422/2016 Sb.
DECREE
of 14 July 1999. December 2016
on radiation protection and the security of radioactive sources
State Office for nuclear safety, establishes, pursuant to section 236 of the Act No.
263/2016 Coll., the Atomic Act, for the implementation of § 9 para. 2 (a). (c)), and (j)), §
Article 17(1). 3, § 24 para. 7, § 25 para. 2 (a). a) to (d)), § 60 para. 4, §
paragraph 61. 6, § 63 para. 6, section 66 paragraph 1. 6, section 67 para. 4, § 68 para. 2
(a). a) to i), § 69 para. 2, § 70 para. 2 (a). (b)), and (c)), § 71 para. 2,
§ 72 para. 5, § 73 para. 3, section 74 para. 4, section 75 para. 5 (b). and, § 76)
paragraph. 6, § 77 para. 2, § 78 para. 3, § 81 para. 3, § 83 para. 7, § 84
paragraph. 6, § 85 para. 4, § 86 para. 3, § 87 para. 5, § 88 para. 6, § 89
paragraph. 2, section 93 para. 4, § 95 para. 6, § 96 para. 3, § 98 para. 4, § 99
paragraph. 5, § 100 para. 3, § 101 paragraph. 4, § 104 paragraph. 9 and § 164 of paragraph 1. 2:
PART THE FIRST
INTRODUCTORY PROVISIONS
§ 1
The subject of the edit
This Decree incorporates the relevant provisions of Euratom ^ 1) and establishes
requirements for the provision of radiological protection in exposure situations and
security of radioactive sources, including
source 1. up to 3. security categories.
The concepts of
§ 2
For the purposes of this Ordinance, means the
and the proportion of medium dose) absorbed power passed to ionizing
radiation in a volume element, and the weight of the substances that are contained in this
volume element,
(b)) share of activity expected values the number of nuclear transformations of
energy State and time period in which these transformations
will take place,
c) D-value of the activity of the radionuclide in the source, which
can cause severe tissue reaction, unless under supervision; D-value
set out in annex 1 to this notice,
d) equivalent dose the product of the radiation weighting factor and medium
absorbed dose in organ or tissue for ionizing radiation or the sum of the
such products, if the radiation field is composed of multiple
species or energy; the radiation weighting factor set out in annex 2 to this
the Decree,
(e) the sum of the products of effective dose) of tissue weighting factors and
the equivalent dose in the irradiated tissues or organs; tissue weighting
the factor set out in annex 2 to this Decree,
(f) collective effective dose) the sum of the effective doses of all
individuals in a particular group,
g) period of tau
1. the 50 years for receipt of radionuclides in adults, or
2. the period to 70 years of age for receipt of radionuclides in children
h) committed effective dose the time integral of the input of the effective dose
for tau from receipt of the radionuclide,
I) committed equivalent dose the time integral of the equivalent
the dose for tau from the intake of the radionuclide,
j) the batch product absorbed dose equivalent at a point in tissue
and quality factor expressing the different biological effectiveness
different types of ionizing radiation; quality factor set out in annex No. 2
This Decree,
to batch equivalent) dose equivalent at a point under the
the surface of the body at a depth of tissue
l) ICRU sphere ball with a diameter of 30 cm, made of a material of equivalent
the tissue with a density of 1 g/cm3 and mass composition of 76.2% oxygen, 11.1%
carbon, 10.1% hydrogen and 2.6% nitrogen,
m) spatial batch equivalent dose equivalent at a given point
the field of radiation, which would create a much greater and accordingly
Advanced field in the ICRU sphere at a depth of 10 mm on the RADIUS opposing
the direction of motion of the particles in the focused,
n) directional dose equivalent the dose equivalent at a given point field
the radiation that would be created by the corresponding expanded field, in the ICRU SPHERE
the sphere at a depth of 0.07 mm for the RADIUS in a specified direction,
about volume activity of radon) equivalent weighted sum volume
activity a1 218Po, 214Pb a2 activity concentration and activity concentration a3
214Bi; equivalent volume activity of radon is equal to the sum of the 0.106 x
A1, a2 and 0.381 0.513 x x a3,
p) income of the radionuclide activity of a radionuclide taken in human
the organism from the environment, in particular the ingestion or inhalation,
q) conversion factor income factor indicating the radionuclide
effective dose per unit intake of the radionuclide;
the conventional values of the conversion factors of intake of the radionuclide shall lay down
Annex No. 3 to this Decree,
r) hing conversion factor income of the radionuclide ingestion,
with a conversion factor of hinh) radionuclide intake by inhalation,
t) Iing the annual income of the radionuclide ingestion,
the annual income of the radionuclide Iinh) inhalation,
indicative dose time in) effective dose from an annual intake of all
radionuclides present in the water, with the exception of tritium, 40 k, 222Rn and
short-term products its transformation,
w) dental tomografem dental panoramic computing device or other
devices used in medical exposure in dental radiodiagnostic medicine for
photography of the teeth, jaw or skull, which allows a tomography or
panoramic photography with a wide conical volume or photography with
using computed tomography, or creating three-dimensional images, or
tomography scans, and
x) neužitečným radiation ionizing radiation originating from the source.
ionizing radiation, which is outside the main volume of radiation.
PART TWO
RADIATION PROTECTION
TITLE I OF THE
GENERAL RULES OF RADIATION PROTECTION
Part 1
Limits
§ 3
General limits for residents
(§ 63 para. 6 of the Atomic Act)
The General limits for residents from radiation exposure of all permitted or
registered activities in one calendar year are
and for the sum of the effective doses) of external exposure and time efficient
benefits of internal exposure of 1 mSv,
(b)) for the equivalent dose in the lens of the eye 15 mSv and
(c)) for the average equivalent dose to any 1 cm2 of skin 50 mSv without
regardless of the size of the irradiated area.
§ 4
Limits for radiation worker
(§ 63 para. 6 of the Atomic Act)
(1) the limits for radiation worker must be used to limit the
professional exposure and are
and for the sum of the effective doses) of external exposure and time efficient
the benefits of the internal irradiation of 20 mSv per calendar year or the value of the
approved by the authority pursuant to § 63 para. 4 the Atomic Act, but not more than 100
mSv per 5 consecutive calendar years and at the same time 50 mSv in one
the calendar year,
(b)) for the equivalent dose in the lens of the eye 100 mSv in 5 consecutive
calendar years and at the same time 50 mSv in one year,
(c)) for the average equivalent dose to any 1 cm2 of skin 500 mSv per
the calendar year, regardless of the size of the irradiated areas and
(d)) for the equivalent dose for the hands from fingertips to the forearm and legs from
feet up to the ankles 500 mSv in any one calendar year.
(2) in considering whether to avoid exceeding the limits for radiation
the worker must
and be carried out consistently,)
(b) the sum of the doses from) consider all exposure pathways and in all work
activities that radiation worker performs, and
(c) in the case of radiation) take into consideration the worker who is not external
worker, the performance of the activities, where it is exposed to
exposure limits for radiation worker subject, for more
informants, registrantů or permit holders.
(3) Radiation worker, which has been found to be exceeding the limits
exposure, must be temporarily removed from the work with the source of ionising
radiation until it is evaluated by his medical fitness to the next
work is the source of ionising radiation and to define the conditions for the
job.
(4) the limits for radiation worker who is found to be
the disabled are eligible pursuant to paragraph 3, it is not the reason for its exclusion
from the usual working activity or for transfer to another place of work,
If the person for whom the work is exercised, does not have such a
exclusion of other serious reasons.
§ 5
Limits for the student and the student's
(§ 63 para. 6 of the Atomic Act)
(1) compliance with the limits for the student and the student must be the holder of the
authorisation, on whose work the pupil and the student in the course of their studies,
working with the source of ionizing radiation.
(2) in considering whether to avoid exceeding the limits for the student and the student's
must
and) be carried out consistently and
(b) the sum of the doses from) consider all exposure pathways, and in all the activities,
that pupil and student with a source of ionizing radiation.
(3) limits for the pupil and student between the ages of 16 and 18 years who are
in the course of their studies, are obliged to work with the source of ionising radiation,
are for one calendar year
and for the sum of the effective doses) of external exposure and time efficient
benefits of internal exposure 6 mSv,
(b)) for the equivalent dose in the lens of the eye 15 mSv,
(c)) for the average equivalent dose to any 1 cm2 of skin mSv 150 without
regardless of the area exposed, and
(d)) for the equivalent dose for the hands from fingertips to the forearm and legs from
feet up to the ankles 150 mSv.
(4) the limits for the pupil and student younger than 16 years of age, who are required to
in the course of their studies, work with the source of ionising radiation, are
consistent with the General limits for residents.
(5) limits for the pupil and student older than 18 years of age, who are required to
in the course of their studies, work with the source of ionising radiation, are
the same as the limits for radiation worker.
§ 6
Derived limits
(§ 63 para. 6 of the Atomic Act)
(1) the limits for radiation workers are considered to be nepřekročené, if
quantitative indicators are not exceeded, expressed in measurable
inputs (hereinafter referred to as "derived limits").
(2) derived from external exposure limits are
and) for personal dose equivalent at a depth of 0.07 mm 500 mSv per value
the calendar year,
(b)) for the personal dose equivalent at a depth of 3 mm, a value of 20 mSv per
calendar year, and
(c)) for the personal dose equivalent at a depth of 10 mm, a value of 20 mSv per
calendar year.
(3) for internal exposure limits Derived for the calendar year, in addition to
the cases provided for in paragraph 5, are to receive individual
radionuclide radiation worker
the ingestion activity)
0.02
-------------------------------
Hing
(b)) by activity
0.02
-------------------------------
hinh
(4) while the external and internal radiation exposure during a calendar
of the year, except in the cases referred to in paragraph 6 shall be considered as limits for the
radiation workers in nepřekročené, if at the same time
HP (0.07) = 0.5 MW and <
HP (10) + SUM of hi, ing Ii, ing + SUM of hi, inh and inh = 0.02, < Sv
where
HP (0.07) (Sv) is the annual personal dose equivalent at a depth of 0.07 mm,
HP (10) (Sv) is the annual personal dose equivalent at a depth of 10 mm,
Hi, ing (Sv/Bq) is a conversion factor for receiving individual radionuclide
the ingestion; conversion factor set out in annex 3 to this Decree,
(Ii), ing (Bq) is the annual income of the individual radionuclide ingestion,
Hi, inh (Sv/Bq) is a conversion factor for receiving individual radionuclide
by inhaling; conversion factor set out in annex 3 to this
the decree and the
(Ii), inh (Bq) is the annual income of the individual radionuclide
by inhaling.
(5) for the calculation referred to in paragraph 4 for unidentified radionuclides,
chemical forms of the inhaled aerosol properties or the annual
intake of radionuclides, their forms or properties of the inhaled
aerosol, for which it set out in annex 3 to this Supreme Decree
conversion factor for the reception of ingestion, or inhalation.
(6) For irradiation of mixtures of radionuclides emitting alpha radiation long term
uranium-radio series is derived income limit by 3 200 Bq per
calendar year.
Part 2
Optimization of radiation protection
Optimization of radiation protection practices
§ 7
[To section 66 paragraph 6 (b), (c)) of the Atomic Act]
(1) when the optimization of radiation protection has to anyone who conducts activities
in the context of exposure situations, provide variants ensure radiation
protection and of them select the optimal variant of ensure radiation protection in
the exposure situation.
(2) the selection of the optimal ensure radiation protection must be
carried out by examining the possibility of planned and potential reduction of benefits
individuals or groups of the population. The measures taken to
the protection of individuals or groups of the population against the influence of the resources
ionizing radiation can be applied
and for sources of ionising radiation),
(b)) in the environment between the source of ionizing radiation and a natural person, or
(c)) for natural persons.
(3) when selecting the optimal variants of ensuring radiation protection must be
preferred size limit exposure directly at the source of ionising
radiation.
(4) in selecting the optimal variants ensure radiation protection must be
taken into account representative characters that are associated with the appropriate
activities. Representative characters as stipulated in annex 4 to this notice.
(5) when selecting the optimal variants ensure radiation protection can be, if
possible, make comparing the cost of various measures to increase the
radiation protection, in particular the transfer of individuals or construction
additional barriers, with the financial rating of the expected reduction
exposure to radiation.
(6) a comparison of the costs referred to in paragraph 5 shall be carried out so that the
reduction of the collective effective dose for a group of people under consideration is multiplied by
by a factor of
and 0.5 million). EUR/MW radiation activity, which is the average effective
the dose for an individual of less than 1/10 of the relevant dose limits,
(b)) 1 million. EUR/MW radiation activity, which is the average effective dose
in individuals greater than 1/10, but less than 3/10 of the relevant limits
exposure,
c) 2.5 mil. EUR/MW radiation activity, which is the average effective
dose in individuals greater than 3/10 of the relevant dose limits,
(d)) 1 million. CZK/mass for medical exposure,
e) 0.5 million. CZK/mass for exposures from natural sources of ionizing radiation,
that is not caused by the radiation of the activities, or
f) 2.5 mil. CZK/mass for emergency exposure.
§ 8
[To section 66 paragraph 6 (b), (c)) of the Atomic Act]
(1) the optimization of radiation protection Procedures shall anyone who performs
activities in the context of exposure situations, use regularly, so that
have not been omitted from the newly established conditions for the relevant exposure situation
or new options to provide radiation protection for this exposure
the situation, in particular if the exceeding of dose limits laid down
batch optimization limits or reference levels.
