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GB 11930-2010: Radiation protection regulations for handling unsealed source
Status: Valid GB 11930: Evolution and historical versions
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| GB 11930-2010 | English | 229 |
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Radiation protection regulations for handling unsealed source
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GB 11930-2010
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| GB 11930-1989 | English | 359 |
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Regulation of radiation protection for handling nonsealed radioactive material
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GB 11930-1989
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PDF similar to GB 11930-2010
Basic data | Standard ID | GB 11930-2010 (GB11930-2010) | | Description (Translated English) | Radiation protection regulations for handling unsealed source | | Sector / Industry | National Standard | | Classification of Chinese Standard | F70 | | Classification of International Standard | 13.280 | | Word Count Estimation | 10,160 | | Date of Issue | 2010-11-10 | | Date of Implementation | 2011-09-01 | | Older Standard (superseded by this standard) | GB 11930-1989 | | Quoted Standard | GB 5294; GB 8999; GB 11217; GB 11806; GB 14500; GB 18871-2002; HJ/T 61-2201 | | Regulation (derived from) | Announcement of Newly Approved National Standards 2010 No. 8 (No. 163 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 applies to the production and application of radioisotopes to operate the real face of unsealed sources chamber activities, other operating activities of non- sealed sources may refer to the use. | GB 11930-2010: Radiation protection regulations for handling unsealed source---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.
Radiation protection regulations for handling unsealed source
ICS 13.280
F70
National Standards of People's Republic of China
Replacing GB 11930-1989
Operating unsealed sources of radiation protection
Issued on. 2010-11-10
2011-09-01 implementation
Administration of Quality Supervision, Inspection and Quarantine of People's Republic of China
Standardization Administration of China released
Foreword
4.1.1,5.1.1,7.1.1,9 this standard is mandatory, the rest are recommended.
This standard replaces GB 11930-1989 "Regulations for radiation protection operation of open radioactive material."
This standard compared with GB 11930-1989, the major changes are as follows.
--- Added "Terms and Definitions";
--- Original standard overall framework and specific technical contents have been revised;
--- Original 3.1 "general principle" to increase the dose limiting, optimization of radiation protection, defense in depth and related requirements;
--- Increased radiation in the workplace grading requirements, accident prevention and emergency response reg;
--- Remove the original standard "Safety Management" reg;
--- Remove the original Appendix B radiation protection standards body or person primary responsibility (reference);
--- Original standard table contents and format of the cycle has been revised A.1 workplace routine monitoring.
Appendix A of this standard is the data 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 Institute of Atomic Energy, Institute of Nuclear Industry Standardization.
The main drafters of this standard. Xuchang, Zhang Xin.
This standard replaces the standards previously issued as follows.
--- GB 11930-1989.
Operating unsealed sources of radiation protection
1 Scope
This standard specifies the operation unsealed sources of radiation protection principles and requirements.
This standard applies to the production of radioisotopes and applications operating unsealed sources of laboratory activities; unsealed sources other operating activities
Reference may be used.
2 Normative references
The following documents for the application of this document is essential. For dated references, only the dated version suitable for use herein
Member. For undated references, the latest edition (including any amendments) applies to this document.
GB 5294 occupational exposure individual monitoring for external exposure monitoring
GB 8999 ionizing radiation monitoring quality assurance GENERAL PROVISIONS
GB 11217 General provisions for monitoring effluents at nuclear facilities
GB 11806 Regulations for the Safe Transport of Radioactive Substances
GB 14500 radioactive waste management
GB 18871-2002 ionizing radiation protection and safety of radiation sources basic standards
HJ/T 61-2001 environmental radiation monitoring technical specifications
3 Terms and Definitions
The following terms and definitions apply to this standard.
3.1
Unsealed sources unsealedsource
Source does not meet the definition of sealed sources in the conditions listed. The definition of a sealed source is. sealed in a capsule or in tightly bonded to the cover layer in
And showed solid form radioactive material. Cladding or covering layer sealed source should have sufficient strength so that a source in the conditions of use and design of the mill
Damage under the conditions and in anticipated event conditions, can maintain the sealing performance, there will be no radioactive material leaked out.
3.2
Inclusive containment
Method of preventing or physical structure or boundaries shift to the outside through the diffusion of the radioactive material is determined, even in the general case of an accident, this
Class method or physical structure can prevent leakage of radioactive material reaches an unacceptable level.
3.3
Airtight barrier confinementbarrier
By the road or a system of physical barriers together with the corresponding auxiliary equipment (including ventilation equipment) constituted, the system can effectively limit
Or prevent the release of radioactive material to the outside world under normal and abnormal conditions.
