What is Decree No. 184 / 1997 Coll.?

Decree of the State Office for Nuclear Safety No. 184 / 1997 Coll., on requirements for radiation protection — Decree of the State Office for Nuclear Safety on radiation protection requirements.

When it became Decree No. 184 / 1997 Coll. effectiveness?

Decree No. 184 / 1997 Coll. became effective 19.08.1997.

Is Decree No. 184 / 1997 Coll. still valid?

Yes, Decree No. 184 / 1997 Coll. is still valid and effective.

How many times was it Decree No. 184 / 1997 Coll. amended?

Decree No. 184 / 1997 Coll. has 2 time versions of the text.

Decree No. 184 / 1997 Coll. - Decree of the State Office for Nuclear S...

184

DECLARATION

State Office for Nuclear Security

of 24 July 1997

on radiation protection requirements

According to § 47 (7) for the implementation of § 2 (c) and (o), § 4 (4), (5), (6) and (10), § 6 (2), § 7 (2), § 8 (1), § 9 (1) (i), § 13 (3) (d), § 17 (1) (d), § 18 (1) (a) and (c), § 22 (e) and § 24 (4) of Act No. 18 / 1997 Coll., on the peaceful use of nuclear energy and ionising radiation (Atomic Act) and on the amendment and addition of certain laws (hereinafter "the Act '):

ČÁST PRVNÍ

INTRODUCTORY AND GENERAL PROVISIONS

Subject matter

§ 1

(1) The Order provides for:

(a) the level of radionuclide content or pollution by which substances or articles are radionuclide radionuclides according to § 2 (a) above. (c) point 1 of the Act;

(b) the level of radionuclide content or pollution by which materials, substances and articles may be used outside the workplace with sources of ionising radiation, discharge into water or air or otherwise put into the environment;

(c) criteria for the distribution of sources of ionising radiation;

(d) technical and organisational requirements and indicative values to demonstrate a reasonably achievable level of exposure and a procedure to demonstrate that level otherwise;

(e) exposure limits.

(2) This Decree also provides for details of the manner and extent of radiation protection in the activities leading to exposure, in the interventions to reduce natural exposure and in the interventions to reduce radiation accidents, in particular by:

(a) specify the extent and manner of treatment of the source of ionising radiation for which authorisation is required and adapt the details for ensuring radiation protection in the different ways of handling the source of ionising radiation;

(b) provide for details of the treatment of radioactive waste, the placing of radionuclides in the environment and certain other activities leading to exposure, including details of the conditions of medical exposure and indicative values for such exposure;

(c) lay down technical and organisational conditions for the safe operation of sources of ionising radiation and workplaces with them, including details of the definition of the controlled zone and the classification of workplaces with sources of ionising radiation;

(d) define the quantities, parameters and facts relevant to radiation protection, determine the scope of their monitoring, measurement, evaluation, verification, recording, registration and transmission to the Office of the State for Nuclear Security (the Office),

(e) determine the scope and manner of the documentation approved by the Authority for the authorisation of the treatment of sources of ionising radiation or the management of radioactive waste;

(f) establish indicative values for decision-making on measures to reduce natural exposure, including criteria for assessing the benefits of the proposed measures, and indicative values for assessing the exposure of persons as a result of the occurrence of radon and its transformation products in the internal air of buildings;

(g) establish values for the content of natural radionuclides in building materials and delivered water, where construction materials may not be put into circulation and water delivered to public pipelines, the scope of the register of systematic measurement of natural radionuclides in manufactured building materials and water supplied and the way in which the results of the Authority are reported;

(h) establish indicative values and details of the rules for taking measures to prevent or reduce exposure in a radiation accident.

