Decree No. 422 / 2016 Coll.
Ordonnance on Radiation Protection and Security of Radionuclide Source
Valid
Order
Effective from 01.01.2017
Contents
ČÁST PRVNÍ
§ 1
§ 2
ČÁST DRUHÁ
HLAVA I
Díl 1
§ 3
§ 4
§ 5
§ 6
Díl 2
§ 7
§ 8
§ 9
Díl 3
§ 10
§ 11
§ 12
§ 13
§ 14
§ 15
§ 16
§ 17
§ 18
§ 19
§ 20
Díl 4
§ 21
§ 22
§ 23
§ 24
§ 25
Díl 5
§ 26
§ 27
§ 28
§ 29
§ 30
§ 30a
§ 31
§ 32
Díl 6
§ 33
§ 34
§ 35
§ 36
§ 37
§ 38
§ 39
§ 40
§ 41
§ 42
HLAVA II
Díl 1
§ 43
§ 44
§ 45
Díl 2
§ 46
§ 47
§ 48
§ 49
Díl 3
§ 50
§ 51
§ 52
§ 53
§ 54
Díl 4
§ 55
§ 56
§ 57
§ 58
§ 59
Díl 5
§ 60
§ 61
§ 62
Díl 6
§ 63
§ 64
§ 65
Díl 7
§ 66
§ 67
§ 68
§ 69
§ 70
§ 71
§ 72
§ 73
§ 74
Díl 8
§ 75
§ 76
§ 77
§ 78
§ 79
§ 80
§ 81
§ 82
Díl 9
§ 83
§ 84
Díl 10
§ 85
§ 86
Díl 11
§ 87
§ 88
§ 89
§ 90
§ 91
HLAVA III
§ 92
§ 93
§ 94
§ 95
§ 96
§ 97
§ 98
§ 99
§ 100
§ 101
§ 102
§ 103
HLAVA IV
§ 104
§ 105
HLAVA V
§ 106
§ 107
§ 108
§ 109
§ 110
ČÁST TŘETÍ
§ 111
§ 112
§ 113
§ 114
§ 114a
ČÁST ČTVRTÁ
§ 115
§ 116
§ 117
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422
DECLARATION
of 14 December 2016
on radiation protection and protection of radionuclide source
The State Office of Nuclear Safety provides, pursuant to § 236 of Act No. 263 / 2016 Coll., Atomic Act, for the implementation of § 9 (2) (c) and (j), § 17 (3), § 24 (7), § 25 (2) (a) to (d), § 60 (4), § 61 (6), § 63 (6), § 66 (6), § 67 (4), § 68 (2) (a), § 88 (6), § 93 (5), § 69 (2), § 70 (2) (b), § 78 (3), § 81 (3), § 83 (7), § 85 (3), § 74 (4), § 75 (5), § 76 (a), § 77 (6), § 77 (2), § 81 (3), § 81 (3) (3), § 83 (7), § 85), § 85 (5), § 85 (5), § 85 (5), § 85 (5)
INTRODUCTORY PROVISIONS
Subject matter
This decree implements the relevant Euratom1 regulations and lays down requirements for the provision of radiation protection in exposure situations and for the way in which the radionuclide source is secured, including the radionuclide source from 1st to 3rd category of security.
