COUNCIL DIRECTIVE 2013/59/EURATOM
of 5 December 2013
laying down basic safety standards for protection against the dangers arising from exposure to ionising radiation, and repealing Directives 89/618/Euratom, 90/641/Euratom, 96/29/Euratom, 97/43/Euratom and 2003/122/Euratom
CHAPTER I
SUBJECT MATTER AND SCOPE
Article 1
Subject matter
This Directive establishes uniform basic safety standards for the protection of the health of individuals subject to occupational, medical and public exposures against the dangers arising from ionising radiation.
Article 2
Scope
This Directive applies in particular to:
the manufacture, production, processing, handling, disposal, use, storage, holding, transport, import to, and export from the Community of radioactive material;
the manufacture and the operation of electrical equipment emitting ionising radiation and containing components operating at a potential difference of more than 5 kilovolt (kV);
human activities which involve the presence of natural radiation sources that lead to a significant increase in the exposure of workers or members of the public, in particular:
the operation of aircraft and spacecraft, in relation to the exposure of crews;
the processing of materials with naturally-occurring radionuclides;
the exposure of workers or members of the public to indoor radon, the external exposure from building materials and cases of lasting exposure resulting from the after-effects of an emergency or a past human activity.
the preparedness for, the planning of response to and the management of emergency exposure situations that are deemed to warrant measures to protect the health of members of the public or workers.
Article 3
Exclusion from the scope
This Directive shall not apply to:
exposure to the natural level of radiation, such as radionuclides contained in the human body and cosmic radiation prevailing at ground level;
exposure of members of the public or workers other than air or spacecrew to cosmic radiation in flight or in space;
aboveground exposure to radionuclides present in the undisturbed earth's crust.
CHAPTER II
DEFINITIONS
Article 4
Definitions
For the purpose of this Directive, the following definitions shall apply:
"Absorbed dose" (D) is the energy absorbed per unit mass
where
|
|
is the mean energy imparted by ionising radiation to the matter in a volume element, |
|
dm |
is the mass of the matter in this volume element. |
"accelerator" means equipment or installation in which particles are accelerated, emitting ionising radiation with energy higher than 1 mega-electron volt (MeV);
"accidental exposure" means an exposure of individuals, other than emergency workers, as a result of an accident;
"activation" means a process through which a stable nuclide is transformed into a radionuclide by irradiating with particles or high-energy photons the material in which it is contained;
"activity" (A) is the activity of an amount of a radionuclide in a particular energy state at a given time. It is the quotient of dN by dt, where dN is the expectation value of the number of nuclear transitions from that energy state in the time interval dt:
The unit of activity is the becquerel (Bq);
"apprentice" means a person receiving training or instruction within an undertaking with a view to exercising a specific skill;
"authorisation" means the registration or licensing of a practice;
"building material" means any construction product for incorporation in a permanent manner in a building or parts thereof and the performance of which has an effect on the performance of the building with regard to exposure of its occupants to ionising radiation;
"carers and comforters" means individuals knowingly and willingly incurring an exposure to ionising radiation by helping, other than as part of their occupation, in the support and comfort of individuals undergoing or having undergone medical exposure;
"clearance levels" means values established by the competent authority or in national legislation, and expressed in terms of activity concentrations, at or below which materials arising from any practice subject to notification or authorisation may be released from the requirements of this Directive;
"clinical audit" means a systematic examination or review of medical radiological procedures which seeks to improve the quality and outcome of patient care through structured review, whereby medical radiological practices, procedures and results are examined against agreed standards for good medical radiological procedures, with modification of practices, where appropriate, and the application of new standards if necessary;
"clinical responsibility" means responsibility of a practitioner for individual medical exposures, in particular, justification; optimisation; clinical evaluation of the outcome; cooperation with other specialists and staff, as appropriate, regarding practical aspects of medical radiological procedures; obtaining information, if appropriate, on previous examinations; providing existing medical radiological information and/or records to other practitioners and/or the referrer, as required; and giving information on the risk of ionising radiation to patients and other individuals involved, as appropriate;
"committed effective dose" (E(τ)) is the sum of the committed organ or tissue equivalent doses HT(τ) resulting from an intake, each multiplied by the appropriate tissue weighting factor wT. It is defined by:
In specifying E(τ), is given in the number of years over which the integration is made. For the purpose of complying with dose limits specified in this Directive, is a period of 50 years following intake for adults and up to the age of 70 for infants and children. The unit for committed effective dose is the sievert (Sv);
"committed equivalent dose" (HT(τ)) is the integral over time (t) of the equivalent dose rate in tissue or organ T that will be received by an individual as a result of an intake.
It is given by:
for an intake at time t0 where
|
|
is the relevant equivalent dose rate in organ or tissue T at time t, |
|
τ |
is the time over which the integration is performed. |
In specifying HT(τ), is given in number of years over which the integration is made. For the purpose of complying with dose limits specified in this Directive, τ is a period of 50 years for adults and up to the age of 70 for infants and children. The unit for committed equivalent dose is the sievert (Sv);
"competent authority" means an authority or system of authorities designated by Member States as having legal authority for the purposes of this Directive;
"consumer product" means a device or manufactured item into which one or more radionuclides have deliberately been incorporated or produced by activation, or which generates ionising radiation, and which can be sold or made available to members of the public without special surveillance or regulatory control after sale;
"contamination" means the unintended or undesirable presence of radioactive substances on surfaces or within solids, liquids or gases or on the human body;
"controlled area" means an area subject to special rules for the purpose of protection against ionising radiation or preventing the spread of radioactive contamination and to which access is controlled;
"diagnostic reference levels" means dose levels in medical radiodiagnostic or interventional radiology practices, or, in the case of radio-pharmaceuticals, levels of activity, for typical examinations for groups of standard-sized patients or standard phantoms for broadly defined types of equipment;
"disused source" means a sealed source which is no longer used or intended to be used for the practice for which authorisation was granted but continues to require safe management;
"dose constraint" means a constraint set as a prospective upper bound of individual doses, used to define the range of options considered in the process of optimisation for a given radiation source in a planned exposure situation;
"dose limit" means the value of the effective dose (where applicable, committed effective dose) or the equivalent dose in a specified period which shall not be exceeded for an individual;
"dosimetry service" means a body or an individual competent to calibrate, read or interpret individual monitoring devices, or to measure radioactivity in the human body or in biological samples, or to assess doses, whose capacity to act in this respect is recognised by the competent authority;
"effective dose" (E) is the sum of the weighted equivalent doses in all the tissues and organs of the body from internal and external exposure. It is defined by the expression:
where
|
DT,R |
is the absorbed dose averaged over tissue or organ T, due to radiation R, |
|
wR |
is the radiation weighting factor and |
|
wT |
is the tissue weighting factor for tissue or organ T. |
The values for wT and wR are specified in Annex II. The unit for effective dose is the sievert (Sv);
"emergency" means a non-routine situation or event involving a radiation source that necessitates prompt action to mitigate serious adverse consequences for human health and safety, quality of life, property or the environment, or a hazard that could give rise to such serious adverse consequences;
"emergency exposure situation" means a situation of exposure due to an emergency;
"emergency management system" means a legal or administrative framework establishing responsibilities for emergency preparedness and response, and arrangements for decision making in the event of an emergency exposure situation;
"emergency occupational exposure" means exposure received in an emergency exposure situation by an emergency worker;
"emergency response plan" means arrangements to plan for adequate response in the event of an emergency exposure situation on the basis of postulated events and related scenarios;
"emergency worker" means any person having a defined role in an emergency and who might be exposed to radiation while taking action in response to the emergency;
"environmental monitoring" means the measurement of external dose rates due to radioactive substances in the environment or of concentrations of radionuclides in environmental media;
"equivalent dose" (HT) is the absorbed dose, in tissue or organ T weighted for the type and quality of radiation R. It is given by:
where
|
DT,R |
is the absorbed dose averaged over tissue or organ T, due to radiation R, |
|
wR |
is the radiation weighting factor. |
When the radiation field is composed of types and energies with different values of wR, the total equivalent dose, HT, is given by:
The values for wR are specified in Annex II, Part A. The unit for equivalent dose is the sievert (Sv);
"exemption level" means a value established by a competent authority or in legislation and expressed in terms of activity concentration or total activity at or below which a radiation source is not subject to notification or authorisation;
"existing exposure situation" means an exposure situation that already exists when a decision on its control has to be taken and which does not call or no longer calls for urgent measures to be taken;
"exposed worker" means a person, either self-employed or working under an employer, who is subject to exposure at work carried out within a practice regulated by this Directive and who is liable to receive doses exceeding one or other of the dose limits for public exposure;
"exposure" means the act of exposing or condition of being exposed to ionising radiation emitted outside the body (external exposure) or within the body (internal exposure);
"extremities" means the hands, forearms, feet and ankles;
"health detriment" means reduction in length and quality of life occurring in a population following exposure, including those arising from tissue reactions, cancer and severe genetic disorder;
"health screening" means a procedure using medical radiological installations for early diagnosis in population groups at risk;
"high-activity sealed source" means a sealed source for which the activity of the contained radionuclide is equal to or exceeds the relevant activity value laid down in Annex III;
"individual detriment" means clinically observable deleterious effects in individuals or their descendants, the appearance of which is either immediate or delayed and, in the latter case, implies a probability rather than a certainty of appearance;
"inspection" means an investigation by or on behalf of any competent authority to verify compliance with national legal requirements;
"intake" means the total activity of a radionuclide entering the body from the external environment;
"interventional radiology" means the use of X-ray imaging techniques to facilitate the introduction and guidance of devices in the body for diagnostic or treatment purposes;
"ionising radiation" means energy transferred in the form of particles or electromagnetic waves of a wavelength of 100 nanometres or less (a frequency of 3 × 1015 hertz or more) capable of producing ions directly or indirectly;
"licence" means permission granted in a document by the competent authority to carry out a practice in accordance with specific conditions laid down in that document;
"medical exposure" means exposure incurred by patients or asymptomatic individuals as part of their own medical or dental diagnosis or treatment, and intended to benefit their health, as well as exposure incurred by carers and comforters and by volunteers in medical or biomedical research;
"medical physics expert" means an individual or, if provided for in national legislation, a group of individuals, having the knowledge, training and experience to act or give advice on matters relating to radiation physics applied to medical exposure, whose competence in this respect is recognised by the competent authority;
"medical radiological" means pertaining to radiodiagnostic and radiotherapeutic procedures, and interventional radiology or other medical uses of ionising radiation for planning, guiding and verification purposes;
"medical radiological installation" means a facility where medical radiological procedures are performed;
"medical radiological procedure" means any procedure giving rise to medical exposure;
"members of the public" means individuals who may be subject to public exposure;
"natural radiation source" means a source of ionising radiation of natural, terrestrial or cosmic origin;
"non-medical imaging exposure" means any deliberate exposure of humans for imaging purposes where the primary intention of the exposure is not to bring a health benefit to the individual being exposed;
"normal exposure" means exposure expected to occur under the normal operating conditions of a facility or activity (including maintenance, inspection, decommissioning), including minor incidents that can be kept under control, i.e. during normal operation and anticipated operational occurrences;
"notification" means submission of information to the competent authority to notify the intention to carry out a practice within the scope of this Directive;
"occupational exposure" means exposure of workers, apprentices and students, incurred in the course of their work;
"occupational health service" means a health professional or body competent to perform medical surveillance of exposed workers and whose capacity to act in that respect is recognised by the competent authority;
"orphan source" means a radioactive source which is neither exempted nor under regulatory control, e.g. because it has never been under regulatory control or because it has been abandoned, lost, misplaced, stolen or otherwise transferred without proper authorisation;
"outside worker" means any exposed worker who is not employed by the undertaking responsible for the supervised and controlled areas, but performs activities in those areas, including, apprentices and students;
"planned exposure situation" means an exposure situation that arises from the planned operation of a radiation source or from a human activity which alters exposure pathways, so as to cause the exposure or potential exposure of people or the environment. Planned exposure situations may include both normal exposures and potential exposures.
