Basic Standards for Ionizing Radiation Protection and Radiation Source Safety

GB 18871-2002

The State Administration of Quality Supervision, Inspection and Quarantine of the People's Republic of China approved the implementation of 2003-04-01 from October to 08 2002.

Preface

All technical contents of this standard are mandatory.

This standard is d on the International Basic Safety Standards for Ionizing Radiation Protection and Radiation Source Safety approved and jointly issued by six international organizations (i.e. FAO, IAEA, ILO, OECD Nuclear Energy Agency, PAHO and WHO). IAEA Safety Series No. 115, 1996) revised the current basic standards of radiation protection in China. Its technical content is equivalent to those of the international organizations mentioned above.

When revising the current basic standards of radiation protection in China according to the standards of international organizations mentioned above, the experience of implementing the current basic standards of radiation protection in China in the past ten years and the current situation in China are fully taken into account, and the existing standards which have been proved to be suitable for China's national conditions and consistent with the standards of international organizations are retained. Technical content.

This standard will replace GB4792-1984 and GB8703-1988 from the date of publication.

Appendix A, Appendix B, Appendix C, Appendix D, Appendix E, Appendix F and Appendix J of this Standard are Appendix to the Standard.

Appendix G and H are the appendices to the proposal.

This Standard shall be formulated by the Ministry of Health of the People's Republic of China, the State Environmental Protection Administration and China Nuclear Power (in the order of department names and strokes).

Industrial Corporation jointly proposed.

The drafting unit of this standard is the joint drafting group, and the Secretary unit of the drafting group is the Institute of Standardization of Nuclear Industry.

The main drafter of this standard: Pan Ziqiang (following in the order of surname strokes)

Ye Changqing, Zhang Yansheng, Wu Deqiang, Zheng Junzheng, Jin Jiaqi, Xia Yihua and Yu Feng Guan.

1. Scope

This standard stipulates the basic requirements for the protection of ionizing radiation and the safety of radiation sources (hereinafter referred to as "protection and safety").

This standard is applicable to the protection of personnel exposed to ionizing radiation in practice and the safety of sources in practice.

This standard is not applicable to the protection of non-ionizing radiation, such as microwave, ultraviolet, visible and infrared radiation, which may cause harm to personnel.

2. Definition

The terms and definitions used in this Standard are listed in Appendix J (Appendix to the Standard).

3. General requirements

3.1 Applicability

3.1.1 Practice

The practice of applying this standard includes:

(a) Production of sources and applications of radiation or radioactive substances in medicine, industry, agriculture or teaching and scientific research, including activities related to applications involving or capable of involving radiation or radioactive substances.

B) Generation of nuclear energy, including activities in the nuclear fuel cycle involving or possibly involving radiation or radiation exposure of radioactive substances;

C) Practice involving natural source irradiation required to be controlled by the competent authorities.

D) Other practices prescribed by the competent authorities.

3.1.2 Sources

3.1.2.1 The sources of application of this standard to practice include:

(a) Radioactive substances and devices containing or producing radiation, including consumer goods containing radioactive substances, sealed sources, non-sealed sources and radiation generators;

B) Equipment, facilities and radiation-producing equipment, including radiation equipment, mining or llurgical facilities for radioactive ores, processing facilities for radioactive materials, nuclear facilities and radioactive waste management facilities;

C) Other sources prescribed by the competent authorities.

3.1.2.2 Requirements of this Standard shall be applied to each radiation source in a device or facility; necessary

The requirements of this standard shall be applied to the whole device or facility considered as a single source in accordance with the regulations of the competent authority.

3.1.3 irradiation

3.1.3.1 Exposure applicable to the requirements of practice in this standard is occupational exposure, medical exposure or public exposure, including normal exposure and potential exposure, caused by relevant practice or practice sources.

3.1.3.2 Natural source irradiation should normally be regarded as a kind of continuous irradiation, and the intervention requirements of this standard should be followed if necessary. However, if the following circumstances are not excluded or relevant practices or sources are not exempted, the requirements for practice of this Standard shall be followed:

(a) Public exposure resulting from the discharge of effluents from practices involving natural sources or the disposal of radioactive wastes;

B) Occupational exposure of staff caused by natural source irradiation under the following circumstances:

1) Radon exposure to staff members for work needs or directly related to their work, regardless of whether it is higher or lower than the level of action taken to remedy the persistent exposure to radon in the workplace (see Appendix H (Appendix to the hints))

2) Although workers are not exposed to radon regularly at work, they are exposed to higher levels of radon exposure than the level of action taken to remedy the continuous exposure of radon in the workplace (see Appendix H (Appendix to the hints)).

3) Natural source irradiation to the crew during the flight of jet aircraft;

C) Other natural source irradiation required by the competent authorities to comply with the requirements of this standard for practice.

3.1.4 Intervention

3.1.4.1 Interventions for the application of this standard are as follows:

(a) Emergency exposure requiring protective action, including:

1) Accidents and emergencies in which emergency plans or procedures have been implemented;

(2) Any other emergency exposure situation where the competent authorities or intervention organizations confirm that there are justified reasons for intervention;

B) Continuous exposure requiring remedial action, including:

1) Natural source irradiation, such as radon exposure in buildings and work s;

2) Exposure to radioactive residues caused by past events, as well as the system of unawareness and approval (see 4.2.1 and 4.2.1).

4.2.2) Controlling the exposure of radioactive residues caused by past practices and utilization of sources;

3) Any other continuous exposure that the competent authorities or intervention organizations confirm that there are justified reasons for intervention.

3.2 Exclusion

Any irradiation that cannot be substantially controlled by the implementation of the requirements of this Standard, such as 40K radiation in the human body and cosmic rays reaching the earth's surface, is not applicable to this Standard, i.e. should be excluded from the scope of application of this Standard.

3.3 Responsible Parties and Responsibilities for Implementation

3.3.1 Responsible Party

3.3.1.1 The party responsible for the implementation of this Standard (hereinafter referred to as "the main responsible party") shall be:

(a) Registrar or license holder;

B) Employment units.

3.3.1.2 Other parties concerned shall bear their respective responsibilities for the implementation of this Standard. Other parties concerned may include:

(a) The supplier;

B) Staff;

C) The person in charge of radiation protection;

D) Licensed physicians;

E) Medical technicians;

F) Qualified experts;

G) Any other party entrusted with specific responsibilities by the principal responsible party. 3.3.2 Liability

3.3.2.1 Each responsible party shall bear the general and specific responsibilities stipulated in the relevant chapters and articles of this Standard.

3.3.2.2 The general responsibilities of the principal responsible party are:

(a) Establish protection and safety ives that meet the relevant requirements of this Standard;

B) Formulate and implement a written protective safety steel, which shall be responsible for the nature of the dangers of practice and intervention, and

The degree is appropriate and sufficient to ensure compliance with the relevant requirements of this standard. In this large steel, it shall:

1) Identify the measures and resources needed to achieve the ives of protection and safety, and ensure the correct implementation and provision of these measures.

These resources;

2) Maintain a regular review of these measures and resources, and regularly verify whether the ives of protection and security have been achieved;

3) Identify any failures or deficiencies in protective and safety measures and resources, and take steps to correct and prevent their recurrence;

4) Keep relevant records of the performance of responsibilities.

3.4 Supervision and Management of Implementation

3.4.1 The competent authorities shall be responsible for the implementation of this standard and the supervision and management of its implementation, and the intervention organizations shall bear the primary responsibility for the implementation of the relevant requirements of this standard in the case of intervention.

3.4.2 The principal responsible party shall be subject to the supervision of the protection and safety of its authorized practice, including the inspection of its protection and safety records, by persons duly authorized by the competent authority.

3.4.3 In case of violation of the relevant requirements of this Standard, the principal responsible party shall:

(a) To investigate the violation and its causes and consequences;

B) Take appropriate actions to correct and prevent similar violations from recurring;

(c) To report to the competent authorities the reasons for the violation of the standards and corrective or protective actions taken or intended to be taken;

D) Take other necessary actions in accordance with the requirements of this Standard.

3.4.4 The principal responsible party shall promptly report any violation of this Standard. If a violation of the standard has evolved or is about to evolve into an emergency exposure situation, it should be reported immediately.

3.4.5 If the main responsible party fails to take corrective or improvement actions in accordance with the relevant national regulations within the prescribed time after the violation of the standards occurs, the competent authorities shall modify, suspend or revoke the previously issued registration certificates, licenses or other approval documents.

4 Major Requirements for Practice

4.1 Basic Principles

4.1.1 The introduction, implementation, interruption or discontinuation of any practice and the exploitation, llurgy, treatment, design, manufacture, construction, assembly, procurement, import, export, sale, sale, lending, leasing, acceptance, setting, positioning, debugging, holding, use, operation, repair, transfer and withdrawal of any source in practice. Service, disintegration, transportation, storage or disposal shall be carried out in accordance with the relevant requirements of this Standard unless the relevant practice or source of exposure is excluded or the relevant practice or source is exempted from the requirements of this Standard.

4.1.2 For any practice, source in practice or any activity specified in 4.1.1 applicable to this Standard, the implementation of the relevant requirements of this Standard shall be commensurate with the characteristics of the practice or source and the size and possibility of its exposure, and shall conform to the relevant requirements prescribed by the competent authorities.

4.1.3 Transportation of radioactive substances shall comply with the requirements of relevant national regulations and standards for safe transport of radioactive substances.

4.2 Management Requirements

4.2.1 Notification

4.2.1.1 Any legal person who intends to carry out a practice or any activity specified in 4.1.1 of this Standard shall submit a notice to the competent authorities explaining its purpose and plan; for consumer goods containing radioactive substances, only plans concerning manufacture, assembly, import and sale are required.

4.2.1.2 If the practice or activity satisfies the following conditions and is confirmed by the competent authority, only the notification procedure may be performed, otherwise the corresponding approval procedure shall be performed as required by 4.2.2:

(a) Normal exposure is unlikely to exceed a small share of the relevant limits set by the competent authorities;

(b) The possibility and magnitude of potential exposure can be neglected;

C) Any other possible harmful consequences may also be neglected;

4.2.2 Approval: Registration or Permission

4.2.2.1 Any legal person responsible for any sealed source, non-sealed source or radiation generator shall apply to the competent authority for approval unless the source responsible is exempted. Whether such approval is registered or licensed depends on the nature of the source or the practice of using the source and the size and possibility of the exposure. Practice suitable for approval by registration should have the following characteristics:

(a) Safety can be guaranteed to a large extent through the design of facilities and equipment;

B) Simple and easy to run;

C) Very low requirements for safety training;

D) There have been almost no safety problems in operation history;

4.2.2.2 The legal person responsible for any of the following sources shall submit an application to the competent authorities for approval, and the approval of such sources shall be in a licensing manner:

A) Irradiation devices;

B) Mining or llurgical facilities for radioactive ores;

C) Radioactive material processing facilities;

D) Nuclear facilities;

E) Radioactive waste management facilities

F) Any other source that is not exempt and has not yet been specified by the competent authority for approval by registration.

4.2.2.3 Any applicant shall:

(a) To submit to the competent authorities the relevant information required to support their applications;

B) In the submission of the application information, describe the nature, size and possibility of exposure from the source responsible for it.

Analysis and deion of various measures taken or planned to protect staff, the public and the environment.

(c) If the exposure may be greater than a certain level specified by the competent authority, the corresponding safety assessment and environmental impact assessment shall be carried out and submitted to the competent authority as part of its application;

D) No activities specified in this Standard 4.1.1 shall be carried out before the competent authorities issue registration certificates or permits.

4.2.2.4 Applicants for medical exposure practices and their sources shall also:

(a) Describe the qualifications of a licensed physician in radiation protection; or

B) Commitment that only practicing physicians with the professional qualifications for radiation protection specified in the relevant regulations or permits shall be qualified

An application form for examination or a preion for treatment using its source is allowed. 4.2.3 Permitted Legal Persons: Registrars and License Holders

4.2.3.1 Registrars and license holders shall be responsible for the formulation and implementation of the necessary technical and organizational measures to ensure the protection and safety of their authorized sources; they may entrust other parties with certain related activities or tasks, but they themselves shall still bear the primary responsibility for these activities and tasks. Registrars and license holders shall select qualified personnel as required to ensure compliance with this standard.

4.2.3.2 If registrants and license holders intend to modify their approved practices or sources and the proposed modifications may have important implications for protection or safety, they shall notify the competent authorities of their modification plans; such modifications shall not be made until they have been approved by the competent authorities.

4.2.4 Exemption

4.2.4.1 If the source meets one of the following conditions and is confirmed and agreed by the competent authorities, the practice of the source or the use of the source may be exempted from the requirements of this standard:

(a) Compliance with the exemption requirements specified in Appendix A (Appendix to the Standards);

B) The level of exemption determined by the competent authorities in accordance with the exemption criteria specified in Appendix A (Appendix to the Standard).

4.2.4.2 No exemption shall be granted for practices that have not yet proved to be justified.

4.2.5 Uncontrollment

4.2.5.1 Sources (including substances, materials and articles) in practice that have been notified or approved, if they meet the requirements of the competent authorities

If the prescribed level of cleanliness control is approved by the administrative department, it may no longer comply with the requirements of this standard, that is to say, it can be released.

4.2.5.2 Unless otherwise specified by the competent authority, the determination of the level of cleaner release shall take into account the exemption criteria specified in Appendix A (Appendix to the Standard) and the level of cleaner release shall not be higher than that specified in Appendix A (Appendix to the Standard) or the criteria specified by the competent authority in the Appendix. The level of exemption established.

