Draft implementing decree on radiation protection and security of radionuclide sources (319 pages, in English; 307 pages, in Czech)

Draft implementing decree on radiation protection and security of radionuclide sources (319 pages, in English; 307 pages, in Czech)

Based on the authorising provisions in Act No 263/2016, the draft implementing decree governs:· the list of changes influencing radiation protection, radiation situation monitoring and emergency management of a category III workplace and category IV workplace;· a list of construction materials;· samples of registration applications;· a list and content of the documentation for the activity to be registered;· requirements for the content of documentation for licensed activities;· a list of quantities and facts relevant to radiation protection;· the scope, method and time of monitoring, measuring, assessing, reviewing and recording of quantities and facts relevant to radiation protection and the period for which the information thereon needs to be kept;· the scope, method of and deadlines for the delivery of information on quantities and facts important for radiation protection to the State Office for Nuclear Safety;· the scope, method and duration for which recorded documents on sources of ionising radiation shall be archived, and the deadlines for their delivery to the State Office for Nuclear Safety;· exposure of a patient considered to be erroneous for the purposes of defining a radiological event;· radionuclide activity at which a sealed radionuclide source is a high-activity source;· criteria for classifying sources of ionising radiation into categories;· the method of classification of radionuclide sources in security categories;· the criteria for classifying workplaces in the appropriate category;· the rules for classifying staff into category A or B;· exposure limit values and the method of managing them;· reference levels;· the method of application of the reference levels;· procedures used when optimising radiation protection, including the method of determining the dose optimisation limits;· the value and method of application of the exemption level;· the scope and frequency of tests performed pursuant to § 68(1)(f) of the Atomic Act;· the scope and frequency of operating stability tests performed by registered persons;· the rules for determining the scope and frequency of operating stability tests performed by licence holders;· the persons performing operating stability tests;· the persons ensuring the fulfilment of the obligations under § 68(1)(g) of the Atomic Act;· the evaluation procedure of operating stability tests and the method of dealing with the results thereof, including the method and duration for which the results are to be kept;· the criteria for evaluating long-term stability testing and the rules for eliminating defects detected by this testing, and the method of setting a deadline for the removal of these defects;· the scope and content of information provided under § 68(1)(n) of the Atomic Act and the method of providing said information;· the scope and method of continuous training for exposed workers, the method of verifying their knowledge and the frequency and method of documenting continuous training;· the scope and method of radiation protection assurance for the activity performed;· the types of sources of ionising radiation for which inventory checks shall be performed, the scope, method and frequency of inventory checks and the scope of results to be forwarded to the State Office for Nuclear Safety;· the methods of evidencing leak tightness of sealed radionuclide sources;· a list of changes connected with radiation protection, radiation situation monitoring and handling of radiological emergencies at a workplace with a source of ionising radiation;· the scope and method of documenting and reporting to the State Office for Nuclear Safety modifications related to radiation protection, radiation situation monitoring and radiological emergency management in a workplace with a source of ionising radiation;· the scope and method of completing the decommissioning of a category III workplace or a category IV workplace;· the job description of the person responsible for radiation protection of the registered person;· the procedures for ensuring radiation protection by registered persons when using sources of ionising radiation;· the scope and method of retaining records on sources of ionising radiation and forwarding them to the State Office for Nuclear Safety;· the scope and method of performance of the activities of a supervising person;· the category of exposed workers in the case of a supervising person;· the scope and method of performance of the activities of a person directly supervising radiation protection;· the method of classifying persons directly supervising radiation protection in the categories of exposed workers;· the scope and method of performing activities by a specialised radiation protection unit ensuring continuous surveillance of radiation protection at an energy-generating nuclear installation;· the scope and method of delineating a controlled area;· the scope of restrictions on entry into the controlled area;· the conditions for the performance of work in a controlled area;· the requirements for documenting the operation of a controlled area;· requirements regarding the documents connected with the operation of a controlled area;· the scope and method of delineating a supervised area;· the method of radiation protection assurance in a supervised area;· the requirements for documenting the operation of a supervised area;· the conditions for the safe operation of a workplace with a source of ionising radiation with regard to the type of the source of ionising radiation;· the clearance level for workplaces in which activities involving radiation are conducted, and the conditions under which they are considered exceeded;· the scope and method of delineating a supervised area in a temporary workplace;· the method of assurance of radiation protection of the general public, workers and the area surrounding the temporary workplace;· the scope and method of reporting to the State Office for Nuclear Safety the performance of activities in a emporary workplace;· requirements connected with personal monitoring of a radiation protection officer;· the procedures for evaluation of the quantities measured in the context of monitoring;· the rules for equipping exposed workers of category A with personal dosimeters and the handling thereof, as well as the duration of their evaluation;· the way in which the results of personal monitoring are provided to a radiation protection officer;· the rules for issuing individual radiological monitoring