"potential exposure" means exposure that is not expected with certainty but may result from an event or sequence of events of a probabilistic nature, including equipment failures and operating errors;
"practical aspects of medical radiological procedures" means the physical conduct of a medical exposure and any supporting aspects, including handling and use of medical radiological equipment, the assessment of technical and physical parameters (including radiation doses), calibration and maintenance of equipment, preparation and administration of radio-pharmaceuticals, and image processing;
"practice" means a human activity that can increase the exposure of individuals to radiation from a radiation source and is managed as a planned exposure situation;
"practitioner" means a medical doctor, dentist or other health professional who is entitled to take clinical responsibility for an individual medical exposure in accordance with national requirements;
"processing" means chemical or physical operations on radioactive material including the mining, conversion, enrichment of fissile or fertile nuclear material and the reprocessing of spent fuel;
"protective measures" means measures, other than remedial measures, for the purpose of avoiding or reducing doses that might otherwise be received in an emergency exposure situation or an existing exposure situation;
"public exposure" means exposure of individuals, excluding any occupational or medical exposure;
"quality assurance" means all those planned and systematic actions necessary to provide adequate assurance that a structure, system, component or procedure will perform satisfactorily in compliance with agreed standards. Quality control is a part of quality assurance;
"quality control" means the set of operations (programming, coordinating, implementing) intended to maintain or to improve quality. It includes monitoring, evaluation and maintenance at required levels of all characteristics of performance of equipment that can be defined, measured, and controlled;
"radiation generator" means a device capable of generating ionising radiation, such as X-rays, neutrons, electrons or other charged particles;
"radiation protection expert" means an individual or, if provided for in the national legislation, a group of individuals having the knowledge, training and experience needed to give radiation protection advice in order to ensure the effective protection of individuals, and whose competence in this respect is recognised by the competent authority;
"radiation protection officer" means an individual who is technically competent in radiation protection matters relevant for a given type of practice to supervise or perform the implementation of the radiation protection arrangements;
"radiation source" means an entity that may cause exposure, such as by emitting ionising radiation or by releasing radioactive material;
"radioactive material" means material incorporating radioactive substances;
"radioactive source" means a radiation source incorporating radioactive material for the purpose of utilising its radioactivity;
"radioactive substance" means any substance that contains one or more radionuclides the activity or activity concentration of which cannot be disregarded from a radiation protection point of view;
"radioactive waste" means radioactive material in gaseous, liquid or solid form for which no further use is foreseen or considered by the Member State or by a legal or natural person whose decision is accepted by the Member State, and which is regulated as radioactive waste by a competent regulatory authority under the legislative and regulatory framework of the Member State;
"radiodiagnostic" means pertaining to in-vivo diagnostic nuclear medicine, medical diagnostic radiology using ionising radiation, and dental radiology;
"radiotherapeutic" means pertaining to radiotherapy, including nuclear medicine for therapeutic purposes;
"radon" means the radionuclide Rn-222 and its progeny, as appropriate;
"exposure to radon" means exposure to radon progeny;
"reference level" means in an emergency exposure situation or in an existing exposure situation, the level of effective dose or equivalent dose or activity concentration above which it is judged inappropriate to allow exposures to occur as a result of that exposure situation, even though it is not a limit that may not be exceeded;
"referrer" means a medical doctor, dentist or other health professional who is entitled to refer individuals for medical radiological procedures to a practitioner, in accordance with national requirements;
"registration" means permission granted in a document by the competent authority, or granted by national legislation, through a simplified procedure, to carry out a practice in accordance with conditions laid down in national legislation or specified by a competent authority for this type or class of practice;
"regulatory control" means any form of control or regulation applied to human activities for the enforcement of radiation protection requirements;
"remedial measures" means the removal of a radiation source or the reduction of its magnitude (in terms of activity or amount) or the interruption of exposure pathways or the reduction of their impact for the purposes of avoiding or reducing doses that might otherwise be received in an existing exposure situation;
"representative person" means an individual receiving a dose that is representative of the more highly exposed individuals in the population, excluding those individuals having extreme or rare habits;
"sealed source" means a radioactive source in which the radioactive material is permanently sealed in a capsule or incorporated in a solid form with the objective of preventing, under normal conditions of use, any dispersion of radioactive substances;
"storage" means the holding of radioactive material, including spent fuel, a radioactive source or radioactive waste, in a facility with the intention of retrieval;
"supervised area" means an area subject to supervision for the purpose of protection against ionising radiation;
"source container" means an assembly of components intended to guarantee the containment of a sealed source, where it is not an integral part of the source but is meant for shielding the source during its transport and handling;
"spacecraft" means a manned vehicle designed to operate at an altitude of more than 100 km above sea level;
"standard values and relationships" means values and relationships recommended in chapters 4 and 5 of ICRP Publication 116 for the estimation of doses from external exposure and chapter 1 of ICRP Publication 119 for the estimation of doses from internal exposure, including updates approved by Member States. Member State may approve the use of specific methods in specified cases relating to the physico-chemical properties of the radionuclide or other features of the exposure situation or of the exposed individual;
"thoron" means the radionuclide Rn-220 and its progeny, as appropriate;
"undertaking" means a natural or legal person who has legal responsibility under national law for carrying out a practice, or for a radiation source (including cases where the owner or holder of a radiation source does not conduct related human activities);
"unintended exposure" means medical exposure that is significantly different from the medical exposure intended for a given purpose.
CHAPTER III
SYSTEM OF RADIATION PROTECTION
Article 5
General principles of radiation protection
Member States shall establish legal requirements and an appropriate regime of regulatory control which, for all exposure situations, reflect a system of radiation protection based on the principles of justification, optimisation and dose limitation:
Justification: Decisions introducing a practice shall be justified in the sense that such decisions shall be taken with the intent to ensure that the individual or societal benefit resulting from the practice outweighs the health detriment that it may cause. Decisions introducing or altering an exposure pathway for existing and emergency exposure situations shall be justified in the sense that they should do more good than harm.
Optimisation: Radiation protection of individuals subject to public or occupational exposure shall be optimised with the aim of keeping the magnitude of individual doses, the likelihood of exposure and the number of individuals exposed as low as reasonably achievable taking into account the current state of technical knowledge and economic and societal factors. The optimisation of the protection of individuals subject to medical exposure shall apply to the magnitude of individual doses and be consistent with the medical purpose of the exposure, as described in Article 56. This principle shall be applied not only in terms of effective dose but also, where appropriate, in terms of equivalent doses, as a precautionary measure to allow for uncertainties as to health detriment below the threshold for tissue reactions.
Dose limitation: In planned exposure situations, the sum of doses to an individual shall not exceed the dose limits laid down for occupational exposure or public exposure. Dose limits shall not apply to medical exposures.
SECTION 1
Tools for optimisation
Article 6
Dose constraints for occupational, public, and medical exposure
Member States shall ensure that, where appropriate, dose constraints are established for the purpose of prospective optimisation of protection:
for occupational exposure, the dose constraint shall be established as an operational tool for optimisation by the undertaking under the general supervision of the competent authority. In the case of outside workers the dose constraint shall be established in cooperation between the employer and the undertaking.
for public exposure, the dose constraint shall be set for the individual dose that members of the public receive from the planned operation of a specified radiation source. The competent authority shall ensure that the constraints are consistent with the dose limit for the sum of doses to the same individual from all authorised practices.
for medical exposure, dose constraints shall apply only with regard to the protection of carers and comforters and volunteers participating in medical or biomedical research.
Article 7
Reference levels
SECTION 2
Dose limitation
Article 8
Age limit for exposed workers
Member States shall ensure that subject to Article 11(2), persons under 18 years of age may not be assigned to any work which would result in their being exposed workers.
Article 9
Dose limits for occupational exposure
In addition to the limits on effective dose laid down in paragraph 2, the following limits on equivalent dose shall apply:
the limit on the equivalent dose for the lens of the eye shall be 20 mSv in a single year or 100 mSv in any five consecutive years subject to a maximum dose of 50 mSv in a single year, as specified in national legislation.
the limit on the equivalent dose for the skin shall be 500 mSv in a year, this limit shall apply to the dose averaged over any area of 1 cm2, regardless of the area exposed;
the limit on the equivalent dose for the extremities shall be 500 mSv in a year.
Article 10
Protection of pregnant and breastfeeding workers
Article 11
Dose limits for apprentices and students
In addition to the limits on effective dose laid down in paragraph 2, the following limits on equivalent dose shall apply:
the limit on the equivalent dose for the lens of the eye shall be 15 mSv in a year;
the limit on the equivalent dose for the skin shall be 150 mSv in a year, averaged over any area of 1 cm2, regardless of the area exposed;
the limit on the equivalent dose for the extremities shall be 150 mSv in a year.
Article 12
Dose limits for public exposure
In addition to the dose limit referred to in paragraph 2, the following limits on the equivalent dose shall apply:
the limit on the equivalent dose for the lens of the eye shall be 15 mSv in a year;
the limit on the equivalent dose for the skin shall be 50 mSv in a year, averaged over any 1 cm2 area of skin, regardless of the area exposed.
Article 13
Estimation of the effective and equivalent dose
For the estimation of effective and equivalent doses, the appropriate standard values and relationships shall be used. For external radiation, the operational quantities defined in section 2.3 of ICRP Publication 116 shall be used.
CHAPTER IV
REQUIREMENTS FOR RADIATION PROTECTION EDUCATION, TRAINING AND INFORMATION
Article 14
General responsibilities for the education, training and provision of information
Article 15
Training of exposed workers and information provided to them
Member States shall require the undertaking to inform exposed workers on:
the radiation health risks involved in their work;
the general radiation protection procedures and precautions to be taken;
the radiation protection procedures and precautions connected with the operational and working conditions of both the practice in general and each type of workstation or work to which they may be assigned;
the relevant parts of the emergency response plans and procedures;
the importance of complying with the technical, medical and administrative requirements.
In the case of outside workers, their employer shall ensure that the information required in points (a), (b) and (e) is provided.
Article 16
Information and training of workers potentially exposed to orphan sources
Member States shall encourage the management of installations referred to in paragraph 1 to ensure that where workers in their installation may be confronted with a source, they are:
advised and trained in the visual detection of sources and their containers;
informed of basic facts about ionising radiation and its effects;
informed of and trained in the actions to be taken on site in the event of the detection or suspected detection of a source.
Article 17
Prior information and training for emergency workers
Article 18
Education, information and training in the field of medical exposure
For this purpose Member States shall ensure that appropriate curricula are established and shall recognise the corresponding diplomas, certificates or formal qualifications.
CHAPTER V
JUSTIFICATION AND REGULATORY CONTROL OF PRACTICES
SECTION 1
Justification and prohibition of practices
Article 19
Justification of practices
Article 20
Practices involving consumer products
Article 21
Prohibition of practices
Article 22
Practices involving the deliberate exposure of humans for non-medical imaging purposes
Member States shall ensure that special attention is given to the justification of practices involving non-medical imaging exposure, in particular:
all types of practices involving non-medical imaging exposure shall be justified before being generally accepted;
each particular application of a generally accepted type of practice shall be justified;
all individual non-medical imaging exposure procedures using medical radiological equipment shall be justified in advance, taking into account the specific objectives of the procedure and the characteristics of the individual involved;
the general and particular justification of practices involving non-medical imaging exposure, as specified in (a) and (b), may be subject to review;
circumstances warranting non-medical imaging exposures, without individual justification of each exposure, shall be subject to regular review.
Where a Member State has determined that a particular practice involving non-medical imaging exposure is justified, it shall ensure that:
the practice is subject to authorisation;
requirements for the practice, including criteria for individual implementation, are established by the competent authority, in cooperation with other relevant bodies and medical scientific societies, as appropriate;
for procedures using medical radiological equipment
relevant requirements identified for medical exposure as set out in Chapter VII are applied, including those for equipment, optimisation, responsibilities, training and special protection during pregnancy and the appropriate involvement of the medical physics expert;
where appropriate, specific protocols, consistent with the objective of the exposure and required image quality, are put in place;
where practicable, specific diagnostic reference levels are put in place;
for procedures not using medical radiological equipment, dose constraints are significantly below the dose limit for members of the public;
information is provided to and consent sought from the individual to be exposed, allowing for cases where the law enforcement authorities may proceed without consent of the individual according to national legislation;
SECTION 2
Regulatory control
Article 23
Identification of practices involving naturally-occurring radioactive material
Member States shall ensure the identification of classes or types of practice involving naturally–occurring radioactive material and leading to exposure of workers or members of the public which cannot be disregarded from a radiation protection point of view. Such identification shall be carried out by appropriate means taking into account industrial sectors listed in Annex VI.
Article 24
Graded approach to regulatory control
Article 25
Notification
Practices may be exempted from notification, as specified in Article 26.