4.3 Radiation Protection Requirements

4.3.1 Legitimacy of Practice

4.3.1.1 For a practice, it is justified only when social, economic and other relevant factors are taken into account and the benefits it brings to the affected individual or society are sufficient to compensate for the radiation hazards it may cause. Practices that are not legitimate and the sources of such practices should not be approved.

4.3.1.2 The judgment of the validity of the practice concerning medical irradiation shall follow the detailed requirements stipulated in Chapter 7.

4.3.1.3 In addition to being judged to be a legitimate practice involving medical irradiation, it is improper in the following practices to increase the radioactivity of commodities or products for daily use by adding or activating radioactive substances:

(a) Practice involving food, beverage, cosmetics or any other commodity or product for human consumption, inhalation, percutaneous skin intake or skin application;

B) Practice involving the meaningless application of radiation or radioactive substances in commodities or products for daily use (e.g. toys, etc.).

4.3.2 Dose Limitation and Potential Exposure Risk Limitation

4.3.2.1 Normal exposure to individuals shall be limited to ensure that, except for the special circumstances specified in 6.2.2 of this Standard, the total effective dose of individuals and the total equivalent dose of the organs or tissues concerned resulting from comprehensive exposure from various approved practices shall not exceed the corresponding dose limit specified in Appendix B (Appendix to the Standard). 。 Dose limits should not be applied to medical exposures in approved practice.

4.3.2.2 Potential exposure hazards to individuals should be limited so that all potential exposure hazards from approved practices are at the same order of magnitude as the health hazards corresponding to the normal dose limits.

4.3.3 Optimization of Protection and Safety

4.3.3.1 For irradiation from any particular source in a practice, protection and safety should be optimized so that, taking into account economic and social factors, the size of individual exposure dose, the number of irradiated persons and the possibility of exposure should be kept at the lowest level reasonably achievable; such optimization should be d on Personal dose and potential exposure risk caused by source are lower than dose and potential exposure risk constraints respectively (except therapeutic medical exposure).

4.3.3.2 The process of optimizing protection and safety can range from intuitive qualitative analysis to quantitative analysis using assistant decision-making techniques, but all relevant factors should be considered in an appropriate way to achieve the following ives:

(a) Identify the optimal protective and safety measures relative to the dominant situation, taking into account the available protective and safety options, as well as the nature, size and possibilities of exposure;

B) According to the results of optimization, corresponding criteria are formulated to take measures to prevent accidents and mitigate the consequences of accidents, thereby limiting the size of exposure and the possibility of exposure.

4.3.4 dose and potential exposure risk constraints

4.3.4.1 In addition to medical exposure, for any particular source in practice, the dose and potential exposure hazard constraints shall not be greater than those prescribed or approved by the regulatory authorities for such sources, nor greater than those that may lead to exceeding the dose and potential exposure hazard limits;

4.3.4.2 For any source that may release radioactive substances to the environment, dose constraints should also ensure that the cumulative effects of the release of the source over the years are limited so that any member of the public, including its descendants, will be subject to any year after taking into account all other relevant practices and the cumulative release and exposure that the source may cause. The effective dose reached did not exceed the corresponding dose limit.

4.3.5 Guidance Level of Medical Exposure

The level of medical exposure guidance for licensed physicians should be established. The level of such guidance should be:

(a) Formulated in accordance with the detailed requirements of Chapter 7 and with reference to Appendix G (Appendix to the Tips);

B) It is a reasonable dose indication for medium-sized subjects.

C) Provide guidance for current medical practices that are achievable in good medicine rather than in the best medicine;

D) Flexible application when reliable clinical judgement indicates need, i.e. allowing higher exposure;

E) To be revised with technological and technological improvements.

4.4 Operational Management Requirements

4.4.1 Safety Culture Literacy

We should cultivate and maintain a good safety culture, encourage people to take a thoughtful, exploratory and thoughtful attitude toward the protection and safety accidents, and oppose self-esteem, so as to ensure that:

(a) Develop guidelines and procedures that regard protection and safety as paramount;

(b) To identify and correct problems affecting protection and safety in a timely manner, and to adopt methods appropriate to the importance of the problem;

C) Clearly define the responsibility of each person concerned (including senior management) for protection and safety, and each person concerned is properly trained and qualified;

D) Define clearly the power-responsibility relationship for decision-making on protection and safety;

(e) Make organizational arrangements and establish effective communication channels to keep protection and safety information open within and between departments at all levels of registrants or license holders.

4.4.2 Quality Assurance

An outline of quality assurance should be formulated and implemented, which should:

(a) Provide adequate guarantees to meet specific requirements relating to protection and safety;

B) Provide quality control mechanisms and procedures for reviewing and evaluating the comprehensive effectiveness of protective and safety measures;

4.4.3 Human factors

Measures should be taken to ensure that the following requirements are met in order to minimize the possibility of accidents and incidents caused by human errors:

(a) All personnel concerned with protection and safety are properly trained and qualified to understand their responsibilities and to be able to correctly judge and perform their duties in accordance with prescribed procedures;

(b) Design equipment and develop operating procedures in accordance with effective ergonomic principles so as to make the operation or use of equipment as simple as possible, so as to minimize the possibility of accidents caused by operational errors and reduce the possibility of misunderstanding of indicative signals under normal and abnormal conditions;

C) Set up appropriate equipment, safety systems and control procedures and make other necessary provisions to:

1) To minimize the possibility of accidental exposure caused by human errors;

2) Providing means to discover and correct or remedy human errors;

3) It is convenient to intervene in the failure of safety system or other protective measures.

4.4.4 Qualified Experts

4.4.4.1 Registrars and license holders shall select qualified experts as required to provide advice for the implementation of this Standard.

4.4.4.2 Registrars and license holders shall inform the competent authorities of the arrangements for the selection of qualified experts. The information provided at the time of notification shall include the scope of practice or profession of the experts employed.

4.5 Technical Requirements

The technical requirements specified in this article apply to all practices and sources. The registrant or Licensee shall ensure that the protection and safety of its practices and sources conform to the relevant requirements of this Article. The application of these requirements and stringency should be commensurate with the practice of registrants or licensee holders and the magnitude and possibilities of exposure caused by sources. For nuclear facilities and radioactive waste management facilities, in addition to these basic technical requirements stipulated in this article, they should also meet the more specialized technical requirements and other requirements stipulated in the relevant national regulations and standards.

Physical Protection of 4.5.1 Sources

In accordance with the following requirements, the source shall always be protected from theft and damage, and any legal person shall be prevented from carrying out any activities specified in Standard 4.1.1 without approval.

(a) Ensure that the physical protection of the source meets all relevant requirements specified in the registration certificate or license, and that information about the source's loss of control, loss, theft or disappearance is immediately notified to the competent authorities;

B) Not transferring the source to recipients who do not hold valid approval documents;

C) Regular inventory of removable sources to confirm that they are in designated locations and have reliable security measures.

4.5.2 Deep Defense

Mult protective and safety measures (i.e. in-depth defense) should be applied to the source to ensure that when one level of defensive measures fails, they can be compensated or corrected by the next level of defensive measures to achieve:

(a) Preventing accidents that may cause exposure;

B) To mitigate the consequences of any such accident that may occur;

C) To restore the source to a safe state after any such accident.

4.5.3 Good Engineering Practice

In practice, source location, location, design, construction, installation, commissioning, operation, maintenance and retirement should be carried out.

d on effective engineering practice, such engineering practice should:

(a) Compliance with existing regulations, standards and relevant documents;

B) Reliable management and organizational measures are in place to ensure protection and safety during the whole life of the source.

Hold;

C) Keep sufficient safety margins in the design, construction and operation of the source to ensure reliable normal operation performance; reserve safety margins with a view to preventing accidents, mitigating the consequences of accidents and limiting exposure, taking into account the quality and multiplicity of inspectability;

D) Consider the development of technical standards, as well as relevant research findings and lessons learned in the field of protection and safety.

4.6 Safety Confirmation

4.6.1 Safety Assessment

Safety assessment of source protection and safety measures in practice should be carried out at different stages (including site selection, design, manufacture, construction, installation, commissioning, operation, maintenance and decommissioning):

(a) On the basis of the analysis of the influence of external events on the source and the events of the source and its affiliated equipment, various situations that may cause normal and potential exposure are identified;

B) Estimate the size of normal exposure and, to the extent feasible, the likelihood and magnitude of potential exposure;

C) Evaluate the quality and perfection of protective and safety measures.

4.6.2 Monitoring and Verification

4.6.2.1 shall determine the parameters required to verify compliance with the requirements of this Standard and monitor or measure these parameters.

4.6.2.2 Appropriate equipment and procedures shall be provided for the monitoring and verification required. Such equipment should be regularly maintained and inspected, and regularly calibrated with measurement standards traceable to national benchmarks.

4.6.3 Records

Records of monitoring and verification, including equipment inspection and calibration, should be kept.

5 Major Requirements for Intervention

5.1 Basic Principles

5.1.1 In case of intervention, in order to reduce or avoid exposure, such action should be taken as long as protective or remedial action is justified.

5.1.2 The form, scale and duration of any such protective or remedial action should be optimized to maximize the net benefits in general social and economic circumstances.

5.1.3 In the case of emergency exposure, protective action is generally not required unless it exceeds or may exceed the level of intervention or action aimed at protecting members of the public (see E2 of Appendix E (Appendix to Standards).

5.1.4 In the case of continuous exposure, remedial action is generally not required unless the level of action concerned is exceeded (see Appendix H (the appendix to the prompt).

5.1.5 For any specific intervention to which this Standard applies, the application of the relevant requirements of this Standard corresponds to the nature, severity and scope of the intervention.

5.2 Management Requirements

5.2.1 Emergency Exposure

5.2.1.1 Every registrant or license holder, if the source of his responsibility may require emergency intervention, shall formulate a corresponding emergency plan or procedure, which shall be approved by the competent authorities. The emergency plan shall stipulate the emergency responsibility of the registrant or license holder in the field and consider the source of his responsibility. Responsibility for off-site emergency response as appropriate; at the same time, the registrant or licensee holder should be prepared for the implementation of the various protective actions specified (see Chapter 10 of this Standard for detailed requirements).

5.2.1.2 Relevant intervention organizations shall formulate corresponding overall emergency plans (hereinafter referred to as off-site emergency plans) according to the severity of possible emergency interventions and the possible outfield scope involved, so as to coordinate emergency operations within and outside the field and implement the required off-site protection actions in order to support and supplement the basis. The Registrar or Permit Holder's Emergency Plan implements various protective actions. Off-site emergency plans should be implemented only by the appropriate intervention teams.

Intervention organizations should also make arrangements to deal with other unexpected situations that may require emergency intervention, such as illegal entry of sources, entry of radioactive substances released by satellite crashes into the country or from accidents outside the country.

5.2.2 Continuous irradiation

In case of continuous exposure exceeding or possibly exceeding the level of action concerned, the relevant intervention organization shall, as required, formulate a plan of action for the use or site-specific remediation, which shall be approved by the relevant departments. When taking remedial action, the legal person responsible for implementation shall ensure that it is carried out in accordance with the approved remedial action plan.

5.2.3 Protection of staff and the public

5.2.3.1 For occupational exposures to staff members due to intervention, the registrants, license holders, employers or relevant intervention organizations shall bear all the protective responsibilities stipulated in this Standard 10.5, as required by the competent authorities.

5.2.3.2 For public exposure in the case of intervention, the responsibility for public protection shall be borne by the relevant state and local intervention organizations, as well as the registrants or license holders of the practices or sources leading to the intervention, according to the organizational arrangements and functional division determined by the government according to the effective intervention.

5.2.4 Reporting Requirements

When emergency exposure occurs or is expected to require protective action, registrants and license holders shall immediately report to the relevant intervention organizations and regulatory authorities, and shall report to them at any time:

(a) Developments and projected trends of events;

B) Measures taken to protect staff and members of the public;

C) Exposure that has been and is expected to result.

5.3 Radiation Protection Requirements

5.3.1 Intervention is justified only when health protection and social and economic factors are considered comprehensively and the benefits of intervention are expected to outweigh the disadvantages. If the dose level approaches or is expected to approach the level given in Annex E (standard appendix) E1, it is almost always justified to take protective or remedial action under any circumstances.

5.3.2 In the intervention plan, the optimal intervention level and action level should be stipulated; the optimal intervention level and action level should be stipulated.

The determination of the level of action should be d on the criteria given in E2 and H of Appendix E (Standard Appendix) and take into account national conditions and specific local conditions, such as:

(a) Individual and collective doses that can be avoided through intervention;

B) The radiation and non-radiation health risks associated with the intervention itself, as well as the economic and social costs and benefits of the intervention.

5.3.3 In response to the accident, the following factors should be taken into account to justify the intervention and the intended intervention water.

The level of optimization should be reconsidered:

(a) Factors specific to actual conditions, such as the nature of releases, climatic conditions and other relevant non-radioactive factors;

B) The possibility of net benefits from protective action when future conditions are uncertain.

6 Occupational Exposure Control

6.1 Liability

6.1.1 Registrars, license holders and employers shall be responsible for the protection of workers from occupational exposure and shall comply with the relevant requirements of this Standard.