documents, the deadline for the submission of applications and the validity duration for said documents;· the rules for handling the individual radiological monitoring document;· a specimen of the individual radiological monitoring document for outside workers;· the scope and method of updating the information in the individual radiological monitoring document;· the rules for the appointment of a representative person and the medical assessment of his/her radiation exposure;· the content of the optimisation study for establishing the authorised limit of exposure of the representative person;· the content of records on non-medical exposure kept by the licence holder and by the registered person;· the national diagnostic reference levels;· the content of records under § 84(4) and (5) of the Atomic Act;· the scope and method of transmitting data on determining the distribution of medical exposure doses among the general public;· the requirements for sources of ionising radiation used in medical exposure and workplace equipment for x-ray diagnostics and radiotherapy;· the method of therapeutic or diagnostic application of radionuclides;· the conditions for the release of a patient after therapeutic or diagnostic application of radionuclides;· the cases in which patients shall be provided with written instructions on safe behaviour after therapeutic or diagnostic application of radionuclides;· the classification of radiological events according to their seriousness and the procedures in case of their occurrence;· the procedures for the case of a radiological event or a case in which a radiological event could have arisen had the causes not been detected and eliminated in good time;· the period for which the records of investigations and records of the measures taken under § 87(3) shall be retained, as well as the content thereof;· the scope and the period for the provision of information about serious radiological events;· the radiation protection assurance requirements for mining, treating or processing radioactive minerals;· the method of identifying and marking a high-activity source and its accessories;· a list of workplaces using a material with increased content of natural radionuclides;· the method, scope and frequency of the measurements to determine workers individual doses, the method of establishing workers individual doses and the scope and method of recording-keeping of workers individual doses;· the scope and content of information about the workplace to be reported to the State Office for Nuclear Safety, including the identification data of the operator of the workplace and the frequency with which said information is reported;· the level which, when exceeded, radiation protection optimisation shall be ensured in workplaces using materials with an increased content of natural radionuclide;· the scope, method and frequency of measurements and evaluation of the radionuclide content of a radioactive substance discharged from the workplace;· the method of record-keeping of the results of the measurements of the radionuclide content of radioactive substances discharged from the workplace, and the frequency with which said results are reported to the State Office for Nuclear Safety;· the content of internal regulations for the management of radioactive substances discharged from the workplace;· the clearance level for workplaces with potentially increased exposure to a natural source of radiation, and the onditions under which they are considered exceeded;· the conditions for classifying workplaces located on an underground or first ground floor of a building as workplaces with potentially increased exposure to radon;· the scope, method and frequency of performing the measurements to establish the effective doses to workers in the workplace, and the rules for establishing a worker's effective dose;· the scope, method and duration of performing the measurements to establish the effective doses to workers in the workplace;· the scope and content of the information about the workplace to be reported to the State Office for Nuclear Safety, including the identification data of the operator of the workplace and the frequency with which said information is reported to the State Office for Nuclear Safety;· the method of determining the building site radon index;· the criteria for the preparation and evaluation of measures intended to reduce the level of indoor exposure to natural sources of radiation;· the level of annual average radon activity concentration in the air which, when exceeded, owners of buildings with residential rooms or rooms intended to be occupied by persons shall take measures reducing the level of exposure;· maximum permissible value of radon activity concentration in drinking water for public use and for making bottled water available on the market;· the reference level for natural radionuclide content in drinking water for public use and for making bottled water available on the market;· the scope, frequency and method of systematic measurement and evaluation of the natural radionuclide content of water;· the scope and method of record-keeping of the results of measurements and other data, including the identification data of a water supplier and a producer and supplier of bottled water, and the frequency with which said results are reported to the State Office for Nuclear Safety;· the reference level for construction materials;· the method of calculating and the value of the activity concentration index for construction materials;· the scope and method of systematic measurement and evaluation of the natural radionuclide content of building materials;· the scope and method of record-keeping of the results of measurements and other data, including the identification data of a producer and supplier of construction materials, and the frequency with which said results are reported to the State Office for Nuclear Safety;· the conditions for the introduction and withdrawal of, and the requirements for, protective action;· the method of informing emergency workers about the risks associated with response actions and the method of providing evidence of voluntary participation in a response action;· basic characteristics of personal protective equipment and accessories for emergency workers;· the period for which the records and data referred to in § 104(5)(a), (b), (c) and (g) of the Atomic Act shall be retained;· the scope and time of forwarding to the State Office for Nuclear Safety of the data on the magnitude of exposure in response actions obtained from individual monitoring;· the requirements regarding the method of ensuring security of radionuclide sources, including radionuclide sources of security categories 1 to 3.