(2) in the case of medical exposure for radiotherapeutic purposes, including medical
application of the radionuclide shall be the exposure of target volumes for each physical
the person undergoing treatment individually planned and their attainment
adequately verified, and must be taken into account that
benefits for volumes and tissues that are not the target must be as low as
This is when the intended radiotherapeutic purpose of the exposures sensibly
achievable.
(3) in establishing batch optimization limits for radiation activity
or the source of ionising radiation must be taken into account
and) experience with similar activities and sources of ionizing
radiation so that the level of radiation protection has not been lower than has already been
achieved, and
(b)) other activities and effects of ionizing radiation sources so that the
There was no exceeding of dose limits.
(4) when the optimization of radiation protection must be a procedure of this optimization
documented.
(5) the documentation of the optimization of radiation protection must
and a systematic and structured way) describe how this optimization,
(b)) take into account all considerations in the exposure situation used in the
This optimization and
(c)) have used variants ensure radiation protection and
representative characters.
§ 9
A representative assessment of exposure of the person and optimization studies
[To section 81, paragraph 3 (b), (d)) and § 82 para. 4 Atomic law]
(1) the assessment of the exposure of the representative person shall be carried out
Conservative estimates. How to perform a conservative estimates
the exposure of the representative of the person laid down in annex 5 to this Decree.
(2) the content optimization studies for determining the authorized limit
the exposure of the representative of the person laid down in annex 6 to this Ordinance.
Part 3
Categorization
§ 10
Waiver
(Section 67, paragraph 4, of the Atomic Act)
(1) exemption levels for radionuclides activity laid down in annex # 7 to the
This Decree. The exemption levels of activity shall apply to the total
quantities of radioactive substances used by the person within a specific
radiological activity.
(2) the exemption levels for radionuclides activity concentration used in the
the exact radiation activities set out in annex # 7 to this Decree.
(3) the Activity of a mixture of radionuclides is less than the exemption levels, if
the sum of the shares of the individual activities of radionuclides and the relevant
exemption levels of activities is less than 1.
(4) the concentration of the mixture of radionuclides is less than the exemption
levels if the sum of the weight of the activities of individual shares
radionuclides and the relevant exemption levels by weight of activities is
less than 1.
§ 11
High-activity source
[To section 60, paragraph 4 (b)) of the Atomic Act]
The level of activity, which is a closed source radioactive
high-activity source, set out in annex 8 to this Ordinance.
Categorisation of sources of ionizing radiation
§ 12
[§ 61 para. 6 (a)) of the Atomic Act]
Minor source of ionizing radiation is
and) generator of radiation emitting ionizing radiation with an energy of not more than
5 keV, which is not a significant source of ionizing radiation,
(b)) and the cathode tube intended for the display or other electrical equipment
operating at a potential difference not exceeding 30 kV, which is
power consumption of the 3-d dose equivalent at any accessible
place at a distance of 0.1 m from the surface of the device is less than 1 mikroSv/h,
or
c) radioactive substance, for which the sum of the shares
1. the activities of radionuclides and the relevant exemption activity levels
is greater than 1, or
2. the activities of radionuclides by weight and the relevant exemption levels
activity concentration not greater than 1.
section 13 of the
[§ 61 para. 6 (a)) of the Atomic Act]
Small source of ionizing radiation is
and radiation generator) is not a least, or a significant source of
ionizing radiation, designed so that on any accessible
place at a distance of 0.1 m from the surface of the device is the power consumption of the 3-d
dose equivalent is less than 1 mikroSv/h, and in places intended for the
normal working conditions for the handling and operation of the appliance exclusively
hands is the power consumption of the directional dose equivalent of not more than 250 mikroSv/h,
(b)) means a radioactive source, which is not an insignificant source of
ionizing radiation, for which the sum of the activities of radionuclides and shares
applicable exemption levels of activity or the sum of the shares
by weight of activities of radionuclides and the relevant exemption levels
activity concentration is less than 100, in the case of long-term
radioactive sources emitting radiation alpha, including
radioactive sources emitting neutrons, and less than 1 000 v
the other cases,
c) equipment containing radioactive sealed source, which is not
minor source of ionizing radiation, designed so that the
any accessible place, at a distance of 0.1 m from the surface of the device is
3-d dose equivalent power consumption of less than 1 mikroSv/h, and on the
places designated under normal working conditions for the handling and operating instructions
the device exclusively with your hands is the power consumption of the directional dose equivalent
up to 250 mikroSv/h, or
(d) a radiopharmaceutical) open source who is not insignificant source of
ionizing radiation, in which the combined share of activities and the relevant
exemption levels of activities or by weight of the combined share of activities and
the relevant exemption levels of radionuclide nuclide is
less than 10.
§ 14
[§ 61 para. 6 (a)) of the Atomic Act]
A simple source of ionizing radiation is ionizing radiation source,
that is not insignificant, small, significant or very significant source of
ionizing radiation.
§ 15
[§ 61 para. 6 (a)) of the Atomic Act]
A major source of ionizing radiation is
and radiation generator), intended for medical exposure, in addition to the bone
a densitometer x-ray and dental equipment, other than dental
the compute tomography,
b) particle accelerator,
c) source of ionizing radiation intended to radiotherapy protons, neutrons and
other heavy particles,
d) equipment containing radioactive sealed source intended for
radiotherapy,
e) equipment containing radioactive sealed source intended for irradiation
items, including foodstuffs, raw materials, subjects of normal use, or
other things,
f) mobile closed-source of the radionuclide flaw detector, or
g) high-activity source.
section 16 of the
[§ 61 para. 6 (a)) of the Atomic Act]
A very significant source of ionizing radiation is a nuclear reactor.
Categorization for the purposes of cross-border mobility and security
§ 17
[§ 61 para. 6 (b)) of the Atomic Act]
(1) the source of ionising radiation 1. Security category
and) radiopharmaceutical thermoelectric generator
(b)) a radiopharmaceutical ozařovač, including ozařovače of tissues and blood,
(c) a radioactive source), which is the ratio of the current activity
and D-value equal to 1 000 or more, or
(d) radioactive source) open, which is the ratio of not more than
processed activities in the workplace and the D-value is equal to 1,000 or more.
(2) the source of ionising radiation 2. Security category
and radioactive source) designed for defectoscopy,
(b) the radioactive source) designed for brachytherapy treatment with high or
middle of the batch input,
(c) radioactive source) other than those mentioned in point (a)), or (b))
which is the ratio of the current activity and D-values less than 1 000 and
at the same time equal to 10 or more, or
(d) radioactive source) open, which is the ratio of not more than
processed activities in the workplace and the D-values less than 1 000 and
at the same time equal to 10 or more.
(3) source of ionising radiation 3. Security category
and radioactive source) for logging,
(b) the radioactive source) closed in the indicating or measuring devices,
that is a high-activity source,
(c) radioactive source) other than those mentioned in point (a)), or (b))
which is the ratio of the current activity and D-value is less than 10, and at the same time
equal to 1 or greater,
(d) radioactive source) open, which is the ratio of not more than
processed activities in the workplace and the D-value is less than 10, and at the same time
equal to 1 or more, or
e) liquid or solid substance containing more than 30% of the uranium, of which
the activity is greater than 160 MBq.
(4) the source of ionizing radiation 4. Security category
and radioactive source) designed for brachytherapy treatment with a low
batch input with the exception of the eye applicator and permanent
the implant,
(b) the radioactive source) closed in the indicating or measuring devices,
that is not a high-activity source,
(c) radioactive source) closed in the static electricity Eliminator
(d) radioactive source) other than those mentioned in points (a) to (c)))
which is the ratio of the current activity and D-values less than 1, and at the same time
equal to 0.01 or greater, or
(e) a radioactive source), which is the ratio of not more than
processed activities in the workplace and the D-values less than 1, and at the same time
equal to or greater than 0.01.
(5) the source of ionizing radiation 5. Security category
and) eye applicator and a permanent implant for radiotherapy,
b) source of ionizing radiation for radionuklidovou rentgenofluorescenční
analysis,
(c) the electron capture detector),
d) radiopharmaceutical source for Mössbauerovskou,
e) calibration source of ionizing radiation for positron emission
tomography,
(f) a radioactive source), which is the ratio of the current activity
and D-values less than 0.01 and current activity is higher than the
the exemption level, or
g) open a radiopharmaceutical resource that is the ratio of not more than
processed activities in the workplace and the D-values less than 0.01 and
at the same time, the current activity is higher than the exemption level.
section 18
[§ 61 para. 6 (b)) of the Atomic Act]
(1) A workplace where the collection of radionuclide
resources must be used for the purposes of security security categories
the entire file of ionizing radiation sources in the workplace or in the
transport packaging file.
(2) the Security category of the whole set of ionizing radiation sources
referred to in paragraph 1 must be established on the basis of the aggregate ratio of A/D,
calculated in the following way:
SUM and Ai, n
A/D = SUM-----------
n Dn
where Ai, n is an activity, and each resource and the radionuclide n and
DN is the D-value for radionuclide n.
§ 19
Categorization of sites
[§ 61 para. 6 (b), (c)) of the Atomic Act]
(1) a Workplace category I is
and with a small source of) ionizing radiation, whose type is not
approved by the authority,
b) workplace with bone densitometer, which is not a small source of
ionizing radiation,
c) workplace with a health or dental x-ray equipment,
d) workplace with cabin x-ray equipment,
e) workplace with the indicating or measuring device containing a closed
radioactive source, in which the nature of the activity does not require radiation
definition of the controlled area, and
f) workplace with technical x-ray equipment, in which the character of the
radiation activity does not require the definition of controlled area.
(2) Workplace II. a category is a
and with a simple source of) ionizing radiation, which is not
workplace category I,
b) workplace with x-ray equipment intended for radiodiagnostic medicine or
radiotherapy, with the exception of
1. bone densitometer,
2. dental x-ray equipment, or
3. veterinary x-ray equipment,
(c)) of the workplace with a cell containing a closed conduit
means a radioactive source,
d) workplace with mobile ozařovačem containing sealed radioactive
the source,
e) workplace with the indicating or measuring device containing a closed
radioactive source, in which the character of the radiation activity requires
the definition of controlled area,
f) workplace with technical x-ray equipment, in which the character of the
radiation requires a definition of the controlled area, and
g) workplace with compact extracorporeal blood containing ozařovačem
closed means a radioactive source.
(3) Workplace III. a category is a
and with a particle accelerator),
b) workplace equipment containing radioactive sealed source,
which is intended for radiotherapy,
c) recognised by the UK,
d) workplace equipment containing sealed radioactive source and
intended for irradiation of items, including food and raw materials, objects
normal use, or other things, and
e) departments, which carry out activities linked to obtaining
the radioactive mineral, with the exception of rehabilitation and reclamation carried out in the
extractive waste storage areas, on which mining was discontinued
activity.
(4) Workplace IV. a category is a
and the site of the nuclear installation) and
(b)) of the workplace with the storage of radioactive waste, which is not a nuclear
device.
(5) the criterion for classification of workplaces with open radionuclide
the source of the category, in addition to the departments referred to in paragraph 3 (b). (e)), and
paragraph 4, the equipment of the workplace ventilation, insulation and shield
devices and the implementation of the sewage system. Standard equipment requirements
the workplace for the purpose of its inclusion in the categories set out in annex 9 to the
This Decree.
section 20
Categorization of exposed workers
[§ 61 para. 6 (b), (d)) of the Atomic Act]
(1) the classification of radiation worker in category A or B must be
taken into account
and the worker's radiation exposure) expected during normal operation and
b) potential exposure of radiation worker.
(2) Radiation worker category and is the radiation worker who would
able to receive the
and) effective dose greater than 6 mSv per year,
b) equivalent dose greater than 3 mSv to the lens of the eye, or
c) equivalent dose greater than 3/10 limit exposure of skin and
the limb.
(3) the radiation worker category B is the radiation worker, other than
referred to in paragraph 2, if the Atomic law required
categorization.
Part 4
Quantities and really important from the point of view of radiation protection
section 21
Enumeration values and facts critical from the standpoint of radiation protection
[To section 25, paragraph 2 (a)) of the Atomic Act]
(1) the Quantities important in terms of radiation protection quantities are
and) used for determining personal doses of natural persons,
b) characterizing the radiation field and the occurrence of radionuclides to the
workplace,
(c) discharges of radionuclides to characterize) around the workplace,
d) characterizing the radiation field and the occurrence of radionuclides in
around the workplace,
(e)), used in the assessment of the properties of ionizing radiation sources,
f) characterizing the source of ionizing radiation and
g) used for the assessment of exposure from natural sources of radiation.