Article 26
Exemption from notification
Member States may decide that justified practices involving the following do not need to be notified:
radioactive materials where the quantities of the activity involved do not exceed in total the exemption values set out in Table B, column 3, of Annex VII, or higher values that, for specific applications, are approved by the competent authority and satisfy the general exemption and clearance criteria set out in Annex VII; or
without prejudice to Article 25(4), radioactive materials where the activity concentrations do not exceed the exemption values set out in Table A of Annex VII, or higher values that, for specific applications, are approved by the competent authority and satisfy the general exemption and clearance criteria set out in Annex VII; or
apparatus containing a sealed source, provided that:
the apparatus is of a type approved by the competent authority;
conditions for recycling or disposal have been specified by the competent authority; or
any electrical apparatus provided that:
it is a cathode ray tube intended for the display of visual images, or other electrical apparatus operating at a potential difference not exceeding 30 kilo volt (kV), or it is of a type approved by the competent authority; and
Article 27
Registration or licensing
Member States shall require either registration or licensing of the following practices:
the operation of radiation generators or accelerators or radioactive sources for medical exposures or for non-medical imaging purposes;
the operation of radiation generators or accelerators, except electron microscopes, or radioactive sources for purposes not covered by point (a).
Article 28
Licensing
Member States shall require licensing for the following practices:
the deliberate administration of radioactive substances to persons and, in so far as the radiation protection of human beings is concerned, animals for the purpose of medical or veterinary diagnosis, treatment or research;
the operation and decommissioning of any nuclear facility and the exploitation and closure of uranium mines;
the deliberate addition of radioactive substances in the production or manufacture of consumer products or other products, including medicinal products, and the import of such products;
any practice involving a high-activity sealed source;
the operation, decommissioning and closure of any facility for the long term storage or disposal of radioactive waste, including facilities managing radioactive waste for this purpose;
practices discharging significant amounts of radioactive material with airborne or liquid effluent into the environment.
Article 29
Authorisation procedure
Article 30
Release from regulatory control
Materials for disposal, recycling or reuse may be released from regulatory control provided that the activity concentrations:
for solid material do not exceed the clearance levels set out in Table A of Annex VII; or
comply with specific clearance levels and associated requirements for specific materials or for materials originating from specific types of practices; these specific clearance levels shall be established in national legislation or by the national competent authority, following the general exemption and clearance criteria set out in Annex VII, and taking into account technical guidance provided by the Community.
CHAPTER VI
OCCUPATIONAL EXPOSURES
Article 31
Responsibilities
Without prejudice to paragraphs 1 and 2, Member States shall arrange for a clear allocation of responsibilities for the protection of workers in any exposure situation, to an undertaking, an employer or any other organisation, in particular for the protection of:
emergency workers;
workers involved in the remediation of contaminated land, buildings and other constructions;
workers who are exposed to radon at work, in the situation specified in Article 54(3).
This shall also apply to the protection of self-employed individuals and individuals who work on a voluntary basis.
Article 32
Operational protection of exposed workers
Member States shall ensure that the operational protection of exposed workers is based, in accordance with the relevant provisions of this Directive, on:
prior evaluation to identify the nature and magnitude of the radiological risk to exposed workers;
optimisation of radiation protection in all working conditions, including occupational exposures as a consequence of practices involving medical exposures;
classification of exposed workers into different categories;
control measures and monitoring relating to the different areas and working conditions, including, where necessary, individual monitoring;
medical surveillance;
education and training.
Article 33
Operational protection of apprentices and students
Article 34
Consultations with a radiation protection expert
Member States shall require undertakings to seek advice from a radiation protection expert within their areas of competence as outlined in Article 82, on the issues below that are relevant to the practice:
the examination and testing of protective devices and measuring instruments;
prior critical review of plans for installations from the point of view of radiation protection;
the acceptance into service of new or modified radiation sources from the point of view of radiation protection;
regular checking of the effectiveness of protective devices and techniques;
regular calibration of measuring instruments and regular checking that they are serviceable and correctly used.
Article 35
Arrangements in workplaces
Such arrangements shall be appropriate to the nature of the installations and sources and to the magnitude and nature of the risks.
For an undertaking operating aircraft where the effective dose to the crew from cosmic radiation is liable to exceed 6 mSv per year, the relevant requirements set out in this Chapter shall apply, allowing for the specific features of this exposure situation. Member States shall ensure that where the effective dose to the crew is liable to be above 1 mSv per year, the competent authority requires the undertaking to take appropriate measures, in particular:
to assess the exposure of the crew concerned;
to take into account the assessed exposure when organising working schedules with a view to reducing the doses of highly exposed crew;
to inform the workers concerned of the health risks their work involves and their individual dose.
to apply Article 10(1) to pregnant air crew.
Article 36
Classification of workplaces
Article 37
Controlled areas
Member States shall ensure that the minimum requirements for a controlled area are the following:
The controlled area shall be delineated and access to it shall be restricted to individuals who have received appropriate instructions and shall be controlled in accordance with written procedures provided by the undertaking. Wherever there is a significant risk of the spread of radioactive contamination, specific arrangements shall be made, including for the access and exit of individuals and goods and for monitoring contamination within the controlled area and, where appropriate, in the adjacent area.
Taking into account the nature and extent of radiological risks in the controlled area, radiological surveillance of the workplace shall be organised in accordance with the provisions of Article 39.
Signs indicating the type of area, the nature of the sources and their inherent risks shall be displayed.
Working instructions appropriate to the radiological risk associated with the sources and the operations involved shall be laid down.
The worker shall receive specific training in connection with the characteristics of the workplace and the activities.
The worker shall be provided with the appropriate personal protective equipment.
Article 38
Supervised areas
Member States shall ensure that the requirements for a supervised area are the following:
taking into account the nature and extent of radiological risks in the supervised area, radiological surveillance of the workplace shall be organised in accordance with the provisions of Article 39;
if appropriate, signs indicating the type of area, the nature of the sources and their inherent risks shall be displayed;
if appropriate, working instructions appropriate to the radiological risk associated with the sources and the operations involved shall be laid down.
Article 39
Radiological surveillance of the workplace
Member States shall ensure that the radiological surveillance of the workplace referred to in point (b) of Articles 37(1) and point (a) of Article 38(1) comprises, where appropriate:
the measurement of external dose rates, indicating the nature and quality of the radiation in question;
the measurement of the activity concentration in air and the surface density of contaminating radionuclides, indicating their nature and their physical and chemical states.
Article 40
Categorisation of exposed workers
Member States shall ensure that for the purposes of monitoring and surveillance, a distinction is made between two categories of exposed workers:
category A: those exposed workers who are liable to receive an effective dose greater than 6 mSv per year or an equivalent dose greater than 15 mSv per year for the lens of the eye or greater than 150 mSv per year for skin and extremities;
category B: those exposed workers who are not classified as category A workers.
Article 41
Individual monitoring
Article 42
Dose assessment in the case of accidental exposure
Member States shall ensure that in the case of accidental exposure, the undertaking is required to assess the relevant doses and their distribution in the body.
Article 43
Recording and reporting of results
For the purposes of paragraph 1, the following information on exposed workers shall be retained:
a record of the exposures measured or estimated, as the case may be, of individual doses pursuant to Articles 41, 42, 51, 52, 53 and, if decided by the Member State pursuant to Article 35(2), 54(3);
in the case of exposures as referred to in Articles 42, 52 and 53, the reports relating to the circumstances and the action taken;
the results of workplace monitoring used to assess individual doses where necessary.
Article 44
Access to the results of individual monitoring
The Member States shall require that the results of the individual monitoring set out in Articles 41, 42, 52, 53 and, if decided by the Member State pursuant to Article 35(2), 54(3) be:
made available to the competent authority, to the undertaking, and to the employer of outside workers;
made available to the worker concerned in accordance with paragraph 2;
submitted to the occupational health service in order for it to interpret the implications of the results for human health, as provided for in Article 45(2);
submitted to the data system for individual radiological monitoring established by the Member State in accordance with provisions set out in Annex X.
Article 45
Medical surveillance of exposed workers
Medical surveillance shall include:
a medical examination prior to employment or classification as a category A worker to determine the worker's fitness for a post as a category A worker for which the worker is being considered;
periodic reviews of health at least once a year, in order to determine whether the category A workers remain fit to perform their duties. The nature of these reviews, which can be performed as many times as the occupational health service considers necessary, shall depend on the type of work and on the individual worker's state of health.
Article 46
Medical classification
Member States shall ensure that the following medical classification is established with respect to fitness for work as a category A worker:
fit;
fit, subject to certain conditions;
unfit.
Article 47
Prohibition to employ or classify unfit workers
Member States shall ensure that no worker may be employed or classified for any period in a specific post as a category A worker if medical surveillance establishes that the worker is unfit for that specific post.
Article 48
Medical records
Article 49
Special medical surveillance
Article 50
Appeals
Member States shall lay down the procedure for appeal against the findings and decisions made pursuant to Articles 46, 47 and 49.
Article 51
Protection of outside workers
In particular, Member States shall ensure that, as a minimum requirement, the undertaking shall:
for category A workers entering controlled areas, check that the outside worker concerned has been passed as medically fit for the activities to be assigned to the worker;
check whether the categorisation of the outside worker is appropriate in relation to the doses liable to be received within the undertaking;
for entry into controlled areas, ensure that, in addition to the basic training in radiation protection the outside worker has received specific instructions and training in connection with the characteristics of the workplace and the conducted activities, in accordance with points (c) and (d) of Article 15(1);
for entry into supervised areas, ensure that the outside worker has received working instructions appropriate to the radiological risk associated with the sources and the operations involved, as required in point (c) of Article 38(1);
ensure that the outside worker has been issued with the necessary personal protective equipment;
ensure that the outside worker receives individual exposure monitoring appropriate to the nature of the activities, and any operational dosimetric monitoring that may be necessary;
ensure compliance with the system of protection as defined in Chapter III;
for entry into controlled areas, ensure or take all appropriate steps to ensure that after every activity the radiological data from individual exposure monitoring of each category A outside worker within the meaning of Annex X, Section B, point 2, are recorded.
Member States shall ensure that employers of outside workers ensure, either directly or through contractual agreements with the undertaking, that the radiation protection of their workers is in accordance with the relevant provisions of this Directive, in particular by:
ensuring compliance with the system of protection as defined in Chapter III;
ensuring that the information and training in the field of radiation protection referred to in points (a), (b) and (e) of Article 15(1), Article 15(2), (3) and (4) is provided.
guaranteeing that their workers are subject to appropriate assessment of exposure and, for category A workers, medical surveillance, under the conditions laid down in Articles 39 and 41 to 49;
ensuring that the radiological data from the individual exposure monitoring of each of their category A workers within the meaning of Annex X, Section B, point 1, are kept up to date in the data system for individual radiological monitoring referred to in point (d) of Article 44(1).
Article 52
Specially authorised exposures
Member States may decide that in exceptional circumstances evaluated case by case, excluding emergencies, the competent authority may, where a specific operation so requires, authorise individual occupational exposures of identified workers exceeding the dose limits set out in Article 9, provided that such exposures are limited in time, confined to certain working areas and within the maximum exposure levels defined for the particular case by the competent authority. The following conditions shall be taken into account:
only category A workers as defined in Article 40 or spacecraft crew may be subject to such exposures;
apprentices, students, pregnant workers, and, if there is a risk of intake or bodily contamination, breastfeeding workers, are excluded from such exposures;
the undertaking justifies such exposures in advance and thoroughly discuss them with the workers, their representatives, the occupational health service and the radiation protection expert;
information about the risks involved and the precautions to be taken during the operation are provided to the relevant workers in advance;
the workers have consented;
all doses relating to such exposures are separately recorded in the medical record referred to in Article 48 and the individual record referred to in Article 43.
Article 53
Emergency occupational exposure
For situations where the above condition is not feasible, the following conditions shall apply:
reference levels for emergency occupational exposure shall be set, in general below an effective dose of 100 mSv;
in exceptional situations, in order to save life, prevent severe radiation-induced health effects, or prevent the development of catastrophic conditions, a reference level for an effective dose from external radiation of emergency workers may be set above 100 mSv, but not exceeding 500 mSv.
Article 54
Radon in workplaces
Member States shall require that radon measurements are carried out:
in workplaces within the areas identified in accordance with Article 103(3), that are located on the ground floor or basement level, taking into account parameters contained in the national action plan as under point 2 of Annex XVIII, as well as
in specific types of workplaces identified in the national action plan taking into account point 3 of Annex XVIII.