Terms
For the purposes of this decree:
(a) the absorbed dose share of the mean energy transmitted by ionising radiation in the volume element and the mass of the substance contained in that volume element;
(b) by activity, the proportion of the expected value of the number of nuclear transformations from the energy state and the time interval in which such transformations take place;
(c) D-value of radionuclide activity in a radionuclide source which may cause a severe tissue reaction, unless it is supervised; The D-value is set out in Annex No 1 to this Order,
(d) equivalent to the product of the radiation weighting factor and the mean absorbed dose in the body or tissue for ionising radiation, or the sum of such products if the field of ionising radiation is composed of several species or energy; the radiation weighting factor is set out in Annex 2 to this Decree,
(e) an effective dose of the sum of the products of tissue weighting factors and an equivalent dose in irradiated tissues or organs; the tissue weighting factor is set out in Annex 2 to this Decree,
(f) a collective effective dose of the sum of the effective doses of all individuals in a particular group;
(g) time τ
1.50 years for receiving radionuclides in adults, or
2. periods up to 70 years of age for receiving radionuclides in children;
(h) by binding an effective dose, the time integral of the effective dose power over a time interval from the intake of radionuclide,
(i) by binding an equivalent dose, the temporal integrity of the equivalent dose power over a Cmax period from the intake of radionuclide;
(j) dose equivalent of the product of the absorbed dose at a specific point of tissue and a quality factor expressing the different biological efficacy of the different types of ionising radiation; the quality factor is set out in Annex 2 to this Decree,
(k) personal dose equivalent dose equivalent at a point below the body surface at the depth of the tissue;
(l) ICRU sphere diameter 30 cm made of material of equivalent tissue with a density of 1 g / cm3 and a mass composition of 76,2% oxygen, 11,1% carbon, 10,1% hydrogen and 2,6% nitrogen,
(m) the spatial dose equivalent of the dose equivalent at a given point in the field of radiation which would be created by an appropriate rectified and expanded field in the ICRU sphere at a depth of 10 mm on a radius facing the direction of particle movement in the directed field;
(n) a dose-equivalent directional dose equivalent at a given point in the radiation field which would be created by the corresponding extended field in the ICRU sphere at a depth of 0,07 mm on the radius in the specified direction;
o) equivalent to the volume activity of radon weighted sum of volume activity a1 218Po, volume activity a2 214Pb and volume activity a3 214Bi; the equivalent volume activity of radon is equal to 0,106 × a1, 0,513 × a2 and 0,381 × a3;
(p) by receiving radionuclide, the activity of radionuclide taken into the human organism from the environment, in particular by ingestion or inhalation;
(q) the conversion factor for receiving radionuclide, the coefficient indicating the time-effective dose per unit dose of radionuclide; the conventional conversion factors for radionuclide intake are set out in Annex 3 to this Decree,
r) Hing conversion factor of radionuclide intake by ingestion;
s) Hindh conversion factor of intake of radionuclide by inhalation,
t) Iing annual intake of radionuclide by ingestion,
u) Iinh annual intake of radionuclide by inhalation,
(v) an indicative dose-time effective dose from the annual intake of all radionuclides present in the water with the exception of tritium, 40K, 222Rn and short-term products of its transformation; and
(w) dental computational tomography of dental panoramic equipment or other equipment used for medical exposure in dental radiodiagnostic imaging for dental, jaw or skull imaging, which allows tomographic or panoramic imaging with broad conical volume or imaging using computational tomography or creating three-dimensional images or tomography scans.
RADIATION PROTECTION
GENERAL RULES ON RADIATION PROTECTION
Limits
General limits for residents
(Paragraph 63 (6) of the Atomic Act)
The general limits for exposure residents from all authorised or registered activities per calendar year shall be:
(a) for the sum of effective external exposure doses and effective internal exposure doses of 1 mSv;
(b) for an equivalent dose in an eye lens of 15 mSv; and
(c) for an average equivalent dose per 1 cm2 of skin of 50 mSv regardless of the size of the irradiated area.
Limits for a radiation worker
(Paragraph 63 (6) of the Atomic Act)
(1) Limits for a radiation worker must be used to reduce occupational exposure and are:
(a) for the sum of effective external exposure doses and time-limits of effective internal exposure doses of 20 mSv per calendar year or value approved by the Authority pursuant to Paragraph 63 (4) of the Atomic Act, but not more than 100 mSv per 5 consecutive calendar years and 50 mSv per calendar year;
(b) for the equivalent dose in the lens 100 mSv in 5 consecutive calendar years and 50 mSv in one calendar year,
(c) for an average equivalent dose for each 1 cm2 of skin 500 mSv per calendar year, regardless of the size of the irradiated area; and
(d) for an equivalent dose on the hands from the fingers to the forearm and on the feet from the feet to the ankles of 500 mSv per calendar year.