§ 2

For the purposes of this decree:

(a) by radionuclide - the type of atoms having the same number of protons and the same number of neutrons, the same energy status and subject to spontaneous change in the composition or state of the atomic nuclei;

b) natural radionuclide - radionuclide, which in nature originated or originates spontaneously, without human intervention,

(c) natural irradiation - irradiation [§ 2 (b) of the Act] from natural radionuclides or other spontaneously without the intervention of humans produced sources of ionising radiation, except where such sources are deliberately and knowingly used;

d) internal irradiation - exposure of a person from radionuclides occurring in the body of that person, generally as a result of the intake of radionuclides by ingestion or inhalation;

(e) by external exposure - exposure of persons from sources of ionising radiation found outside it,

(f) a radiator - a device in which an ionising radiation of more than 5 keV is produced in operation but which is not or contains a radionuclide radiator;

(g) the workplace with open radiators - the workplace with sources of ionising radiation [§ 2 (s) of the Act], on which it is handled with open radionuclide radiators,

(h) working position - part of the workplace with sources of ionising radiation, clearly characterised by its protective (insulating, ventilation and shielding) properties, defined by spatial or technological (work desk, application or investigation box, digestor, hermetized vacuum housing etc.) where separate work with sources of ionising radiation may be carried out; there may be more than one room if each one constitutes a separate unit from the point of view of the organisation of the work,

(i) personal benefits - aggregate labelling for quantities characterising the degree of external and internal exposure of an individual, in particular the effective dose, the effective time dose and equivalent doses in each organ or tissue; the devices by which personal doses are measured are referred to as personal dosimeters and the sum of the measurement and evaluation of personal doses is referred to as personal dosimetry;

(j) a worker of category A - a worker with a source of ionising radiation (hereinafter referred to as "worker with a source"), over 18 years of age, who comes into contact with sources of ionising radiation in his work knowingly and voluntarily and after a demonstrable lesson on the degree of potential exposure at work and the risks associated with which personal doses are systematically measured, evaluated, registered and notified to the State system of the health record of workers with sources maintained by the Office pursuant to Article 3 (1) (m) of the Act, and which, moreover, has undergone a preventive medical examination in the last 24 months to the extent appropriate to the assessment of medical fitness at risk work1), and the conclusion of this survey is not contrary to work with the source of ionising radiation;

(k) a worker of category B - a worker with a source, over 18 years old, who comes into contact with sources of ionising radiation in his work knowingly and voluntarily and after a proven lesson on the extent of potential exposure at work and the risks associated therewith;

(l) critical population group - a model group of persons who are reasonably homogeneous in terms of exposure from a given source of ionising radiation and a given route of exposure and characterising individuals from the population who receive the highest effective or equivalent doses by that source,

(m) discharge - a substance discharged from the workplace with sources of ionising radiation into the environment, containing radionuclides in a quantity not exceeding the conditions for authorisation to place radionuclides in the environment,

n) optimising radiation protection - procedures to achieve and maintain a level of radiation protection so that the risk of life, human health and the environment is as low as can reasonably be achieved in the light of economic and social considerations;

(o) the guide value - the indicator or criterion which is the guide for the assessment of measures in radiation protection, its overrun or non-compliance usually indicates that radiation protection is not optimised; the indicative values are used to decide on the relevant measures, unless the specific conditions and circumstances of the activity carried out lead to exposure or to action to reduce exposure, which would allow the application of radiation protection optimisation on the basis of individual case-specific data,

(p) reference level - indicator or criterion the excess or non-compliance of which is an incentive to initiate radiation protection measures;

q) monitoring - measurement and assessment of exposure of workers with resources and other persons and pollution of the workplace and its surroundings by ionising radiation or radionuclides;

(r) normal operation - operation of the source of ionising radiation under the conditions laid down in the Authority's authorisation for its operation or handling and in the Authority's approved documentation,

s) living space - living rooms and kitchens in residential buildings 2) and other building rooms or enclosed spaces intended to accommodate persons for at least a thousand hours per calendar year;

(t) construction material - selected products for construction and selected feedstock listed in Table 1 of Annex No 11.