CHAPTER VII
MEDICAL EXPOSURES
Article 55
Justification
Member States shall ensure that the principle defined in paragraph 1 is applied and in particular that:
new types of practices involving medical exposure are justified in advance before being generally adopted;
all individual medical exposures are justified in advance taking into account the specific objectives of the exposure and the characteristics of the individual involved.
if a type of practice involving medical exposure is not justified in general, a specific individual exposure of this type can be justified, where appropriate, in special circumstances, to be evaluated on a case-by-case basis and documented.
the referrer and the practitioner, as specified by Member States, seek, where practicable, to obtain previous diagnostic information or medical records relevant to the planned exposure and consider these data to avoid unnecessary exposure.
medical exposure for medical or biomedical research are examined by an ethics committee, set up in accordance with national procedures and/or by the competent authority;
specific justification for medical radiological procedures to be performed as part of a health screening programme are carried out by the competent authority in conjunction with appropriate medical scientific societies or relevant bodies.
the exposure of carers and comforters show a sufficient net benefit, taking into account the direct health benefits to a patient, the possible benefits to the carer / comforter and the detriment that the exposure might cause.
any medical radiological procedure on an asymptomatic individual, to be performed for the early detection of disease, is part of a health screening programme, or requires specific documented justification for that individual by the practitioner, in consultation with the referrer, following guidelines from relevant medical scientific societies and the competent authority. Special attention shall be given to the provision of information to the individual subject to medical exposure, as required by point (d) of Article 57(1).
Article 56
Optimisation
For all medical exposure of patients for radiotherapeutic purposes, exposures of target volumes shall be individually planned and their delivery appropriately verified taking into account that doses to non-target volumes and tissues shall be as low as reasonably achievable and consistent with the intended radiotherapeutic purpose of the exposure.
Member States shall ensure that for each medical or biomedical research project involving medical exposure:
the individuals concerned participate voluntarily;
these individuals are informed about the risks of exposure;
a dose constraint is established for individuals for whom no direct medical benefit is expected from exposure;
in the case of patients who voluntarily accept to undergo an experimental medical practice and who are expected to receive a diagnostic or therapeutic benefit from this practice, the dose levels concerned shall be considered on an individual basis by the practitioner and/or referrer prior to the exposure taking place.
Member States shall ensure that:
dose constraints are established for the exposure of carers and comforters, where appropriate;
appropriate guidance is established for the exposure of carers and comforters.
These instructions shall be handed out before leaving the hospital or clinic or a similar institution.
Article 57
Responsibilities
Member States shall ensure that:
any medical exposure takes place under the clinical responsibility of a practitioner;
the practitioner, the medical physics expert and those entitled to carry out practical aspects of medical radiological procedures are involved, as specified by Member States, in the optimisation process;
the referrer and the practitioner are involved, as specified by Member States, in the justification process of individual medical exposures;
wherever practicable and prior to the exposure taking place, the practitioner or the referrer, as specified by Member States, ensures that the patient or their representative is provided with adequate information relating to the benefits and risks associated with the radiation dose from the medical exposure. Similar information as well as relevant guidance shall be given to carers and comforters, in accordance with point (b) of Article 56(5).
Article 58
Procedures
Member States shall ensure that:
written protocols for every type of standard medical radiological procedure are established for each equipment for relevant categories of patients;
information relating to patient exposure forms part of the report of the medical radiological procedure;
referral guidelines for medical imaging, taking into account the radiation doses, are available to the referrers;
in medical radiological practices, a medical physics expert is appropriately involved, the level of involvement being commensurate with the radiological risk posed by the practice. In particular:
in radiotherapeutic practices other than standardised therapeutic nuclear medicine practices, a medical physics expert shall be closely involved;
in standardised therapeutical nuclear medicine practices as well as in radiodiagnostic and interventional radiology practices, involving high doses as referred to in point (c) of Article 61(1), a medical physics expert shall be involved;
for other medical radiological practices not covered by points (i) and (ii), a medical physics expert shall be involved, as appropriate, for consultation and advice on matters relating to radiation protection concerning medical exposure.
clinical audits are carried out in accordance with national procedures;
appropriate local reviews are undertaken whenever diagnostic reference levels are consistently exceeded and that appropriate corrective action is taken without undue delay.
Article 59
Training and recognition
Member States shall ensure that training and recognition requirements, as laid down in Articles 79, 14 and 18, are met for the practitioner, the medical physics expert and the individuals referred to in Article 57(2).
Article 60
Equipment
Member States shall ensure that:
all medical radiological equipment in use is kept under strict surveillance regarding radiation protection;
an up-to-date inventory of medical radiological equipment for each medical radiological installation is available to the competent authority;
appropriate quality assurance programmes and assessment of dose or verification of administered activity are implemented by the undertaking; and
acceptance testing is carried out before the first use of the equipment for clinical purposes, and performance testing is carried out thereafter on a regular basis, and after any maintenance procedure liable to affect the performance.
Member States shall ensure that:
the use of fluoroscopy equipment without a device to automatically control the dose rate, or without an image intensifier or equivalent device, is prohibited.
equipment used for external beam radiotherapy with a nominal beam energy exceeding 1 MeV has a device to verify key treatment parameters. Equipment installed prior to 6 February 2018 may be exempted from this requirement.
any equipment used for interventional radiology has a device or a feature informing the practitioner and those carrying out practical aspects of the medical procedures of quantity of radiation produced by the equipment during the procedure. Equipment installed prior to 6 February 2018 may be exempted from this requirement.
any equipment used for interventional radiology and computed tomography and any new equipment used for planning, guiding and verification purposes has a device or a feature informing the practitioner, at the end of the procedure, of relevant parameters for assessing the patient dose.
equipment used for interventional radiology and computed tomography has the capacity to transfer the information required under 3(d) to the record of the examination. Equipment installed prior to 6 February 2018 may be exempted from this requirement.
without prejudice to points (c), (d) and (e) of paragraph 3, new medical radiodiagnostic equipment producing ionising radiation has a device, or an equivalent means, informing the practitioner of relevant parameters for assessing the patient dose. Where appropriate, the equipment shall have the capacity to transfer this information to the record of the examination.
Article 61
Special practices
Member States shall ensure that appropriate medical radiological equipment, practical techniques and ancillary equipment is used in medical exposure:
of children;
as part of a health screening programme;
involving high doses to the patient, which may be the case in interventional radiology, nuclear medicine, computed tomography or radiotherapy.
Special attention shall be given to quality assurance programmes and the assessment of dose or verification of administered activity for these practices.
Article 62
Special protection during pregnancy and breastfeeding
Article 63
Accidental and unintended exposures
Member States shall ensure that:
all reasonable measures are taken to minimise the probability and magnitude of accidental or unintended exposures of individuals subject to medical exposure;
for radiotherapeutic practices the quality assurance programme includes a study of the risk of accidental or unintended exposures;
for all medical exposures the undertaking implements an appropriate system for the record keeping and analysis of events involving or potentially involving accidental or unintended medical exposures, commensurate with the radiological risk posed by the practice;
arrangements are made to inform the referrer and the practitioner, and the patient, or their representative, about clinically significant unintended or accidental exposures and the results of the analysis;
the undertaking declares as soon as possible to the competent authority the occurrence of significant events as defined by the competent authority;
the results of the investigation and the corrective measures to avoid such events are reported to the competent authority within the time period specified by the Member State;
mechanisms are in place for the timely dissemination of information, relevant to radiation protection in medical exposure, regarding lessons learned from significant events.
Article 64
Estimates of population doses
Member States shall ensure that the distribution of individual dose estimates from medical exposure for radiodiagnostic and interventional radiology purposes is determined, taking into consideration where appropriate the distribution by age and gender of the exposed.
CHAPTER VIII
PUBLIC EXPOSURES
SECTION 1
Protection of members of the public and long-term health protection in normal circumstances
Article 65
Operational protection of members of the public
Member States shall ensure that the operational protection of members of the public in normal circumstances from practices subject to licensing shall include, for relevant facilities, the following:
examination and approval of the proposed siting of the facility from a radiation protection point of view, taking into account relevant demographic, meteorological, geological, hydrological and ecological conditions;
acceptance into service of the facility subject to adequate protection being provided against any exposure or radioactive contamination liable to extend beyond the perimeter of the facility or radioactive contamination liable to extend to the ground beneath the facility;
examination and approval of plans for the discharge of radioactive effluents;
measures to control the access of members of the public to the facility.
The competent authority shall where appropriate establish authorised limits as part of the discharge authorisation and conditions for discharging radioactive effluents which shall:
take into account the results of the optimisation of radiation protection;
reflect good practice in the operation of similar facilities.
In addition, these discharge authorisations shall take into account, where appropriate, the results of a generic screening assessment based on internationally recognised scientific guidance, where such an assessment has been required by the Member State, to demonstrate that environmental criteria for long-term human health protection are met.
Article 66
Estimation of doses to the members of the public
For the realistic assessment of doses to the members of the public, the competent authority shall:
decide on a reasonable extent of surveys to be conducted and information to be taken into account in order to identify the representative person, taking into account the effective pathways for transmission of the radioactive substances;
decide on a reasonable frequency of monitoring of the relevant parameters as determined in point (a);
ensure that the estimates of doses to the representative person include:
assessment of the doses due to external radiation, indicating, where appropriate, the type of the radiation in question;
assessment of the intake of radionuclides, indicating the nature of the radionuclides and, where necessary, their physical and chemical states, and determination of the activity concentrations of these radionuclides in food and drinking water or other relevant environmental media;
assessment of the doses that the representative person, as identified in point (a), is liable to receive;
require records to be kept and be made available on request to all stakeholders relating to measurements of external exposure and contamination, estimates of intakes of radionuclides, and the results of the assessment of the doses received by the representative person.
Article 67
Monitoring of radioactive discharges
Article 68
Tasks for the undertaking
Member States shall require the undertaking to carry out the following tasks:
achieve and maintain an optimal level of protection of members of the public;
accept into service adequate equipment and procedures for measuring and assessing exposure of members of the public and radioactive contamination of the environment;
check the effectiveness and maintenance of equipment as referred to in point (b) and ensure the regular calibration of measuring instruments;
seek advice from a radiation protection expert in the performance of the tasks referred to in points (a), (b) and (c).
SECTION 2
Emergency exposure situations
Article 69
Emergency response
Member States shall ensure that provision is made for protective measures with regard to:
the radiation source, to reduce or stop the radiation, including the release of radionuclides;
the environment, to reduce the exposure to individuals resulting from radioactive substances through relevant pathways;
individuals, to reduce their exposure.
In the event of an emergency on or outside its territory, the Member State shall require:
the organisation of appropriate protective measures, taking account of the real characteristics of the emergency and in accordance with the optimised protection strategy as part of the emergency response plan, whereby the elements to be included in an emergency response plan are indicated in Section B of Annex XI;
the assessment and recording of the consequences of the emergency and of the effectiveness of the protective measures.
Article 70
Information to the members of the public likely to be affected in the event of an emergency
Article 71
Information to the members of the public actually affected in the event of an emergency
SECTION 3
Existing exposure situation
Article 72
Environmental monitoring programme
Member States shall ensure that an appropriate environmental monitoring programme is in place.
Article 73
Contaminated areas
Member States shall ensure that optimised protection strategies for managing contaminated areas shall include, where applicable, the following:
objectives, including long-term goals pursued by the strategy and corresponding reference levels, in accordance with Article 7;
delineation of the affected areas and identification of the affected members of the public;
consideration of the need for and extent of protective measures to be applied to the affected areas and members of the public;
consideration of the need to prevent or control access to the affected areas, or to impose restrictions on living conditions in these areas;
assessment of the exposure of different groups in the population and assessment of the means available to individuals for controlling their own exposure.
For areas with long-lasting residual contamination in which the Member State has decided to allow habitation and the resumption of social and economic activities, Member States shall ensure, in consultation with stakeholders, that arrangements are in place, as necessary, for the ongoing control of exposure with the aim of establishing living conditions that can be considered as normal, including:
establishment of appropriate reference levels;
establishment of an infrastructure to support continuing self-help protective measures in the affected areas, such as information provision, advice and monitoring;
if appropriate, remediation measures;
if appropriate, delineated areas.