(2) The assessment of whether the limits for the radiation worker have not been exceeded must:
(a) be carried out consistently;
(b) take into account the sum of the doses from all routes of exposure and in all the work carried out by the radiation worker; and
(c) take into account, in the case of a non-external worker, the performance of work in which he is exposed to radiation exposure subject to limits for the radiation worker, for several notifiers, registries or holders of authorisations.
(3) A radiator who has been found to exceed the exposure limits must be temporarily removed from work with a source of ionising radiation until his medical fitness for further work with a source of ionising radiation has been assessed and the conditions for such work laid down.
(4) The excess of the limits for a radiation worker who is found to be disabled in accordance with paragraph 3 shall not constitute grounds for excluding him from normal work or transfer to another place of work, unless the person for whom he carries out the work has other serious reasons for such exclusion.
Limits for pupil and student
(Paragraph 63 (6) of the Atomic Act)
(1) Compliance with the limits for pupils and students must be assessed by the permit holder or by the registrar at whose workplace the pupil and student work with the source of ionising radiation during their studies.
(2) Assessment of whether the limits for pupils and students have not been exceeded
(a) be carried out consistently; and
(b) take into account the sum of doses from all routes of exposure and in all activities carried out by the pupil and student with source of ionising radiation.
(3) The limits for pupils and students aged 16 to 18 who are obliged to work with a source of ionising radiation during their studies are for one calendar year
(a) for the sum of effective external exposure doses and effective internal exposure doses of 6 mSv;
(b) for an equivalent dose in an eye lens of 15 mSv,
(c) for an average equivalent dose per 1 cm2 of skin of 150 mSv regardless of the area irradiated; and
(d) for an equivalent dose on the hands from the fingers to the forearm and on the legs from the feet to the ankles of 150 mSv.
(4) The limits for pupils and students under 16 who are obliged to work with a source of ionising radiation during their studies are identical to the general limits for residents.
(5) The limits for pupils and students aged over 18 who are required to work with a source of ionising radiation during their studies are identical to those for the radiation worker.
Derived limits
(Paragraph 63 (6) of the Atomic Act)
(1) Limits for radiation workers are considered not to be exceeded unless quantitative indicators expressed in measurable quantities (hereinafter "derived limits") are exceeded.
(2) 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 3 mm, the value of 20 mSv per calendar year; and
(c) for personal batch equivalent at a depth of 10 mm, the value of 20 mSv per calendar year.
(3) The derived limits for internal exposure per calendar year, except in the cases provided for in paragraph 5, are a radiation worker for the reception of individual radionuclide
(a) ingestion of activity
0,02hing
b) Inhaling activity
0,02hinh
(4) In the case of current external and internal exposure during the calendar year, except in the cases referred to in paragraphs 6 to 8, the limits for radiation workers shall be deemed not to have been exceeded if they apply simultaneously:
Hp (0,07) ≤ 0,5 St a
Hp10 + ihihi, ingIi, ing + ihihi, inhii, inh ≤ 0,02Sv
where
Hp (0,07) (Sv) is the annual personal batch equivalent at a depth of 0,07 mm,
Hp (10) (Sv) is the annual personal batch equivalent at a depth of 10 mm,
hi, ing (Sv / Bq) is the conversion factor for receiving a single radionuclide by ingestion; the conversion factor is set out in Annex 3 to this Decree,
Ii, ing (Bq) is the annual intake of a single radionuclide by ingestion,
hi, inh (Sv / Bq) is the conversion factor for receiving a single radionuclide by inhalation; the conversion factor is set out in Annex 3 to this Decree; and
Ii, inh (Bq) is the annual intake of a single radionuclide by inhalation.