§ 3

For the purposes of this decree, radiation protection quantities shall mean:

(a) equivalent dose of HT, the product of the radiation weighting factor wR listed in Table 1 of Annex 5 and the mean absorbed dos3) DTR in the organ or tissue T for ionising radiation R, or the sum of such products if the ionising radiation field consists of multiple species or energy;

(b) the effective dose E, which is the sum of the products of the mass weighting factors wT listed in Table 2 of Annex 5 and the equivalent HT dose in irradiated tissues or organs T;

(c) a collective effective or equivalent dose, which is the sum of the effective or equivalent doses of all individuals in a particular group;

(d) the time-effective dose E (τ), or equivalent dose HT (τ), which is the time-integral of the effective dose power, or equivalent dose, for the duration of the dose from the intake of radionuclide; unless otherwise indicated, this period shall be 50 years for the intake of radionuclides in adults and up to 70 years for the intake of radionuclides in children; Similarly, collective effective or equivalent benefits are also defined at a time,

(e) the dose equivalent H, which is the product of the absorbed dose at the tissue point under consideration and the Q-value factor listed in Table 3 of Annex 5, expressing the different biological efficacy of the different types of radiation,

(f) personal dose equivalent Hp (d), which is the dose equivalent at a given point below the body surface at the depth of the tissue d,

(g) the equivalent volume activity of radon aecv, which is the weighted sum of volume activity 3) and 1 polonium 218 volume activity a2 lead 214 and the volume activity a3 vision 214 determined by the relationship aecv = 0,106.a1 + 0,513.a2 + 0,381. a3.

§ 4

Radionuclide content or pollution exceeding which the substances or articles are radionuclide radionuclides

[to implement § 2 (c) (1) of the Act]

(1) The substance or article is a radionuclide radionuclide radiator according to § 2 (b). (c) point 1 of the Act when activity3) is greater than the value given in the second column of Table 1 of Annex 1 and at the same time the mass activity 3) is greater than that indicated in the third column of Table 1 of Annex 1.

(2) Where a substance or article contains several radionuclides or is contaminated by several radionuclides, the radionuclide radionuclide shall be the radionuclide radionuclide radionuclide when the sum of the activity shares (s) of the individual radionuclides and the activity values of the activities listed for these radionuclides in the third column of Table 1 of Annex 1 is greater than one.

(3) For selected radionuclides, identified in the first column of Table 1 of Annex No 1 and listed in Table 2 of Annex No 1, the activity and mass activities values in Table 1 of Annex No 1 shall apply not only to these radionuclides themselves but also to those of their radioactive transformation products listed in the second column of Table 2 of Annex No 1.

§ 5

The level of radionuclide content or pollution by them, which allows placing into the environment

[to implement § 8 (1) and § 2 (o) of the Act]

(1) Use outside the workplace with sources of ionising radiation, discharge into water or air, store in landfills or otherwise place in the environment

(a) without the authorisation of the Office under Article 9 (1) (h) of the Act, only materials, substances and articles containing or contaminated by radionuclides to the extent that any of the following conditions apply:

1. in no calendar year, the average effective dose for a critical population group shall not exceed 10 µSv and the collective effective dose shall not exceed 1 Sv,

2. when placing into the environment of solids and articles, the sum of the proportions of the activity by weight of the individual radionuclides and release levels of the activity by weight of the relevant radionuclides listed in Table 1 of Annex 2 or the sum of the proportion by weight of the activity by weight of the individual radionuclides and release levels of the activity by weight of the relevant radionuclides listed in Table 1 of Annex 2 shall not exceed one;

3. in the case of discharges into surface water, except discharges from workplaces with very significant resources, the sum of the amounts of the volume activities of individual discharges of radionuclides and conversion factors of hing for the intake of these radionuclides by ingesting an adult person from the population according to the tables in Annex 3 is not greater than 10-4 Sv.m-3;

4. in the case of discharges into the air, except discharges from workplaces with very significant resources, the sum of the amounts of the volume activities of individual discharges of radionuclides and conversion factors of the hinh for receiving these radionuclides by inhalation by an adult person from the population according to the tables in Annex 3 shall not exceed 10-6 Sv.m-3;

5. in the case of landfill sites, the sum of the mass activities of individual stored radionuclides and conversion factors for receiving these radionuclides by an adult population according to the tables in Annex 3 is not greater than 10-4 Sv.K.1, the sum of the shares of the surface activities of individual stored radionuclides and the release levels of the surface activity of the relevant radionuclides listed in Table 1 of Annex 2 is not greater than one and the deposit is carried out in such a way that it does not cause an increase in dose equivalent power of more than 0,1 µSv / h from the original natural background in that location or the supply equivalent above 0,4 µSv / h at a distance from the landfill surface,