Article 74
Indoor exposure to radon
Article 75
Gamma radiation from building materials
For building materials which are identified by the Member State as being of concern from a radiation protection point of view, taking into account the indicative list of materials set out in Annex XIII with regard to their emitted gamma radiation, Member States shall ensure that, before such materials are placed on the market:
the activity concentrations of the radionuclides specified in Annex VIII are determined, and that,
information to the competent authority on the results of measurements and the corresponding activity concentration index, as well as other relevant factors, as defined in Annex VIII, are provided if requested.
CHAPTER IX
GENERAL RESPONSIBILITIES OF MEMBER STATES AND COMPETENT AUTHORITIES AND OTHER REQUIREMENTS FOR REGULATORY CONTROL
SECTION 1
Institutional infrastructure
Article 76
Competent authority
Member States shall designate a competent authority to carry out tasks in accordance with this Directive. They shall ensure that the competent authority:
is functionally separate from any other body or organisation concerned with the promotion or utilisation of practices under this Directive, in order to ensure effective independence from undue influence on its regulatory function;
is given the legal powers and human and financial resources necessary to fulfil its obligations.
Article 77
Transparency
Member States shall ensure that information in relation to the justification of classes or types of practices, the regulation of radiation sources and of radiation protection is made available to undertakings, workers, members of the public, as well as patients and other individuals subject to medical exposure. This obligation includes ensuring that the competent authority provides information within its fields of competence. Information shall be made available in accordance with national legislation and international obligations, provided that this does not jeopardise other interests such as, inter alia, security, recognised in national legislation or international obligations.
Article 78
Information on equipment
Article 79
Recognition of services and experts
Member States shall ensure that arrangements are in place for the recognition of:
occupational health services;
dosimetry services;
radiation protection experts;
medical physics experts.
Member States shall ensure that the necessary arrangements are in place to ensure the continuity of expertise of these services and experts.
If appropriate, Member States may establish the arrangements for the recognition of radiation protection officers.
Article 80
Occupational health services
Member State shall ensure that occupational health services perform medical surveillance of exposed workers, in accordance with Chapter VI, with regard to their exposure to ionising radiation and their fitness for the tasks assigned to them involving work with ionising radiation.
Article 81
Dosimetry services
Member State shall ensure that dosimetry services determine internal or external doses to exposed workers subject to individual monitoring, in order to record the dose in cooperation with the undertaking and in the case of outside workers, the employer, and where relevant the occupational health service.
Article 82
Radiation protection expert
The advice of the radiation protection expert shall cover, where relevant, but not be limited to, the following:
optimisation and establishment of appropriate dose constraints;
plans for new installations and the acceptance into service of new or modified radiation sources in relation to any engineering controls, design features, safety features and warning devices relevant to radiation protection;
categorisation of controlled and supervised areas;
classification of workers;
workplace and individual monitoring programmes and related personal dosimetry;
appropriate radiation monitoring instrumentation;
quality assurance;
environmental monitoring programme;
arrangements for radioactive waste management;
arrangements for prevention of accidents and incidents;
preparedness and response in emergency exposure situations;
training and retraining programmes for exposed workers;
investigation and analysis of accidents and incidents and appropriate remedial actions;
employment conditions for pregnant and breastfeeding workers;
preparation of appropriate documentation such as prior risk assessments and written procedures;
Article 83
Medical physics expert
Member States shall ensure that depending on the medical radiological practice, the medical physics expert takes responsibility for dosimetry, including physical measurements for evaluation of the dose delivered to the patient and other individuals subject to medical exposure, give advice on medical radiological equipment, and contribute in particular to the following:
optimisation of the radiation protection of patients and other individuals subject to medical exposure, including the application and use of diagnostic reference levels;
the definition and performance of quality assurance of the medical radiological equipment;
acceptance testing of medical radiological equipment;
the preparation of technical specifications for medical radiological equipment and installation design;
the surveillance of the medical radiological installations;
the analysis of events involving, or potentially involving, accidental or unintended medical exposures;
the selection of equipment required to perform radiation protection measurements;
the training of practitioners and other staff in relevant aspects of radiation protection;
Article 84
Radiation protection officer
Depending on the nature of the practice, the tasks of the radiation protection officer in assisting the undertaking, may include the following:
ensuring that work with radiation is carried out in accordance with the requirements of any specified procedures or local rules;
supervise implementation of the programme for workplace monitoring;
maintaining adequate records of all radiation sources;
carrying out periodic assessments of the condition of the relevant safety and warning systems;
supervise implementation of the personal monitoring programme;
supervise implementation of the health surveillance programme;
providing new workers with an appropriate introduction to local rules and procedures;
giving advice and comments on work plans;
establishing work plans;
providing reports to the local management;
participating in the arrangements for prevention, preparedness and response for emergency exposure situations;
information and training of exposed workers;
liaising with the radiation protection expert.
SECTION 2
Control of radioactive sources
Article 85
General requirements for unsealed sources
Article 86
General requirements for sealed sources
Article 87
Requirements for control of high-activity sealed sources
Member States shall ensure that, before issuing authorisation for practices involving a high-activity sealed source:
adequate arrangements have been made for the safe management and control of sources, including when they become disused sources. Such arrangements may provide for the transfer of disused sources to the supplier or their placement in a disposal or storage facility or an obligation for the manufacturer or the supplier to receive them;
adequate provision, by way of a financial security or any other equivalent means appropriate for the source in question, has been made for the safe management of sources when they become disused sources, including the case where the undertaking becomes insolvent or ceases its activities.
Article 88
Specific requirements for licensing of high-activity sealed sources
In addition to the general licensing requirements set out in Chapter V, Member States shall ensure that the licence for a practice involving a high-activity sealed source includes, but does not have to be limited to:
responsibilities;
minimum staff competencies, including information and training;
minimum performance criteria for the source, source container and additional equipment;
requirements for emergency procedures and communication links;
work procedures to be followed;
maintenance of equipment, sources and containers;
adequate management of disused sources, including agreements regarding the transfer, if appropriate, of disused sources to a manufacturer, a supplier, another authorised undertaking or a waste disposal or storage facility.
Article 89
Record keeping by the undertaking
Member States shall require that the records for high-activity sealed sources include the information set out in Annex XIV and that the undertaking provides the competent authority with an electronic or written copy of all or part of these records upon request and at least under the following conditions:
without undue delay, at the time of the establishment of such records, which shall be as soon as is reasonably practicable after the source is acquired;
at intervals to be determined by Member States;
if the situation indicated on the information sheet has changed;
without undue delay upon the closure of the records for a specific source when the undertaking no longer holds this source, whereby the name of the undertaking or waste disposal or storage facility to which the source is transferred shall be included;
without undue delay upon the closure of such records when the undertaking no longer holds any sources.
The undertaking's records shall be available for inspection by the competent authority.
Article 90
Record keeping by the competent authority
Member States shall ensure that the competent authority keeps records of any undertaking authorised to perform practices with high-activity sealed sources and of the high-activity sealed sources held. These records shall include the radionuclide involved, the activity at the time of manufacture or, if this activity is not known, the activity at the time of the first placing on the market or at the time the undertaking acquired the source, and the type of source. The competent authority shall keep the records up to date, taking transfers of the sources and other factors into account.
Article 91
Control of high-activity sealed sources
SECTION 3
Orphan sources
Article 92
Detection of orphan sources
Member States shall ensure that arrangements are made for:
raising general awareness of the possible occurrence of orphan sources and associated hazards; and
issuing guidance for persons who suspect or have knowledge of the presence of an orphan source on informing the competent authority and on the actions to be taken.
Article 93
Metal contamination
Article 94
Recovery, management, control and disposal of orphan sources
The campaigns may include the financial participation of Member States in the costs of recovering, managing, controlling and disposing of the sources and may also include surveys of historical records of authorities and of undertakings, such as research institutes, material testing institutes or hospitals.
Article 95
Financial security for orphan sources
Member States shall ensure that a financial security system or other equivalent means is established to cover intervention costs relating to the recovery of orphan sources and which may result from implementation of Article 94.
SECTION 4
Significant events
Article 96
Notification and recording of significant events
Member States shall require the undertaking to:
implement, as appropriate, a recording and analysis system of significant events involving or potentially involving accidental or unintended exposures;
promptly notify the competent authority of the occurrence of any significant event resulting or liable to result in the exposure of an individual beyond the operational limits or conditions of operation specified in authorising requirements with regard to occupational or public exposure or as defined by the competent authority for medical exposure, including the results of the investigation and the corrective measures to avoid such events.
SECTION 5
Emergency exposure situations
Article 97
Emergency management system
Article 98
Emergency preparedness
Article 99
International cooperation
SECTION 6
Existing exposure situations
Article 100
Programmes on existing exposure situations
Article 101
Establishment of strategies
Each strategy shall contain
the objectives pursued;
appropriate reference levels, taking into account the reference levels laid down in Annex I.
Article 102
Implementation of strategies
Member States shall ensure that those responsible for the implementation of a strategy shall regularly:
evaluate the available remedial and protective measures for achieving the objectives and the efficiency of planned and implemented measures;
provide information to exposed populations on the potential health risks and on the available means for reducing their exposure;
provide guidance for the management of exposures at individual or local level;
with regard to activities that involve naturally occurring radioactive material and are not managed as planned exposure situations, provide information on appropriate means for monitoring concentrations and exposures and for taking protective measures.
Article 103
Radon action plan
SECTION 7
System of enforcement
Article 104
Inspections
Article 105
Enforcement
Member States shall ensure that the competent authority has the power to require any individual or legal person to take action to remedy deficiencies and prevent their recurrence or to withdraw, where appropriate, authorisation when the results of a regulatory inspection or another regulatory assessment indicate that the exposure situation is not in compliance with the provisions adopted pursuant to this Directive.
CHAPTER X
FINAL PROVISIONS
Article 106
Transposition
Article 107
Repeal
Directives 89/618/Euratom, 90/641/Euratom, 96/29/Euratom, 97/43/Euratom, and 2003/122/Euratom are repealed with effect from 6 February 2018.
References to the repealed Directives shall be construed as references to this Directive and shall be read in accordance with the correlation table in Annex XIX.
Article 108
Entry into force
The Directive shall enter into force on the twentieth day following that of its publication in the Official Journal of the European Union.
Article 109
Addressees
This Directive is addressed to the Member States.
ANNEX I
Reference levels for public exposure as referred to in Articles 7 and 101
1. Without prejudice to reference levels set for equivalent doses, reference levels expressed in effective doses shall be set in the range of 1 to 20 mSv per year for existing exposure situations and 20 to 100 mSv (acute or annual) for emergency exposure situations.
2. In specific situations, a reference level below ranges referred to in point 1 may be considered, in particular:
a reference level below 20 mSv may be set in an emergency exposure situation where appropriate protection can be provided without causing a disproportionate detriment from the corresponding countermeasures or an excessive cost;
a reference level below 1 mSv per year may be set, where appropriate, in an existing exposure situation for specific source-related exposures or pathways of exposure.
3. For the transition from an emergency exposure situation to an existing exposure situation, appropriate reference levels shall be set, in particular upon the termination of long-term countermeasures such as relocation.
4. The reference levels set shall take account of the features of prevailing situations as well as societal criteria, which may include the following:
for exposures below or equal to 1 mSv per year, general information on the level of exposure, without specific consideration of individual exposures;
in the range up to or equal to 20 mSv per year, specific information to enable individuals to manage their own exposure, if possible;
in the range up to or equal to 100 mSv per year, assessment of individual doses and specific information on radiation risks and on available actions to reduce exposures.