(5) For the calculation referred to in paragraph 4, the conversion factor set out in Annex 3 to this Decree for all unspecified forms of radionuclide shall be used for the unidentified form and properties of radionuclide.
(6) The derived limit corresponding to the effective dose of 20 mSv for exposure to mixtures of long-term radionuclides emitting alpha uranium-radio series is the intake of 1,600 Bq per calendar year.
(7) The derived limit corresponding to the effective dose of 20 mSv for radiation of radon transformation products is the intake of latent energy in underground workplaces
(a) with forced ventilation of 8 mJ per calendar year,
(b) with natural ventilation of 4 mJ per calendar year.
(8) If the radiation worker is simultaneously exposed to the external and internal radiation products of radon transformation and mixtures of long-term radionuclides emitting alpha uranium radio series, the limit for external radiation workers is considered not to be exceeded, if met, that Eext + Eint, Rn + Eint, dl.alpha, ≤ 0,02 Sv, kdeEext (Sv) is the effective dose from external radiation by gamma, Eint, Rn (Sv) is the time effective dose from internal radiation products of radon, Eint, dl.alpha (Sv) is the time effective dose from internal radiation by inhalation of a mixture of long-term radionuclides emitting alpha uranium radio series.
Optimisation of radiation protection
Radiation protection optimisation procedures
[Paragraph 66 (6) (c) of the Atomic Act]
(1) When optimising radiation protection, anyone carrying out activities in exposure situations shall determine the variants of radiation protection protection and choose from them the optimal variant of radiation protection in the relevant exposure situation.
(2) The selection of the optimal alternative to radiation protection must be made by comparing the possibilities of reducing the planned and potential doses to natural persons or groups of the population. Measures taken to protect individuals or groups of the population against the influence of the source of ionising radiation may be applied
(a) at the source of ionising radiation;
(b) in an environment between a source of ionising radiation and a natural person; or
(c) the natural person.
(3) When selecting an optimal alternative to providing radiation protection, priority shall be given to limiting the amount of radiation directly at the source of ionising radiation.
(4) When selecting the optimal alternative to providing radiation protection, account shall be taken of the representative features related to the activity concerned. The representative characters are set out in Annex 4 to this Decree.
(5) When selecting the optimal alternative to providing radiation protection, a comparison may be made, where possible, of the costs of various measures to increase radiation protection, in particular the relocation of individuals or the construction of additional barriers, with a financial assessment of the expected reduction of radiation.
(6) A comparison of the costs referred to in paragraph 5 shall be made by multiplying the reduction of the collective effective dose for the group of persons under consideration by the coefficient
a) 0.5 million CZK / St. for radiation activity where the average effective dose for an individual is less than 1 / 10 of the relevant exposure limits;
b) 1 million CZK / St. for radiation activity where the average effective dose for an individual is greater than 1 / 10 but less than 3 / 10 of the relevant exposure limits;
c) 2.5 million CZK / St. for radiation activity where the average effective dose for an individual is higher than 3 / 10 of the relevant exposure limits;
d) 1 mil. CZK / St. for medical exposure,
(e) 0,5 mil. CZK / St. for irradiation from a natural source of ionising radiation which is not caused by radiation activity; or
f) 2.5 mil. CZK / St. for emergency exposure.
[Articles 24 (7) and 66 (6) (c) of the Atomic Act]
(1) Radiation protection optimisation procedures shall be used on a regular basis by anyone carrying out activities in exposure situations so as not to omit the newly created conditions for the relevant exposure situation or the new possibilities of providing radiation protection for that exposure situation, in particular if there is a lack of compliance with exposure limits, dose optimisation limits or reference levels.
(2) For medical exposures for radiotherapeutic purposes, including therapeutic applications of radionuclide, the exposure of target volumes for each natural person undergoing treatment must be individually planned and adequately verified, taking into account that doses for volumes and tissues not target must be as low as reasonably achievable for the intended radiotherapy purpose.