(2) the Facts relevant from the point of view of radiation protection are
and source properties of ionizing radiation),
(b)) the protective properties of personal protective equipment and other
protective gear and equipment for working with the source of ionising radiation,
(c)) for the transport packaging properties, storage or disposal of
radioactive or fissile substance,
d) properties of an accessory that has an impact on radiation protection,
e) evidence type-approval if the source of ionising
radiation which is subject to approval
(f)) the fact on the certificate contained a radioactive source,
(g)) the matters referred to in the accompanying document of the open
resources,
h) information on the methods used to monitor people, workplace, neighborhood
workplace and effluents, and the results of this monitoring,
I) evidence informing of radiation worker about the risk
his work,
j) evidence of individuals entering the lesson
controlled area,
k) evidence verifying knowledge of radiation worker of
the safe management of sources of ionizing radiation and the eligibility to
regular tests, it
l) conclusions of the preventive medical examinations to verify the health
radiation worker categories and eligibility,
m) fact demonstrating non-compliance with the requirements of the radiation protection
established in the framework of continuous surveillance,
n) data on the radiation worker, the workplace, and the results of its
individual monitoring,
about) the personal data held in the radiation of the card,
p) data on inputs and length of stay of individuals in a controlled area,
q) the results of the inventory of closed radioactive sources and
r) the facts listed in the logs of measurement issued by the holder of the
an authorisation pursuant to § 9 para. 2 (a). h) points 2 and 5 to 7 of the Atomic Act.
section 22
The scope of monitoring, measurement, evaluation, verification and recording quantities
and the facts relevant in terms of radiation protection
[To section 25, paragraph 2 (b)) of the Atomic Act]
(1) the properties of ionizing radiation sources must be monitored, measured,
evaluated, validated and recorded
and, imports) for the production or distribution to the extent necessary to
1. the conformity assessment of sources of ionizing radiation to the approved type,
2. assessment of the conformity of the sources of ionizing radiation with the requirements of the relevant
technical regulations,
3. the issue of the certificate of the closed of the source, or
4. the issue of the movement of the source of the open worksheet,
(b)) when taking the sources of ionizing radiation, and before his
the use of a form of acceptance testing and
(c) in the course of use of resources) of ionizing radiation in the form of
1. tests of long-term stability and
2. testing the operational stability.
(2) evidence type-approval, the facts referred to in
the certificate contained a radioactive source and the matters referred to in
accompanying report of the source must be open
recorded to the extent necessary for the registration of ionizing sources
radiation.
(3) the evidence informing the worker about the risk of radiation
his work and the fact evidencing the lessons of natural persons
entering the controlled area shall be monitored and recorded
in the range, under section 50 and the input data and the time of stay of individuals
controlled area must be monitored and recorded in the range according to the
§ 33 para. 3.
(4) the facts demonstrating knowledge of radiation worker of
the safe management of sources of ionizing radiation and the eligibility to
him regular tests must be monitored and recorded in the
scope according to § 50.
(5) the personal data held in the radiation of the licence must be tracked
evaluated and recorded in the range, under section 36.
(6) the results of the inventory of sealed radioactive sources must be
recorded in the range under section 41.
The facts contained in the certificate of the source
Article 23 of the
[To section 25, paragraph 2 (b)) of the Atomic Act]
The facts set out in the certificate contained a radioactive source must
be recorded in the following range:
and identification number certificate enclosed) of the source,
(b)) or the identification number of the closed-end of the source,
(c)), the manufacturer and country of origin of the contained of the source,
(d)) of an approved type, with the designation whose properties are properties
the closed-end of the source in concert,
(e) information on the nature of the radionuclide),
(f)) activity data contained with date of the source,
to which the activity is covered, and an indication of the highest content of
the radionuclide,
g) in the case of a significant source of ionizing radiation kermová yield in
the air indicating the date, to which the kermová coverage applies,
h) data on the physical and chemical form of the radionuclide and its carriers,
I) details about the dimensions of a closed of the source,
j) data on the encapsulation or protective overlay,
the degree of resistance to closed) of the source relative to the
the approved type
l) the results of tests of radioactive contamination and leakage
the closed-end of the source,
m) the recommended duration of use of the closed-end of the source,
n) date of issue of the certificate of the source and the closed
about) the identification of the person the certificate enclosed
of the source posted and signature of an authorised representative of this
of the person.
section 24
[To section 25, paragraph 2 (b)) of the Atomic Act]
In the case of closed-end of the source, that the technical
to mark the brand and the serial number and is not high-activity
the source, a must for all closed radioactive sources of the same type
and of the same size, which contain the same quantity of the same radionuclides
and treats the same person, the facts referred to in the certificate
the closed-end of the source are recorded in the following
range:
and identification number certificate enclosed) of the source,
(b)) the number of sealed radioactive sources of the same holder of the authorization,
(c)) of an approved type, with the designation whose properties are properties
the closed-end of the source in concert,
(d) an indication of the nature of the radionuclide),
(e) an indication of the activity) sealed radioactive sources with an indication of the date on
to which the activity is covered,
f) indication of the highest content of radionuclide in closed
radioactive sources,
g) data on the physical and chemical form of the radionuclide and its carriers,
h) dimensions of sealed radioactive sources,
I) data encapsulation or protective overlay,
j) resistance of sealed radioactive sources due to the
the approved type
the results of the tests carried out to) of radioactive contamination and leakage
sealed radioactive sources,
the recommended duration of use l) sealed radioactive sources and other
details for the planned verification of their tightness and
m) date of issue of the certificate of closed radioactive sources and
identification data of the person who the certificate sealed radioactive
resources issued and signature of the authorized representative of that person.
§ 25
The facts set out in the accompanying document of the open
resources
[To section 25, paragraph 2 (b)) of the Atomic Act]
(1) the matters referred to in the accompanying document of the open
resources must be recorded in the following range:
and) identification number of the passport of an open
resources,
(b)) or identification number of an open specification of
resources,
(c)) in the case of an open undertaking subject
the approval of an approved type, with whose characteristics are
Open the properties of the source in concert,
(d) an indication of the nature of the radionuclide),
e) data on the physical and chemical form of the radionuclide and its carriers,
(f)) activity data and mass activity of the open
sources with an indication of the time to which the information relates,
g) data on the chemical and radiochemical purity, if possible,
h) information about the type of packing of the open of the source,
I) date of issue of passport open of the source,
j) changes in the facts referred to in subparagraphs (a) (d)) to (i)) and
to) the identification of the person accompanying the open worksheet
of the source posted and signature of an authorised representative of this
of the person.
(2) for the same open source together must be passed to the radionuclide
be set forth in the accompanying document of the open
sources recorded in the range referred to in paragraph 1 and for an individual
radionuclide or mixture of radionuclides, the individual must be given
the total number of transmitted unsealed sources.
(3) if they are from a nuclear device or from the duty station at which the operation
arise or are transferred to other concentration
person objects or substances contaminated with radionuclides, these must be
the facts set out in the accompanying document of the open
sources recorded in the following range:
and) the information pursuant to paragraph 1. a), b), (d)), h), (i)) and k),
(b)) and the activity of the highest wattage dose
equivalent at a distance of 0.1 m from the surface and
(c) the highest area) information about the activity on 100 cm2 surface in case of
surface contamination of radionuclides.
Part 5
Test sources of ionizing radiation
section 26
Acceptance test
[To section 68, paragraph 2 (a)) and § 69 para. 2 (a). (c)) of the Atomic Act]
(1) the acceptance test must be performed after the installation source
ionizing radiation before use.
(2) the acceptance test must include the
and a Visual check of integrity and) integrity of the sources of ionizing
radiation,
(b)) in the case of an open undertaking to verify the data referred
in the accompanying document issued by the manufacturer of the source open
According to § 25 para. 1 (b). and) and (b)),
(c) in the case of restricted) of the source
1. verify the information contained on the certificate of
resources and
2. leak test, including the determination of measurement uncertainty; scope and method
perform leak tests contained a radioactive source down
Appendix 10 to this Decree,
(d)) in the case of devices with sealed radioactive source
1. verify the functionality of devices with sealed radioactive source
2. verify the functionality of the management, control, security,
signalling and indicator systems
3. verification of the operating parameters and the properties of the device with a closed
the source of the radionuclide,
4. determination of quantities important in terms of the dosimetry of the purpose of use
This device, in the case of radiotherapy, including their uncertainties
5. test the tightness of the closed-end of the source test abrasion
the replacement desktop, including the determination of measurement uncertainty; scope and method
abrasion test on replacement desktop, set out in annex 10 to this no.
the decree and the
6. the measurement or estimation of useless radiation in the vicinity of equipment with closed
the source of the radionuclide,
e) in the case of radiation generator
1. Verify that the radiation generator
2. verify the functionality of the management, control, security,
signalling, display and imaging systems,
3. verification of the operating parameters and properties of radiation generator
4. determination of quantities important in terms of the dosimetry of the purpose of use
radiation generator, in the case of radiotherapy, including their uncertainties and
5. measurement of radiation in the vicinity of useless radiation generator or its
estimate, in the case of intraoral dental or dental panoramic x-ray
the device, and
(f)) to verify the data from the manufacturer that are significant for the way
the use of the device in terms of radiation protection, or in the event that this
verification cannot be performed in a standard mode of operation, check that the
validation of these data, the person who carried out a source of ionizing radiation
installed.
(3) in the case of sources of ionizing radiation which is subject to the approval of
acceptance test must be carried out in the range referred to in paragraph 2 and
decision on approval of the product.
(4) a person who performs the acceptance test, must adapt its
the scope of the specific purpose of use and the specific characteristics of the source
ionizing radiation and its accessories, which has an impact on radiation
the protection.
The test of long-term stability
section 27 of the
[To section 68, paragraph 2 (a)) of the Atomic Act]
(1) long-term stability Test must be carried out
and with the frequency) regularly at least once per period
1. the 12 months in the case of sources of ionising radiation intended for medical
exposures in radiotherapy,
2. the 12 months in the case of a significant source of ionizing radiation intended
for medical exposure in radiodiagnostic medicine or Interventional Radiology,
3. the 12 months in the case of a mobile device with a closed defektoskopického
the source of the radionuclide,
4. as provided for in annex 11 to this Ordinance in the case of restricted
a radioactive source, which is not part of the device with a closed
radionuclide source, or it can be to perform
separate tests of the long-term stability of this device cut,
5.24 months in the case of significant sources of ionizing radiation
not mentioned in points 1 to 4 and
6.36 months in the case of a simple source of ionizing radiation
not mentioned in points 1 to 4,
(b)) at each time about the suspected source to function incorrectly
ionizing radiation or its accessories, which has an impact on radiation
protection,
c) leakage is suspected, the closed-end of the source,
(d)) if the test results indicate operating stability, or point to the
ionizing radiation source to function incorrectly or its accessories,
that has an impact on radiation protection,
e) after maintenance, repair or other service that is important from the
radiation protection and could significantly affect the property
validated during the test of long-term stability or parameter when it
being validated, in particular after exchanges of x-ray tubes or the image receptor, after
for service to the system kolimace a volume or to systems that determine the
the geometry of the exposure or after fixing the exposure automatically or generator,
f) after replacing the accessory sources of ionizing radiation, which has an impact on
radiation protection, and
g) after removal of deficiencies found during the test of long-term stability.
(2) the long-term stability of Test carried out pursuant to paragraph 1. and)
must be made no later than the calendar month during which the
the deadline for its implementation.
section 28
[To section 68, paragraph 2 (a)) and § 69 para. 2 (a). (c)) of the Atomic Act]
(1) long-term stability Test must include a Visual inspection of the
integrity and the integrity of the sources of ionizing radiation, and in the case of
and the closed of the source)
1. verify the information contained on the certificate of
resources and
2. leak test, including the determination of measurement uncertainty; scope and method
perform leak tests contained a radioactive source down
Appendix 10 to this Decree,
(b)) closed radionuclide source
1. verify the functionality of devices with sealed radioactive source
2. verify the functionality of the management, control, security,
signalling and indicator systems
3. verification of the operating parameters and the properties of the device with a closed
radionuclide sources and their stability,
4. determination of quantities important in terms of the dosimetry of the purpose of use
This device, verify their stability and in the case of radiotherapy
determination of their uncertainties
5. test the tightness of the closed-end of the source test abrasion
the replacement desktop, including the determination of measurement uncertainty; scope and method
abrasion test on replacement desktop, set out in annex 10 to this no.
the decree and the
6. the measurement or estimation of useless radiation in the vicinity of equipment with closed
the source of the radionuclide in the case that there was a change in its use,
which may affect the values referred to in the last measurement or estimate
balanced the radiation,
c) radiation generator
1. Verify that the radiation generator
2. verify the functionality of the management, control, security,
signalling, display and imaging systems,
3. verification of the operating parameters and radiation generator and their properties
stability,
4. determination of quantities important in terms of the dosimetry of the purpose of use
radiation generator, verify their stability and in the case of radiotherapy
determination of their uncertainties and
5. measurement of radiation in the vicinity of the generator of useless radiation or in the case of
Dental intraorálního or dental panoramic x-ray
his estimate of the device, if there is such a change in its use, which
could affect the values referred to in the last measurement or estimate
balanced the radiation,
d) sources of ionizing radiation which is subject to the approval of the tests in the
the scope of the decision on the approval of the product, and
e) tests of long-term stability after replacing accessories resources
ionizing radiation, which has an impact on radiation protection, authentication
accuracy of the information in the technical dossier of the
accessories that have meaning in terms of radiation protection for common
the use of sources of ionizing radiation or its accessories.
(2) a person who performs the test of long-term stability, must adapt to
its scope to a specific purpose of use and the specific characteristics of the source
ionizing radiation and its accessories, which has an impact on radiation
the protection.
section 29
[To section 68, paragraph 2 (a)) of the Atomic Act]
(1) the test of long-term stability to be implemented under section 27 para. 1 (b). (b))
to g) can be implemented on a limited scale so that, in the case referred to in
and section 27 para.) 1 (b). (b)) was confirmed or refutation of the suspected
ionizing radiation source to function incorrectly or its accessories,
that has an impact on radiation protection,
(b)) § 27 para. 1 (b). (c)) was confirmed or refutation of the suspected
leakage of the closed of the source,
c) section 27 para. 1 (b). (d)) has been verified by the properties of the source of ionising
radiation or its accessories, which has an impact on radiation protection,
that may be associated with the test result of operating stability,
d) section 27 para. 1 (b). (e)) have been verified by the properties and parameters of the audited
in the test of long-term stability, which could affect maintenance, repair
or service,
e) section 27 para. 1 (b). (f)) has been verified by the properties and parameters of the audited
in the test of long-term stability, which could affect the exchange of
Accessories sources of ionizing radiation, which has an impact on radiation
protection, and
f) section 27 para. 1 (b). g) to ensure that the
1. defect recorded in the previous test, the long-term stability of the
removed and
2. deleting the defects suffered another glitch.