6.1.2 Registrars, license holders and employers shall undertake to all staff engaged in or likely to be involved in occupational exposure activities:

(a) Restrict occupational exposure in accordance with Appendix B of this Standard (Appendix to the Standard);

B) To optimize occupational protection and safety in accordance with the relevant requirements of this Standard;

C) Record decisions on occupational protection and safety measures and inform the parties concerned of such decisions;

(d) Establish protective and safety policies, procedures and organizational structures for the implementation of relevant requirements of this Standard; give priority to engineering design and technical measures for occupational exposure control;

(e) Provide adequate and adequate protective and safety facilities, equipment and services, whose type and perfection should be commensurate with the projected level of occupational exposure and possibilities;

F) Provide appropriate protective devices and monitoring equipment, and make arrangements for the correct use of these devices and equipment;

G) Providing necessary health care and services;

(h) Provide adequate and adequate human resources, make arrangements for protection and safety training, and arrange regular retraining as needed to update knowledge to ensure that staff meet the required level of competency;

I) Keep relevant records in accordance with the requirements of this Standard;

J) Consultation and cooperation with staff members or their representatives on how to effectively implement the standards and the protective and safety measures adopted;

K) Provide the necessary conditions for promoting safety culture literacy.

6.1.3 When recruiting new staff, registrants, license holders and employing units shall obtain their original occupational license records and other relevant information from their original employing units.

6.1.4 Registrars, license holders and employers require staff members to comply with this standard, and administrative measures should be taken when necessary to ensure that staff members understand that they have the obligation and responsibility to protect themselves from or be less exposed to radiation in stages and to maintain the safety of sources.

6.1.5 The duties and responsibilities of staff shall be:

(a) Compliance with relevant protection and safety regulations, rules and procedures;

B) Correct use of monitoring instruments and protective equipment and clothing;

(c) Collaborate with registrants, license holders and employers on protection safety (including health surveillance and dose assessment) to provide experience and information on protecting oneself and others;

D) Do not intentionally engage in any activities that may lead to violations of the requirements of this Standard by oneself and others;

(e) Learning about protection and safety, receiving necessary training and guidance on protection and safety so that they can work in accordance with the requirements of this standard.

6.1.6 If a staff member finds a violation or disadvantage in complying with this Standard, he shall report it to the registrant, license holder or employer as soon as possible.

6.2 Dose Control of Occupational Exposure

Dose Control of 6.2.1 Normal Irradiation

The dose control of normal irradiation should conform to the regulation of 4.3.2, and should follow the relevant requirements of the optimization of radiation protection in 4.3.3.

6.2.2 Dose Control under Special Conditions

6.2.2.1 If a practice is justified and designed and implemented according to good engineering practice, its radiation protection has been optimized in accordance with the requirements of this standard, and its occupational exposure is still beyond the dose limit of normal exposure, but it is expected that after reasonable efforts, the relevant occupational exposure dose will be kept at the normal dose. Under the limit, in this case, the competent authorities may exceptionally approve some temporary change in the dose limit requirements in accordance with Appendix B (Appendix to Standards) B1.1.2.

6.2.2.2 Temporary changes in dosage restriction requirements shall be explained in the application document by the Registrar or license holder in respect of special circumstances requiring such temporary changes, and evidence shall be provided to prove that:

(a) Every effort has been made to reduce exposure and to optimize protective and safety measures in accordance with the requirements of this standard;

B) Consultations have been held with relevant employers and staff, and consensus has been reached on the need and conditions for temporary changes in dose limits;

C) Every reasonable effort is being made to improve working conditions until the dose limits specified in Appendix B (Standard Appendix) B1.1.1 are met;

D) The monitoring and recording of personal licenses of staff members is sufficient to demonstrate compliance with the relevant requirements in Appendix B (Appendix to Standards) and to facilitate the transfer of licensed records between the employing units concerned;

6.2.2.4 Temporary changes in the requirements for dose limitation shall be as follows:

(a) In accordance with the dose limitation requirements specified in Appendix B (Appendix to Standards) for special cases;

B) Limit the duration of the change;

C) To be reviewed year by year;

D) No further extension;

E) Restricted to the prescribed workplace.

6.2.3 Control of Surface Radioactive Pollution

Control of surface radioactive contamination of workers'voxels, underwear, work clothes, and workplace equipment and ground shall comply with the restrictions specified in Appendix B (Appendix to Standards) B2.

6.3 Conditions for Work

6.3.1 Work Treatment

Special compensation, shorter working hours or preferential arrangements in terms of vacation, pension or special insurance shall not be substituted for protective and safety measures required to meet the requirements of this standard.

6.3.2 Working conditions of pregnant women

Female staff should inform the employing unit in time when they find themselves pregnant, so as to improve their working conditions when necessary. Pregnant women and lactating women should avoid exposure to internal radiation.

The employing unit shall not use pregnancy as a reason for refusing female staff members to continue their work. Employers are responsible for improving the working conditions of pregnant female staff to ensure that the same level of protection is provided for embryos and fetuses as for members of the public.

6.3.3 Working conditions of minors

Persons younger than 16 years of age are not allowed to receive occupational exposure. Persons younger than 18 years of age shall not work in the control area unless they are trained and supervised; their doses shall be controlled in accordance with B1.1.1.2 in Appendix B (Standard Appendix).

6.3.4 Job Transfer

When the examining and managing department or health guardianship institution determines that a staff member is no longer suitable for work involving occupational exposure due to health reasons, the employing unit shall replace the appropriate position for the staff member.

6.4 Zoning of Radiation Workplaces

Radiation workplace should be divided into control area and supervision area to facilitate radiation protection management and occupational exposure control. 6.4.1 Control Zone

6.4.1.1 Registrars and license holders shall designate areas requiring and possibly requiring special protective measures or safety measures as control zones in order to control normal exposure under normal working conditions or prevent the spread of pollution and prevent potential exposure or limit the scope of potential exposure.

6.4.1.2 When determining the boundary of the control zone, the expected normal exposure level, the possibility and magnitude of potential exposure, as well as the nature and scope of the necessary protective measures and safety measures should be taken into account.

6.4.1.3 For large control areas, if the level of radiation or pollution varies greatly in different parts and different special protective measures or safety measures need to be implemented, different sub-areas can be divided according to the need to facilitate management.

6.4.1.4 Registrars and license holders shall:

(a) Delimitation of control zones by entity boundaries; other appropriate means may also be used when the entity boundaries are unrealistic;

B) When the operation or opening of the source is only intermittent or when the source is moved from one place to another, the control area is delineated by a method appropriate to the dominant situation and the irradiation time is specified;

(c) To set up a striking warning sign at the import, export and other appropriate locations of the control zone, which meets the requirements of Appendix F (Standard Appendix), and to give the corresponding instructions on radiation and pollution levels;

(d) Establishing occupational protection and safety measures, including rules and procedures applicable to control areas;

(e) Restriction of access to the control area by administrative procedures (e.g. the work permit system for access to the control area) and physical barriers (including door locks and interlocking devices); the severity of the restriction should be commensurate with the projected exposure level and possibility;

F) Provide protective clothing, monitoring equipment and personal clothing storage cabinets at the entrance to the control area as required;

(g) Provide contamination monitors for skin and work clothes, contamination monitoring equipment for items carried out, washing or shower facilities and contaminated protective clothing storage cabinets at the exit of the control area as required;

H) Periodically review the actual situation of the area under control to determine whether it is necessary to change the means of protection or security measures in the area or the boundary of the area.

6.4.2 Supervisory Area

6.4.2.1 Registrars and license holders shall designate the following areas as supervisory areas: such areas are not designated as controlled areas, in which special protective measures or safety measures are usually not required, but often need to be monitored and evaluated under occupational exposure conditions.

6.4.2.2 Registrars and license holders shall:

(a) Use appropriate means to delineate the boundaries of the supervised areas;

(b) Establish a sign indicating the supervised area at an appropriate place at the entrance of the supervised area;

C) Conditions in the area are regularly reviewed to determine whether protective measures and safety regulations are required or whether changes in the boundaries of the supervisory area are required.

6.4.3 Grading of Unsealed Source Workplaces

Classification of non-sealed source workplaces shall be carried out in accordance with Appendix C (Appendix to Standards). Preparation and Application of 6.5 Personal Protective Equipment

6.5.1 Registrars, license holders and employers shall, according to actual needs, provide staff with appropriate, adequate and conforming personal protective equipment, such as various protective clothing, aprons, gloves, masks and respiratory protective equipment, and shall make them aware of the protective equipment they use. Performance and usage method.

6.5.2 Staff members should be instructed to use respiratory protective devices correctly and check whether they are suitable for wearing.

6.5.3 For tasks requiring the use of special protective devices, only those who are qualified and trained and authorized by the physician who serves as the health guardian can undertake them.

6.5.4 personal protective devices should be backed up properly for use in intervention events. All personal protective appliances should be properly kept and their performance should be regularly inspected.

6.5.5 For any given task, if protective appliances are needed, the increase in radiation exposure due to inconvenience or prolonged working hours caused by the use of protective appliances should be considered, and the possible non-radiation hazards associated with the use of protective appliances should be considered.

6.5.6 Registrars, license holders and employers should minimize their dependence on administrative and personal protective appliances during normal operation by using appropriate protective measures and safety measures, including good engineering control devices and satisfactory working conditions.

6.6 Monitoring and evaluation of occupational exposure

6.6.1 Registrars, license holders and employers shall formulate appropriate occupational exposure monitoring syllabus and conduct corresponding monitoring and evaluation in accordance with their responsible practices and specific conditions of sources and in accordance with the principle of optimizing radiation protection. The results of monitoring and evaluation should be reported regularly to the auditing and administrative departments; abnormal situations should be reported at any time.

6.6.2 Persons Monitoring and Evaluation

6.6.2.1 Registrars, license holders and employers shall be responsible for arranging the monitoring and evaluation of occupational exposure of staff. The evaluation of occupational exposure should be d on personal monitoring.

6.6.2.2 Personal monitoring shall be carried out for any staff working in the control area, or those who sometimes enter the control area and may be exposed to significant occupational exposure, or those whose occupational exposure dose may be greater than 5 msv/a. In the case of unrealistic or impracticable personal monitoring, the occupational exposure of staff can be evaluated d on the results of workplace monitoring and the information of the place and time of exposure after approval by the competent authorities.

6.6.2.3 Personal surveillance should be carried out as far as possible for staff working in the supervised area or only occasionally entering the control area if their occupational exposure dose is expected to be within the range of 1 mSv/a to 5 mSv/a. The occupational exposure of such personnel should be evaluated.

Price evaluation should be d on the results of individual monitoring or workplace monitoring.

6.6.2.4 Personal surveillance should be carried out for all persons exposed to occupational exposure, if possible. However, personal monitoring is generally not allowed for staff whose exposure dose is never greater than 1 mSv/a.

6.6.2.5 The type, period and uncertainty requirements of personal monitoring should be determined according to the level and variation of radiation level in the workplace and the possibility of potential exposure.

6.6.2.6 Registrars, license holders and employers shall arrange appropriate internal radiation monitoring for staff (including those using respiratory protective devices) who may be contaminated by radioactive substances in order to demonstrate the effectiveness of the protective measures implemented and, if necessary, provide the required photographs for the evaluation of internal radiation exposure. Input or pending equivalent dose data.

6.6.3 Workplace Monitoring and Evaluation

6.6.3.1 Registrars and license holders shall formulate, implement and periodically review the workplace monitoring syllabus with the cooperation of qualified experts and radiation protection officers (and, if necessary, employers).

6.6.3.2 The content and frequency of workplace monitoring shall be determined according to the level of radiation in the workplace, its variation and the possibility and magnitude of potential exposure, and shall ensure that:

(a) Ability to assess radiation status in all workplaces;

B) Radiation exposure to staff members can be evaluated;

C) Can be used to review the appropriateness of the division of control and supervision areas.

6.6.3.3 The Workplace Monitoring Outline shall provide that:

(a) Quantities to be measured;

B) Time, place and frequency of measurements;

C) The most appropriate measurement methods and procedures;

D) Actions to be taken when the reference level and the reference level exceed the reference level.

6.6.3.4 Quality Assurance of Monitoring

Quality assurance should run through the whole process from the formulation of monitoring outline to the evaluation of monitoring results. The monitoring outline must include

Quality assurance requirements to ensure that: measurement equipment has the required measurement characteristics (such as accuracy, stability, range and resolution) and can be properly maintained, measurement and analysis procedures can be correctly established and implemented, monitoring results can be correctly recorded, evaluated and properly maintained.

6.7 Occupational Exposure Management of Registrars, License Holders and Employers

6.7.1 Registrars, license holders and employing units shall formulate and implement written rules and procedures for the control and management of occupational exposure in their respective units to ensure that the level of protection and safety of staff and other personnel meets the requirements of this Standard.

6.7.2 The rules and procedures to be formulated shall include specific numerical values relating to the level of investigation and management, as well as procedures to be implemented when these values are exceeded.

6.7.3 Training on protection and safety and cultivation of safety culture should be strengthened so as to enhance the awareness of staff and related personnel in understanding and implementing the rules, procedures and provisions on protection and safety. All training records should be properly archived and kept.

6.7.4 A supervisory system should be established and a person in charge of radiation protection appointed in accordance with the requirements of the competent authorities. All work involving occupational exposure should be fully supervised and reasonable steps should be taken to ensure compliance with various rules, procedures, protection and safety regulations.