3.4
Control area controledarea
In one area of radiation in the workplace division within this area require or may require to take special protective measures and safety measures,
so that.
a) under normal operating conditions to control or prevent the spread of contamination normal irradiation;
b) to prevent or limit the extent of potential exposure.
3.5
Supervised area supervisedarea
Not determined to be the control area, usually you do not need to take special protective measures and security measures, but we must continue to check the condition of any occupational exposure
HE area.
3.6
Simulation test mock-upexperiment
Before a test experiment to verify certain parameters, technical training operations carried out such purposes. It can also refer to radiation after the accident
In order to determine the conditions of similar experiments by accident Dose personnel carried out.
3.7
Cold test coldtesting
Non-radioactive substance (tracer can sometimes amount of radioactive material) instead of high-level radioactive material to certain methods, procedures, equipment or device
Preparation of the tests carried out.
3.8
Thermal Test hottesting
Under normal operating conditions, the expected level of radioactivity of certain methods, procedures, instruments and equipment tests carried out.
3.9
Tasks (Operation) Monitoring task (operational) monitoring
Aims to provide operational management for specific tasks (operations) immediate decision or optimization of radiation protection and the relevant information needed to carry out
An unconventional monitoring.
3.10
Special monitoring specialmonitoring
In an investigative suspicion or lack of enough information to tell whether the security situation in the workplace under control, had carried out
Measure, designed to provide detailed information to clarify certain issues and identify the next steps to be taken way.
4 General Principles
4.1 dose limit
4.1.1 normal irradiation of radiation workers engaged in non-sealed sources should be subject to operating restrictions, the operation to deal with the real unsealed sources
Public exposure practice activities arising from restrictions, determine dose limits, control the level of surface contamination and dose constraint value shall follow
GB 18871-2002 requirements.
4.1.2 should develop management limits, and other reference levels based on national standards, optimization of protection and safety principles. These values may include.
a) a practice of individual dose control target value;
b) radionuclides maximum operating capacity and storage capacity;
c) the radiation levels in the workplace each operating area or surface contamination level;
d) Radiation levels under normal circumstances, neighborhood, workplace air concentrations of radionuclides;
e) work under normal conditions inside the aerosol concentration and radiation levels;
f) of the effluent radioactivity concentration and the total activity;
g) determining the safety and protective equipment should be replaced or repaired relevant parameters.
4.2 ALARA
4.2.1 Operation after unsealed sources should enable optimization of protection and safety, so that the practice of taking into account the economic and social factors, individual subject
According to the size of the dose, the number of irradiated and the possibility of irradiated were maintained at a low level as far as reasonably achievable.
4.2.2 Optimization of protection and safety during the operation should be considered all relevant factors, qualitative and quantitative methods and analysis
Appropriate and feasible method.
4.2.3 determine optimized protection and safety measures should be fully taken into account for the use of protection and security options, and the nature of the irradiation dose
Size and possibilities.
4.2.4 performs optimization measures relevant criterion to take to prevent accidents and mitigate the consequences of accidents, thereby limiting the size of the irradiated and by
The possibility of exposure.
Measures 4.2.5 for all categories of personnel doses strict control should at least include.
a) the use of non-sealed sources, the selection of non-sealed sources Radionuclides as small as possible, toxicity as low as possible;
b) instead of the non-hermetic sealing operation is possible with the operation;
c) improve the operational proficiency of staff, shorten the operation time;
d) as far as possible to increase the operating distance;
e) to determine the optimal protection and safety measures.
4.3 Defense in Depth
4.3.1 To prevent possible radiation accidents, to mitigate the consequences of accidents, and the operation of non-sealed sources of practice, should be used to its potential exposure
The size and the possibility to adapt to multiple (ie, defense in depth) protection and safety measures.
4.3.2 take multiple layers of protection and safety measures include chains (device), inclusive, barrier closed, so as to ensure that when the previous level of defense
When the measures fail, to be filled or corrected by the next level of defense.
5 safe operation
5.1 General Requirements
5.1.1 to carry out radiation protection and management of occupational exposure control, unsealed sources in the workplace should be a strict partition, classification
Management, zoning, classification management measures, should follow the requirements of GB 18871-2002.
5.1.2 should be prominently hanging radiation in the workplace (post) radiation warning signs, traffic routes and transfer of radioactive material should
Strict implementation of the relevant provisions, to prevent cross-contamination. We should formulate strict radiation protection regulations and procedures.