(2) an examination of the long-term stability carried out to a limited extent by
paragraph 1 (hereinafter referred to as "partial test of long term stability") cannot be
replace the test of long-term stability in accordance with § 27 para. 1 (b). and).
section 30
Evaluation tests of long-term stability and troubleshooting
[To section 68, paragraph 2 (b), (g)) of the Atomic Act]
(1) deficiencies found during the test of long-term stability to categorize
as very serious or less serious. Rules of categorization of defects
found in the test of long-term stability provided for in annex 12 to the
This Decree.
(2) long-term stability Test is considered successful
and if it is not) deficiencies,
(b)) for the passage of the deadline for the removal of less severe deficiencies found
the test of long-term stability, or
(c) if the partial test) long-term stability made pursuant to section 29 of the
paragraph. 1 (b). (f)), there were glitches.
(3) long-term stability Test shall be considered unsuccessful, if
and it has been) very serious defect, or
b) less serious problem has already been deleted, or its deletion
confirmed by the deadline set by a successful test of the long-term stability
or successful partial examination of long-term stability.
(4) If during the test detected very serious long-term stability
glitch, a person who performs the test shall promptly disclose in writing to the
This fact to the holder of the authorisation or registrantovi and clinical
radiological physicist, if its availability is required by
other legislation and bring it in the Protocol of tests of long-term
stability.
(5) the time limit for the removal of less severe deficiencies must provide for the person who
performs a test of long-term stability, which is this defect.
The deadline for the removal of less severe deficiencies and operational restrictions
from this defect, the person must
and after finding this) immediately inform the holder of the permit or glitches
registrantovi and clinical radiological physicist, if required
its availability under another law, and
(b) is in the log) State from the test of long-term stability.
(6) in determining the time limit for the removal of less severe defects must be
take into account the nature of the detected less serious defects, and the way the current
the use of sources of ionizing radiation and its accessories, which has
effect on radiation protection.
(7) the deadline for the removal of less severe defects cannot be longer than 3
months and runs from the date the test of long-term stability, which
This glitch was detected for the first time.
Operational stability test
section 31
[To section 68, paragraph 2 (b)), and (c)) and § 69 para. 2 (a). (c)) of the Atomic Act]
(1) the Registrant must perform tests in the scope and operational stability
the frequency of that provided for in annex 13 to this Decree.
(2) the extent and frequency of the tests, the holder must establish operational stability
authorisation to include
and a Visual check of integrity and) integrity of the sources of ionizing
radiation,
(b) verification of the characteristic operating parameters) and source properties
ionizing radiation and its accessories, which has an impact on radiation
protection, and it
1. regularly with a frequency corresponding to the influence of the authenticated facts on
normal operation,
2. each time about the suspected source to function incorrectly
ionizing radiation or its accessories, which has an impact on radiation
protection, particularly after a change in normal view after you change the snapshot
batch indications, or when you suspect a change in geometry or kolimace
the volume of radiation,
3. after maintenance, repair or other service that is important from the
radiation protection and could significantly affect the property
a validated operational stability test, especially after repair or
calibration of diagnostic monitor, after the intervention of the digitizing software
image or after the reprogramming of exposure, and preferences
4. when changing accessories sources of ionizing radiation, which has an impact on
radiation protection, and
(c) in the case of restricted) of the source or device with him
leak test contained radioactive sources,
1. periodically, at least once every 12 months,
2. use in chemically aggressive environments or where there is a
increased risk of mechanical damage, at least once every 3 months,
3. after each cleaning and
4. When you suspect a leak closed a radioactive source.
(3) the extent and method to perform leak tests contained
of the source provides Appendix 10 to this Decree.
(4) in determining the extent and frequency of operational stability test must
the authorisation holder shall take into account the
and the status of the sources of ionizing radiation) and its accessories, which has the effect of
on radiation protection,
(b)) and the operation of common ways to use sources of ionising radiation and its
Accessories, that has an impact on radiation protection,
(c)) the extent and frequency of these examinations, which are referred to in
1. the instructions from the manufacturer of the sources of ionizing radiation,
2. the decision of approval of a type of ionizing radiation source, or
3. Protocol on the acceptance test or the test of long-term stability, and
d) codes of good practice to ensure radiation protection when using
sources of ionizing radiation.
§ 32
[To section 68, paragraph 2 (b), (d)) to (f)) of the Atomic Act]
(1) tests of operating stability of ionizing radiation sources used
When the medical exposure must be carried out
and, for the examination) which is the established frequency higher than monthly,
1. a physician who routinely in clinical practice, describes the x-ray monitor
images, if it is a test of operating stability of
check the appropriate diagnostic monitor in radiodiagnostic medicine, or
2. Radiology Assistant, that in clinical practice, the source of ionising
radiation is used, if it is a test of operating stability of resources
ionizing radiation used in computer tomography,
(b)) for the test, for which the frequency is fixed monthly or greater,
1. a health professional in clinical practice, the source of ionising
radiation is used, if it is a test of operating stability of resources
ionizing radiation used in interventional radiology, dental
radiodiagnostic medicine, skiaskopii or bone denzitometrii, or
2. Radiology Assistant, that in clinical practice, the source of ionising
radiation is used, if it is a test of operating stability of resources
ionizing radiation used in mammography, or skiagrafii, which
is not in the control of radiodiagnostic medicine diagnostic monitor, and
c) Radiology Assistant, that in clinical practice, the source of ionising
radiation uses, radiological technician radiological physicist, or if
This is a test of the operational stability of the sources of ionizing radiation
used in radiotherapy.
(2) a person liable to ensure the authentication properties for the source of ionising
radiation through the test operating stability, continuous evaluation of
the results of this test, and in the case of non-conforming implementation results
any corrective action is
and clinical medical physics expert), if its availability is required
under other legislation, or
(b)) if it is not under another law required availability
Clinical Radiological Physics,
1. supervising the person disposes of the radiation source holder
the authorization, or
2. the person ensuring radiation protection of the registrant, shall be treated to
the source of ionizing radiation to registrant.
(3) a person liable to determine the extent and frequency of the tests the operating stability
for the holder of the authorization is
and clinical medical physics expert), if its availability is required
under other legislation, or
(b) the supervising person) if under another law required
the availability of clinical Radiological Physics.
(4) the evaluation of the test results must be operational stability
and) made immediately after its implementation,
(b)) in writing and recorded
(c) without delay to the person) to under paragraph 2.
(5) where, on the basis of the results of the test carried out operational stability
corrective measures must be informed about these corrective measures taken
all personnel using, in normal operation, the source of ionizing
radiation.
Part 6
Registration
§ 33
Storage of personal benefits by
[To section 25, paragraph 2 (b)), and (c)) of the Atomic Act]
(1) the holder of the authorization must be kept in the records of the individual doses
exposed workers of category A, the following information:
and) surname,
(b) the name or names),
(c)), social security number, if assigned, or date of birth,
(d)) the size of the individual doses and other data related to the personal dose
that were received from the holder of the authorization to perform individual measurements,
and
(e)), information that the characterization of the exposure programme
monitoring.
(2) the information referred to in paragraph 1 must be kept for the duration of
activities involving exposure to ionizing radiation, and in addition to the time when
radiation worker reaches or would have reached 75 years of age, at least
for 30 years after the operation, during which it was a radiation worker
exposed to ionizing radiation.
(3) the operator of a controlled area must record the physical input
people that are not exposed category A workers, in a checked
zone, with the exception of natural persons who are undergoing rehabilitation in a controlled
zone medical or non-medical radiation or voluntarily help the physical
the person undergoing medical exposure in a controlled area. In the register
entry into the controlled area must be brought to a natural person
guided by the following data:
and) surname,
(b) the name or names),
(c)) date of birth,
(d)) duration of stay,
(e) the results of the individual monitoring), if they are available, and
(f)) a conservative estimate of the effective dose, if no data available
under (e)).
(4) the information referred to in paragraph 3, the operator controlled area
keep for a period of 10 years.
(5) personal benefits from the exceptional exposure and from accidental exposure must be
recorded separately.
(6) the holder of the authorization shall notify the authority the following information on the exposure of
exposed workers:
and) personal data of radiation worker category and details
characterize its expected exposure within 1 month from the start of the work,
When that is the radiation a worker exposed to ionizing radiation, and when
any change in such information; the enumeration of such data provided for in annex No. 2 to the
This Decree,
(b) the particulars of individual doses) of exposed workers of category A in 2
months after the end of the monitoring period, and
(c) the annual review of individual doses) all exposed workers of category A
until 31 December 2006. March in the year preceding.
(7) the information referred to in paragraph 6 shall be notified to the Office electronically in
machine readable format that allows database processing.
(8) the holder of the authorization shall notify the Authority forthwith
and effective dose of) external exposure exceeding the value of 10 mSv or
the equivalent dose in the lens of the eye from external exposure exceeding 10 mSv
or 150 mSv dose ekvivaletní on a limb or skin, reached for the
the monitoring period, or in a lump sum, with the evaluation of the causes of such
the situation and adopted the conclusions,
(b)) the effective dose from external exposure exceeding 15 mSv, or value
the equivalent dose in the lens of the eye from external exposure exceeding 15 mSv
or ekvivaletní dose 300 mSv on a limb or skin that were
achieved by summing the individual monitoring periods, and also in the
during the year, with the evaluation of the causes of this situation and adopted the conclusions,
and
(c)) time effective dose for internal radiation exposure exceeding 6 mSv,
and součtově, with the evaluation of the causes of such situations and
adopted conclusions.
(9) the notification referred to in paragraph 8 (b). and) or
(b)) must be carried out if the dosimeter, which was
found exceeding the values set on the effective dose, was placed on the
protective apron. Attenuation caused by the apron must be taken into account in
the evaluation of the causes of this situation.
§ 34
Storage of personal doses of the holder of the authorization to carry out personal
dosimetry
[To section 25, paragraph 2 (b)) and § 78 para. 3 (b). the Atomic Act)]
(1) the holder of an authorization to perform individual measurements must retain data
of individual doses of exposed workers of category A at least throughout the
calendar year following the year in which the information originated.
(2) the holder of an authorization to perform individual measurements must pass
the results of the assessment of exposure categories of exposed workers and holders of
authorisation, for which personal dosimetry and to the Office, immediately after
and dozimetru due to) the evaluation of an unplanned single exposure,
(b)) the findings
1. the effective dose from external exposure exceeding 10 mSv,
2. the equivalent dose from external exposure exceeding 10 mSv for the eye
lens or 150 mSv for a limb or skin, or
3. the committed effective dose from internal exposure in excess of 6 mSv.
(3) the holder of an authorization to perform individual measurements must notify the Office
within 1 month of acquisition or termination of the Treaty on the implementation of the personal
measurements made with the holder of the authorization to the treatment of source
ionizing radiation.
(4) the holder of an authorization to perform individual measurements must notify the Office
within 1 month from the end of the monitoring period the name or names, and
the last name of radiation worker category and for which has not been evaluated
personal benefit from personal dozimetru, and identification data
the holder of a radiation worker in this rectangular phalanx formation
He recalled.
Personal radiation license
§ 35
(§ 79 para. 9 of the Atomic Act)
(1) the person required to provide radiation protection, an external worker must
request the authority to issue a personal card before beginning radiation
the implementation of the activities of this radiation worker. The request for extradition
personal radiation licence, the applicant must attach a photo of
size 3.5 x 4.5 cm.
(2) personal radiation licence consists of
and to part A) ongoing records of batch and valid until the full
information, but no longer than 10 years since the release of personal radiation card, and
(b)) to register part B benefits in a calendar year and shall be valid for
This calendar year.
(3) the validity of a personal certificate of radiation ends
and an external worker,) the death or
(b) the permit is) termination of an external worker at the same time the holder
the authorization.
(4) the Pattern of personal radiation certificate laid down in annex 15 to this
the Decree.
section 36
(§ 79 para. 9 of the Atomic Act)
(1) the person required to provide radiation protection, an external worker must
and request the authority for a new) part B personal radiation within
30. November, the previous calendar year,
(b) submit to the Office) by 28. February of the following calendar year
(B) personal radiation card in which are recorded all
an external worker benefits from the previous calendar year, and
the total annual personal dose evaluated and confirmed the authorisation holder,
that on the issue of radiation licence requested,
(c) immediately inform the Office of the loss) personal radiation card,
(d)) shall immediately request the authority to issue new personal radiation
in the case of card loss of personal radiation card and add to it
all data from the card, personal pozbytého radiation
(e) send the part and personal) of radiation licence Authority after its full,
(f) request the authority to issue) new personal radiation within
30 days before the expiry of the term of validity of the personal
radiation of the card,
(g) submit to the Office a personal radiation) licence no later than 30 days after the end of
employment of an external worker or closure,
If this is itself an external worker,
(h)) to notify Authority changes in the data referred to in point 1, 7 or 8 of part A of
personal radiation card and submit personal radiation licence authority to
Noting these changes,
I) record in part personal radiation doses received for card
the previous four-year period so that you can always keep track of the five-year
total personal dose an external worker,
j) record in part B of the personal radiation licence that was issued
during a calendar year, any personal benefits received by the external
worker until the release of personal effects of the radiation of the card so that the
possible to evaluate the total annual personal dose an external worker,
to record in part B) personal radiation card monthly summaries
the outside worker's individual doses, incorporating the results of monitoring in
all operators of controlled zones, for which an external worker in
calendar month activity,
l) record in part A personal radiation licence total personal
the annual dose an external worker,
m) record in the personal radiation medical examination results card
outside worker made pursuant to § 80 para. 4 the Atomic Act and
n) record information and the preparation of an external worker under section 50.