6. in the case of combustion plants, the combustion gases discharged into the air comply with the requirement laid down in point 4 and where the ash resulting from the incineration complies with the requirement laid down in point 2 or where such ash is placed on the landfill of municipal waste referred to in point 5,

7. in the case of discharges into public sewerage, except discharges from workplaces with very significant resources, the sum of the products of the volume activities of individual discharges of radionuclides and conversion factors for the intake of these radionuclides by an adult person from the population according to the tables in Annex 3 shall not exceed 10-2 Sv.m-3;

(b) on the basis of the authorisation of the Office under Article 9 (1) (h) of the Act, only materials, substances and articles containing or contaminated by radionuclides to such an extent that in no calendar year the average effective dose for the critical population group does not exceed 250 µSv.

(2) In the case of uneven contamination of radionuclide, the average mass activity in one kilogram of solid substance, or the average volume in the cubic meter of liquid or gaseous substance, shall be compared to the values referred to in paragraph 1. In the case of uneven surface contamination of radionuclide, the average surface activity of 100 cm2 shall be compared to the values referred to in paragraph 1.

§ 6

Criteria for distribution of sources of ionising radiation

[to implement § 2 (c) of the Act]

(1) The criteria for the distribution of sources of ionising radiation are:

(a) dose equivalent power;

(b) technical modification and method of implementation of the source of ionising radiation;

(c) for radionuclide emitters, activity and mass activity;

(d) the typical way in which they are handled and the associated level of potential exposure;

(e) the potential risk arising from foreseeable failures and deviations from normal operation.

(2) Depending on technical modifications, radionuclide radionuclides are divided into closed and open. The closed radionuclide radionuclide lamp is a radionuclide radionuclide lamp, the treatment of which, e.g. by encapsulating or covering it, ensures a proven tightness by tests, thereby excluding, under foreseeable conditions of use and wear, the leakage of radionuclides from the radionuclide lamp. An open radionuclide radiator is a radionuclide radionuclide that is not a closed radionuclide radion. Where a closed radionuclide lamp is not accompanied by a valid certificate in accordance with Paragraph 55, or where its tightness is not demonstrated by others in the conditions of authorisation, it shall be treated as if it were an open lamp.

(3) On the basis of those criteria, sources of ionising radiation are divided into insignificant, small, simple, significant and very important sources depending on the increasing severity of the threat to human health and the environment.

(4) The non-significant sources of ionising radiation are:

(a) radiation generators designed to power dose equivalent at any accessible location at a distance of 0,1 m from the surface of the device is less than 1 µSv / h, except where the accelerating potential exceeds 30 kV;

(b) thetalon sealed radionuclide radionuclide lamps used for calibration, for which the sum of the activity shares or the sum of the activities by weight of each radionuclide and the activity values or activity values of these radionuclides listed in Table 1 of Annex 1 is less than 10;

(c) a device containing closed radionuclide radionuclide radionuclide lamps designed so that the power of dose equivalent at any accessible location at a distance of 0,1 m from the surface of the device is less than 1 µSv / h and, taking into account the typical way in which they are handled, the associated level of potential exposure and the potential risk arising from foreseeable disturbances and deviations from normal operation, this classification has been confirmed in the framework of type approval pursuant to Section 23 of the Act, 4)

(d) autonomous ionization fire detectors.

