by radioactive contamination, the victim's response
Clothing and body surface exposure were α, β surface contamination monitoring and internal exposure monitoring.
7.3.1.5 individuals inside and outside the radiation dose greater than the value of life 1mSv/a, but is unlikely to exceed the annual dose limit 5mSv/a person can pass
Routine monitoring of working hours and workplace investigated radon, radon progeny and γ external irradiation to estimate, on the part of a representative of the staff can
Radon progeny and γ radiation personal dose monitoring.
When 7.3.1.6 When radiation workers within a year, equal to or higher than the dose from external exposure annual dose limit 5mSv/a, to identify the causes and to
Corresponding radiation protection evaluation.
7.3.1.7 When the radiation staff radiation injury diagnosis should be based on personal dose monitoring data as a basis.
Their personal archive should be transferred to the radiation dose management agencies when the new unit 7.3.1.8 radiation worker transferred. Personal file dose should
Saved to radiation workers from radiation work 30a.
7.3.2 Monitoring and evaluation of workplace
7.3.2.1 radiation in the workplace should be according to the provisions of GB 18871-2002 in 6.6.3 to carry out routine monitoring.
Monitoring Project 7.3.2.2 uranium workplace should include.
a) radon, radon progeny α potential concentration of dust concentration in the air and long-lived α aerosol concentration.
b) γ radiation levels.
c) effluent uranium, radium, thorium content, total α and total β.
d) ventilation system, "three wastes" processing systems and related facilities protective effect detection.
7.3.2.3 Periodic monitoring of various types of radiation workplace in Table 2.
Table 2, all kinds of radiation in the workplace monitoring cycle units/month
Monitoring Project machine digging trenches hand dug trenches broken between sample analysis chamber
Radium standard
Source Library
Ore Model
Studio
Remark
Radon, radon progeny concentration 2/1 1/1 1/6 1/6 1/12 2/1
2/1 1/1 2/1 2/1 dust concentration
γ external irradiation 2/1 1/1 1/1 1/12 2/1
Wastewater 1/1
Air concentrations of long-lived α aerosol 1/3 1/3 1/3
Wind speed, wind 1/1 1/1 1/6 1/6
7.3.3 Radiation Protection Evaluation of radiation in the workplace in accordance with GB 18871 standards.
7.3.4 Individual dose monitoring and radiation moni...
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