(2) the operator of a controlled area in which external specialist
the activity executes, it must ensure, in accordance with the programme for monitoring
its controlled area evaluation of personal benefits received by the external
Analyst, in carrying out its activities in a controlled area.
If we determine that the dose must be recorded continuously, not in
using intervals, in part (B) of personal radiation certificate
outside worker.
(3) If the operator of a controlled area referred to in paragraph 2 does not
all the measurement results before the termination of activities of the outside worker in
its controlled area, must be sent in writing to these results immediately
After the evaluation of the benefits to a person required to provide radiation protection of external
the worker.
§ 37
Evidence of other facts and important in terms of radiation
the protection of the
[To section 25, paragraph 2 (b)), and (c)) of the Atomic Act]
(1) the holder of the authorization to the treatment of source of ionizing radiation in accordance with section
9. 2 (a). f) point 8 of the Atomic Act and to perform services.
relevant from the point of view of radiation protection referred to in § 9 para. 2 (a). (h))
2 and 5 of the Atomic Act shall forward to the Authority within one month after the implementation of
measurement, assessment or determination of the Protocol with the results
a) measurement and evaluation properties of sources of ionizing radiation,
b) measurements for the determination of individual doses, the worker, or
c) measurement and assessment of exposure from natural sources of radiation.
(2) evidence of the conclusions of the preventive medical examinations to verify the
medical radiation worker category and must be
stored until radiation worker reaches or would have reached 75
years of age, but at least for a period of 30 years after the operation, during which
radiation was exposed to ionising radiation.
(3) the results of workplace monitoring, IV. a category that is
workplace with nuclear facilities, must be kept for
and operation of this site,)
b) decommissioning of this work and
c) 10 years after the decommissioning of the site.
(4) unless otherwise provided by this Ordinance or an Ordinance on radiation monitoring
the situation otherwise, quantities and really important from the point of view of radiation
protection must be kept for a period of 10 years.
Registration of ionizing radiation sources the authorisation holder and registrantem
§ 38
[To section 25, paragraph 2 (b), (d)) of the Atomic Act]
(1) the permit holder or registrant shall maintain for each source
ionizing radiation, which disposes of the following documents and information:
and a description of the sources of ionizing radiation) to allow it to be uniquely
identification, including name, type designation, name of the manufacturer and
production or identification number,
(b) the purpose of the management of the source of) ionizing radiation,
(c)) other decisions relating to the management of the source of
ionizing radiation,
d) operating records characterizing the manner and extent of the treatment
the source of ionizing radiation, in the case of open of the
also the purpose of the source and the balance of its consumption, and
e) records concerning the handling of ionizing radiation sources
taken in the context of the continuous surveillance of radiation protection, and the records of the
control activities.
(2) the permit holder or registrant shall maintain for each source
ionizing radiation, which has in its possession the following documents and further
details:
and physical resources takeover date) ionizing radiation,
(b) the acquisition of possession of the document source) ionizing radiation,
c) in the case of ionizing radiation sources subject to approval, with the
the exception of the source, a declaration of conformity issued
a manufacturer, importer or distributor,
(d)) in the case of closed-end of the source certificate enclosed
of the source,
e) in the case of the source open passport issued
When you pass this source the previous holder,
(f) Protocol on the acceptance test) and long-term test reports
stability, if these tests are for the source of ionizing radiation
required,
g) records with the results of the measurements carried out within the operational test
stability and images resulting from their implementation,
h) if the source of ionizing radiation being passed into the possession of another person, an indication of the
how, to whom and when it was passed, and in the case of open of the
also accompanying sources sheet issued during this transfer,
even) if the source of the radionuclide released from the workplace, records of his
the release from the workplace,
(j)) is a radioactive source disposed as radioactive waste,
about how, to whom and when it was passed, and the accompanying list of radioactive waste
issued when this transfer and
k) for high-activity source photo or other similar
the representation, if so provided by Atomic Act.
(3) the Protocol on the acceptance test shall be kept for a period of use
sources of ionizing radiation.
(4) the Protocol on long-term stability test must be kept to a
perform the following tests of long-term stability, at least
period of 3 years from the execution of the test of long-term stability. In the case that
the test was part of the long-term stability of the measurement or estimation
balanced the radiation in the vicinity of sources of ionizing radiation, must be
the Protocol on the long-term stability of this test to be stored all the time
operation of the sources of ionizing radiation.
(5) records with the results of the measurements carried out within the operational test
stability and images resulting from their implementation must be kept to a
the following tests of long-term stability, but at least for 1 year
Since their acquisition.
(6) unless otherwise provided by this Decree, the data referred to in paragraphs 1 and 2 shall
shall be kept for a minimum period of 2 years from the completion of loading, the source of
ionizing radiation.
§ 39
[To section 25, paragraph 2 (b), (d)) of the Atomic Act]
(1) the holder of the authorization to the treatment of source of ionizing radiation and
Registrant must be sent in writing to the Office of the information about the source of ionising
radiation, which have in their possession, in addition to significant sources of ionizing
radiation and sources of ionizing radiation, a type approved
The Office, by
and radiation by generator) 1 month after
1. the successful acceptance test,
2. change the data,
3. transfer of the possession of another person, and
4. decommissioning,
(b)) closed source not later than 1 month after
1. the physical receipt of the closed of the source,
2. change the data,
3. transfer of the possession of another person, and
4. delete as radioactive waste or other disposal,
c) closed source by radionuclide within 1 month
After
1. the successful acceptance test,
2. change the data,
3. transfer of your device to another person, and tenure
4. the decommissioning.
(2) the scope of the information sent to the Office in accordance with paragraph 1, provided for in annex No.
16 of this Decree.
(3) the holder of a permit to manufacture, import, distribution or export resources
ionizing radiation and the registrant must be sent in writing to the Office overview
manufactured, imported, exported, distributed or resources
ionizing radiation in summary for the preceding calendar quarter
not later than 1 month after its expiry. The range of the data sent
set out in annex 17 to this Decree.
section 40
Registration of ionizing radiation sources ohlašovatelem
(Section 71, paragraph 2, of the Atomic Act)
(1) the declarant shall keep and maintain the sources of ionizing radiation
the following data:
and a description of the sources of ionizing radiation) to allow it to be uniquely
identify, in particular name, type designation, manufacturer's name and production
or identification number,
(b) purpose of use of resources) of ionizing radiation and
(c)) the information contained in the instructions for the use of sources of ionizing radiation.
(2) the declarant must be kept of the source of ionising radiation on
the following data:
and physical resources takeover date) ionizing radiation,
(b) details of acquisition) sources of ionizing radiation,
(c)) the information contained in the Declaration of conformity issued by the manufacturer, importer
or distributor of sources of ionizing radiation,
(d)) in the case of closed-end of the source data specified in
the certificates closed of the source,
e) in the case of open source of information referred to in
accompanying report of the open of the source and
f) data on the location of the sources of ionizing radiation.
(3) the declarant shall keep the information referred to in paragraphs 1 and 2, at least
period of 2 years from delivery of the ionizing radiation source to another person or his
for destruction.
§ 41
Inventory of sources of ionizing radiation
[To section 69, paragraph 2 (b)) of the Atomic Act]
(1) the counting must be inspected for closed
radioactive sources, which are a simple source of radioactive
radiation, or a significant source of ionizing radiation.
(2) the Inventory check must be carried out
and as at 31 December each year.) March,
(b)) without delay after the bankruptcy decision the authorisation holder and
(c)), at least once a month in the case that a high-activity source which is
part of the technological unit, is not used for a period longer than 30 days.
(3) Inventory review shall be conducted in the following range:
and, in the case referred to in paragraph) 2 (a). and) or (b))
1. the examination of the documents relating to the closed radionuklidovému
the source and
2. examination of the physical presence of the contained of the source in the
the housing and
(b)) in the case referred to in paragraph 2 (a). (c) examination of the physical presence of the)
the closed-end of the source in the housing.
(4) the permit holder must submit to the Office by the end of the following month after
made to inventory control in accordance with paragraph 2 (a). and reporting) or b)
containing the
and the serial number of the closed) of the source, the number of the certificate
the closed-end of the source, and an indication of the nature of the radionuclide,
(b) an indication of the type of housing), in which the radioactive source is located, and its
serial number,
(c) the designation of the premises or part of the) technology, in which the radiopharmaceutical
the source is located, and
(d) the date of the inventory control).
(5) the result of the examination of the physical presence of the closed-end of
the resources referred to in paragraph 2 (a). (c)), the authorisation holder may experience.
§ 42
Identification and marking of high-activity sources
(Section 89, paragraph 2, of the Atomic Act)
(1) the holder of a permit to manufacture or import high-activity sources must
and high-activity source) distinctive identifier,
(b)) to engrave, printed or otherwise permanently affixed to the identifier
high-activity source, if practicable,
(c)) to engrave, printed or otherwise permanently affixed on the package identifier
high-activity source; If this is not feasible, or in the case of
transport packaging for multiple use, the holder of the authorization to place the
on the package information on the nature of the high-activity source,
(d) the packaging of high-activity source) and, if feasible, also
high-activity source of radiation danger sign and
(e)) to ensure that each part of the documentation produced or
imported type high-activity source was a photo or other
similar depictions of the high-activity source and usually used for it
packaging.
(2) a person who has held high-activity source, must ensure that
and high-activity source) and its packaging have always been accompanied by a written
information to identify the high-activity source and of its nature,
(b)) high-activity source and its container, if it is feasible,
marked and provided with a radiation danger sign and markings and labels
remain legible and
(c) the documentation contained a high-activity source) photos, technical
drawings or other similar representation of the high-activity source, packaging
source, transport packaging, device, which is a high-activity source
part of it, and its equipment; photos or other similar representation
high-activity sources may not be ensured if you cannot obtain it without
dismantling of the device.
TITLE II
PLANNED EXPOSURE SITUATIONS
Part 1
Systematic supervision of radiation protection
§ 43
The supervising person
[To section 72, paragraph 5 (a)), and (b)) of the Atomic Act]
(1) the supervisor of a person at the workplace, where it is defined, controlled
zone must be radiation worker category and in other cases.
is the person supervising the radiation worker category A or B.
(2) the supervising person must exercise supervision of radiation protection
and) monitoring and evaluating the implementation of the obligations of the holder of the authorization
ensure all measures for
1. the safe management of sources of ionizing radiation,
2. implementation of the radiological activities,
3. safe operation of workplaces where radiation activity is carried out, and
4. the decommissioning of the site where the radiation carries out activity, and
(b) cooperation with the holder) ensuring authorization
1. the preparation and the implementation of new activities related to ensuring the
radiation protection, and
2. the purchase of sources of ionizing radiation, protective devices and resources
or the measurement devices.
(3) the supervising entity shall provide for the holder of the authorization, in particular
and informing of radiation worker and) persons serving in the
controlled or supervised area on the pursuit of the professions of the facts
important from the point of view of radiation protection,
(b) radiation worker training)
(c) preparation of the programme, monitoring) implementation, monitoring and evaluation
the results of the monitoring referred to in the monitoring programme,
(d) records of individual doses), including the sum of the individual doses from all
work activities, radiation worker
(e) the determination of the effective dose of a person), which entered into a controlled
bandwidth,
f) implementation of the optimization of radiation protection and determination of the batch
optimization limits
g) keeping the documentation for the povolovanou activity, including a Windows program
control or ensure radiation protection program,
(h) means of ensuring implementation of the reviews), radiation protection,
I) registration of ionizing radiation sources, equipment and apparatus having a
effect on the radiation protection and management information about their movements and the State,
j) implementation of the annual inventory checks of ionizing radiation sources,
k) organizing acceptance tests and tests of long-term stability and
cooperation with a person who performs them,
l) test the operational stability, unless otherwise provided by this Decree,
m) investigation of radiation emergencies, loss, theft or damage
sources of ionizing radiation and the elaboration of proposals for the adoption of corrective
measure and monitor the implementation of corrective measures,
n) radiological event solutions
o) tracking and resolution of disagreement, that is not a radiological emergency,
in the field of radiation protection,
p) supervision over ensuring the provision of occupational health services
from exposures to the worker
q) operative communication with a radiation worker and another person, if the
the necessary consultation with regard to the current situation, and radiation
so that the information be communicated clearly, distinctly and without
undue delay, and
r) methodological guidance of persons with direct supervision of radiation protection and
coordination of their activities.
§ 44
The person with direct supervision of radiation protection
[To section 72, paragraph 5 (b), (c) and (d))) the Atomic law]
(1) the person with direct supervision of radiation protection at the workplace, where it is
defined in the controlled area, radiological worker category must be
And in other cases, the person with direct supervision of radiation protection
radiation worker category A or B.