(5) Minor sources of ionising radiation are:

(a) radiation generators which are not non-significant sources, designed so that the power input of batch equivalent at any accessible point at 0,1 m from the surface of the device is less than 1 µSv / h, except for those designated under normal working conditions for handling and operation of equipment solely by hands where the power input of batch equivalent may reach up to 250 µSv / h;

(b) thetalon sealed radionuclide radionuclide lamps used for calibration, for which the sum of the activity shares or the proportion by weight of the activity of individual radionuclides and the activity values or activity values of those radionuclides listed in Table 1 of Annex 1 is equal to or greater than 10 but less than 100;

(c) equipment containing closed radionuclide radionuclide lamps, which are not non-significant sources, designed so that the power consumption of batch equivalent at any accessible point at 0,1 m from the surface of the device is less than 1 µSv / h except where the power consumption of batch equivalent may be up to 250 µSv / h under normal working conditions for handling and operation of equipment solely by hands;

(d) equipment containing closed radionuclide radionuclide radionuclide lamps for which, taking into account the typical way in which they are handled, the associated level of potential exposure and the potential risk arising from foreseeable disturbances and deviations from normal operation has been confirmed in the framework of type approval pursuant to Article 23 of the Law, 4)

(e) open radionuclide radionuclide lamps, for which the sum of the activities or mass activities of individual radionuclides and the activity or activity values of these radionuclides listed in Table 1 of Annex 1 is less than 10;

(f) ionisation fire detectors, except autonomous ones.

(6) Simple sources of ionising radiation are all sources of ionising radiation which are not minor, minor, significant or very significant sources of ionising radiation, such as stationary cabin X-rays, dental X-rays, mammographic X-rays, X-ray devices for computer tomography, radiodiagnostic detection walls, mobile X-ray devices for radiodiagnostic and defectoscopy, compact extractive blood irradiators with closed radionuclide radionuclides.

(7) The major sources of ionising radiation are:

(a) stationary X-ray equipment, except cabin equipment, dental X-rays, mammographic X-ray equipment, computer tomography X-ray equipment and radiodiagnostic examination walls;

(b) particle accelerators for which, in view of the typical way in which they are handled, the associated level of potential exposure and the potential risk arising from foreseeable disturbances and deviations from normal operation has thus been determined in the framework of type approval pursuant to Article 23 of the Law, 4)

(c) sources of ionising radiation intended for radiotherapy of protons, neutrons and other heavy particles;

(d) equipment containing closed radionuclide radionuclide lamps intended for radiotherapy, including brachytherapy;

(e) stationary irradiation and other stationary equipment containing closed radionuclide radionuclide radiators, except compact extracurricular blood irradiators and other similar devices, where, in view of their typical handling, the associated level of potential irradiation and the potential risk arising from foreseeable disturbances and deviations from normal operation has thus been determined within the scope of the type-approval provided for in Article 23 of the Law, 4)

(f) mobile defectoscopes with closed radionuclide lamps;

(g) mobile irradiators with closed radionuclide radionuclide radiators, except for equipment where, in view of the typical way in which they are handled, the associated level of potential exposure and the potential risk resulting from foreseeable disturbances and deviations from normal operation has thus been determined in the framework of type approval under § 23 of the Act, 4)

(h) open radionuclide radionuclide emitters whose activity is greater than 600 Sv / hinh and at the same time less than or equal to 8000 Sv / hinh, where hinh is the conversion factor for intake by the worker with resources according to the tables in Annex 3.

(8) Very significant sources of ionising radiation are:

(a) the nuclear reactor and the related technological facilities;

(b) industrial irradiators containing closed radionuclide radionuclide lamps intended for the irradiation of consumables, objects of common use and other materials by ionising radiation;

(c) open radionuclide radionuclide radiators whose activity is greater than 8000 Sv / hinh, where Hindh is the conversion factor for intake by inhalation of the worker with the sources according to the tables in Annex 3.

§ 7

Technical and organisational requirements, indicative values and procedures to demonstrate a reasonably achievable level of radiation protection

(to implement § 4 (4) of the Act)

(1) Technical and organisational requirements to demonstrate a reasonably achievable level of radiation protection include:

(a) prior to the commencement of the activity leading to the exposure of the assessment and comparison of the options for radiation protection solutions that are considered in the intended activity and the costs of appropriate protective measures, collective doses and doses in the relevant critical population, generally using the procedures referred to in paragraph 4;

(b) during the operation of the irradiation activity, a regular analysis of the doses received in relation to the operations carried out, consideration of possible further measures to ensure radiation protection and comparison with similar previously operated and socially acceptable activities;

(c) prior to and in the course of the action to reduce natural exposure or to reduce exposure as a result of radiation accidents, an assessment of possible variations and a choice of which, by way of implementation, scope and duration, will give the greatest possible net benefit, using the procedures referred to in paragraph 4.