6.7.5 All staff members shall be provided with:

(a) Occupational exposure (including normal and potential exposure) and possible health effects;

B) Appropriate training and guidance on protection and safety;

C) Information on the significance of their actions to protection and safety.

6.7.6 The following information should be provided to female staff who may enter the control or supervisory areas;

(a) Pregnant women are at risk of exposure to radiation for embryos and fetuses;

B) The importance of informing registrants, license holders and employers as soon as possible after pregnancy;

C) The risk of infants breastfeeding on radioactive substances.

6.7.7 Relevant information, guidance and training should be provided to staff who may be affected by the contingency plan.

6.8 Occupational Health Care

6.8.1 Registrars, license holders and employers shall arrange corresponding health supervision in accordance with relevant regulations.

Protect.

6.8.2 Health surveillance should be d on the general principles of occupational medicine. Its purpose is to evaluate the competence and continuity of staff for their expected work.

6.9 Records of Occupational Exposure

6.9.1 Registrars, license holders and employers must keep occupational exposure records for each staff member.

6.9.2 Occupational exposure records shall include:

(a) General information on work involving occupational exposure;

B) Dose and intake at or above the recorded level, and data on which dose evaluation is d;

(c) For staff who have been transferred to work units, information on their working hours and the doses and intakes they receive in each unit;

(d) Records of doses and intakes received as a result of emergency intervention or accidents; such records shall be accompanied by relevant investigation reports and shall be distinguished from those received during normal working hours.

6.9.3 Registrars, license holders and employers shall:

(a) To submit monitoring records and evaluation reports of occupational exposure in accordance with the relevant provisions of the national regulatory authorities;

(b) To allow staff members and health care supervisors access to radiation records and related information;

(c) When a staff member changes his or her work unit, a copy of the staff member's exposure record shall be provided to the new employing unit;

D) When a staff member ceases to work, the registrant, license holder and employer shall make arrangements for the preservation of the staff member's occupational exposure records in accordance with the requirements of the competent authority or the designated authority of the competent authority;

(e) When registrants, license holders and employers stop activities involving occupational exposure, arrangements shall be made for the preservation of staff records in accordance with the regulations of the competent authorities.

6.9.4 Occupational exposure records should be kept for staff members before they reach the age of 75. After the workers stop radiation work, their radiation records should be kept for at least 30 years.

7 Medical Exposure Control

7.1 Responsibility

7.1.1 The license holder shall be responsible for ensuring the protection and safety of the patient and the patient under examination. Relevant practitioners and medical technicians, responsible persons for radiation protection, qualified experts and suppliers of medical irradiation equipment should also bear corresponding responsibilities for ensuring the protection and safety of patients and patients.

7.1.2 License holders shall ensure that:

(a) Only a licensed physician with appropriate qualifications can issue an application form for examination or a preion for treatment of medical exposure;

B) Diagnostic and therapeutic medical licences can only be granted to patients and patients according to the examination application form or treatment preion for medical irradiation.

Shoot;

(c) When issuing medical radiation checklist or treatment preion, and during the implementation of medical radiation, the licensed physician assumes the main responsibility and obligation to ensure the protection and safety of the patients and patients;

(d) Medical and technical personnel provided to meet the needs and have received appropriate training to undertake assigned tasks in the implementation of the diagnostic or therapeutic procedures prescribed by medical radiation checklists or treatment preions;

E) Develop and implement training guidelines approved by the competent authorities.

7.1.3 When applying ionizing radiation to treatment or diagnosis, the license holder shall listen to the opinions of qualified experts in radiotherapy physics, nuclear medicine physics or radiodiagnostic physics, and shall implement corresponding quality assurance requirements.

7.1.4 Licensed physicians and relevant medical technicians should report the problems and needs of the protection and safety of the patients and patients to the licensee holders in time, and take appropriate measures as far as possible to ensure the protection and safety of the patients and patients.

7.2 Justification of Medical Exposure

7.2.1 General Principles of Justice Judgment

After considering the benefits and risks of alternative methods available that do not involve medical irradiation, the medical irradiation is justified only when the benefits of medical irradiation to the irradiated individual or society are proved to be greater than the possible radiation hazards by weighing the advantages and disadvantages.

For complex diagnosis and treatment, attention should be paid to the case-by-case judgment of legitimacy. We should also pay attention to re-judging the legitimacy of medical irradiation which was considered legitimate in the past according to the development of medical technology and level.

7.2.2 Justification of Diagnostic Examination

In judging the validity of radiological or nuclear medical examination, we should take good indications, use diagnostic medical irradiation correctly and reasonably, and avoid unnecessary repeated examinations. We should judge the validity of radiological or nuclear medical examination for women and children more carefully.

7.2.3 Justification of Group Examination

In judging the legitimacy of group examinations involving medical exposures, consideration should be given to possible diseases identified through censuses, the possibility of effective treatment of identified diseases and the benefits to the public as a result of the control of certain diseases, which are sufficient to compensate for the economic and social costs (including This kind of inspection is justified when it comes to radiation hazards. Screening screening for X-ray diagnosis should also avoid the use of fluoroscopy.

7.2.4 Control of radiological examinations unrelated to clinical indications

In judging the justification of radiological examination for occupational, legal or health insurance purposes, consideration should be given to the availability of useful information on the health status under examination and the need to obtain such information, and consultation should be conducted with relevant professional bodies.

7.2.5 Exposure to Volunteers in Medical Research

Exposure to volunteers in medical research should be carefully examined in accordance with relevant national regulations (including ethical review involving human biomedical research); the potential risk of receiving such exposure should be controlled at an acceptable level and informed to volunteers; this can only be done by persons with appropriate qualifications and well-trained personnel. Seed irradiation.

7.3 Optimizing the Protection of Medical Exposure

The protection optimization of medical irradiation should not only meet the relevant requirements of other chapters of this standard, but also meet the following requirements.

7.3.1 Equipment Requirements

7.3.1.1 The radiation sources used for medical irradiation shall meet the relevant requirements for the safety of radiation sources specified in other chapters of this Standard; in particular, the system used for medical irradiation shall be designed to detect the faults of individual components in the system in a timely manner so as to minimize any unplanned medical irradiation to patients and facilitate its exhaustion.  It is possible to avoid reducing human errors.

7.3.1.2 In cooperation with the equipment supplier, the Licensee shall guarantee that:

(a) The equipment used, whether imported or domestic, conforms to the relevant national standards and regulations;

B) Provide equipment performance specifications and operation and maintenance instructions, especially protection and safety instructions;

C) Display operation terms (or their abbreviations) and operation values on the operating disk when practicable;

D) Setting up radiation beam control devices, such devices shall include components that can clearly and in a fault-safe manner indicate that the radiation beam is in an "on" or "off" state;

(e) The equipment is equipped with a beam alignment device so that the irradiation can be limited to the site under examination or treatment as far as possible;

(f) In the absence of any radiation beam adjusting device, the radiation field at the diagnosis and treatment site should be as uniform as possible, and the non-uniformity of the radiation field should be explained by the equipment supplier;

G) Keep the irradiation rate generated by radiation leakage or scattering at non-diagnostic and non-diagnostic sites as low as reasonably achievable

Ping.

7.3.1.3 For radiodiagnostic equipment, the licensee, in cooperation with the equipment supplier, shall ensure that:

(a) The design and manufacture of radiation generators and their accessories facilitate the maintenance of medical exposures at a reasonably low level to which sufficient diagnostic information can be obtained;

B) For radiation generators, various operating parameters can be clearly and accurately indicated, such as tube voltage, filter characteristics, focal position, distance between source and image receiver, size of irradiation field, tube current and time or product of both.

(c) Radiographic equipment is equipped with a radiation stopping device, which can automatically stop the radiation after reaching the preset time, the product of tube current and time or dose;

D) Fluorescence fluoroscopy equipment is equipped with a control switch for X-ray tube operation. Only when the switch is pressed continuously can the X-ray tube work. It is equipped with an exposure time indicator and/or an incident body surface dose monitor.

7.3.1.4 For radiotherapy equipment, the licensee, in cooperation with the equipment supplier, shall ensure that:

(a) Radiation generators and irradiation devices are equipped with devices for reliable selection, indication and (if necessary and feasible) verification of operational parameters such as radiation type, energy index, beam adjustment factor, treatment distance, field size, beam direction, treatment time or preset dose;

B) The irradiation device using the radiation source is fail-safe, i.e. once the power supply is interrupted, the radiation source will be automatically shielded and maintained until the beam control mechanism is restarted by the console;

(c) For high-energy radiotherapy equipment, there are at least two separate fail-safe protection systems for terminating irradiation, equipped with safety interlocking devices or other hand shields to prevent the equipment from being used clinically under conditions different from those selected on the console;

D) When performing maintenance procedures, if the interlocking is bypassed, the design of the safety interlocking device ensures that the irradiation device can operate only when the maintenance personnel use appropriate devices, codes or keys for direct control;

E) Radiation sources for both long-range and short-range treatment conform to Appendix J (Standard Appendix)

Requirements for sealed sources given in J2.8;

F) Installation or provision of monitoring equipment capable of providing alarm signals for abnormal situations occurring in the use of radiotherapy equipment when necessary.

7.3.2 Operational Requirements

7.3.2.1 License holders shall:

(a) Identification of equipment failures and human errors that may cause unplanned medical exposures on the basis of analysis of the information provided by the supplier;

B) Take all reasonable measures to prevent failures and failures, including the selection of qualified personnel, the establishment of appropriate quality assurance and operation procedures, and adequate training and regular retraining of relevant personnel on the implementation, protection and safety of procedures;

C) Take all reasonable measures to minimize the consequences of possible failures and failures;

D) Develop contingency plans or procedures for dealing with various possible incidents and conduct emergency training when necessary.

7.3.2.2 For radiological diagnosis, the Licensee shall ensure that:

(a) The equipment used by practitioners and relevant medical technicians who issue or implement applications for radiological diagnosis is appropriate to ensure that the patient receives the minimum exposure required to achieve the desired diagnostic ives, taking into account the acceptable image quality standards established by the relevant professional bodies and the relevant medical exposure guidance levels; Attention should be paid to consulting the previous inspection data to avoid unnecessary additional inspection.

B) Practitioners and relevant medical technicians should carefully select and synthesize the following parameters in order to ensure that the irradiation received by the examinee is the lowest irradiation consistent with acceptable image quality and the purpose of clinical examination. Particular attention should be paid to the selection and treatment of the following parameters for child examinees and interventional radiology:

1) Examination site, number of photographs (or number of tomographic sections) and scope of each examination or time of each fluoroscopy;

2) Type of image receiver;

3) The use of anti-scattering filter grids;

4) Strict alignment at the end of primary X-ray;

5) tube voltage, tube current and time or their product;

6) Image storage method;

7) Appropriate image processing factors.

(c) Portable and mobile radiological examination equipment can only be used if it is unrealistic or medically unacceptable to transfer a patient to a fixed radiological examination equipment and strict radiation protection measures have been taken.

D) Avoid radiological examinations of pregnant or potential pregnant women that may cause radiation to their abdomen or pelvis, except for clinically justified examinations;

(e) Carefully arrange any diagnostic examination of the abdomen or pelvis of fertile women so as to minimize the dose to which a potential embryo or fetus is exposed;

F) Provide appropriate shielding for radiation-sensitive organs (e.g. gonads, ocular lenses, breasts and thyroid) as far as possible.

7.3.2.3 For nuclear medicine, the Licensee shall guarantee:

(a) The radiation exposure to a patient by a licensed physician or a medical technician who has issued or implemented an application form for radionuclide imaging examination is the minimum required to achieve the desired diagnostic purpose after taking into account the relevant medical exposure guidance level, and attention should be paid to consulting the previous examination data to avoid unnecessary additional examinations;

B) Licensed physicians and relevant medical technicians should properly select the available radiopharmaceuticals and their dosage according to the characteristics of different patients, use the method of blocking the absorption of non-examination organs (if necessary, to promote drainage), and pay attention to the appropriate image acquisition and processing technology so that the irradiation of the examinee is for the purpose of obtaining. The minimum irradiation required to achieve the desired image quality;

C) Avoid using radioactivity in pregnant or potential pregnant women for diagnosis or treatment, except for obvious clinical indications

Nuclides;

D) After taking radiopharmaceuticals, lactating women are advised to stop breastfeeding as appropriate until the amount of radiopharmaceuticals secreted in their bodies ceases to bring unacceptable doses to infants;

(e) Radionuclide imaging can be performed on children only when there are obvious clinical indications, and dosage of radiopharmaceuticals should be reduced according to the weight, body surface area or other applicable criteria of the children under examination, and long half-life radionuclides should be avoided as far as possible.

7.3.2.4 For radiotherapy, the Licensee shall ensure that:

(a) While applying the required dose to the target volume of planned irradiation, the irradiation to normal tissues during radiotherapy should be controlled at a reasonably low level, and organ shielding measures should be adopted when feasible and appropriate;

B) Avoid radiation to the abdomen or pelvis of pregnant or potential pregnant women, except for obvious clinical indications.

Treatment;

C) Notify patients of the risks that may arise from radiotherapy.

7.3.3 Quality Assurance of Medical Exposure

7.3.3.1 License holders shall formulate a comprehensive quality assurance program for medical exposures in accordance with the quality assurance requirements specified in this standard and other relevant standards for quality assurance of medical exposures; qualified experts in relevant fields such as radiophysics and radiopharmaceuticals shall be invited to participate in the formulation of such an outline.