(2) the person with direct supervision of radiation protection must keep control
on the implementation of the radiation in the workplace activities of the holder of the authorization and
in particular, the
and) cooperate with their supervisor,
(b) to plan and prepare) workflows and process documents for
activity,
(c) radiation worker and) inform other natural person about the current
radiation situation and measures responding to the situation,
d) verify that the radiation worker and other natural person entering
in the controlled area in carrying out radiation activity satisfies the requirements
protection of health and the technical and administrative requirements to ensure
radiation protection,
e) to participate in the investigation of radiation emergencies,
(f)) to participate in the solution of a disagreement in the field of radiation protection, which is not
radiation emergency, and
g) to communicate with the radiation worker and another person, if required
consultation with regard to the current situation or channelling radiation
their activities, so that the information be communicated clearly,
clearly and without undue delay.
§ 45
Specialized radiation protection unit to ensure continuous surveillance over the
radiation protection at nuclear power facilities
[To section 72, paragraph 5 (b), (e)) of the Atomic Act]
(1) specialized radiation protection unit to ensure continuous surveillance
radiation protection in the nuclear facility should provide
the activities referred to in § 43 para. 2 and 3 to check the performance of the
requirements for proper radiation protection and in particular to ensure the
and) direct supervision of radiation protection for all individuals
entering the controlled area,
(b) the assessment and implementation of actions) in order to ensure radiation protection
all of the individuals entering into the controlled area,
(c)) preparation
1. proposals for changes in the documentation for the povolovanou activity related to
radiation protection and
2. the internal regulations of the holder of the authorization relating to radiation
the protection,
(d) evaluation of the impact of discharges on) the representative person and checking out
authorized limits,
(e)) the investigation of events related to radiation protection, including
drawing up proposals on the adoption of remedial measures and synergies with other
the services of the holder of the authorization in their implementation and
(f)) work with other services of the authorisation holder in coping with radiation
extraordinary events.
(2) specialized radiation protection unit to ensure continuous surveillance
radiation protection at nuclear power facilities in ensuring
continuous surveillance of radiation protection of individuals engaged in
the provision of services in a controlled area, the operator of the site (IV).
category must
and work with their supervisor) the holder of the authorisation to provide
services in the controlled area, the operator of the site (IV). category,
(b) radiation worker and) inform other natural person about the current
radiation situation and measures responding to the situation,
c) verify that the radiation worker and other natural person entering
in the controlled area in carrying out radiation activity satisfies the requirements
protection of health and the technical and administrative requirements to ensure
radiation protection and
(d)) to communicate with the radiation worker and another person, if required
consultation with regard to the current situation or channelling radiation
their activities, so that the information be communicated clearly,
clearly and without undue delay.
Part 2
Controlled and monitored zone
The controlled area
§ 46
(Section 73, paragraph 3, of the Atomic Act)
(1) the controlled area shall be delineated as part of workplace
and comprehensive and clearly identified),
(b)) is separated structurally practicable, and
c) protected against entry by unauthorized individuals.
(2) the controlled area shall be marked at the entrance or border
and the radiation danger sign)
(b)) the controlled area ' notification sources of ionizing radiation,
unauthorized entry prohibited "and
(c) information on the nature of the sources) of ionizing radiation and the risks
United.
(3) the controlled area shall be delineated in a range that includes all
jobs, where it cannot be excluded that the
and the average power consumption of the dose), equivalent to the
place in a calendar year may be higher than 2.5 mikroSv/h,
(b) the sum of the products of vol) activities of individual radionuclides in
the air in the workplace, and conversion factors for inhaled intake hinh
radiation worker can be in diameter per year greater than 2.5
mikroSv/m3, or
(c)) at the workstation surface contamination may be higher than the value of
area activities set out in annex 18 to this Decree.
(4) into the controlled area can enter only a natural person knowledgeable about
How behavior, which does not endanger their health and the health of other physical
persons. In the case of a natural person to be in a controlled area
undergo a medical exposure or exposure, nelékařskému lessons by
first sentence is not required.
(5) a person under the age of 18 years of age may enter into a controlled area, if
in the controlled area, preparing for a profession or has
undergo a medical exposure or exposure nelékařskému.
(6) a pregnant woman may enter into the controlled area, where, in the
controlled area have to undergo any medical radiation or nelékařskému
radiation or in a controlled area works.
(7) in a controlled area may perform work only radiation worker
the category and the other natural person may perform in a controlled area
and necessary and incidental activities)
1. after the necessary period and
2. under the supervision of radiation worker category and specified
the operator of a controlled zone, or
(b)) in the case of radiation worker category (B), the activities of
providing assistance to individuals undergoing medical exposure.
(8) into the controlled area can individually access the Inspector of the authority.
(9) Cleaning or maintenance in the controlled area may independently carry out
and radiation worker category B) or other natural person at the workplace
radiation generator, radionuclide closed source or
devices with sealed radioactive source, if it is ensured that in
While their presence cannot be put into operation, or
(b) category B radiation worker) in the workplace (II). or (III). category
with the open source of the radionuclide, if the work area with
This source at the time of his presence and measurement is not confirmed
that surface contamination in the work place is less than the value of the area
the activities set out in annex 18 to this Decree.
§ 47
(Section 73, paragraph 3, of the Atomic Act)
Radiation protection in the controlled area shall be ensured by the following
follows:
and the room space and) space in a controlled zone workplace with
nuclear facilities, where they are consistently exceeded the values referred to in § 46
paragraph. 3, the table must be marked with an indication of the extent of risk exposure;
If these values are exceeded temporarily, these must be of the room,
spaces and places marked with an indication of the measured value table input
3-d dose equivalent, and volume and surface
radionuclides,
(b)) surface contamination of jobs, equipment or construction
parts of the controlled area shall be at a time when the source
ionizing radiation, not less than the value of the surface
laid down in annex 18 to this Decree; If it exceeds the surface
contamination of these values, must be made effective decontamination,
(c)) the operator controlled area must equip itself with a natural person
entering the controlled area personal protective equipment and
AIDS appropriate radiation situation in a controlled area and how
work to be performed and the reasons of entry into the controlled area,
d) in the case that during normal operation or in foreseeable deviations from the
normal operation may input the spatial dose equivalent in
controlled area may exceed 1 mSv/h, the operator controlled
zone equipped with any natural person entering the controlled area,
with the exception of natural persons, that is to be in a controlled area to submit
medical exposure or exposure, operational nelékařskému personal
rectangular phalanx formation with features distinct alarm levels to be exceeded,
e) if in a controlled area surface contamination cannot be ruled out
entering the natural persons can enter after changing clothes in the clothing of the specified
internal regulation of the operator-controlled zone; When you leave the
must be carried out to check the surface contamination of natural persons, and in the
the case of detection of surface contamination of personal cleansing and decontamination;
If you cannot remove the surface contamination, natural person may leave the
the controlled area under the conditions provided for in the internal rules
operator controlled area,
(f)) If you cannot exclude objects from the control of the surface contamination
controlled area must be checked for their surface
in case of detection of contamination and surface contamination of their
decontamination,
(g)) in a controlled area of the workplace with the open source of the radionuclide
It is forbidden to smoke; eat and drink in the case that, given the extent of the
controlled area and the type of activity carried out in the short term, it cannot be
leave; in this case, the operator of a controlled area
define for the consumption of a specific area with a surface scan options
contamination of natural persons, and to provide negative contamination
food, and
h) for a physical person who is not a radiation worker and enters the
controlled area, the operator must establish in the controlled area
program monitoring operational values in order to ensure the respect of
batch optimization limits for residents.
§ 48
(Section 73, paragraph 3, of the Atomic Act)
(1) documentation for povolovanou activity, that is the definition of
controlled area must contain the
and controlled area listing) range of rooms and the schematic plan
(b) a justification of the proposed range) controlled area, in particular
calculations and other information demonstrating compliance with the requirements of this order and
the Atomic Act,
(c) a description of the construction and technical) ensure controlled area against
the entry of unauthorised individuals,
d) description of how to ensure radiation protection in a controlled area and
e) details of the expected number of physical persons working in the
a controlled area and how their lessons about the risks when working in
a controlled area.
(2) documentation of the operation of the controlled area shall contain the
and guidelines for entry to) the controlled area and the conditions for entry into the
controlled area for radiation worker and the other natural person,
(b)) the procedures for individual activities performed in a controlled area,
(c) the procedures for assessment of exposure) other natural persons entering
controlled area and
(d)) conditions for leaving the controlled area is a natural person and
removing objects from the controlled area, including how to conduct
decontamination.
§ 49
The monitored zone
(Section 74, paragraph 4, of the Atomic Act)
(1) the monitored zone must be defined as part of the workplace
and comprehensive and clearly intended) and
(b)) is separated structurally practicable.
(2) the monitored zone shall be marked at the entrance or border
and the radiation danger sign)
(b)) ' notification of the monitored zone, sources of ionizing radiation ", and
(c) information on the nature of the sources) of ionizing radiation and the risks
United.
(3) radiation protection in the supervised area shall be ensured
in the following way:
and radiation activity can perform) only radiation worker category and
or (B),
(b)) for a physical person who is not a radiation worker and enters the
the monitored zone, the operator must reference zone to lay down in
program monitoring operational values in order to ensure the respect of
batch optimization limits for residents,
(c)) job in the supervised area must be equipped with
resources and AIDS, and depending on the nature of the source of ionising illuminated
radiation, with which it is treated, and
d) surface contamination of jobs, equipment or construction
part of the reference zone should be at a time when the source of ionising
radiation is not less than the value of the surface laid down in annex
# 18 of this Decree; If it exceeds the surface contamination of these
the values must be made effective decontamination.
(4) documentation of the operation of the monitored zone must include procedures for
the various activities carried out in the reference zone.
Part 3
Personnel, documentation and evaluation of radiation protection
§ 50
Informing and training workers
[To section 68, paragraph 2 (b), (h) and (i))) the Atomic law]
(1) a radiation worker and a natural person who is prepared in
a controlled area or the supervised area on the profession, must be
the holder of the authorization or informed of registrantem
and the nature and extent of the potential) risk to health risks associated with
work in an environment of ionizing radiation and the possible health detriment,
(b) the general procedures and policies) of radiation protection and the measures
must be taken to the respective activities,
c) specific operational and working conditions relating to the
workplace and activities that may be assigned,
(d)) the importance of the protection of health and request technical and administrative
in order to ensure radiation protection requirements,
(e)) the importance of safety culture to ensure the radiation protection and
(f) the need for early Declaration of pregnancy) and breastfeeding because of the risk
resulting from any exposure to the unborn baby and infants,
in the case of a woman.
(2) the permit holder or registrant must provide the information referred to in
paragraph 1 to record. Radiation worker must record or physical
the person who is preparing in a controlled area or the reference zone
on the practice of the profession, to confirm your signature.
(3) the authorization holder or registrant must provide a system of ongoing
education of exposed workers so that workers know
and) the General rules and procedures of radiation protection,
b) radiation protection measures in the performance of radiation activity
during normal operation, the foreseeable deviations from this service or
during a radiological emergency and
c) internal rules and documentation for povolovanou activity.
(4) for radiation worker working in the controlled area
workplace IV. the category of continuing education system must include
getting familiar with the internal rules and documentation for this controlled
zone.
(5) knowledge of radiation worker and his ability to safely
the performance of radiation activities must be checked before starting work and further
regularly, at least once per calendar year, the test of which must
the record is to be performed. In the case that a radiation worker during the test
He failed, must be provided for measures to remedy the situation.
(6) a record of the test referred to in paragraph 5 shall contain the
and validated knowledge, range)
(b) a list of the names of all the tested) of exposed workers,
(c)) date of test,
(d) tests, evaluation criteria)
e) test result and
f) description of corrective measures in the event that the radiation worker when the
the test failed.
(7) the verification referred to in paragraph 5 shall not require the
a) for radiation worker who actively performs the function of supervising
person for the holder of the authorization, or
(b)) for radiation worker for the Registrant for the actively
performs the function of a person to ensure the radiological protection of the registrant.
Radiation protection programme
§ 51
(Section 24 para. 7 of the Atomic Act)
Radiation protection program must include
and a description of the activity, povolované)
(b)) the place of povolované activities,
(c)) the specification of the kinds of ionizing radiation sources in the framework of the povolované
activities,
(d) a description of the organizational structure) persons performing an activity, povolovanou
(e)) the rights, obligations and relations of individuals that control
perform or evaluate povolovanou activities,
(f) a description of how the management of documentation) and records in povolované
activities, including a list of the documentation and records
g) a description of how the transmission of information to the Office,
h) description of how to resolve disagreements, including the application of corrective measures and
the evaluation of their effectiveness,
I) description of the system of information and education in radiation worker
radiation protection and preparedness to response to a radiological emergency
the event and its knowledge and
(j) a description of the scope of the monitoring) measurement, evaluation, and validation
recording the facts and important in terms of radiation
the protection.
§ 52
(Section 24 para. 7 of the Atomic Act)
Radiation protection programme must also include for
and the management of resources) of ionizing radiation in the workplace I or II.
category
1. a description of how to ensure the provision of occupational health services
radiation workers
2. Description of metrological assurance of measurement and measuring instruments
3. a description of the manner of acceptance tests and tests of long-term
stability,
4. the scope and description of how to carry out tests, operational stability and
5. the operating frequency of the tests for stability,
(b)) management of sources of ionizing radiation in the workplace with open
radionuklidovými source
1. principles of management of radioactive waste,
2. guidelines for the release of radioactive substances from the workplace and
3. the principles of the use of personal protective equipment and assistive devices, their
characteristics and description of their allocation,
(c)) management of sources of ionizing radiation in the workplace, where
performs medical exposure.