(2) The indicative exposure values considered sufficient to demonstrate a reasonably achievable level of radiation protection for the management of the source of ionising radiation are 1 St for the annual collective effective dose, 1 mSv for the annual effective dose for category A or B workers and 50 µSv for the annual effective dose for other persons. The reasonably achievable level of radiation protection shall be considered sufficiently demonstrated if none of the above indicative values can be exceeded by either person, even as a foreseeable deviation from normal operation.

(3) For flight crew members for which an effective dose of less than 1 mSv per calendar year cannot be reduced by limiting flight height to less than 1 mSv, the reasonably achievable level of radiation protection is achieved by changing the organisation of flights, by providing sufficient information to crew members with the size of the exposure and resulting health risk and by adjusting the working conditions of pregnant women so as not to exceed the specific limit referred to in Article 12 (2). For other persons working in an environment where there is an increased risk of natural exposure, which means in particular those cases of work, e.g. in baths, waterworks, caves, mines or underground areas, where even after the implementation of corrective measures it is not possible to reduce the volume activity of radon in the air at the time of work below 1000 Bq / m3, the reasonably achievable level of radiation protection is understood to be the application of requirements for work in the controlled working area with sources of ionising radiation.

(4) The reasonably achievable level of radiation protection can be demonstrated by a process whereby the cost of alternative measures to increase radiation protection (e.g. building additional barriers) is compared with the financial assessment of the expected reduction of radiation (hereinafter "the benefit of the measure '). A reasonably achievable level of radiation protection is considered to be demonstrated and the measure may not be implemented if the costs would be higher than the benefit of the measure. The benefit of the measure is calculated by multiplying the reduction of the collective effective dose of the irradiated group of workers with resources or in the population by the factor

a) 0.5 mil. CZK. Sv-1 for irradiated activities where the effective dose on average for an individual does not exceed one tenth of the relevant baseline limits,

(b) CZK 1 million. Sv-1 for irradiated activities where the effective dose on average for an individual exceeds one tenth but not three tenths of the relevant baseline limits,

(c) CZK 2.5 million. Sv-1 for irradiated activities where the effective dose on average for an individual exceeds three tenths of the relevant baseline limits,

(d) 1 mil.

(e) 1 mil. CZK. Sv-1 for natural exposure,

(f) 5 mil. Kč. Sv-1 for radiation exposure in radiation accidents.

(5) The factors referred to in paragraph 4 apply for 1997. For the following calendar years, it shall be multiplied by a coefficient expressing the inflation rate, which is derived from the annual rolling average of the change in consumer prices for the previous calendar year according to the Czech Statistical Office index. The coefficient to be applied shall be that set out and published in the Price Bulletin by the Ministry of Finance for the purposes of a special regulation. 5)

Radiation limits

(to implement § 4 (6) of the Act)

§ 8

(1) Radiation limits as mandatory quantitative indicators, the excess of which is not permitted in terms of radiation protection under Section 4 (6) of the Act, are:

(a) the basic limits applicable to exposure from all irradiation activities, except:

1. exposure directly related to the work carried out by category A or B workers;

2. exposure, knowingly, voluntarily and after learning the risks associated with it, to persons during their specialised preparation for the pursuit of a profession with sources of ionising radiation,

3. medical exposure,

4. the exposure of persons involved in interventions in the event of a radiation accident;

5. exposures subject to special limits pursuant to § 12;

(b) basic limits for workers with sources of radiation exposed directly to the work carried out by category A or B workers;

(c) the basic limits for apprentices and students on exposures to whom they are knowingly, voluntarily and after learning about the risks associated with them, during their specialised preparation for the pursuit of the profession with sources of ionising radiation;

(d) specific limits applicable to exposure in specific cases under § 12;

(e) derived limits applicable to the same cases of exposure as basic limits for workers, but expressed in easier measurable quantities than basic limits.