Unit 5.1.3 Operation unsealed sources of radiation protection program should be developed and the overall responsibility for its implementation and evaluation. Unit shall establish appropriate
Safety and Protection Agency (or, part-time security and protection personnel), and the form of documents with clearly defined responsibilities.
5.1.4 should establish security and protection training system, to cultivate and maintain a good security staff cultural awareness, consciously abide by the rules and regulations, palm
Grip the basic principles of radiation protection, radiation protection and the protection of basic knowledge skills.
5.1.5 radiation workers certain procedures when necessary to advance simulation test, cold test, hot test, when the master operating skills
It can work only after the official launch.
5.1.6 If during operation found abnormal situation should be promptly report and analyze the causes and take measures to prevent recurrence of similar incidents.
5.1.7 should regularly check the effectiveness of the protection and workplace safety measures, to develop appropriate remedies against insecurity, and
Conscientiously implement to ensure that the workplace is in good running condition.
Radionuclide day equivalent maximum operating 5.1.8 for new work under existing facilities (including major changes in the process and improve
Quantity) is required if you plan to operate the type of radionuclide, the amount of operation, operation and protection facilities and equipment beyond the original design specifications,
Must be submitted to the protection and safety analysis report to the competent authorities, it can be carried out by the competent authorities after examination and approval.
5.1.9 there is a critical security issues such as conduct operations should also comply with the relevant national critical security requirements.
5.2 Operating Conditions
5.2.1 unsealed sources and characteristics of the operation should be based on the amount of radioactive material operated, the selection criteria in line with the requirements of safety and protection, do
It may be carried out in the fume hood, glove box or work.
5.2.2 Operation procedure used equipment, instruments, meters, instruments and transmission pipelines shall comply with the safety and protection requirements. Draw exercise fluid
Should be used as a suitable fluid suction equipment, prevent radioactive liquid spills, spill, pollution. Storage of radioactive solution container shall not
Breakable material.
5.2.3 There are potentially polluting steps should be covered with plastic or stainless steel and easy to remove contaminated work surface or enamel pan
get on.
5.2.4 container used in the operation, if necessary, in its outside plus a can large enough to hold all of its radioactive solution is not easy to rupture
Sets barrel.
5.2.5 Operation explosive substance, or operation in high temperature, high voltage and high pressure equipment, should be reliable to prevent overheating or overpressure
Protective measures, and comply with relevant national safety regulations.
5.2.6 accompanied by strong external exposure operation should be possible to shorten the operation time, the use of suitable masks or other protective use long-handled operate machinery
Measures.
5.2.7 If work is required to open the closed door into or remove items and other more dangerous operations, should be taken to safety and protection
Measures to protect personnel and under supervision.
5.2.8 of pollution equipment maintenance, should prepare a plan in advance. The main content of the work and the protective measures taken by the field of protection of people
Members agreed to review before proceeding and after the implementation of radiation protection measures.
5.3 Personal Protection
5.3.1 Staff should be familiar with radiation safety and protection skills, obtain the appropriate qualifications.
5.3.2 radiation workers should be equipped according to the actual need for the sufficient standard and personal protective equipment (equipment, clothing equipment), and master
Its performance and use. Personal protective equipment should be backed up, should be properly safeguarded and respond to test its performance on a regular basis.
5.3.3 radiation in the workplace should have the appropriate means of protection and safety measures, proper personal protection work.
5.3.4 with external exposure in the workplace, should make individual external radiation protection, including β external radiation protection.
5.3.5 Under no circumstances do not allow direct contact with bare hands radioactive substances or pollutants operation member.
5.3.6 radiation in the workplace should be provided with appropriate medical protective equipment and emergency medicine boxes unsealed sources according to the characteristics of the operations for processing things
Therefore, when using. Medical treatment of serious pollution incidents should be conducted under the guidance of medical personnel protection.
6 Radiation Protection Monitoring
6.1 General Requirements
6.1.1 Operation unsealed source unit should have the appropriate radiation protection monitoring capacity, with qualified personnel and related radiation protection provided
Prepare, develop appropriate radiation monitoring programs. Preparation of radiation monitoring plan should be implemented GB 8999, GB 11217, GB 5294, HJ/T 61-
Relevant provisions of the 2001's.
6.1.2 should be recorded and stored radiation monitoring data, create the file. Monitoring results should be recorded while recording the measurement conditions, measuring and test methods
The amount of the instrument, the measurement time and measurement name and so on.
6.1.3 should regularly evaluate the results of radiation monitoring, recommendations for improvement of radiation protection, and monitoring and evaluation of the results should be to
Examination and administration department report; if there is abnormal situation should be promptly reported.
6.1.4 For unconventional special operations in order to strengthen operation management, safety and optimization of protection, the task should be carried out (operation) phase
Off monitoring.