(3) When determining dose optimisation limits for radiation activity or source of ionising radiation, account shall be taken of:
(a) experience so far with similar activities and sources of ionising radiation that the level of radiation protection is not lower than already achieved; and
(b) the effects of other activities and sources of ionising radiation so as to avoid exceeding the exposure limits.
(4) When optimising radiation protection, the process of this optimisation shall be documented.
(5) Radiation protection optimisation procedures must:
(a) systematically and structurally describe the process of this optimisation;
(b) take into account all relevant aspects in the exposure situation used in this optimisation; and
(c) contain the uses of radiation protection and representative features.
Assessment of exposure by the representative and optimisation studies
[Articles 81 (3) (d) and 82 (4) of the Atomic Law]
(1) The assessment of the exposure of the representative must be made by conservative estimates. The procedures for carrying out conservative estimates of exposure to a representative person are set out in Annex 5 to this Decree.
(2) The content of the optimisation study for the determination of the authorised exposure limit of the representative person is set out in Annex 6 to this Decree.
Classification
Discharge
(K § 67 (4) of the Atomic Act)
(1) The exemption levels for radionuclides are set out in Annex 7 to this Decree. The abatement levels apply to the total amounts of radioactive substances handled under a specific radiation activity.
(2) The abatement levels of activity by mass for radionuclides used in a specific radiation activity are set out in Annex 7 to this Decree.
(3) The activity of the mixture of radionuclides is lower than the exemption level if the sum of the activities of the individual radionuclides and the respective exemption levels of activities is less than 1.
(4) The mass activity of the mixture of radionuclides is lower than the abatement level if the sum of the mass activities of individual radionuclides and the respective abatement levels of the mass activities is less than 1.
High-activity source
[K § 60 (4) (b) of the Atomic Act]
The level of activity that makes a closed radionuclide source a high-activity source is set out in Annex 8 to this Decree.
Classification of sources of ionising radiation
[Paragraph 61 (6) (a) of the Atomic Act]
An insignificant source of ionizing radiation is
(a) a radiation generator emitting ionising radiation with an energy not exceeding 5 keV which is not a significant source of ionising radiation;
(b) cathode-ray tube designed for imaging or other electrical equipment operating at a potential difference of not more than 30 kV where the power input of the spatial dose equivalent at any accessible point is less than 1 µSv / h at 0,1 m from the surface of the device; or
(c) a radioactive substance for which the sum of the shares
1. the activity of radionuclides and relevant activity abatement levels is not greater than 1; or
2. the activity of radionuclides and the respective abatement levels of mass activity is not greater than 1.
[Paragraph 61 (6) (a) of the Atomic Act]
A small source of ionising radiation is
(a) a radiation generator, which is not an insignificant or significant source of ionising radiation, designed in such a way that, at any point accessible at a distance of 0,1 m from the surface of the device, the power input of the spatial dose equivalent is less than 1 µSv / h and, at places designated under normal working conditions for handling and use of the equipment by hand only, the power input of the directional dose equivalent is not more than 250 µSv / h;
(b) a closed radionuclide source which is not an insignificant source of ionising radiation, where the sum of the shares of the activities of the radionuclides and the respective abatement levels of the activity or the sum of the shares of the activities of the radionuclides and the respective abatement levels of the mass activity is less than 100 for long-term radionuclide sources emitting alpha, including those of neutrons, and less than 1000 in other cases;
(c) a device containing a closed radionuclide source which is not an insignificant source of ionising radiation, designed so that, at any accessible location at a distance of 0,1 m from the surface of the device, the wattage of the spatial dose equivalent is less than 1 µSv / h and at places designated under normal working conditions for handling and operation of the equipment by hand only is the wattage of the directional dose equivalent of not more than 250 µSv / h; or
(d) an open source of radionuclide, which is not an insignificant source of ionising radiation, for which the sum of the activity shares and the respective activity exemptions levels or the sum of the mass activities and the relevant activity limits of the radionuclide mass activities is less than 10.