7.3.3.2 The Outline of Quality Assurance for Medical Exposure shall include:

(a) Measurement of physical parameters of radiation generators, display devices and irradiation devices (including measurements during commissioning and periodic measurements after commissioning);

(b) Validation of the physical and clinical factors used in the diagnosis and treatment of patients;

C) Written records of relevant procedures and results;

D) Calibration of dosimetry and monitoring instruments and verification of working conditions;

E) Periodic and independent quality audits and reviews of the quality assurance syllabus for radiotherapy.

7.3.3.3 License holders should pay attention to the calibration of radioactivity and radioactivity measurements to ensure that:

(a) Calibration of radiation sources for medical irradiation can be traced back to dose standard laboratories;

B) Calibration of radiotherapy equipment according to the radiation quality or energy and the absorbed dose or absorbed dose rate at a predetermined distance under specified conditions;

C) Calibration of sealed sources for brachytherapy according to the activity of a specific reference date, the specific kinetic energy release rate of reference air or the absorbed dose rate at specified distances in a prescribed medium;

D) Calibration of the non-sealed sources used in nuclear medicine according to the activity of the radiopharmaceuticals to be taken and the activity measured and recorded at the time of taking the drugs;

E) The calibration shall be carried out during the commissioning of the equipment after any maintenance that may affect the dosimetry and at the end of the time interval approved by the competent authority.

7.3.3.4 License holders shall ensure that the following clinical dosimetry is documented:

(a) In radiological examination, the representative values of the incident body surface dose, the area of dose and area, the dose rate, the irradiation time or organ dose of typical adult subjects;

B) For patients treated with external beam radiotherapy equipment, the maximum and minimum absorbed dose of the target volume is planned, as well as the absorbed dose of the relevant parts (e.g. the target volume center or other parts selected by the prescribing practitioner);

(c) The absorbed dose at the selected site of each patient in close treatment using sealed sources;

D) Typical absorbed dose of the patient or patient in the diagnosis or treatment using an unsealed source;

E) The absorbed dose of the organs involved in various radiotherapy.

7.4 Guidance Level and Dose Constraint of Medical Exposure

7.4.1 Guidance Level of Medical Exposure

7.4.1.1 For commonly used diagnostic medical irradiation, it should be deduced through extensive quality survey data, and in accordance with the provisions of this standard (see 4.3.5), the corresponding professional institutions and regulatory departments should formulate the guidance level of medical irradiation, and constantly revise it according to the progress of technology for the reference of the relevant practicing physicians. Use South for:

(a) When the dose or activity of a test exceeds the corresponding guidance level, take action to improve the optimization level so as to minimize the exposure dose of the patient while ensuring the necessary diagnostic information;

B) When the dose or activity is significantly lower than the corresponding guidance level and the irradiation fails to provide useful diagnostic information and bring expected medical benefits to the patient, corrective action should be taken as needed.

7.4.1.2 Considering the stipulations of b) and C in 4.3.5 of this standard, the determined level of medical exposure guidance should not be regarded as a guide to ensure the best performance under any circumstances; specific conditions should be taken into account when applying these levels in practice, such as the level of medical technology, the body and age of the examinee, etc.

7.4.2 Guidance Level of Medical Radiation for Radiological Diagnosis

For typical adult subjects, the dose or dose rate guidance levels for various commonly used X-ray photography, X-ray CT examination, mammography and X-ray fluoroscopy are shown in Appendix G (Appendix to the Tips) G1.

7.4.3 Guidance Level of Medical Exposure for Nuclear Medical Diagnosis

For typical adult patients, the activity guidance levels for various commonly used nuclear medical diagnoses are shown in Appendix G (Appendix to the Tips).

G 2.

7.4.4 Other relevant dose constraints

7.4.4.1 Medical exposures to volunteers in medical research do not bring direct benefits to the individuals exposed. The competent authorities or their authorized agencies shall prescribe appropriate dose restrictions for optimizing the protection of such personnel.

7.4.4.2 License holders shall control the dose of radiation to persons who voluntarily assist in nursing, supporting and consoling, or visiting patients undergoing medical irradiation, knowing that they are exposed to radiation. The individual dose to such personnel shall be limited to the values specified in Appendix B (Standard Appendix) B1.2.2.

7.4.4.3 Patients receiving radionuclide therapy should be discharged after their activity of radioactive substances has dropped to a certain level in order to control the possible exposure of their families and members of the public. Patients treated with iodine 131 should not be discharged until their radioactivity in vivo drops below 400 MBq. If necessary, the patient should be provided with written guidance on radiation protection measures in contact with other persons.

7.5 Prevention and Investigation of Accidental Medical Exposure

7.5.1 License holders shall take all reasonable measures, including continuously improving the safety culture of all relevant personnel, to prevent potential accidental medical exposures.

7.5.2 License holders shall promptly investigate the following incidents:

(a) Various treatment events, such as those that mistake patients or tissues, misuse drugs, or dosage or fractional dosage, are seriously inconsistent with preion values and may lead to excessive acute secondary effects;

B) Diagnostic irradiation events, such as diagnostic irradiation in which the dose is significantly greater than the predicted value, or diagnostic irradiation in which the dose is repeated and significantly higher than the prescribed level of guidance;

C) Equipment failures, accidents or other abnormal incidents that may cause significant differences in the patient's radiation dose from the expected value.

7.5.3 For each investigation required by 7.5.2, the license holder shall: calculate or estimate the doses and their distribution in the body of the patient and the patient under examination; propose corrective measures to prevent the recurrence of such incidents; implement all corrective measures within its scope of responsibility; and submit them to the Audit and Management Department as soon as possible as required. Door submits a written report to explain the cause of the incident and the situation of taking corrective measures; inform the patients, patients and related personnel of the incident and its investigation and correction.

7.5.4 The license holder shall keep the following records within the time limit prescribed by the competent authority and, if necessary, provide them:

(a) In radiological diagnosis, the information necessary for retrospective dose evaluation, including the number and duration of fluoroscopy in special examinations;

B) In nuclear medicine, the type and activity of radiopharmaceuticals used;

(c) For radiotherapy, the deion of the planned target volume, the dose at the center of the target volume and the maximum and minimum dose to the target volume, the dose to other related organs, the fractional dose and the total treatment time;

D) The results of calibration and periodic checking of selected physical and clinical parameters for radiotherapy;

E) The dose of radiation to volunteers in medical research.

8 Control of public exposure

8.1 Responsibility

8.1.1 Registrars and license holders shall exercise control over public exposure to sources or practices for which they are responsible, as required by this Standard, unless such exposure is excluded or practices or sources causing such exposure are exempted. For non-excluded or Non-exempted natural sources, registrants and license holders shall implement the relevant requirements of this standard in accordance with the regulations of the competent authorities, except that radon-induced exposure is lower than the level of sustained exposure action established by the competent authorities (see 3.1.3.2).

8.1.2 The source, registrant and license holder responsible for:

(a) To formulate and implement principles and procedures for protection and safety related to public exposure control, and to establish appropriate organizational structures;

B) To formulate, adopt and adhere to appropriate measures to ensure that:

1) The protection of public members exposed to the source of their responsibility is the most optimal;

2) The normal exposure of key population groups exposed to source radiation is limited, so that the total exposure dose of individual members of the group (see 4.3.2) does not exceed the dose limit of public members specified in Appendix B (Standard Appendix).

(c) Develop, adopt and maintain all necessary measures to ensure the safety of sources so that the control of potential exposure related to the public meets the requirements of this standard;

(d) Provide appropriate and adequate facilities, equipment and services for public protection whose performance and scope should be commensurate with the possibility and magnitude of exposure;

E) Training and regular retraining of relevant staff members on protection and safety and environmental protection to ensure that they are always protected

Maintain the required level of competency;

(f) To formulate and implement a public exposure monitoring syllabus in accordance with the requirements of the regulatory authorities, and to provide corresponding monitoring equipment for the evaluation of public exposure;

G) To keep detailed records of supervision and monitoring in accordance with the requirements of this Standard;

H) To formulate contingency plans or procedures appropriate to the nature and size of the hazards involved and to prepare for them in accordance with the relevant requirements of Chapters 5 and 10 of these Standards.

8.1.3 Registrars and license holders shall be responsible for ensuring that the optimization of emission control measures for radioactive substances adopted follows dose constraints formulated or approved by the regulatory authorities, taking into account the following relevant factors:

(a) Dose contribution from other sources or practices, including those that have actually been evaluated for possible future occurrences;

B) Possible changes in any condition of public exposure, such as changes in source characteristics and operating conditions, exposure routes, habits or distribution of residents, changes in key population groups, or changes in environmental dispersion conditions, etc.

C) Operational experience and lessons learned from similar sources or practices;

D) Various uncertainties in radiation assessment, especially when the key population groups and sources are far apart in space or time.

8.2 External Exposure Source Control

If the competent authorities confirm that an external source of exposure may cause public exposure, the registrant or license holder of such a source shall ensure that:

(a) Before commissioning, all the layout and equipment layout information of new facilities utilizing such external sources and all major modifications of existing facilities have been reviewed and approved by the regulatory authorities, and shall not be debugged or modified without review and written approval;

B) Establish specific dose constraints for the operation of such sources and submit them to the auditing authorities for approval;

C) Provide optimum shielding and other protective measures in accordance with the relevant requirements of this Standard.

8.3 Radioactive pollution control registration and permit holders in non-open places shall ensure that:

(a) In accordance with the requirements of this Standard, to take measures to optimize the sources responsible for pollution according to the circumstances, so as to limit public exposure in areas accessible to the public;

B) Establish specific inclusion measures for the construction and operation of sources to prevent pollution from spreading to areas accessible to the public

Scattered.

8.4 Visitors'control registrants and license holders shall:

(a) Ensure that visitors to the controlled area are accompanied by staff who are aware of the protection and safety measures in the area;

B) Provide adequate information and guidance to visitors before they enter the control area to ensure their protection and that of other persons who may be affected by their actions;

(c) Setting up visible signs in the supervisory area and taking other necessary measures to ensure proper control of visitors'entry into the supervisory area.

8.5 Radioactive Waste Management

8.5.1 Registrars and license holders shall ensure that the activity and volume of radioactive wastes generated by the practices and sources under realistic and feasible conditions are kept to a minimum.

8.5.2 Registrars and license holders shall, in accordance with the requirements of this Standard and other relevant regulations and standards of the State, administer the radioactive wastes generated by their responsible practices and sources in a good manner, collect, treat, prepare, transport, store and dispose of radioactive wastes in a classified manner, so as to ensure that:

(a) Reducing acceptable water for possible hazards of radioactive waste to the health and environment of workers and the public

Ping;

B) Make the projected impact of radioactive waste on the health of future generations less than the current acceptable level;

C) Do not impose undue burdens on future generations.

8.5.3 Registrars and license holders should take full account of the interrelationship between the generation and management of radioactive wastes, and according to the type, content, half-life, concentration of radioactive nuclides in the generated wastes, as well as the volume and other physical and chemical properties of the wastes. The same type of radioactive wastes are collected and treated separately in order to optimize waste management.

8.6 Control of Radioactive Material Emission to the Environment

8.6.1 Registrars and license holders shall ensure that the time of emission of radioactive substances from their approved practices and sources to the environment is the same.

All the following conditions have been met and approved by the competent authorities:

(a) Emissions shall not exceed the emission limits approved by the regulatory authorities, including the total emission limits and concentration limits;

B) Proper flow and concentration monitoring equipment and controlled emissions;

(c) Waste liquids containing radioactive substances are discharged in troughs;

D) Public exposure due to emissions meets the dose limitation requirements specified in Appendix B (Appendix to the Standards);

E) The emission control has been optimized in accordance with the relevant requirements of this standard.

8.6.2 Radioactive waste liquid shall not be discharged into ordinary sewers unless it is confirmed by the regulatory authorities to be a low-level waste liquid satisfying the following conditions, it may be discharged directly into ordinary sewers with discharge volume greater than 10 times, and records shall be made for each discharge:

(a) The total activity of monthly emissions does not exceed 10 ALImin (ALImin is the smaller of the intake and inhalation ALI values corresponding to occupational exposure, and the specific values can be obtained in accordance with the provisions of B1.3.4 and B1.3.5);

B) The activity of each discharge shall not exceed 1 ALImin, and flushing shall be carried out with no less than 3 times the amount of water discharged after each discharge.

Wash.

8.6.3 Before starting to discharge any liquid or airborne radioactive material into the environment from its responsible source, registrants and license holders shall complete the following tasks as required and report the results in writing to the competent authorities:

(a) To determine the characteristics and activity of the substances to be discharged and the possible location and method of their discharge;

B) Identify all important exposure routes for which radioactive nuclides emitted may cause public exposure through environmental surveys and appropriate pre-operation tests or mathematical simulations;

C) Estimate the radiation dose to key population groups that may be caused by planned emissions.

8.6.4 Registrars and license holders shall:

(a) Maintaining the emission of all radioactive substances at the lowest reasonably achievable level below the emission management limits;

B) Enough detailed and accurate monitoring of radionuclide emissions to demonstrate compliance with emission management limits and to estimate exposure doses in key population groups d on monitoring results;

C) Record the monitoring results and estimated dose;

D) Reporting the monitoring results to the competent authorities as required;

(e) Report any emissions exceeding the prescribed limits to the auditing authorities in a timely manner in accordance with the reporting system prescribed by the auditing authorities.

8.6.5 Registrars and license holders shall be composed of key groups according to the accumulation of operational experience and exposure routes.