1. Description of the method of recording the radiological event, in implementing its
examination and adoption of measures to prevent its occurrence and limitations
the consequences and
2. guidelines for the use of personal protective equipment and assistive devices, their
characteristics and description of their allocation, and
(d)) the import, export or distribution of sources of ionizing radiation
1. specification of the documentation transmitted to users of the imported, exported
or distributed sources of ionizing radiation and
2. a description of the manner of transport of ionizing radiation sources, with
the exception of radiation generator
(e)) the provision of services in the controlled area, the operator workplace
IV. category
1. enumeration of controlled zones, in which the povolovaná activity
exercised,
2. a description of how to ensure the provision of occupational health services
radiation workers
3. a description of the monitoring and evaluation system of personal dose of radiological
workers,
4. Description of the system of personal management of radiological services,
5. Description of the activities provided by the supplier and
6. the principles of the use of personal protective equipment and assistive devices, their
characteristics and description of their allocation,
f) evaluation of properties of ionizing radiation sources in accordance with § 9 para. 2
(a). f) point 8 of the Atomic Act
1. a description of how to ensure the provision of occupational health services
radiation workers
2. guidelines for the use of personal protective equipment and assistive devices, their
characteristics and description of their allocation,
3. a description of how interoperability with the person for which the
evaluation of properties of ionizing radiation sources,
4. Description of how the evaluation of the results of the test of long-term stability and
acceptance testing,
5. Description of determining periods to remove minor defects,
6. Description of the procedure in the case that it is in the context of the examination of long-term stability
designed to change the extent of the studies the operational stability,
7. Description of the method of storage of materials derived from testing resources
ionizing radiation and
8. Description of the activities provided by the supplier,
g) disposal of the products resulting from mining activities in the activities
related to the obtaining of the radioactive mineral, and stored on a
odvalech and tailings
1. principles of waste products generated during mining activities
activities related to obtaining of the radioactive mineral,
2. the principles for the release of products arising from mining activities
activities related to obtaining of the radioactive mineral to
of the environment and
3. the principles of the use of personal protective equipment and assistive devices, their
characteristics and description of the allocation, and
h) significant service in terms of radiation protection referred to in § 9 para. 2 (a).
h) points 2 and 5 to 7 of the Atomic Act
1. Description of metrological assurance of measurement and measuring instruments
2. Description of the system of education of individuals involved in the
the execution of this service and
3. the degree of physical participation natural persons managing the execution of this service when you
measurements carried out in the framework of the execution of the service.
§ 53
Other documentation
(Section 24 para. 7 of the Atomic Act)
The contents of the other documentation for povolované activities under exposure
situations, rather than the programme ensuring radiation protection, as stipulated in annex No.
19 to this Decree.
§ 54
Reviews how to ensure radiation protection
[To section 69, paragraph 2 (a)) of the Atomic Act]
(1) an evaluation of the means of ensuring radiation protection of the authorisation holder
must include the
and assessment) description of the optimization of radiation protection on the basis of the results of the
individual monitoring or surveillance of the workplace,
(b) overview and analysis) deviations from normal operation and exceeded
monitoring levels or batch optimization limits and received
measures,
(c) an overview of the performance of the obligations of the holder),
1. ensuring the provision of occupational health services to the radiation
workers,
2. education of exposed workers, and
3. verification of the eligibility of the exposed workers to safely exercise
radiation activities
(d) an assessment of the availability of the means of protection) and AIDS,
e) assessment of the State of ionizing radiation sources based on the results
carried out the tests,
(f) an assessment of the security resources) ionizing radiation,
g) evaluation by the inventory control of sealed radioactive
resources,
(h) evaluation of the balance consumed) things to unsealed
resources,
I) overview and analysis of the radiological events and cases where the
radiological events could occur, if not the causes in a timely manner
detected and deleted,
j) revision history of local diagnostic reference levels and
k) description reviews carried out emergency exercises.
(2) an evaluation of the means of ensuring radiation protection must be approved by the
the holder of the authorisation or its governing body, as a legal
person.
Part 4
The operation of the site
section 55
Conditions of safe operation of workplace radiation generator
[To section 75, paragraph 5 (a)) of the Atomic Act]
(1) the radiation Generator may be used only for the time strictly necessary to
achieve the desired purpose.
(2) radiation Generator must clearly indicate the State of which generates
ionizing radiation.
(3) Stationary radiation generator, with the exception of sources of ionizing radiation
used for medical exposure, which is due to the right
the procedure required the presence of health care workers in the facility,
must be served from obsluhovny or service point, which
the design excludes exceed the set batch optimization
limits. If the facility is placed more radiation generators, must not be
used at the same time.
(4) the appliance or device, part of which is the generator of radiation and
protective shield can be used, if it is
and) ensures that the device or the device cannot be put into operation if the
protective shield is removed, and
(b)) or the device automatically excluded from activities when you open
the protective shielding.
§ 56
The conditions for the safe operation of the closed-end of the source,
equipment and work with it
[To section 75, paragraph 5 (a)) of the Atomic Act]
(1) the radioactive Sealed Source must be used only for
is strictly necessary to achieve the desired purpose.
(2) if there is no closed source is being used, a radiopharmaceutical must be stored in the
the shielding to the housing or otherwise obstructed so that
and storage space power) dose equivalent
1. on the surface of the lid, container, shielded storage space,
safes and shielded pits does not exceed the value of the 100 mikroSv/h, and
2. at a distance of 1 m from the surface of the lid, container, shielded
storage sheds, vaults or shaded boxes does not exceed the value of the
10 mikroSv/h, and
(b)) when carrying the closed of the source in the workplace
power consumption of the 3-d dose equivalent at a distance of 1 m from the surface of the
the housing does not exceed the value of the transport mikroSv/100 h.
(3) when the irradiation and Radioscopy closed radionuclide source must
be after work or before entering the defined or shielded
radiated area measuring or signalling verified that the source is
are blocked or properly inserted into the shielding enclosure.
(4) when handling closed-source of the radionuclide, which cannot be
to exclude its release from the facility or its loss, it must
be used in the gauge, which allows you to fix the location under all conditions
This source.
(5) the functionality of the mobile device with the enclosed accessories
radioactive source must be checked periodically, at least once
per year.
(6) in the event of the discovery of the source of a leak closed
It must be ensured the unset of the source and the closed
the device out of operation and with it their proper protection against abuse.
(7) in the case of considerable leakage of more than stonásobkem limit values
According to annex 10, point 2 to this Decree, shall be closed around
the closed-end of the source and the device with him, until it is
test of radioactive contamination and, if necessary, effective
decontamination.
§ 57
Conditions of safe operation of workplaces with open radionuclide
the source of the
[To section 75, paragraph 5 (a)) of the Atomic Act]
(1) a workplace with an open source of the radionuclide I to III.
categories can be on individual workstations to process at the same time
maximum activity determined on the basis of criteria taking into account the facilities
ventilation, insulation jobs and shield devices and
the implementation of sanitation, physical characteristics of the substances to be
processed, in particular, the volatility and the dust, and the difficulty and risk
the expected work activities. To determine the maximum processed
the activities set out in annex 9 to this Decree.
(2) if there is no open source of used radioactive and if this is not about
the source, which is made up of technological units or the media of the workplace,
must be placed in a protective stínicím cover or container that
effectively preventing the dispersion of radioactive substances, so that the
and storage space power) dose equivalent
1. on the surface of the lid, container, shielded storage space,
safes and shielded pits does not exceed the value of the 100 mikroSv/h, and
2. at a distance of 1 m from the surface of the lid, container, shielded
storage sheds, vaults or shaded boxes does not exceed the value of the
10 mikroSv/h, and
(b)) when carrying an open undertaking in the workplace
power consumption of the 3-d dose equivalent at a distance of 1 m from the surface of the
shipping container does not exceed the value of the 100 mikroSv/h.
(3) the requirements of paragraph 1 shall not apply to
and) workplace III. category, where the activities are carried out
obtaining of the radioactive mineral,
(b) the site of the nuclear installation) and
(c)) of the workplace with the storage of radioactive waste, which is not a nuclear
device.
Transitional workplace
§ 58
(To section 77, paragraph 2, of the Atomic Act)
(1) the holder of an authorisation using the source of ionizing radiation on
Transitional workplace must ensure the radiation protection of the population,
workers and around the transitional site
and the direction of the primary volume) of ionizing radiation to
prevent exposure of individuals,
(b) selecting the time of carrying out an activity) with regard to the movement of natural persons
around the transitional site,
c) informing individuals that could be affected by the activities of the
the transitional work, and
d) using natural barriers to entry by unauthorized physical
persons in the definition of controlled area.
(2) the boundaries of the controlled area to a temporary workplace must be
marked
warning tape)
(b) the radiation danger sign)
c) controlled area ' notification sources of ionizing radiation,
unauthorized entry prohibited "and
d) in the case of poor visibility light-signalling.
(3) ensuring the activities of the Working Group on transitional work,
where is defined in the controlled area shall be at the time of the performance of activities
present at least two categories of exposed workers and eligible for
the safe performance of the relevant radiation activity, one of which is
their supervisor or person with direct supervision of radiation protection
in the area of the use of sources of ionizing radiation.
(4) the working group must be equipped with a meter to monitor
workplace to the extent corresponding to the used sources of ionizing
radiation.
(5) if the power consumption of the 3-d dose equivalent on the transitional
workplace may exceed 1 mSv/h must be fitted with a radiation worker
the operational functions of the clear rectangular phalanx formation with the personal alarm
the set level.
§ 59
(To section 77, paragraph 2, of the Atomic Act)
(1) the holder of the authorisation of the use of ionizing radiation sources, which is
minor, minor or simple source of ionizing radiation,
In addition to the defektoskopického and karotážního devices of the x-ray device with
sealed radioactive sources must inform the Office before the first
using sources of ionizing radiation in the workplace transition
and an overview of the sources used) ionizing radiation,
(b) a description of the work) and
(c) the estimated number of trips on) a transitional site for calendar
year.
(2) the holder of the authorisation of the use of ionizing radiation sources, which is
a major source of ionizing radiation, x-ray defectoscopic
device or device with sealed radioactive deformations
the source, you must notify the Office in writing at least one day in advance
and start work,)
(b)) the estimated time of work on a transitional work,
(c) a description of the work),
d) overview of the used sources of ionizing radiation and
e) telephone contact to a worker to carry out the systematic
supervision on a transitional work.
(3) the holder of the authorization for the use of sources of ionizing radiation, which is
a major source of ionizing radiation, x-ray defectoscopic
device or device with sealed radioactive deformations
the source, you must notify the Office before starting work unambiguously to identify the
the place of work is the source of ionizing radiation, and by indicating
geographical coordinates or address the transitional site, including the number
the buildings in the area or parcelního numbers.
(4) the holder of the authorisation of the use of ionizing radiation sources must
inform the Office of their work on the transition
workplace.
Part 5
Changes in radiation protection
section 60
Enumeration of changes affecting the radiation protection of the workplace III. the categories and
workplace IV. category
[To section 9, paragraph 2 (b), (c)) of the Atomic Act]
(1) a workplace Change that affect radiation protection IV. a category is a
and project construction) the change in workplace IV. category,
(b) reconstruction of ionizing radiation sources) or a change that alters the
shading properties of its accessories,
(c)) the change in the arrangement of the controlled area that changes the way its
the use of, or
(d) organizational change management activities) particularly important from the point of view
radiation protection.
(2) a Change affecting the radiation protection of the workplace III. the categories and
workplace IV. a category is a
and) change the building part or parts of the technology or equipment
controlled zone workplace that change their shading, insulation
or protective properties,
(b)) change in building part or equipment controlled area of the workplace,
that changes the way the security of sources of ionizing radiation,
(c)) to change how the decommissioning of such workplaces,
(d)) variation of the conditions of the territory and of the systems, structures or
After the decommissioning of the components of such a site, unless it is a
full disposal, or
e) change options for the accumulation of radioactive substances in the environment
During its long release from the workplace.
(3) a Change affecting the radiation protection of the workplace III. category,
In addition to the site where the medical exposure is performed, and the workplace
IV. the category of the change of the method of determining the value of the monitored variables,
the architecture of the installed monitoring systems, the concept of processing
data or physical principle of measurement for
and monitoring device whose) output is compared with the limits and
terms and conditions,
b) monitoring device that is used
1. to verify compliance with dose limits,
2. to verify compliance with the authorized limits for discharges, or
3. for the purposes of the release of radioactive substances from the workplace, or
(c) stationary monitoring devices) which is intended for the detection of
leakage of radioactive substances or radiation monitoring of the situation in
radiation emergencies.
§ 61
Enumerate changes related to radiation protection at the workplace with a source
ionizing radiation
[To section 69, paragraph 2 (b), (d)) of the Atomic Act]
(1) by changing the related to workplace radiation protection IV. a category is a
change the type of monitoring equipment while maintaining the physical principle
measurement or change the number of stationary monitoring devices,
and) whose outputs are compared with the limits and conditions,
(b))
1. to verify compliance with dose limits,
2. to verify compliance with the authorized limits for discharges, or
3. for the purposes of the release of radioactive substances from the workplace, or
(c)) that are designed to detect leaks of radioactive substances or to
monitoring of the radiation situation in the event of a radiological emergency.
§ 62
Range and method of documenting the changes related to radiation protection on
the workplace is the source of ionizing radiation a way and time-limits of the
notification of the Office
[To section 69, paragraph 2 (b), (e)) of the Atomic Act]
(1) documentation of changes related to radiation protection in the workplace
ionizing radiation source must include
a) description and justification of the changes
(b)) a list of documentation for the updated activity in povolovanou
connection with the change,
(c)) the expected time schedule of changes and
(d) assess the impact of changes on) radiation protection.