ANNEX II
Radiation and tissue weighting factors as referred to in points (25) and (33) of Article 4
A. Radiation weighting factors
|
Radiation type |
wR |
|
Photons |
1 |
|
Electrons and muons |
1 |
|
Protons and charged pions |
2 |
|
Alpha particles, fission fragments, heavy ions |
20 |
|
Neutrons, En < 1 MeV |
|
|
Neutrons, 1 MeV ≤ En ≤ 50 MeV |
|
|
Neutrons, En > 50 MeV |
|
|
Note: All values relate to the radiation incident on the body or, for internal radiation sources, emitted from the incorporated radionuclide(s). |
|
B. Tissue weighting factors
|
Tissue |
wT |
|
Bone-marrow (red) |
0,12 |
|
Colon |
0,12 |
|
Lung |
0,12 |
|
Stomach |
0,12 |
|
Breast |
0,12 |
|
Remainder tissues (*1) |
0,12 |
|
Gonads |
0,08 |
|
Bladder |
0,04 |
|
Oesophagus |
0,04 |
|
Liver |
0,04 |
|
Thyroid |
0,04 |
|
Bone surface |
0,01 |
|
Brain |
0,01 |
|
Salivary glands |
0,01 |
|
Skin |
0,01 |
|
(*1)
The wT for the remainder tissues (0,12) applies to the arithmetic mean dose of the 13 organs and tissues for each sex listed below. Remainder tissues: adrenals, extrathoracic (ET) region, gall bladder, heart, kidneys, lymphatic nodes, muscle, oral mucosa, pancreas, prostate (male), small intestine, spleen, thymus, uterus/cervix (female). |
|
ANNEX III
Activity values defining high-activity sealed sources as referred to in point (41) of Article 4
For radionuclides not listed in the table below, the relevant activity is identical to the D-value defined in the IAEA publication Dangerous quantities of radioactive material (D-values), (EPR-D-VALUES 2006).
|
Radionuclide |
Activity (TBq) |
|
Am-241 |
6 × 10–2 |
|
Am-241/Be-9 (1) |
6 × 10–2 |
|
Cf-252 |
2 × 10–2 |
|
Cm-244 |
5 × 10–2 |
|
Co-60 |
3 × 10–2 |
|
Cs-137 |
1 × 10–1 |
|
Gd-153 |
1 × 100 |
|
Ir-192 |
8 × 10–2 |
|
Pm-147 |
4 × 101 |
|
Pu-238 |
6 × 10–2 |
|
Pu-239/Be-9 (1) |
6 × 10–2 |
|
Ra-226 |
4 × 10–2 |
|
Se-75 |
2 × 10–1 |
|
Sr-90 (Y-90) |
1 × 100 |
|
Tm-170 |
2 × 101 |
|
Yb-169 |
3 × 10–1 |
|
(1)
The activity given is that of the alpha-emitting radionuclide |
|
ANNEX IV
Justification of new classes or types of practices involving consumer products as referred to in Article 20
A. Any undertaking intending to manufacture or import into a Member State consumer products for which the intended use is likely to lead to a new class or type of practice, shall provide the competent authority of this Member State with all relevant information, as to the:
intended use of the product;
technical characteristics of the product;
in the case of products containing radioactive substances, information as to their means of fixation;
dose rates at relevant distances for the use of the product, including dose rates at a distance of 0,1 m from any accessible surface;
expected doses to regular users of the product.
B. The competent authority shall examine that information and in particular assess whether:
the performance of the consumer product justifies its intended use;
the design is adequate in order to minimise exposures in normal use and the likelihood and consequences of misuse or accidental exposures, or whether there should be conditions imposed on the technical and physical characteristics of the product;
the product is adequately designed to meet the exemption criteria, and, where applicable, is of an approved type and does not necessitate specific precautions for disposal when no longer in use;
the product is appropriately labelled and suitable documentation is provided to the consumer with instructions for proper use and disposal.
ANNEX V
Indicative list of practices involving non-medical imaging exposure as referred to in Article 22
Practices using medical radiological equipment:
Radiological health assessment for employment purposes;
Radiological health assessment for immigration purposes;
Radiological health assessment for insurance purposes;
Radiological evaluation of the physical development of children and adolescents with a view to a career in sports, dancing, etc.;
Radiological age assessment;
Use of ionising radiation for the identification of concealed objects within the human body.
Practices not using medical radiological equipment:
Use of ionising radiation for detection of concealed objects on or attached to the human body;
Use of ionising radiation for detection of concealed humans as part of cargo screening;
Practices involving the use of ionising radiation for legal or security purposes.
ANNEX VI
List of industrial sectors involving naturally-occurring radioactive material as referred to in Article 23
When applying Article 23 the following list of industrial sectors involving naturally-occurring radioactive material, including research and relevant secondary processes, shall be taken into account:
ANNEX VII
Exemption and clearance criteria as referred to in Articles 24, 26 and 30
1. Exemption
Practices may be exempted from notification either directly, on the basis of compliance with exemption levels (activity values (in Bq) or activity concentration values (in kBq kg-1)) laid down in section 2, or on the basis of higher values that, for specific applications, are established by the competent authority, satisfying the general exemption and clearance criteria set out in section 3. Practices subject to notification may be exempted from authorisation by law or general administrative act, or through an ad-hoc regulatory decision, on the basis of the information provided in conjunction with the notification of the practice and in line with general exemption criteria set out in section 3.
2. Exemption and clearance levels
(a) The total activity values (in Bq) for exemption apply to the total activity involved in a practice and are laid down in column 3 of Table B for artificial radionuclides and for some naturally-occurring radionuclides used in consumer products. For other practices involving naturally-occurring radionuclides, such values are, in general, not applicable.
(b) The exempt activity concentration values (in kBq kg-1) for the materials involved in the practice are laid down in Table A, Part 1, for artificial radionuclides, and in Table A, Part 2, for naturally-occurring radionuclides. The values in Table A, Part 1, are given for individual radionuclides, where applicable, including short-lived radionuclides in equilibrium with the parent nuclide, as indicated. The values in Table A, Part 2, apply to all radionuclides in the decay chain of U-238 or Th-232, but for segments of the decay chain, which are not in equilibrium with the parent radionuclide, higher values may be applied.
(c) The concentration values in Table A, Part 1, or in Table A, Part 2, also apply to the clearance of solid materials for reuse, recycling, conventional disposal or incineration. Higher values may be defined for specific materials or specific pathways, taking Community guidance into account, including, where appropriate, additional requirements, in terms of surface activity or monitoring requirements.
(d) For mixtures of artificial radionuclides, the weighted sum of nuclide-specific activities or concentrations (for various radionuclides contained in the same matrix) divided by the corresponding exemption value shall be less than unity. Where appropriate, this condition can be verified on the basis of best estimates of the composition of the radionuclide mix. The values in Table A, Part 2, apply individually to each parent nuclide. Some elements in the decay chain, e.g. Po-210 or Pb-210, may warrant the use of higher values taking Community guidance into account.
(e) The values in Table A, Part 2, may not be used to exempt the incorporation into building materials of residues from industries processing naturally-occurring radioactive material. For this purpose, compliance with the provisions of Article 75 shall be verified. The values laid down in Table B, column 3, apply to the total inventory of radioactive substances held by a person or undertaking as part of a specific practice at any point in time. However, the competent authority may apply these values to smaller entities or packages, for instance to exempt the transport or storage of exempted consumer products, if the general exemption criteria in section 3 are satisfied.
3. General exemption and clearance criteria
(a) The general criteria for the exemption of practices from notification or authorisation or for the clearance of materials from authorised practices are as follows:
the radiological risks to individuals caused by the practice are sufficiently low, as to be of no regulatory concern; and
the type of practice has been determined to be justified; and
the practice is inherently safe.
(b) Practices involving small amounts of radioactive substances or low activity concentrations, comparable to the exemption values laid down in Table A or Table B are deemed to fulfil criterion (iii).
(c) Practices involving amounts of radioactive substances or activity concentrations below the exemption values laid down in Table A, Part 1, or Table B, are deemed to comply with criterion (i) without further consideration. This is also the case for the values in Table A, Part 2, with the exception of the recycling of residues in building materials or the case of specific exposure pathways, for instance, drinking water.
(d) In the case of moderate amounts of material, as specified by Member States for specific types of practice, the activity concentration values laid down in Table B, column 2, may be used instead of the values laid down in Table A, Part 1, for the purpose of exemption from authorisation.
(e) For the purpose of exemption from notification or for the purpose of clearance, where amounts of radioactive substances or activity concentrations do not comply with the values laid down in Table A or Table B, an assessment shall be made in the light of the general criteria (i) to (iii) above. For compliance with the general criterion (i), it shall be demonstrated that workers should not be classified as exposed workers, and the following criteria for the exposure of members of the public are met in all feasible circumstances:
For the purpose of exemption from authorisation, less restrictive dose criteria may be applied.
TABLE A
Activity concentration values for exemption or clearance of materials which can be applied by default to any amount and to any type of solid material
TABLE A PART 1
Artificial radionuclides
|
Radionuclide |
Activity concentration (kBq kg-1) |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
H-3 |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Be-7 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
C-14 |
1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
F-18 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Na-22 |
0,1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Na-24 |
1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Si-31 |
1 000 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
P-32 |
1 000 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
P-33 |
1 000 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
S-35 |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cl-36 |
1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cl-38 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
K-42 |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
K-43 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ca-45 |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ca-47 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Sc-46 |
0,1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Sc-47 |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Sc-48 |
1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
V-48 |
1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cr-51 |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Mn-51 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Mn-52 |
1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Mn-52 m |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Mn-53 |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Mn-54 |
0,1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Mn-56 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Fe-52 () |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Fe-55 |
1 000 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Fe-59 |
1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Co-55 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Co-56 |
0,1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Co-57 |
1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Co-58 |
1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Co-58 m |
10 000 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Co-60 |
0,1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Co-60 m |
1 000 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Co-61 |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Co-62 m |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ni-59 |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ni-63 |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ni-65 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cu-64 |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Zn-65 |
0,1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Zn-69 |
1 000 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Zn-69 m () |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ga-72 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ge-71 |
10 000 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
As-73 |
1 000 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
As-74 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
As-76 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
As-77 |
1 000 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Se-75 |
1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Br-82 |
1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Rb-86 |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Sr-85 |
1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Sr-85 m |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Sr-87 m |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Sr-89 |
1 000 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Sr-90 () |
1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Sr-91 () |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Sr-92 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Y-90 |
1 000 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Y-91 |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Y-91 m |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Y-92 |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Y-93 |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Zr-93 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Zr-95 () |
1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Zr-97 () |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Nb-93 m |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Nb-94 |
0,1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Nb-95 |
1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Nb-97 () |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Nb-98 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Mo-90 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Mo-93 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Mo-99 () |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Mo-101 () |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Tc-96 |
1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Tc-96 m |
1 000 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Tc-97 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Tc-97 m |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Tc-99 |
1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Tc-99 m |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ru-97 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ru-103 () |
1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ru-105 () |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ru-106 () |
0,1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Rh-103 m |
10 000 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Rh-105 |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Pd-103 () |
1 000 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Pd-109 () |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ag-105 |
1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ag-110 m () |
0,1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ag-111 |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cd-109 () |
1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cd-115 () |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cd-115 m () |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
In-111 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
In-113 m |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
In-114 m () |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
In-115 m |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Sn-113 () |
1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Sn-125 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Sb-122 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Sb-124 |
1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Sb-125 () |
0,1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Te-123 m |
1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Te-125 m |
1 000 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Te-127 |
1 000 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Te-127 m () |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Te-129 |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Te-129 m () |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Te-131 |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Te-131 m () |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Te-132 () |
1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Te-133 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Te-133 m |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Te-134 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
I-123 |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
I-125 |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
I-126 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
I-129 |
0,01 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
I-130 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
I-131 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
I-132 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
I-133 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
I-134 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
I-135 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cs-129 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cs-131 |
1 000 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cs-132 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cs-134 |
0,1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cs-134 m |
1 000 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cs-135 |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cs-136 |
1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cs-137 () |
0,1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cs-138 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ba-131 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ba-140 |
1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
La-140 |
1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ce-139 |
1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ce-141 |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ce-143 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ce-144 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Pr-142 |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Pr-143 |
1 000 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Nd-147 |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Nd-149 |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Pm-147 |
1 000 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Pm-149 |
1 000 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Sm-151 |
1 000 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Sm-153 |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Eu-152 |
0,1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Eu-152 m |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Eu-154 |
0,1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Eu-155 |
1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Gd-153 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Gd-159 |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Tb-160 |
1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Dy-165 |
1 000 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Dy-166 |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ho-166 |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Er-169 |
1 000 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Er-171 |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Tm-170 |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Tm-171 |
1 000 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Yb-175 |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Lu-177 |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Hf-181 |
1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ta-182 |
0,1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
W-181 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
W-185 |
1 000 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
W-187 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Re-186 |
1 000 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Re-188 |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Os-185 |
1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Os-191 |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Os-191 m |
1 000 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Os-193 |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ir-190 |
1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ir-192 |
1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ir-194 |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Pt-191 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Pt-193 m |
1 000 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Pt-197 |
1 000 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Pt-197 m |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Au-198 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Au-199 |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Hg-197 |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Hg-197 m |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Hg-203 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Tl-200 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Tl-201 |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Tl-202 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Tl-204 |
1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Pb-203 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Bi-206 |
1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Bi-207 |
0,1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Po-203 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Po-205 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Po-207 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
At-211 |
1 000 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ra-225 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ra-227 |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Th-226 |
1 000 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Th-229 |
0,1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Pa-230 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Pa-233 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
U-230 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
U-231 () |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
U-232 () |
0,1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
U-233 |
1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
U-236 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
U-237 |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
U-239 |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
U-240 () |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Np-237 () |
1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Np-239 |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Np-240 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Pu-234 |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Pu-235 |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Pu-236 |
1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Pu-237 |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Pu-238 |
0,1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Pu-239 |
0,1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Pu-240 |
0,1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Pu-241 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Pu-242 |
0,1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Pu-243 |
1 000 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Pu-244 () |
0,1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Am-241 |
0,1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Am-242 |
1 000 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Am-242 m () |
0,1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Am-243 () |
0,1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cm-242 |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cm-243 |
1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cm-244 |
1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cm-245 |
0,1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cm-246 |
0,1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cm-247 () |
0,1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cm-248 |
0,1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Bk-249 |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cf-246 |
1 000 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cf-248 |
1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cf-249 |
0,1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cf-250 |
1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cf-251 |
0,1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cf-252 |
1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cf-253 |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cf-254 |
1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Es-253 |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Es-254 () |
0,1 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Es-254 m () |
10 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Fm-254 |
10 000 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Fm-255 |
100 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
(1)
Parent radionuclides, and their progeny whose dose contributions are taken into account in the dose calculation (thus requiring only the exemption level of the parent radionuclide to be considered), are listed in the following table.
|
|||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
For radionuclides not listed in Table A, Part 1 the competent authority shall assign appropriate values for the quantities and concentrations of activity per unit mass where the need arises. Values thus assigned shall be complementary to those in Table A, Part 1.