6.1.5 In the new facility operational phase, when the facility or program has been a major change, or there may be special exceptions should be monitored.
6.2 Personal Monitoring
6.2.1 Operation radiation workers unsealed sources of individual monitoring shall follow the requirements of GB 18871-2002, in addition to the necessary personal outside
Exposure monitoring, shall pay particular attention to the use of appropriate methods to do within personal exposure monitoring.
6.2.2 In the individual monitoring to be carried out in accordance with the monitoring plan for pollution monitoring skin, hand dose monitoring.
6.2.3 to participate in special operations or overhaul may cause internal contamination of the staff, before and after the operation shall be subject to internal exposure monitoring
Measurement. If necessary based on results of the analysis to estimate the committed effective dose.
6.2.4 Personal file dose should be kept, save time should be less than 30 years after the individual stops of Radiation.
6.3 workplace monitoring
6.3.1 unsealed sources should be based on the characteristics and mode of operation, good workplace monitoring, including dose rate levels, the concentration of radionuclides in the air
And surface contamination levels and so on.
6.3.2 The content and frequency of workplace monitoring in the workplace based on the possibility of changes in radiation levels and the size and potential exposures into
Line OK. Appendix A presents a reference workplace for routine monitoring of the content and cycles.
6.4 effluent monitoring
6.4.1 radioactive effluent discharge limits shall be the relevant provisions of GB 18871-2002 execution, should be subject to the approval of the regulatory authorities, to deal with
About radionuclide composition, concentration and total activity, etc. to monitor the implementation of controlled emissions.
6.4.2 B and C in the workplace generally gaseous effluent can be monitored by periodic sampling method of measurement; for Grade workplace,
Its gaseous effluent emissions may reach the allowable emission limit values or a significant share of emissions, the need for continuous online monitoring.
6.5 Environmental Monitoring
6.5.1 Operation unsealed source unit should be based on the type of effluent radionuclides, the nature and quantity of emissions and environmental conditions determine the form
Given environment monitoring programs, the scope and period, should ensure timely detection of changes in the level of radioactivity in the environment trends and anomalies.
6.5.2 estimate a higher radionuclide emission activity, environmental monitoring should be carried out immediately. Monitoring shall continue until the results of the investigation clearly when
until.
7 Radioactive Waste Management
7.1 General requirements
7.1.1 Management of radioactive waste should follow the GB 18871-2002, GB 14500 of the relevant provisions, to optimize the management.
7.1.2 source control should reduce the production of radioactive waste, to prevent the spread of contamination.
7.1.3 purchasing and storage of waste should be classified, as far as possible to take effective method of reducing the content or reuse, and strive to achieve waste minimization.
7.1.4 should be prepared to waste generation, handling and disposal (including emissions) records, filing saved.
7.2 radioactive liquid waste
7.2.1 Operation Unit unsealed sources, the general radioactive waste processing system should be established to ensure proper handling of the waste generated. Can not
The radioactive liquid waste discharged into the general sewer, associated control should follow the requirements of GB 18871-2002; do not allow the use of lower sewage water system
Washing system is contaminated with radioactive materials; waste emissions allowed by seepage wells.
7.2.2 waste should be properly collected in a closed container. Containing waste containers, in addition to the material to be easily adsorbed radioactive material outside,
It should also take appropriate measures to ensure that in the event of breakage of the container in which the waste collection and treatment still. In case when a strong external exposure, the waste collection site
External radiation should be protective measures.
7.2.3 After waste water treatment in emissions to the environment before, should be sent to the monitor groove by groove analyzed before discharge to meet the discharge standards.
7.2.4 Use a small amount of short-lived radionuclides or units may be established to take the decay of a radioactive liquid waste treatment and disposal methods system, the
System should be sufficient leakage resistance.
7.3 solid radioactive waste
7.3.1 generated solid radioactive waste shall establish more solid waste staging base to ensure the storage of waste retrievability.
7.3.2 Operation unsealed sources of waste per unit produced (including radioactive waste), should be required to send the designated waste repository scratch. Get receptacles
Waste receptacles should meet the delivery conditions.
7.3.3 is available for short-lived waste placed decay approach to be radioactive decay to clearance levels was made after the general waste disposal
Management, in order to minimize the amount of radioactive waste.
7.4 Radioactive emissions
7.4.1 workplace radioactive waste or aerosol emission system, should always check the validity of purification and filtration apparatus.
7.4.2 Where is expected to produce significant quantities of radioactive waste or aerosols which may contaminate the environment one-time operation, and shoul...
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