Change, review and adjust the emission control measures of the source under its responsibility, but any adjustment can only be implemented with the approval of the auditing department in writing.

8.7 Monitoring of Public Exposure

8.7.1 Registrars and license holders shall, in accordance with the requirements of the competent authorities and in the light of the actual situation of the practices and sources they are responsible for:

(a) Develop and implement detailed monitoring outlines to ensure that the requirements of this standard for public exposure from external sources are met and that such exposure can be evaluated;

(b) Develop and implement detailed monitoring outlines to ensure that the requirements of this standard for the discharge of radioactive substances into the environment and the requirements formulated by the regulatory authorities are met so that the regulatory authorities can confirm that the assumptions in deriving emission management limits remain valid and that key populations can be estimated d on monitoring results. The dose of irradiation in group A;

C) Preserving monitoring records as required;

D) To submit a summary report of the monitoring results to the competent authorities within the prescribed time limit;

(e) Timely reporting to the competent authorities of significant increases in environmental radiation levels or pollution; if such increases may be caused by radiation or radioactive effluents from the sources responsible for them, they should be reported promptly;

(f) Establish and maintain the capability of emergency monitoring in case of accidental increase of environmental radiation level or radioactive pollution level caused by accidents or other abnormal events;

G) Verify the validity of the assumptions made in the pre-assessment of the radioactive consequences of emissions.

8.8 Management of Consumer Goods Containing Radioactive Substances

8.8.1 No person shall sell to the public consumables capable of causing radiation exposure unless:

(a) The irradiation caused is excluded;

B) Consumer goods themselves meet the exemption requirements specified in Appendix A (Appendix to Standards) and have been exempted by the competent authorities;

or

C) Consumer goods themselves have been approved and sold by the competent authorities.

8.8.2 Manufacturers and suppliers of non-exempt consumer goods shall ensure that their products meet the requirements of this Standard, and in particular shall ensure that their products are designed and manufactured in the course of normal operation and use or in the case of misoperation, misuse, accident or disposal.

The characteristics affecting the exposure of personnel have been optimized. When optimizing these characteristics, dose constraints formulated or approved by the regulatory authorities should be implemented, and the following factors should be taken into account:

(a) The various radionuclides used and their radiation types, radiation energy, activity and half-life;

B) Chemical and physical forms of radionuclides used and their effects on protection and safety under normal and abnormal conditions

Ring;

C) Inclusion and shielding of radioactive substances in consumer goods and the possibility of exposure to such substances under normal and abnormal circumstances;

D) Demand for after-sales services and ways of providing them;

E) Experience in similar consumer goods.

8.8.3 Manufacturers and suppliers of consumer goods shall ensure that:

(a) Fixed a striking label firmly on the visible surface of each consumer product by printing, pasting or other means, indicating that the consumer product contains radioactive substances and that the sale of the consumer product has been approved by the relevant regulatory authorities;

B) The information specified in (a) is also clearly marked on each package book for the supply of consumer goods.

8.8.4 Manufacturers and suppliers of consumer goods shall provide a deion with each consumer product, giving clear and appropriate instructions and guidance on the following aspects:

(a) Installation, use and maintenance of the consumer goods;

B) After-sales service;

(c) Radionuclides contained and their activity on specified dates and years;

D) Radiation dose rates during normal use, service and repair;

E) Recommended disposal methods.

9. Control of Potential Exposure - Source Safety

9.1 Responsibility

9.1.1 Registrars and license holders shall be responsible for the control of potential exposure (i.e. source safety) of the source they are responsible for.

The General requirements stipulated in Chapter 3 and the main requirements stipulated in Chapters 4 and 5 of this Standard shall be implemented, and the detailed requirements stipulated in this Chapter shall be implemented in accordance with the actual situation of the source under its responsibility.

In addition to the requirements of this Standard, license holders who are authorized to operate nuclear facilities or radioactive waste management facilities shall comply with the requirements specified in the special national regulations and standards for the protection and safety of nuclear facilities and radioactive waste management facilities.

9.1.2 Registrars and license holders shall ensure the source in practice by cooperating legally and effectively with the supplier or designer of the source, the builder or manufacturer of the source, such as through contracts:

(a) Well designed and constructed;

B) Compliance with relevant protection and safety requirements and corresponding quality standards;

C) After inspection, it is confirmed that it meets the requirements of the corresponding technical specifications.

9.1.3 Registrars and license holders shall be fully responsible for the safety of the source operation they are responsible for. Registrars and license holders may delegate the responsible source operation tasks to other parties, but they are still responsible for ensuring that all source operation meets the requirements of this standard.

9.2 Safety Assessment

9.2.1 Registrars and license holders shall conduct safety assessments of the sources they are responsible for in accordance with the relevant requirements specified in Chapter 4 (see 4.2.2.3 and 4.6.1). For the same type of source with the same structure, system and component design, if the safety evaluation of the technical performance of the source already exists, the safety evaluation of the source can only be carried out on the local setting, use and operation conditions. In other cases, a comprehensive and detailed specialized safety assessment should normally be carried out.

9.2.2 Safety evaluation should be d on the actual situation of the source, including a comprehensive and rigorous review of the following issues:

(a) Operational limits and operating conditions of the source;

B) Possibility, nature and magnitude of potential exposure;

C) Ways that may lead to potential exposure or to failure of structures, systems, components and procedures related to protection and safety (single or combined failure), and the possible consequences of such failure;

D) The ways in which environmental change may affect protection and safety, and the possible consequences of such effects;

E) Ways in which operational procedures related to protection and safety may be erroneous and the possible causes of such errors

Consequence;

F) Any proposed design modifications or operational modifications and their implications for protection and safety.

9.2.3 In the safety evaluation, the following issues should also be considered according to the actual situation of the source:

(a) Factors and maximum activity that may lead to sudden mass release of radioactive substances, as well as prevention or control

Measures that can be taken to control such releases;

B) Factors that may lead to continuous small releases of radioactive substances and what can be done to prevent or control such releases

Measures;

C) The factors that may cause accidental exposure of any radiation beam and the measures that can be taken to prevent, identify and control such incidents;

D) The independence of safety devices used to limit the possibility and size of potential exposure, and the appropriateness of redundancy and diversity of safety devices.

9.2.4 The safety evaluation shall be documented and, if necessary, the registered or license holder shall organize an independent review of the safety evaluation documents in accordance with the relevant quality assurance outline.

Registrars and license holders shall submit safety assessment documents to the competent authorities for review in accordance with the requirements of the competent authorities.

9.2.5 Safety assessment shall be re-conducted or supplemented if necessary in the following circumstances:

(a) Major modifications to the source or source-related facilities, operational procedures or maintenance procedures are proposed;

B) Operational experience or information on accidents, failures, errors or incidents that cause or may cause potential exposure indicate that existing safety assessments are inappropriate or ineffective;

C) The activity of the source has changed or may have changed significantly, or the safety guidelines or technical standards have changed.

9.3 Requirements for Design

9.3.1 General requirements

9.3.1.1 Source shall be designed and constructed to ensure that the source:

(a) To meet the protection and safety requirements specified in this Standard;

B) To meet the technical specifications for engineering, performance and function;

C) To meet the quality standards appropriate to the protection and safety functions and performance of components and systems;

D) To facilitate retirement in the future on the premise that the protection and safety requirements specified in this Standard are met.

9.3.1.2 For simple sources, information on proper installation, use and safety precautions should be provided; for complex and more complex sources, detailed design information should also be provided. All information should be easily understood and executed by its users.

Location or Location of 9.3.2 Sources

9.3.2.1 When selecting sites for sources with large amounts of radioactive substances and potential releases of these radioactive substances, consideration should be given to the site characteristics that may affect the radiation safety of the source and the site characteristics that may be affected by the source, as well as to the implementation of off-site interventions (including emergency plans and protective actions). Feasibility.

9.3.2.2 In determining the location of small sources in devices and facilities (e.g. hospitals and manufacturing plants), consideration should be given to:

(a) Factors that may affect the safety and security of the source;

B) Factors that may affect occupational and public exposure caused by the source, including ventilation, shielding, distance from the person's area of activity, etc.

C) The feasibility of engineering design after considering the above factors.

9.3.3 Accident prevention and mitigation of accident consequences

9.3.3.1 The design, construction and fabrication of various systems, components and equipment related to protection or safety of the source shall be as effective as possible to prevent all possible accidents, incidents or abnormal events related to the source, and to limit the size and possibility of exposure to workers and members of the public to the extent reasonably achievable. Low-level.

9.3.3.2 The design should be d on the principle of in-depth defense (see 4.5.2). Multiple protective and safety measures should be set up to suit the size and possibilities of the potential exposure of the source, and appropriate redundancy, diversity and independence of the important systems, components and equipment of the source's protection and safety should be ensured so that all kinds of foreseeable events will occur. The possibilities are reduced to sufficiently low levels and their consequences are effectively controlled or mitigated.

9.3.3.3 The design shall provide the necessary systems and equipment for identifying abnormal operating conditions that may significantly affect protection or safety. The systems and equipment provided shall have a sufficiently rapid response to enable timely corrective action.

9.3.3.4 No matter what kind of source, an appropriate automatic safety system should be set up whenever necessary. Once the source runs beyond the prescribed operating conditions, it can automatically turn off the source safely or reduce the radiation output of the source.

9.3.3.5 The design shall also make appropriate arrangements to:

(a) To ensure that periodic inspections and inspections of safety-critical systems, components and equipment are carried out, and to provide appropriate methods and means for such inspections and inspections;

(b) Provide appropriate methods and means to ensure that staff members are not exposed to excessive exposure during maintenance, inspection and inspection in compliance with protection and safety regulations;

(c) Providing the specialized equipment and means required for staff training in operational operations and maintenance;

D) Provide staff with appropriate means to implement the necessary emergency response plans or procedures.

Improvement of 9.3.4 Design

9.3.4.1 For sources already used in practice, if it is deemed necessary to improve the protection and safety measures of such sources due to the results of the safety assessment or for any other reason, then only after further appropriate safety assessment of the proposed improved meaning of protection and safety has been made, in particular, should it be evaluated or excluded. This improvement can only be implemented after its possible negative impact on protection and safety; if the proposed improvement may have a significant impact on protection and safety, it must also be reported to the competent authorities for approval before it can be implemented (see 4.2.3.2).

9.4 Requirements for Operation

9.4.1 General requirements

9.4.1.1 Registrars and license holders shall:

(a) Establish a clear responsibility relationship to manage the protection and safety of the source throughout its operational life, and, if necessary, establish and improve the protection and safety management organization;

B) Develop written operation procedures to ensure that the source operation is carried out in accordance with the established procedures, and periodically review and update the operation procedures in accordance with the corresponding quality assurance outline;

(c) Periodically review the overall effectiveness of protective and safety measures, and regularly or as required carry out appropriate inspection, maintenance, testing and maintenance of the source's protective and safety-related systems, components and equipment to enable the source to meet its protection and safety design requirements throughout its operational life.

9.4.1.2 Registrars and license holders shall be provided with sufficient qualified operational personnel and necessary managerial personnel in accordance with the actual situation of their responsible practices and sources, and regularly or irregularly trained and evaluated to enable them to possess and maintain the required competencies.

9.4.2 Source Inventory

9.4.2.1 Registrars and license holders must establish and maintain a strict system of checking sources, keep abreast of the number, storage, distribution and transfer of sources, and strictly prevent sources from being forgotten, out of control, lost, missing or stolen. For long-term idle sources and sources that can no longer be applied or no longer applied, we should insist on strict checks.

9.4.2.2 At least the following information shall be recorded and maintained by registrants and license holders in their inventory of the sources for which they are responsible:

(a) Location, morphology, activity and other deion of each source;

B) The quantity, activity, form, distribution, packaging and storage location of each radioactive substance.

9.4.3 Investigation and Tracking of Abnormal Events and Accidents

9.4.3.1 Registrars and license holders shall, in accordance with the requirements of this Standard and the relevant regulations of the regulatory authorities, formulate procedures for investigation, tracking and reporting of abnormal incidents.

9.4.3.2 In any of the following circumstances, the registrant and the Licensee shall investigate and follow up the procedures prescribed by the competent authority:

(a) Protection and safety-related quantities exceed the required level of investigation, or protection and safety-related operational parameters exceed the prescribed operating conditions;

B) Faults, failures, errors or other abnormal events that may result in a quantity exceeding the relevant limits or operating conditions;

C) Accidents occurred;

D) The damage or leakage of the source exceeds the requirements of the technical specifications;

E) Source lost or stolen.

9.4.3.3 An investigation shall be carried out as soon as possible after the occurrence of an incident or an accident, and a written report shall be submitted including the following:

(a) The process and causes of an incident or accident;

B) Radiation dose and pollution and other consequences;

C) Measures and recommendations to prevent the recurrence of similar incidents or accidents.

9.4.3.4 Registrars and license holders shall submit formal investigation reports of accidents or reported incidents to the competent authorities as soon as possible and to other parties concerned in accordance with the regulations of the competent authorities.

9.4.4 Accident Handling Criteria

9.4.4.1 For reasonably predictable operational errors or accidents involving the source under their responsibility, registrants and license holders should be prepared in advance so that necessary actions can be taken to respond to and correct them as needed.