TABLE A PART 2
Naturally occurring radionuclides
Values for exemption or clearance for naturally occurring radionuclides in solid materials in secular equilibrium with their progeny:
|
Natural radionuclides from the U-238 series |
1 kBq kg-1 |
|
Natural radionuclides from the Th-232 series |
1 kBq kg-1 |
|
K-40 |
10 kBq kg-1 |
TABLE B
Total activity values for exemption (column 3) and exemption values for the activity concentration in moderate amounts of any type of material (column 2)
|
Radionuclide |
Activity concentration (kBq kg-1) |
Activity (Bq) |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
H-3 |
1 × 106 |
1 × 109 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Be-7 |
1 × 103 |
1 × 107 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
C-14 |
1 × 104 |
1 × 107 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
O-15 |
1 × 102 |
1 × 109 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
F-18 |
1 × 101 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Na-22 |
1 × 101 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Na-24 |
1 × 101 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Si-31 |
1 × 103 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
P-32 |
1 × 103 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
P-33 |
1 × 105 |
1 × 108 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
S-35 |
1 × 105 |
1 × 108 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cl-36 |
1 × 104 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cl-38 |
1 × 101 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ar-37 |
1 × 106 |
1 × 108 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ar-41 |
1 × 102 |
1 × 109 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
K-40 (1) |
1 × 102 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
K-42 |
1 × 102 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
K-43 |
1 × 101 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ca-45 |
1 × 104 |
1 × 107 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ca-47 |
1 × 101 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Sc-46 |
1 × 101 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Sc-47 |
1 × 102 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Sc-48 |
1 × 101 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
V-48 |
1 × 101 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cr-51 |
1 × 103 |
1 × 107 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Mn-51 |
1 × 101 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Mn-52 |
1 × 101 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Mn-52 m |
1 × 101 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Mn-53 |
1 × 104 |
1 × 109 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Mn-54 |
1 × 101 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Mn-56 |
1 × 101 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Fe-52 |
1 × 101 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Fe-55 |
1 × 104 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Fe-59 |
1 × 101 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Co-55 |
1 × 101 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Co-56 |
1 × 101 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Co-57 |
1 × 102 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Co-58 |
1 × 101 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Co-58 m |
1 × 104 |
1 × 107 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Co-60 |
1 × 101 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Co-60 m |
1 × 103 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Co-61 |
1 × 102 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Co-62 m |
1 × 101 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ni-59 |
1 × 104 |
1 × 108 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ni-63 |
1 × 105 |
1 × 108 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ni-65 |
1 × 101 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cu-64 |
1 × 102 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Zn-65 |
1 × 101 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Zn-69 |
1 × 104 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Zn-69 m |
1 × 102 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ga-72 |
1 × 101 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ge-71 |
1 × 104 |
1 × 108 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
As-73 |
1 × 103 |
1 × 107 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
As-74 |
1 × 101 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
As-76 |
1 × 102 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
As-77 |
1 × 103 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Se-75 |
1 × 102 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Br-82 |
1 × 101 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Kr-74 |
1 × 102 |
1 × 109 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Kr-76 |
1 × 102 |
1 × 109 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Kr-77 |
1 × 102 |
1 × 109 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Kr-79 |
1 × 103 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Kr-81 |
1 × 104 |
1 × 107 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Kr-83 m |
1 × 105 |
1 × 1012 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Kr-85 |
1 × 105 |
1 × 104 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Kr-85 m |
1 × 103 |
1 × 1010 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Kr-87 |
1 × 102 |
1 × 109 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Kr-88 |
1 × 102 |
1 × 109 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Rb-86 |
1 × 102 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Sr-85 |
1 × 102 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Sr-85 m |
1 × 102 |
1 × 107 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Sr-87 m |
1 × 102 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Sr-89 |
1 × 103 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Sr-90 () |
1 × 102 |
1 × 104 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Sr-91 |
1 × 101 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Sr-92 |
1 × 101 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Y-90 |
1 × 103 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Y-91 |
1 × 103 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Y-91 m |
1 × 102 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Y-92 |
1 × 102 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Y-93 |
1 × 102 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Zr-93 () |
1 × 103 |
1 × 107 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Zr-95 |
1 × 101 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Zr-97 () |
1 × 101 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Nb-93 m |
1 × 104 |
1 × 107 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Nb-94 |
1 × 101 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Nb-95 |
1 × 101 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Nb-97 |
1 × 101 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Nb-98 |
1 × 101 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Mo-90 |
1 × 101 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Mo-93 |
1 × 103 |
1 × 108 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Mo-99 |
1 × 102 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Mo-101 |
1 × 101 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Tc-96 |
1 × 101 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Tc-96 m |
1 × 103 |
1 × 107 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Tc-97 |
1 × 103 |
1 × 108 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Tc-97 m |
1 × 103 |
1 × 107 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Tc-99 |
1 × 104 |
1 × 107 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Tc-99 m |
1 × 102 |
1 × 107 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ru-97 |
1 × 102 |
1 × 107 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ru-103 |
1 × 102 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ru-105 |
1 × 101 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ru-106 () |
1 × 102 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Rh-103 m |
1 × 104 |
1 × 108 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Rh-105 |
1 × 102 |
1 × 107 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Pd-103 |
1 × 103 |
1 × 108 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Pd-109 |
1 × 103 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ag-105 |
1 × 102 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ag-108 m |
1 × 101 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ag-110 m |
1 × 101 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ag-111 |
1 × 103 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cd-109 |
1 × 104 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cd-115 |
1 × 102 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cd-115 m |
1 × 103 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
In-111 |
1 × 102 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
In-113 m |
1 × 102 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
In-114 m |
1 × 102 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
In-115 m |
1 × 102 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Sn-113 |
1 × 103 |
1 × 107 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Sn-125 |
1 × 102 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Sb-122 |
1 × 102 |
1 × 104 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Sb-124 |
1 × 101 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Sb-125 |
1 × 102 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Te-123 m |
1 × 102 |
1 × 107 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Te-125 m |
1 × 103 |
1 × 107 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Te-127 |
1 × 103 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Te-127 m |
1 × 103 |
1 × 107 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Te-129 |
1 × 102 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Te-129 m |
1 × 103 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Te-131 |
1 × 102 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Te-131 m |
1 × 101 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Te-132 |
1 × 102 |
1 × 107 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Te-133 |
1 × 101 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Te-133 m |
1 × 101 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Te-134 |
1 × 101 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
I-123 |
1 × 102 |
1 × 107 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
I-125 |
1 × 103 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
I-126 |
1 × 102 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
I-129 |
1 × 102 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
I-130 |
1 × 101 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
I-131 |
1 × 102 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
I-132 |
1 × 101 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
I-133 |
1 × 101 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
I-134 |
1 × 101 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
I-135 |
1 × 101 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Xe-131 m |
1 × 104 |
1 × 104 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Xe-133 |
1 × 103 |
1 × 104 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Xe-135 |
1 × 103 |
1 × 1010 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cs-129 |
1 × 102 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cs-131 |
1 × 103 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cs-132 |
1 × 101 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cs-134 m |
1 × 103 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cs-134 |
1 × 101 |
1 × 104 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cs-135 |
1 × 104 |
1 × 107 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cs-136 |
1 × 101 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cs-137 () |
1 × 101 |
1 × 104 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cs-138 |
1 × 101 |
1 × 104 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ba-131 |
1 × 102 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ba-140 () |
1 × 101 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
La-140 |
1 × 101 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ce-139 |
1 × 102 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ce-141 |
1 × 102 |
1 × 107 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ce-143 |
1 × 102 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ce-144 () |
1 × 102 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Pr-142 |
1 × 102 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Pr-143 |
1 × 104 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Nd-147 |
1 × 102 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Nd-149 |
1 × 102 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Pm-147 |
1 × 104 |
1 × 107 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Pm-149 |
1 × 103 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Sm-151 |
1 × 104 |
1 × 108 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Sm-153 |
1 × 102 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Eu-152 |
1 × 101 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Eu-152 m |
1 × 102 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Eu-154 |
1 × 101 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Eu-155 |
1 × 102 |
1 × 107 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Gd-153 |
1 × 102 |
1 × 107 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Gd-159 |
1 × 103 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Tb-160 |
1 × 101 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Dy-165 |
1 × 103 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Dy-166 |
1 × 103 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ho-166 |
1 × 103 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Er-169 |
1 × 104 |
1 × 107 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Er-171 |
1 × 102 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Tm-170 |
1 × 103 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Tm-171 |
1 × 104 |
1 × 108 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Yb-175 |
1 × 103 |
1 × 107 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Lu-177 |
1 × 103 |
1 × 107 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Hf-181 |
1 × 101 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ta-182 |
1 × 101 |
1 × 104 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
W-181 |
1 × 103 |
1 × 107 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
W-185 |
1 × 104 |
1 × 107 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
W-187 |
1 × 102 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Re-186 |
1 × 103 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Re-188 |
1 × 102 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Os-185 |
1 × 101 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Os-191 |
1 × 102 |
1 × 107 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Os-191 m |
1 × 103 |
1 × 107 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Os-193 |
1 × 102 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ir-190 |
1 × 101 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ir-192 |
1 × 101 |
1 × 104 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ir-194 |
1 × 102 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Pt-191 |
1 × 102 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Pt-193 m |
1 × 103 |
1 × 107 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Pt-197 |
1 × 103 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Pt-197 m |
1 × 102 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Au-198 |
1 × 102 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Au-199 |
1 × 102 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Hg-197 |
1 × 102 |
1 × 107 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Hg-197 m |
1 × 102 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Hg-203 |
1 × 102 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Tl-200 |
1 × 101 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Tl-201 |
1 × 102 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Tl-202 |
1 × 102 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Tl-204 |
1 × 104 |
1 × 104 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Pb-203 |
1 × 102 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Pb-210 () |
1 × 101 |
1 × 104 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Pb-212 () |
1 × 101 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Bi-206 |
1 × 101 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Bi-207 |
1 × 101 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Bi-210 |
1 × 103 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Bi-212 () |
1 × 101 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Po-203 |
1 × 101 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Po-205 |
1 × 101 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Po-207 |
1 × 101 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Po-210 |
1 × 101 |
1 × 104 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
At-211 |
1 × 103 |
1 × 107 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Rn-220 () |
1 × 104 |
1 × 107 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Rn-222 () |
1 × 101 |
1 × 108 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ra-223 () |
1 × 102 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ra-224 () |
1 × 101 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ra-225 |
1 × 102 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ra-226 () |
1 × 101 |
1 × 104 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ra-227 |
1 × 102 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ra-228 () |
1 × 101 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Ac-228 |
1 × 101 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Th-226 () |
1 × 103 |
1 × 107 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Th-227 |
1 × 101 |
1 × 104 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Th-228 () |
1 × 100 |
1 × 104 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Th-229 () |
1 × 100 |
1 × 103 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Th-230 |
1 × 100 |
1 × 104 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Th-231 |
1 × 103 |
1 × 107 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Th-234 () |
1 × 103 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Pa-230 |
1 × 101 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Pa-231 |
1 × 100 |
1 × 103 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Pa-233 |
1 × 102 |
1 × 107 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
U-230 |
1 × 101 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
U-231 |
1 × 102 |
1 × 107 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
U-232 () |
1 × 100 |
1 × 103 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
U-233 |
1 × 101 |
1 × 104 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
U-234 |
1 × 101 |
1 × 104 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
U-235 () |
1 × 101 |
1 × 104 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
U-236 |
1 × 101 |
1 × 104 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
U-237 |
1 × 102 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
U-238 () |
1 × 101 |
1 × 104 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
U-239 |
1 × 102 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
U-240 |
1 × 103 |
1 × 107 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
U-240 () |
1 × 101 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Np-237 () |
1 × 100 |
1 × 103 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Np-239 |
1 × 102 |
1 × 107 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Np-240 |
1 × 101 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Pu-234 |
1 × 102 |
1 × 107 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Pu-235 |
1 × 102 |
1 × 107 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Pu-236 |
1 × 101 |
1 × 104 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Pu-237 |
1 × 103 |
1 × 107 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Pu-238 |
1 × 100 |
1 × 104 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Pu-239 |
1 × 100 |
1 × 104 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Pu-240 |
1 × 100 |
1 × 103 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Pu-241 |
1 × 102 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Pu-242 |
1 × 100 |
1 × 104 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Pu-243 |
1 × 103 |
1 × 107 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Pu-244 |
1 × 100 |
1 × 104 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Am-241 |
1 × 100 |
1 × 104 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Am-242 |
1 × 103 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Am-242 m () |
1 × 100 |
1 × 104 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Am-243 () |
1 × 100 |
1 × 103 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cm-242 |
1 × 102 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cm-243 |
1 × 100 |
1 × 104 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cm-244 |
1 × 101 |
1 × 104 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cm-245 |
1 × 100 |
1 × 103 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cm-246 |
1 × 100 |
1 × 103 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cm-247 |
1 × 100 |
1 × 104 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cm-248 |
1 × 100 |
1 × 103 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Bk-249 |
1 × 103 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cf-246 |
1 × 103 |
1 × 106 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cf-248 |
1 × 101 |
1 × 104 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cf-249 |
1 × 100 |
1 × 103 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cf-250 |
1 × 101 |
1 × 104 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cf-251 |
1 × 100 |
1 × 103 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cf-252 |
1 × 101 |
1 × 104 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cf-253 |
1 × 102 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Cf-254 |
1 × 100 |
1 × 103 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Es-253 |
1 × 102 |
1 × 105 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Es-254 |
1 × 101 |
1 × 104 |
||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
|
Es-254 m |
1 × 102 |
1 × 106 |
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Fm-254 |
1 × 104 |
1 × 107 |
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Fm-255 |
1 × 103 |
1 × 106 |
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(1)
Potassium salts in quantities less than 1 000 kg are exempted.