(2) Failure to exceed the established derived limits (Paragraph 13) is deemed to be a requirement not to exceed the basic limits for workers with resources. For multiple pathways of exposure (e.g. external exposure, internal exposure from the ingestion of radionuclides, internal exposure from inhalation of radionuclides), the absence of the essential limits for workers is considered to be met if the sum of the exposure shares from the individual route of exposure and the respective derived limits is less than one.

(3) For activities leading to exposure or source of ionising radiation for which limits are laid down by the Authority under the conditions of authorisation pursuant to Article 4 (6) of the Act specifically for the activity or source already taking into account possible exposures from other potential activities and sources, the excess of those limits shall be considered as not exceeding the corresponding basic limits.

(4) The exposure limits shall not apply to the exposure of persons involved in interventions in the event of a radiation accident, but such exposure shall not exceed 10 times the basic limits for workers with resources, unless it is a case of saving people's lives or preventing the development of a radiation accident with possible large-scale social and economic consequences.

(5) The use of irradiance limits at workplaces with sources of ionising radiation shall not include radiation from natural sources, except irradiation from those natural sources which are consciously and intentionally used, and except where even after the implementation of corrective measures it was not possible to reduce the volume activity of radon in the air at the time of work below 1000 Bq / m3.

§ 9

(1) The basic limits of the general are:

(a) for the sum of effective external exposure doses and time-limits of effective internal exposure doses, the value of 1 mSv per calendar year or under the conditions laid down in the permit for operating the workplace with significant or very significant sources of ionising radiation, exceptionally, the value of 5 mSv for five consecutive calendar years;

(b) for an equivalent dose in the lens, the value of 15 mSv per calendar year;

(c) for an average equivalent dose of 1 cm2 of skin, the value of 50 mSv per calendar year.

(2) The basic limits of the general for the population around the workplace with sources of ionising radiation apply to the average calculated exposure in the critical population of the population, for all routes of exposure from all sources of ionising radiation and all activities leading to exposure that come into consideration. If there is no direct basis for calculation, conservative estimates of variations in factors affecting the spread of radionuclides or exposure of individuals in a critical group shall be used in accordance with § 47.

§ 10

(1) The basic limits for workers with resources are:

(a) for the sum of effective external exposure doses and time-limits of effective internal exposure doses, the value of 100 mSv over five consecutive calendar years;

(b) 50 mSv per calendar year for the sum of effective external exposure doses and effective internal exposure doses;

(c) for an equivalent dose in the lens, a value of 150 mSv per calendar year;

(d) for an average equivalent dose of 1 cm2 of skin, the value of 500 mSv per calendar year;

(e) for an equivalent dose on the hands from fingers to forearms and feet from feet to ankles of 500 mSv per calendar year.

(2) The basic limits for workers with sources shall apply to the sum of doses from all irradiated routes and, in all working activities carried out by a category A or B worker, for one or more holders of a permit for the treatment of ionising radiation sources, or as a separate holder of an authorisation for the management of ionising radiation sources.

§ 11

(1) The basic limits for apprentices and students are from the year in which they reach 16 years of age to the year in which they reach 18 years of age:

(a) for the sum of effective external exposure doses and effective internal exposure doses, the value of 6 mSv per calendar year;

(b) for an equivalent dose in the lens, the value of 50 mSv per calendar year;

(c) for an average equivalent dose of 1 cm2 of skin, the value of 150 mSv per calendar year;

(d) for the equivalent dose on hands from fingers to forearms and feet from feet to ankles, the value of 150 mSv per calendar year.

(2) The basic limits for apprentices and students shall be the same for persons younger than those referred to in paragraph 1 as the basic limits for general and for persons older than those referred to in paragraph 1 as the basic limits for workers with resources.

§ 12

(1) The exposure of persons who voluntarily, outside their professional or employment obligations, tend to or reside in one household with patients who have been released from a medical institution after the application of radionuclides is limited to not exceeding 1 mSv for persons under 18 years of age and 5 mSv for other persons during the investigation or treatment period.

(2) The exposure of pregnant women working in workplaces with sources of ionising radiation shall be limited immediately after the pregnancy has been detected and reported to the employer, by adjusting the conditions of work so that the sum of effective doses from external exposure and time of effective doses from internal exposure to the fetus is unlikely to exceed 1 mSv for at least the remainder of the pregnancy.