9.4.4.2 For sources that may cause abnormal exposure, where action is possible to control or affect the accident process and mitigate the consequences of the accident, the registrant and the Licensee shall:

(a) Develop accident handling procedures in advance, taking into account the expected response of source protection and safety devices to accidents; or

guide

B) Training and regular on-the-spot training for operational and emergency personnel to enable them to understand the procedures to be implemented in case of accidents;

C) Keep the equipment, instruments and diagnostic aids that may be needed to control the process and consequences of the accident readily available.

9.4.5 Operational Experience Feedback

9.4.5.1 Registrars and license holders shall have operated and retired normally and irregularly at the source they are responsible for.

In order to improve the protection and safety of the source responsible for oneself, we should accumulate and summarize the experience and information of great importance to the protection and safety from the events and accidents that have occurred, and submit them to the competent authorities and other parties concerned (such as suppliers, designers and similar sources of the source) in accordance with the regulations of the competent authorities. This information should include dose data, maintenance data, event deion and corrective actions related to the given activity.

9.4.5.2 Registrars and license holders shall, in consultation with the supplier or designer of the source, establish and maintain a mechanism to enable the latter to provide timely feedback to the Registrar and license holder on the protection and safety of the source they have obtained.

9.5 Quality Assurance

9.5.1 Registrars and license holders shall be responsible for formulating and implementing quality assurance outlines or procedures that meet the main requirements specified in 4.4.2 of this Standard. The nature and scope of the quality assurance outline or procedure formulated and implemented should be commensurate with the potential exposure of the source for which the registrant and Licensee are responsible.

9.5.2 The Quality Assurance Outline shall stipulate that:

(a) Planned and systematic activities to ensure that the specified design and operational requirements related to protection and safety (including experience feedback requirements) are met;

B) Management mechanisms to enable the correct and effective implementation and completion of various tasks related to the design and operation of the source, such as task analysis, method development, standard-setting and skill identification;

C) Confirmation procedures for validation of design, supply and use of materials, manufacturing processes, inspection and inspection methods, operational procedures and other procedures.

10. Intervention in emergency exposure

10.1 Responsibility

The registrant or license holder, the relevant intervention organizations and the competent authorities shall comply with the relevant state regulations and these standards.

Responsibility for the preparation, implementation and management of interventions in case of emergency exposure is required.

10.2 Emergency Plan

10.2.1 Emergency plans should be formulated according to the type, scale and site characteristics of the sources. Responsibility for the preparation, implementation and management of emergency interventions should be clearly defined and corresponding arrangements should be made both on-site and off-site. On-site and off-site emergency plans should be ed and coordinated.

10.2.2 Registrars and license holders, and relevant intervention organizations and regulatory authorities shall ensure that:

(a) Emergency plans have been developed and approved for any practice or source that may require emergency intervention.

Procedures;

B) Intervention organizations participate in the formulation of relevant emergency plans;

(c) When determining the nature, content and scope of the emergency plan, not only the results of accident analysis of the source, but also the experience and lessons learned from the operation and accidents of the same source are taken into account.

D) Regular review and revision of emergency plans;

(e) Provide training for personnel involved in the implementation of emergency plans and make arrangements for emergency response exercises at appropriate intervals;

F) Provide early information to members of the public who are expected to be affected by the accident.

10.2.3 The contingency plan shall include the following elements as appropriate:

(a) The delineation and arrangement of responsibilities in reporting relevant departments and initiating interventions;

(b) Identification of operational and other conditions of sources that may lead to emergency intervention;

C) The level of intervention for protective actions and their scope of application determined in accordance with the guidelines given in Appendix E (Appendix to Standards) E2 and taking into account the severity of possible accidents or emergencies;

(d) Procedures for contacting relevant intervention organizations (including communication arrangements) and for obtaining support from fire control, medical, public security and other relevant organizations;

(e) Deion of methods and instruments used to evaluate accidents and their consequences on and off the site;

(f) Arrangements for publishing public information in case of accidents;

G) Guidelines for termination of each type of protective action.

10.2.4 Registrars and license holders shall ensure that appropriate arrangements are made for the prompt acquisition and transmission of sufficient information to the relevant emergency response organizations in order to:

(a) Early prediction or assessment of the extent and severity of any radioactive discharge to the environment;

B) Tracking and evaluating accidents rapidly and continuously with the development of accidents;

C) Identify the need for protective action.

10.3 Intervention Decision-making and Intervention Level

10.3.1 General requirements

10.3.1.1 Intervention under emergency irradiation should be carried out according to the level of intervention and action. The level of intervention is expressed by the dose that is expected to be prevented when a specific protective action is taken in the intervention; the level of action is expressed by the radioactivity concentration of radionuclides in food, water and crops, and sometimes by the anticipated dose rate or anticipated dose.

10.3.1.2 The level of intervention and action corresponding to the protective action should be optimized, but it should not exceed the level of action of acute radiation dose required for intervention under any circumstances given in Appendix E (Standard Appendix) E1. The level of intervention determined in the emergency plan should only be the initial criteria for the operation to implement protective action; the level of intervention should be revised accordingly in response to the accident, taking into account the prevailing situation at that time and its possible evolution.

10.3.2 Justice of Intervention

It is almost always justified to take protective action if the expected dose (rather than preventable dose) or dose rate of any individual approaches or is expected to approach the threshold that may lead to serious injury (as listed in Appendix E (Standard Appendix) E1) (see 5.3.1). In this case, the legitimacy of any decision not to take urgent protective action must be judged.

10.3.3 OPTIMIZATION OF PROTECTIVE ACTION: INTERVENTION LEVEL AND ACTION LEVEL OF EMERGENCY PROTECTIVE ACTION

10.3.3.1 Decision-making for emergency protective action should be d on the dominant situation in the event of an accident. When practicable, it should be d on the projected release scenario of radioactive substances to the environment, but it should not be deferred until the measurement results after the release commences in order to verify the release. In addition to these emergency protective actions, there are other protective actions that may be implemented under specific circumstances, such as personnel decontamination or simple respiratory protection, but this standard does not specify a specific level of intervention for such protective actions.

10.3.3.2 The level of intervention corresponding to emergency protection actions (including concealment, evacuation and iodine prevention) should be clearly defined in the contingency plan in accordance with the guidelines set out in Appendix E (Appendix to the Standards) E2.1, and should be considered when the preventable dose of any group is expected to exceed the prescribed level of intervention. Corresponding protective actions.

10.3.3.3 Where necessary, the level of action to stop and replace the supply of specific food and drinking water should be specified in the contingency plan.

10.3.3.4 In the absence of food shortages and other mandatory social or economic factors, the level of action to stop and replace the supply of specific food and drinking water should be determined in accordance with the criteria set out in Appendix E (Appendix to Standards) E2.2. The level of action determined should be applied to foods that can be eaten directly and to dry or concentrated foods that are diluted or rehydrated.

10.3.3.5 In some cases, if food shortage or other important social or economic factors are considered, a slightly higher optimal level of food and drinking water action can be adopted. However, when the level of action used is higher than that given in Appendix E (Standard Appendix), the decision to take action must be judged by the legitimacy of the intervention and the optimal analysis of the level of action.

10.3.3.6 For foods that consume very little (e.g. less than 10 kg per person per year), such as spices, because their share in the total diet of the people is very small, the increase in personal exposure is also very small, so the level of action can be 10 times higher than that of the main foods.

10.3.4 optimization of protective action; intervention level and action level of longer-term protective action

10.3.4.1 Agricultural, hydrological and other technical or industrial protective actions should be considered in light of the contamination of soil or water after the accident.

10.3.4.2 The international trade of food contaminated by radionuclides shall follow the criteria specified in Appendix E (Appendix to Standards) E2.2.

10.3.4.3 Intervention levels for temporary evacuation and return of licensed personnel shall be specified in the contingency plan in accordance with the guidelines set out in Appendix E (Appendix to Standards) E2.3.

10.3.4.4 Intervention organizations should make temporary evacuees aware of the general time of their return to their homes and the protection of their property.

10.3.4.5 Permanent resettlement of licensed persons shall be considered in accordance with the guidelines set out in Appendix E (Appendix to Standards) E2.3:

(a) It is anticipated that the time of temporary evacuation will exceed the agreed period; or

B) Permanent resettlement is justified on the basis of preventable doses.

10.3.4.6 Before the implementation of the permanent resettlement plan, full consultation should be conducted with those who may be affected.

10.4 Post-accident Evaluation and Monitoring

10.4.1 All reasonable steps should be taken to evaluate the exposure to members of the public caused by the accident, and the evaluation results should be made public by appropriate means.

10.4.2 The evaluation should be d on the most valuable information available and should be revised in a timely manner in the light of any new information that can substantially produce more accurate results.

10.4.3 All evaluations and their modifications, as well as the results of staff, public and environmental monitoring, should be fully documented and properly preserved.

10.4.4 If the evaluation indicates that it is no longer justified to continue to implement protective actions, the protective actions implemented should be discontinued.

10.5 Protection of staff engaged in intervention

10.5.1 Except for actions taken under the following circumstances, the exposure of staff engaged in intervention shall not exceed the maximum single-year dose limit for occupational exposure specified in Appendix B (Standard Appendix):

(a) To save lives or avoid serious injury;

B) To avoid large collective doses;

C) In order to prevent catastrophic situations from evolving.

When intervening in these situations, all reasonable efforts must be made to save lives.

Personnel are exposed to doses that are less than twice the maximum dose limit in a single year. For life-saving actions, efforts should be made to keep the exposure dose of staff below 10 times the maximum dose limit in a single year in order to prevent deterministic health effects. In addition, when the radiation dose of the staff taking action may reach or exceed 10 times the maximum dose limit for a single year, the action should be taken only if the benefit to others brought by the action is significantly greater than the risk to the staff themselves.

10.5.2 When actions are taken to make the dose to staff members likely to exceed the maximum single-year dose limit, the staff members taking these actions should be voluntary; the staff members should be notified clearly and comprehensively in advance of the health risks to be faced by the actions and, to the extent practicable, what action is required. They should be trained.

10.5.3 The legal person responsible for ensuring that the requirements specified in 10.5.1 and 10.5.2 are met shall be clearly defined in the contingency plan.

10.5.4 Once the emergency intervention phase is over, all the specific requirements for occupational exposure stipulated in Chapter 6 of this Standard shall be met by the workers engaged in rehabilitation work (such as repair of factories and buildings, waste disposal, or decontamination of factories and surrounding areas, etc.).

10.5.5 All reasonable steps should be taken to provide appropriate protection for emergency intervention and to evaluate and record the exposure of staff involved in emergency intervention. At the end of the intervention, the staff concerned should be informed of the dose they received and the possible health risks.

10.5.6 Staff members shall not be refused to work with occupational exposure in the future because they have received doses in case of emergency exposure. However, if a staff member who has undergone emergency exposure is exposed to doses 10 times higher than the maximum dose limit for a single year, or if the staff member requests it himself, they should listen carefully to the medical advice of a qualified doctor before they receive any further exposure.

Intervention of continuous irradiation

11.1 Responsibility

The registrant or license holder, as well as the relevant intervention organizations and regulatory authorities, shall assume the responsibility for the preparation, implementation and management of the intervention in the case of continuous exposure in accordance with the relevant national regulations and the requirements of this standard.

11.2 Remedial Action Plan

11.2.1 Intervention organizations should develop action plans for remediation of persistent exposure that can be used or dedicated to the site, as appropriate.

The plan should provide for legitimate and optimal remedial actions and corresponding levels of action, taking into account the following factors:

(a) Individual and collective irradiation;

B) Radiation and non-radiation hazards;

C) Economic and social costs, benefits and liabilities for the payment of required funds for remedial action. 11.3 Judgment of the Legitimacy of Remedial Action

11.3.1 In the case of continuous irradiation, if the dose level approaches or is expected to approach Appendix E (Standard Appendix)

The values listed in E1.2 almost always justify remedial action regardless of the circumstances (see 5.3.1). In this case, the legitimacy of any decision not to take remedial action should be judged.

11.3.2 Remedial action against the following two categories of situations is not justified:

(a) The level of pollution and dosage is low and not worth the cost of remedial action;

B) Pollution is very serious and widespread, and the cost of recovery operations is too high.

11.3.3 Judgment of the legitimacy of remedial actions relating to specific practices should take into account the registration or licensing of practices:

(a) For practices registered or licensed and under the control of the radiation protection system, when considering remedial actions related to the practice of continuous exposure, the justification of such practices should be an integral part of the justification of such practices, and the net benefits of remedial actions themselves should not be taken into account separately;

(b) In the past practice of failing to perform registration or licensing procedures, the justification of remedial actions can be judged only on the basis of various factors directly related to remedial actions, such as the value of site opening, the avoidable health hazards of decontamination, investment and public acceptance.

11.3.4 For a remedial action that has been determined to be legitimate, i.e. a remedial action that is justified by verifying that it can bring net benefits, the detailed characteristics of the remedial action should be constantly adjusted in the course of implementation so as to maximize the net benefits obtained.

11.4 Level of Action or Dose Constraints for Continuous Exposure

11.4.1 The level of action to intervene through remedial action should be defined in appropriate quantities, such as considering the annual dose rate at the time of remedial action or the appropriate average activity concentration of radionuclides present.

11.4.2 Action Level of Continuous Radon Exposure

11.4.2.1 For continuous radon exposure in homes and workplaces, the optimal level of action should be within the level specified in Appendix H (Appendix to the Tips).

11.4.2.2 After considering the relevant social or legal conditions, the competent authorities or intervention organizations should make a decision on whether to enforce or recommend the remedial action for the continuous radon exposure in residential buildings.