(2)
Parent radionuclides, and their progeny whose dose contributions are taken into account in the dose calculation (thus requiring only the exemption level of the parent radionuclide to be considered), are listed in the following:
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ANNEX VIII
Definition and use of the activity concentration index for the gamma radiation emitted by building materials as referred to in Article 75
For the purposes of Article 75(2), for identified types of building materials, the activity concentrations of primordial radionuclides Ra-226, Th-232 (or its decay product Ra-228) and K-40 shall be determined.
The activity concentration index I is given by the following formula:
where CRa226, CTh232 and CK40 are the activity concentrations in Bq/kg of the corresponding radionuclides in the building material.
The index relates to the gamma radiation dose, in excess of typical outdoor exposure, in a building constructed from a specified building material. The index applies to the building material, not to its constituents except when those constituents are building materials themselves and are separately assessed as such. For application of the index to such constituents, in particular residues from industries processing naturally-occurring radioactive material recycled into building materials, an appropriate partitioning factor needs to be applied. The activity concentration index value of 1 can be used as a conservative screening tool for identifying materials that may cause the reference level laid down in Article 75(1) to be exceeded. The calculation of dose needs to take into account other factors such as density, thickness of the material as well as factors relating to the type of building and the intended use of the material (bulk or superficial).
ANNEX IX
Indicative list of information for licence applications as referred to in Article 29
Responsibilities and organisational arrangements for protection and safety.
Staff competences, including information and training.
Design features of the facility and of radiation sources.
Anticipated occupational and public exposures in normal operation.
Safety assessment of the activities and the facility in order to:
identify ways in which potential exposures or accidental and unintended medical exposures could occur;
estimate, to the extent practicable, the probabilities and magnitude of potential exposures;
assess the quality and extent of protection and safety provisions, including engineering features, as well as administrative procedures;
define the operational limits and conditions of operation.
Emergency procedures.
Maintenance, testing, inspection and servicing so as to ensure that the radiation source and the facility continue to meet the design requirements, operational limits and conditions of operation throughout their lifetime.
Management of radioactive waste and arrangements for the disposal of such waste, in accordance with applicable regulatory requirements.
Management of disused sources.
Quality assurance.
ANNEX X
Data system for individual radiological monitoring as referred to in Articles 43, 44 and 51
GENERAL PROVISIONS
The data system for individual radiological monitoring established by a Member State may be realised either as a network or as a national dose register. This data system may include the issuance of individual radiological monitoring documents for outside workers.
1. Any data system of the Member States for individual radiological monitoring of exposed workers shall comprise the following sections:
particulars concerning the worker's identity;
particulars concerning the medical surveillance of the worker;
particulars concerning the undertaking of the worker and, in the case of an outside worker, the employer of the worker;
the results of the individual monitoring of the exposed worker.
2. The competent authorities of the Member States shall take the measures necessary to prevent any forgery or misuse of, or tampering with, the data system for individual radiological monitoring.
A. Data to be included in the data system for individual radiological monitoring
3. Data on the worker's identity shall include the worker's:
surname;
first name;
sex;
date of birth;
nationality; and
unique identification number.
4. Data on the undertaking shall include the name, address and unique identification number of the undertaking.
5. Data on the employment of the worker shall include:
the name, address and unique identification number of the employer;
the starting date of individual monitoring; and where available, the end date;
the categorisation of the worker in accordance with Article 40.
6. The results of the individual monitoring of the exposed worker shall include the official dose record (year; effective dose in mSv; in the event of non-uniform exposure, equivalent doses in the different parts of the body in mSv; and in the event of an intake of radionuclides, the committed effective dose in mSv);
B. Data on outside workers to be supplied via the data system for individual radiological monitoring
1. Before the start of any activity, the employer of the outside worker shall supply the following data to the undertaking via the data system for individual radiological monitoring:
data on the employment of the outside worker in accordance with Section A, point 5;
data on the medical surveillance of the worker shall include:
the medical classification of the worker in accordance with Article 46 (fit; fit, subject to certain conditions; unfit);
information on any restrictions on working with radiation;
the date of the last periodic health review; and
the period of validity of the result.
the results of the outside worker's individual exposure monitoring in accordance with Section A, point 6, and at least for the last five calendar years including the current year.
2. The following data shall be recorded or have been recorded by the undertaking in the data system for individual radiological monitoring after the end of any activity:
the period covered by the activity;
an estimate of any effective dose received by the outside worker (for the period covered by the activity);
in the event of non-uniform exposure, an estimate of the equivalent doses in the different parts of the body;
in the event of an intake of radionuclides, an estimate of the intake or the committed effective dose.
C. Provisions concerning the individual radiological monitoring document
1. Member States may decide to issue an individual radiological monitoring document for every outside worker.
2. The document shall be non-transferable.
3. Member States shall take the measures necessary to prevent a worker from being issued with more than one valid individual monitoring document at the same time.
4. In addition to the information required in Part A and Part B, the document shall include the name and address of the issuing body and the issuing date.
ANNEX XI
Emergency management systems and emergency response plans as referred to in Articles 69, 97 and 98
A. Elements to be included in an emergency management system
1. Assessment of potential emergency exposure situations and associated public and emergency occupational exposures;
2. Clear allocation of the responsibilities of persons and organisations having a role in preparedness and response arrangements;
3. Establishment of emergency response plans at appropriate levels and related to a specific facility or human activity;
4. Reliable communications and efficient and effective arrangements for cooperation and coordination at the installation and at appropriate national and international levels;
5. Health protection of emergency workers;
6. Arrangements for the provision of prior information and training for emergency workers and all other persons with duties or responsibilities in emergency response, including regular exercises;
7. Arrangements for individual monitoring or assessment of individual doses of emergency workers and the recording of doses;
8. Public information arrangements;
9. Involvement of stakeholders;
10. Transition from an emergency exposure situation to an existing exposure situation including recovery and remediation.
B. Elements to be included in an emergency response plan
For emergency preparedness:
Reference levels for public exposure, taking into account the criteria laid down in Annex I;
Reference levels for emergency occupational exposure taking into account Article 53.
Optimised protection strategies for members of the public who may be exposed, for different postulated events and related scenarios;
Predefined generic criteria for particular protective measures;
Default triggers or operational criteria such as observables and indicators of on-scene conditions;
Arrangements for prompt coordination between organisations having a role in emergency preparedness and response and with all other Member States and with third countries which may be involved or are likely to be affected;
Arrangements for the emergency response plan to be reviewed and revised to take account of changes or lessons learned from exercises and events.
Arrangements shall be established in advance to revise these elements, as appropriate during an emergency exposure situation, to accommodate the prevailing conditions as these evolve throughout the response.
For emergency response:
The response to an emergency exposure situation shall be undertaken through the timely implementation of preparedness arrangements, including but not limited to:
Promptly implementing protective measures, if possible, before any exposure occurs;
Assessing the effectiveness of strategies and implemented actions and adjusting them as appropriate to the prevailing situation;
Comparing the doses against the applicable reference level, focusing on those groups whose doses exceed the reference level;
Implementing further protection strategies, as necessary, based on prevailing conditions and available information.
ANNEX XII
Information to members of the public about health protection measures to be applied and steps to be taken in the event of an emergency as referred to in Articles 70 and 71
A. Prior information to the members of the public likely to be affected by an emergency
1. Basic facts about radioactivity and its effects on human beings and on the environment;
2. The various types of emergency covered and their consequences for the public and the environment;
3. Emergency measures envisaged to alert, protect and assist the public in the event of an emergency;
4. Appropriate information on action to be taken by the public in the event of an emergency.
B. Information to be provided to the affected members of the public in the event of an emergency
1. On the basis of the emergency response plan previously drawn up in the Member States, the members of the public actually affected in the event of an emergency shall rapidly and regularly receive:
information on the type of emergency which has occurred and, where possible, its characteristics (e.g. its origin, extent and probable development);
advice on protection, which, depending on the type of emergency, may:
cover the following: restrictions on the consumption of certain foodstuffs and water likely to be contaminated, simple rules on hygiene and decontamination, recommendations to stay indoors, distribution and use of protective substances, evacuation arrangements;
be accompanied, where necessary, by special warnings for certain groups of the members of the public;
announcements recommending cooperation with instructions or requests by the competent authority.
2. If the emergency is preceded by a pre-alarm phase, the members of the public likely to be affected shall already receive information and advice during that phase, such as:
an invitation to the members of the public concerned to tune in to relevant communication channels;
preparatory advice to establishments with particular collective responsibilities;
recommendations to occupational groups particularly affected.
3. This information and advice shall be supplemented, if time permits, by a reminder of the basic facts about radioactivity and its effects on human beings and on the environment.
ANNEX XIII
Indicative list of types of building materials considered with regard to their emitted gamma radiation as referred to in Article 75
1. Natural materials
Alum-shale.
Building materials or additives of natural igneous origin, such as:
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2. |
Materials incorporating residues from industries processing naturally-occurring radioactive material, such as: fly ash;
phosphogypsum;
phosphorus slag;
tin slag;
copper slag;
red mud (residue from aluminium production);
residues from steel production
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ANNEX XIV
Information to be provided in the records for high-activity sealed sources (HASS) as referred to in Article 89