[Paragraph 61 (6) (a) of the Atomic Act]
A simple source of ionising radiation is a source of ionising radiation which is not a minor, minor, significant or very significant source of ionising radiation.
[Paragraph 61 (6) (a) of the Atomic Act]
A significant source of ionising radiation is:
(a) a radiation generator intended for medical exposure, except for an X-ray bone densitometer, an intraoral dental X-ray device and a dental panoramic X-ray device;
(b) a particle accelerator with an energy exceeding 1 MeV;
(c) a source of ionising radiation intended for radiotherapy of protons, neutrons and other heavy particles;
(d) equipment containing a closed radionuclide source intended for radiotherapy;
(e) equipment containing a sealed radionuclide source intended for irradiation of tissues, blood and objects, including food, raw materials, articles of common use or other objects;
(f) mobile defectoscope with closed radionuclide source,
(g) a high-activity source; or
(h) a radiation generator used in veterinary radiotherapy for treatment purposes.
[Paragraph 61 (6) (a) of the Atomic Act]
A nuclear reactor is a very important source of ionizing radiation.
Classification for cross-border movement and security purposes
[Paragraph 61 (6) (b) of the Atomic Act]
(1) The source of ionising radiation of the first category of security is:
a. Radionuclide thermoelectric generator;
(b) radionuclide irradiation, including tissue and blood irradiation;
Contents
ČÁST PRVNÍ
§ 1
§ 2
ČÁST DRUHÁ
HLAVA I
Díl 1
§ 3
§ 4
§ 5
§ 6
Díl 2
§ 7
§ 8
§ 9
Díl 3
§ 10
§ 11
§ 12
§ 13
§ 14
§ 15
§ 16
§ 17
§ 18
§ 19
§ 20
Díl 4
§ 21
§ 22
§ 23
§ 24
§ 25
Díl 5
§ 26
§ 27
§ 28
§ 29
§ 30
§ 30a
§ 31
§ 32
Díl 6
§ 33
§ 34
§ 35
§ 36
§ 37
§ 38
§ 39
§ 40
§ 41
§ 42
HLAVA II
Díl 1
§ 43
§ 44
§ 45
Díl 2
§ 46
§ 47
§ 48
§ 49
Díl 3
§ 50
§ 51
§ 52
§ 53
§ 54
Díl 4
§ 55
§ 56
§ 57
§ 58
§ 59
Díl 5
§ 60
§ 61
§ 62
Díl 6
§ 63
§ 64
§ 65
Díl 7
§ 66
§ 67
§ 68
§ 69
§ 70
§ 71
§ 72
§ 73
§ 74
Díl 8
§ 75
§ 76
§ 77
§ 78
§ 79
§ 80
§ 81
§ 82
Díl 9
§ 83
§ 84
Díl 10
§ 85
§ 86
Díl 11
§ 87
§ 88
§ 89
§ 90
§ 91
HLAVA III
§ 92
§ 93
§ 94
§ 95
§ 96
§ 97
§ 98
§ 99
§ 100
§ 101
§ 102
§ 103
HLAVA IV
§ 104
§ 105
HLAVA V
§ 106
§ 107
§ 108
§ 109
§ 110
ČÁST TŘETÍ
§ 111
§ 112
§ 113
§ 114
§ 114a
ČÁST ČTVRTÁ
§ 115
§ 116
§ 117
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Regulation Information
| Citation | Decree No. 422 / 2016 Coll., on Radiological Protection and Security of Radionuclide Source |
|---|---|
| Regulation Type | Order |
| Author | - |
| Collection | Code of Laws |
| Date of Promulgation | 23.12.2016 |
|---|---|
| Effective from | 01.01.2017 |
| Effective until | - |
| Status | Valid |
The regulation text is for informational purposes only.
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