(3) Infant exposure by the intake of radionuclides from contaminated breast milk shall be restricted, immediately after a woman working at the workplace with sources of ionising radiation has notified the employer that she is breast-feeding the child, by adjusting the conditions of work, usually by removing from work in a controlled area of the workplace with open radionuclide radionuclides.

(4) The exposure of workers to sources in exceptional, one-off or short-term work with sources of ionising radiation, limited to only a small number of persons and to designated premises (hereinafter referred to as "exceptional exposure '), shall be limited so that the effective dose of repeated exceptional exposures does not exceed 500 mSv over a period of five consecutive calendar years. These exceptional exposures may only take place in the scope and under the conditions of authorisation for such treatment of sources of ionising radiation. Only Category A workers may undergo exceptional exposure on a voluntary basis and after previous lessons on the risks involved. This exceptional exposure is not permitted for pregnant and lactating women or persons for whom the effective dose obtained in the event of a radiation accident would exceed 500 mSv in five consecutive calendar years.

§ 13

(1) The derived limits for external exposure are:

(a) for personal batch equivalent at a depth of 0,07 mm, the value of 500 mSv per calendar year;

(b) for personal batch equivalent at a depth of 10 mm, the value of 20 mSv per calendar year.

(2) The derived limits for internal exposure, except in the cases provided for in paragraphs 4 and 5, are:

(a) for the intake of radionuclides by ingesting the 20 mSv share value and the conversion factor hing for the intake of radionuclides by ingesting a worker with the resources referred to in the tables in Annex 3;

(b) for the intake of radionuclides by inhalation of the 20 mSv share value and the Hindh conversion factor for the intake of radionuclides by inhalation by the worker with the source according to the tables in Annex 3.

(3) In the current external and internal exposure over one calendar year, except in the cases referred to in paragraphs 4 and 5, the essential limits for workers shall be deemed not to be exceeded if they apply:

Hp0,07 ≤ 500 mSv

at the same time

Hp10 + ihj, inhIj, inh + ihj, ingIj, ing ≤ 20 mSv,

where

Hp (0,07) or Hp (10) is the annual personal dose equivalent at a depth of 0,07 mm or 10 mm,

Ij, inh, or Ij, ing is the annual intake of the first radionuclide by inhalation or ingestion,

hj, inh, or hj, ing is the conversion factor of the first radionuclide for intake by inhalation or ingestion by a worker with resources

in accordance with the tables in Annex 3.

(4) For exposure to radon transformation products, the derived limit of 3 MBq for annual intake of equivalent radon activity (corresponding to the intake of latent energy of radon transformation products 17 mJ) or 2,5 MBq.h.m-3 for exposure to radon products or 1260 Bq.m-3 for year-round average equivalent volume radon activity.

(5) For irradiation of mixtures of long-term radionuclides emitting alpha-uranium-radio radiation, the derived limit is intake by inhalation of 1850 Bq per calendar year.

ČÁST DRUHÁ

DETAILS FOR THE ELIGIBILITY AND SCOPE OF THE INSURANCE OF RADIATION PROTECTION IN THE ACTIVITIES OF THE IRRITORY

HLAVA I

DETAILS FOR LOAD RESOURCES

[to implement § 9 (1) (i), § 4 (10) and § 13 (3) (d) of the Act]

Citation	Decree of the State Office for Nuclear Safety No. 184 / 1997 Coll., on requirements for radiation protection
Regulation Type	Order
Author	-
Collection	Code of Laws

Date of Promulgation	19.08.1997
Effective from	19.08.1997
Effective until	-
Status	Valid

Decree No. 184 / 1997 Coll.

Decree of the State Office for Nuclear Safety on radiation protection requirements

Contents

ČÁST PRVNÍ

§ 1

§ 2

§ 3

§ 4

§ 5

§ 6

§ 7

§ 8

§ 9

§ 10

§ 11

§ 12

§ 13

ČÁST DRUHÁ

HLAVA I

Contents

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