Dose Constraints of Continuous Irradiation of 11.4.3 Radioactive Residues

11.4.3.1 For sustained exposure caused by approved practice or source decommissioning, the dose constraint shall not be higher than that during the practice or source operation. Typical cases of using such doses are:

(a) Opening of plant sites after decommissioning of nuclear facilities;

B) The redevelopment or utilization of contaminated sites or land in past practices, and such redevelopment or utilization may lead to increased public exposure.

11.4.3.2 dose constraint values should normally be within the range of 10%-30% of the public exposure dose (i.e. 0.1 mSv/a-0.3 mSv/a). However, the use of dose constraints should not replace the optimization requirements. The dose constraints can only be used as the upper limit of the optimization values (see 4.3.4).

11.4.3.3 If there is no possibility of other irradiation and the economic cost of reducing irradiation is too high, the dose constraint value can be relaxed to 1 mSv/a with the approval of the regulatory authorities in this case.

11.4.3.4 If the dose constraint has exceeded 1 mSv/a and the economic cost of adopting technical measures to further reduce sustained exposure is too high, administrative measures should be adopted to organize the control of sustained exposure in such cases. The degree of strictness of organizational control should be determined to adapt it to the situation at that time.

Appendix A

(Appendix to Standards)

Exemption

A1 Exemption Criteria

A1.1 If the competent authority confirms that a practice is justified and that the source of the practice satisfies the exemption criteria or levels specified in this appendix or other levels of exemption specified by the competent authority in accordance with these exemption criteria, the practice and the source of the practice may be exempted from the requirements of this standard.

The general criteria for A1.2 exemption are:

(a) The radiation risk to individuals caused by exempted practices or sources is sufficiently low to make it unnecessary to regulate them

.

(b) The group radiation risk caused by exemption practices or sources is low enough that it is not worthwhile to regulate and control them under normal circumstances;

C) Exempted practices and sources are inherently safe to ensure that the above guidelines a) and b) are always met.

A1.3 If the competent authorities confirm that the following criteria can be met in any practical case, it is not possible to consider further and exempt sources of practice or practice:

(a) The exempted practice or source causes any public member to receive an effective dose of 10? Sv magnitude or less in one year;

and

B) The collective effective dose not exceed 1 person Sv within one year of implementation of the practice, or the optimal evaluation of protection indicates that exemption is the best choice.

The Source and Level of A2 Exemption

A2.1 According to the criteria stipulated in A1.1-A1.3, the following sources of practice can be exempted from the requirements of this standard after being approved by the competent authorities:

(a) Radiation generators and electronic tubes (e.g. cathode ray tubes for imaging) that meet the following requirements and have the type approved by the regulatory authorities;

1) Under normal operating conditions, the ambient dose equivalent rate or directional dose equivalent rate caused at any 0.1 m above the surface of the equipment shall not exceed 1?Sv/h; or

2) The maximum energy of radiation produced is not more than 5 keV.

B) Radioactive substances that meet the following requirements, i.e. the total activity of a given nuclide existing in the place where the practice is carried out at any time period or the activity of a given nuclide used in practice does not exceed the level of exemption given in Table A1 or prescribed by the competent authorities;

The exemption activity concentration and exemption activity of radionuclides given in Table A1 of A2.2 are derived from some irradiation scenarios and modes and parameters that may not be sufficient for unlimited use, and can only be used as the basis for declaring exemptions. When considering exemption, the competent authorities should examine it on a case-by-case basis according to the actual situation, and in some cases, a stricter level of exemption may be required. When applying the level of exemption given in Table A1, the following points should also be noted:

(a) These exemption levels are in principle applicable only to industrial and laboratory or medical applications of small amounts of radioactive substances and sources in well-organized and well-trained workplaces, such as the use of small sealed point source calibration instruments, the loading of small amounts of non-sealed radioactive solutions into containers, industrial tracers, and a bottle of low activity gas. Physical medicine, etc.

B) The application of exemptions for excluded natural radionuclides is limited to natural radionuclides introduced into consumer goods, or used as a radioactive source (e.g. 226Ra, 210Po), or using their elemental characteristics (e.g. thorium and uranium).

(c) If more than one radionuclide exists, exemption may be considered only if the ratio of the activity or activity concentration of various radionuclides to their corresponding exemption activity or concentration is less than 1;

(d) Unless the relevant exposure has been excluded, the exemption of large quantities of radioactive substances, even if their activity concentration is below the exemption level given in Table A1, will require further consideration by the competent authorities;

(e) It is strictly prohibited to reduce the concentration of radioactivity by manual dilution in order to declare exemption.

A2.3 Conditional exemptions may be granted if conditions specified by the competent authorities (e.g. those relating to the physical or chemical form of radioactive substances and conditions relating to the use or disposal of radioactive substances, etc.) are followed.

Such conditional exemption may be granted to equipment containing radioactive substances not exempted in accordance with item A2.1b, which meets the following conditions;

(a) Types approved by the competent authorities;

B) Its radioactive material is in the form of sealed source, which can effectively prevent any contact with radioactive material or effectively prevent the leakage of radioactive material;

C) Under normal operating conditions, the ambient dose equivalent rate or directional dose equivalent rate caused at any 0.1 m from the equipment surface does not exceed 1?Sv/h;

D) The examining and administering authorities have clearly defined the conditions that must be met at disposal.

Table A1 Exemption Level as the Basis for Declaration of Exemption: Exemption Activity Concentration and Exemption Activity of Radionuclides (rounded to integers)

Appendix B

(Appendix to Standards)

Dose Limit and Surface Pollution Control Level

B1 dose limit

The dose limits prescribed in this appendix are applicable to exposure caused by practice, not to medical exposure, nor to exposure from natural sources without any primary responsibility.

The dose limits specified in this appendix are not related to the control of potential exposure, nor to the determination of whether or not to intervene, but the personnel who intervene shall comply with the relevant requirements in Chapter 11.

B1.1 Occupational Exposure

B1.1.1 Dose Limit

B1.1.1.1 shall control the occupational exposure level of any staff member so that it does not exceed the following limits:

(a) Average annual effective dose (without any retrospective average) of 20 mSv for five consecutive years determined by the competent authorities;

B) The effective dose in any year, 50 mSv;

C) The annual equivalent dose of ophthalmic lens, 150 mSv;

D) The annual equivalent dose of limbs (hands and feet) or skin, 500 mSv.

B1.1.1.2 For apprentices aged 16-18 years who receive employment training involving radiation exposure and students aged 16-18 years who need to use radiation sources in their study, their occupational exposure should be controlled so that they do not exceed the following limits:

(a) Annual effective dose, 6 mSv;

B) Equivalent annual dose of ophthalmic lens, 50 mSv;

C) The annual equivalent dose of limbs (hands and feet) or skin, 150 mSv.

B1.1.2 Special case

In exceptional circumstances, the following temporary changes may be made to the dose limit according to the requirements specified in Chapter 6.2.2:

(a) According to the regulations of the competent authorities, the average period of dose indicated in item B1.1.1.1a may be extended to 10 consecutive companies.

In addition, during this period, the average annual effective dose received by any staff member should not exceed 20 mSv, and no single year should exceed 50 mSv. In addition, when the cumulative dose received by any staff member since the beginning of the extended average period reaches 100 mSv, this situation should be examined.

B) Temporary changes in dose limits shall be in accordance with the regulations of the competent authorities, but shall not exceed 50 mSv in any one year and shall not exceed 5 years.

B1.2 Public Exposure

B1.2.1 Dose Limit

Practice has made it possible that the average dose estimates received by members of key groups of the public should not exceed the following limits:

(a) Annual effective dose, 1 mSv;

B) Under special circumstances, if the average annual dose for five consecutive years does not exceed 1 mSv, the effective dose for a single year can be increased to 5 mSv.

C) The annual equivalent dose of ocular lens, 15 mSv;

D) Annual equivalent dose of skin, 50 mSv.

B1.2.2 Dose Limitation for Consolators and Visitors

The dose limit prescribed in B1.2.1 does not apply to patients'consolers (e.g. those who are not their duty, knowingly exposed but voluntarily assist in nursing, supporting and visiting, consoling patients undergoing medical diagnosis or treatment). However, radiation exposure to patients'sympathizers should be restrained so that they are not exposed to excessive doses during diagnosis or treatment.

5 mSv. Children who control the intake of radioactive substances should be limited to doses below 1 mSv.

Confirmation of B1.3 Compliance with Dose Limits

B1.3.1 The dose limits specified in this appendix apply to doses caused by internal and external irradiation during a specified period and during the same period.

The sum of accumulated doses caused by internal intake and the duration of calculation of accumulated doses should be 50 years for adults and 70 years for children.

B1.3.2 In order to confirm compliance with the dose limit, the sum of the individual dose equivalent caused by penetrating radiation during the prescribed period and the accumulated equivalent dose or effective dose caused by radioactive substances intake during the same period should be used.

B1.3.3 One of the following methods should be used to determine whether the dose limit requirements for effective dose are met:

(a) Compare the total effective dose with the corresponding dose limit; here, the total effective dose ET is calculated as follows:

ET_H p(d)e(g) j, ing I j, ing_e(g) j, INH I j, INH I j, INH

J J

Formula: HP (d) - Personal dose equivalent caused by penetrating radiation during the year;

E (g) j, JNG and E (g) j, Jnh - radionuclides per unit intake of food and inhalation in G age group during the same period

J. Post-accumulated effective dose;

Ij, JNG and Ij, Jnh - Intake and inhalation of radionuclide J during the same period.

B) Examine whether the following conditions are met:

H P I j, ing I j, INH < 1

DL J I j, ing.L j, inh.L

Formula: DL - the annual dose limit of the corresponding effective dose;

Ij, jng, L and Ij, jnh, L - Annual Limit of Intake (ALI) of Intake and Intake of Radionuclide J (i.e. the amount of Radionuclide J ingested through the relevant pathways resulting in the accumulated effective dose equal to the dose limit of the effective dose).

C) Can pass any other approved method.

B1.3.4 Radon-reducing daughters and daughters in vitro, tables B3, B6 and B7 respectively give the accumulated effective dose e(g)j, JNG and e(g)j, Jnh caused by unit intake of food and inhalation for occupational and public exposure. Using the following formula, the annual intake limit of radionuclide J can be obtained from the accumulated effective dose of the corresponding unit intake, Ij, L:

I. Ostrich DL

J, L EJ

In the formula: DL - the annual dose limit of the corresponding effective dose

EJ - Effective doses to be accumulated due to unit intake of radionuclide J given in Tables B3 and B6 and B7

The corresponding value.

B1.3.5 For occupational exposure, table B3 gives the dose conversion coefficients for ingestion and inhalation of radionuclides, i.e. the accumulated effective dose per unit intake of ingestion and inhalation; the former is given by different intestinal transfer factors FL corresponding to various chemical forms of elements (i.e., the share of intake transferred to intestinal body fluids); the latter is given by table B3. Corresponding to the default lung absorption categories (F, M and S) given in the new respiratory tract model, and introducing the appropriate fraction of intake nuclides from lung clearance to digestive tract fl. Table B4 gives

The FL value. Table B5 gives the categories of lung absorption of various chemical forms of elements. For occupational exposure, Ij, L can be used as ALI under certain assumptions.

B1.3.6 For public exposure, Table B6 gives the dose conversion coefficients of public members after ingestion of radionuclides with different intestinal transfer factors fl. The FL values used in the calculation also represent the table. Table B7 gives dose conversion coefficients for inhalation of radionuclides by members of the public corresponding to various lung absorption categories (F, M and S). Table B8 lists the lung absorption categories on which the calculations are d and the number of ICRP publications containing detailed information on biodynamic models and absorption categories. For 31 elements whose lung absorption is known, the dose conversion coefficients corresponding to three absorption categories are given. At the same time, the default values that can be used only when the chemical form of radionuclides is unknown are recommended. For the other 60 additional elements, corresponding to F, M and S lung absorption categories, the dose conversion coefficients of radionuclides are given. When calculating the dose of radionuclides, age-related changes in body weight, geometric size and excretion rate are taken into account, but this is not done for the biodynamic model used to calculate the whole body activity. Change.

Table B1.3.7 B9 gives the gas and steam dose conversion coefficients for infants, children and adults. Adult values are applicable to both staff and members of the public. Table B10 gives the effective dose rate for adults exposed to inert gases. These values are applicable to both staff members and adults in the public.

B1.3.8 For radon daughters, if the conversion coefficient is 1.4 mSv/(mJ h m-3), then B1.1.1

33

The mid-dose limit can be interpreted as: 20 mSv is equivalent to 14 mJ H / m (4 working level months); 50 mSv is equivalent to 35 mJ H / m.

(10 work-level months). For radon daughters and daughters, if the phase specified in Table B1 and Table B2 is used

Ij, Jnh and Ij, Jnh and L in the formula B1.3.3 can be expressed by a potential intake, or Ij, Jnh and Ij, Jnh and L can be replaced by a potential exposure (commonly expressed by WLM) when the corresponding limits specified in tables B1 and B2 are adopted.

B1.3.9 After any radionuclide is ingested through a given route, the accumulated equivalent dose of organs or tissues can be determined by the following methods.

(a) The estimated intake of the radionuclide through this route is multiplied by the equivalent dose to be accumulated per unit intake corresponding to the tissue or organ; or

B) Adopt other approved methods.

Control Level of B2 Surface Pollution