(2) the amendment related to radiation protection at the workplace with a source
ionizing radiation shall be notified to the Office in writing 30 days before the
by performing.
Part 6
Registration
§ 63
Job description of a person to ensure the radiological protection of the registrant
[To section 70 para. 2 (b)) of the Atomic Act]
The person providing radiation protection, the registrant must ensure
and radiation worker and information) of the person preparing the
work on the professional conduct of the facts relevant for the
radiation protection and the risk of working with ionizing radiation source,
b) continuous training on the safe use of radiation worker
sources of ionizing radiation,
(c)) the proper keeping of documentation for a registered activity,
(d) records the movement and status) of ionizing radiation sources,
(e) the Organization of carrying out of acceptance tests), long-term tests
stability and operational stability tests of ionizing radiation sources and
participation in them,
(f)) implementation of procedures for the safe handling of radioactive source
radiation, including procedures to prevent unauthorized handling of source
ionizing radiation, the loss, theft or damage, and including
procedures in case of deviations from normal operation,
g) examination of the radiological events and perform follow-up
at her and
h) periodic verification of protective properties of personal protective
funds and other protective gear.
§ 64
Procedures for ensuring radiation protection of registrantem when using
sources of ionizing radiation
[To section 70 para. 2 (b) (c)) of the Atomic Act]
Procedures for ensuring radiation protection of registrantem when using
sources of ionizing radiation stipulated in annex 20 to this Decree.
§ 65
Documentation for the registered activity
(Section 17, paragraph 3, of the Atomic Act)
(1) Documentation for the registered activity is
and acceptance testing or Protocol) of the last examination of the long-term
the stability of the sources of ionizing radiation and
(b) preparation of a person passing) a document ensuring radiation protection
of the registrant.
(2) the patterns of the registration forms provided for in annex 21 to this
the Decree.
Part 7
Monitoring
§ 66
Program monitoring
(Section 24 para. 7 of the Atomic Act)
(1) must have a monitoring programme, depending on the types of monitoring,
that is the holder of the authorization shall be obliged to carry out the following sections:
and workplace monitoring)
(b) the personal monitoring)
(c)) and discharge monitoring
d) monitoring the area.
(2) the monitoring programme shall contain detailed provisions for the current monitoring
operation of the workplace, the predictable deviations from normal operation
workplace, radiation accident and radiation accident,
and the definition of the monitored variables)
(b)) the way the extent and frequency of measurement,
(c)) the way the recording and retention of the measurement results,
(d) procedures for evaluating the results of measurements),
e monitoring levels and values) measures when they are exceeded,
f) values of batch optimization limits
(g) a description of the measurement methods)
h) description of the monitoring of persons according to the internal emergency plan for the
workplace affect in radiation accident or radiological accident,
I) destination points on the body radiation worker, on which it is located
personal dosimeter, and
j) determining the used types of measuring instruments and equipment and their
parameters.
(3) the content of the monitoring programme should be formulated so as to allow for
and) verifying compliance with dose limits,
b) showing that radiation protection is optimized, and
c) early detection of deviations from the normal operation of the workplace.
§ 67
An evaluation of the variables measured in the context of monitoring
[To section 78, paragraph 3 (b), (d)) of the Atomic Act]
(1) if the recalculation activities of radionuclides received on time
the effective dose, conversion factors must be used. In the case of
unidentified radionuclides and chemical forms or properties
the inhaled aerosol must be used for the activity,
their form or an aerosol with the highest conversion factor for income
ingestion or inhalation. Conversion factors for the conversion of the first sentence
and the other is set out in annex 3 to this notice.
(2) if they are not aware of the data in a more appropriate to the situation, in which experiencing
exposure, the amount of inhaled air in one year is for
representative person
and) aged up to 5 years 1 500 m3
(b)) aged from 6 years to 15 years, including 6 500 m3, and
c) 8 500 m3 over 15 years old.
(3) if they are not aware of the data in a more appropriate to the situation, in which experiencing
exposure, the amount of water ingested in one year is for a representative
person
and) aged up to 5 years 275 l,
(b)) aged from 6 years to 15 years, including 365 l and
c) 730 l over 15 years old.
(4) if they are not aware of the data in a more appropriate to the situation, in which experiencing
exposure, then the worker for the year at work lasting for 2 000 hours breathes 2
000 m3, with the exception of the worker referred to in paragraph 7.
(5) if in the determination of external radiation, the recalculation of the average
activity concentration of rare radioactive gas dispersed in the air
the power of effective dose, conversion factors must be used, that
set out in annex 3 to this notice.
(6) to calculate the effective dose due to the inhalation of the products of the conversion
Radon of atmosphere in the areas affected by mining and processing of uranium ore is
the value of the background radon activity concentration equivalent to 10 Bq/m3, unless
in this area, the other value is known.
(7) for the determination of internal exposure to radon and the products of the conversion income
a mixture of long-term inhalation of radionuclides emitting alpha radiation
uranium-a radio series for the year of radiation worker engaged in mining
the activity or activities carried out by using mining techniques in the underground at work
lasting for 2 000 hours 2 400 m3 of air breathes.
§ 68
Monitoring level
[To section 78 para. 3 (b) (c)) of the Atomic Act]
(1) Monitoring levels are
and recording level),
(b) the level of investigation and)
(c) the intervention level).
(2) the recording level must be set at the level
and) 1/10 of the dose limits with regard to the length of the monitoring period, or
(b)) the smallest detectable value of the measurand.
(3) the inquiry shall be established at the level of
and) 3/10 of the dose limits with regard to the length of the monitoring period, or
(b)) the upper limit of normally occurring values of the measurand.
(4) when reaching or exceeding the recording level must be an indication
recorded and stored.
(5) when exceeding the level of investigation must be carried out of the investigation of the causes of
and the findings of the effects of fluctuations of the tracked quantity of radiation protection.
(6) the intervention level is exceeded, must be done by a predetermined
measures to
and the resulting status and remedy)
(b) prevent undesirable development of the merged) State.
§ 69
Monitoring of the workplace
[To section 78, paragraph 3 (b)) of the Atomic Act]
(1) A workplace I to IV. category, with the exception of the workplace as well.
category, where they will only be minor sources of ionizing radiation,
that are not open source, it must be radionuklidovými monitoring
the workplace is carried out by monitoring, measuring, evaluating and recording
variables and parameters that characterize the radiation field and
the occurrence of radionuclides in the workplace.
(2) the monitoring of workplaces must be according to the types of sources used
ionizing radiation is carried out
and monitoring input dose), equivalent to
workplace,
(b) the volume of activities in monitoring) atmosphere and surface
activities at the workplace, or
(c)) by measuring the radiation of useless.
(3) the efficiency of protection against external and internal radiation must be verified
by measuring input of the dose equivalent, activity concentration
or other quantities necessary to verify the effectiveness of protection against
the external and internal radiation, ionizing radiation source,
places of work with him and a possible stay of exposed workers
or other individuals in the
and the commissioning of the workplace)
(b)) change in workflows
(c) changing the proper radiation protection), or
(d) changing the radiation situation).
(4) monitoring of radioactive contamination at the workplace with
Open the source of the radionuclide is carried out so that the
and allow the signal)
1. operational deviations from normal operation and
2. lack of function or failure of barriers to dispersion and
(b) not to exceed the values for another reason) radioactive contamination
the surface; values for radioactive surface contamination laid down in annex
# 18 of this Decree.
(5) the Continuous monitoring of the activity of radionuclides in the air by volume
must be carried out on
and workplace) IV. category,
(b) the workplace, where it is) carried out activities related to obtaining the
the radioactive mineral, and
c) workplace III. category with an open source of the radionuclide,
with regard to the nature of the sources used and the method of
handling may result in contamination of the atmosphere.
Personal radiation worker
section 70
[To section 78 para. 3 (a)), e) and (f)) of the Atomic Act]
(1) personal radiation worker monitoring must be carried out to
determine the individual doses of radiation worker monitoring, measurement and
his assessment of the external and internal exposure.
(2) personal external exposure monitoring personal rectangular phalanx formation must be
provided for the radiation category A worker for radiation
worker categories and is the period for the evaluation of personal dozimetru 1
calendar month.
(3) personal dosimeter must be positioned at the reference point, which is
the front left side of the chest, (hereinafter referred to as the "reference site") or any other
place depending on the geometry of the exposure. When using the protective shielding
aprons must be a personal dosimeter located outside this apron.
(4) If a personal dosimeter does not allow sufficiently accurate determination of
the effective dose and equivalent dose in the organs and tissues, for which
There are limits, must be equipped with a radiation worker other
personal dosimeters, which with its characteristics or by placing this determination
will allow.
(5) the personal dosimeter shall measure all types of radiation involved in the
external exposure of radiation worker. Fails to fulfil this requirement one
personal radiation dosimeter separately, the worker must be equipped with an additional
personal dosimeters, unless another way of monitoring programme
individual monitoring of radiation worker.
(6) Radiation worker who carries out the activities that are carried out and
checked with sources of ionizing radiation for his presence in the
facility in the vicinity of sources of ionizing radiation, and according to the program
the monitor is equipped with a protection shield must have assigned an apron
two personal dosimeters, one of which is located on the apron and the second
under it. In the event that a personal dozimetru, located on the apron is
assessed value of personal dose equivalent at a depth of 10 mm
higher than 10 mSv, must be evaluated also the dosimeter located below the
protective shielding and based on the evaluation of both the dosimeters must
be determined by the attenuation coefficient used protective shielding aprons and
the effective dose received by the worker, taking into account the radiation exposure
uncovered parts of the body.
§ 71
[To section 78 para. 3 (a)), e) and (f)) of the Atomic Act]
(1) a workplace if you cannot eliminate the exceeding of dose limits for
radiation worker as a result of a one-time external exposure, must
be issued with personal radiation dosimeters with functions, the operational
distinct alarm levels set for the monitored
quantities.
(2) if the source of ionizing radiation cause single exposure:
exceeding five times the limits for radiation workers, the personal
radiation worker allow determining benefits and their
distribution in the body of a radiation worker.
(3) in the workplace, where it can occur to the internal exposure of radiation
a worker with income of radionuclides or harnesses for effective dose of
internal exposure of the individual exposed workers must check for
by measuring the activity of radionuclides in the body of the worker's radiation or in its
excreta and its přepočítáním on the intake of radionuclides or harness
the effective dose by using models of the respiratory tract, the gastrointestinal tract, and
the kinetics of the respective chemical elements. If the measurement of the radiation
the worker is not possible, the receiving of radionucleides or time effective
benefits to provide for the measurement of radionuclide activity concentration in the air
workplace, and then translating the income of radionuclides or harness
the effective dose by using models of the respiratory tract, the gastrointestinal tract, and
the kinetics of the respective chemical elements.
(4) when working with an open source of radionuclide measurements must be
the activity of radionuclides in the body of the worker's radiation or in its
excreta in accordance with paragraph 3 carried out
and (IV) in the workplace). category at least once a year and
(b)) in the workplace I to III. categories based on the evaluation of the potential
the risk of internal exposure of radiation worker.
(5) in the case of a suspicion that there was an unplanned single exposure
radiation worker, which could lead to limits being exceeded for
radiation worker, must be ensured immediate evaluation of the personal
dozimetru and dosimetry evaluation of such events.
§ 72
[To section 78 para. 3 (a)), e) and (f)) of the Atomic Act]
(1) personal radiation worker category B must be
to ensure
and rectangular phalanx formation),
(b) the calculation of individual doses) radiation worker monitoring data
site at which carries out work activities, and track time
stay on this site, or
(c)) equipment, one or more exposed category B workers
performing the same work in the same workplace, personal
rectangular phalanx formation and assigning personal benefits received its assessment to the other
the radiation workers without a personal dozimetru on this site.
(2) the results of reviews of the individual doses of radiation worker category (B)
must be used to demonstrate the
and the accuracy of the classification of radiation) category a worker
(b) the exposure conditions on the stability of) the workplace.
(3) the holder of the authorization shall inform the radiation worker
in a meaningful way so that it is clear that the radiation worker
was informed about the
and his results of the individual monitoring) and
(b) the procedures after an investigation of the causes of) the achievement of specified investigative or
intervention levels.
section 73
Discharge monitoring
[To section 81, paragraph 3 (b) and (c))) up to the Atomic Act]
(1) the monitoring of effluents from the workplace shall be carried out by monitoring,
by measuring, recording and evaluation of variables and parameters
characterizing the released radioactive materials, in particular by setting
the balance of the total spilled activity and radionuclide activity concentration.
(2) discharge monitoring must include
continuous monitoring of radionuclides), that there were substantial
involved in the exposure of the population, emitted for a specified period (hereinafter referred to
"the balance"),
b) continuous monitoring of radionuclides, which is capable of quickly
indicate deviation from the normal operation of the site (IV). category, and
(c) operational monitoring) other potential paths of release
radioactive substances from the workplace in case of leakage so that this
the leak could be included in the balance of the effluents.
(3) the Recording level must be determined so that the
and when the balance measurements) comply with the requirements to the minimum detectable
the value of the monitored variables according to the Decree on the radiation monitoring
the situation and
(b) the continuous monitoring of radionuclides) allow to check
all operating States.
(4) the inquiry level must be determined
and when the balance on the measurement) the level of the expected values of balance outlet
the radionuclide monitoring, taking into account the length of the period and
(b)) when monitoring of deviations from the normal operation of the workplace as an upper bound
normally occurring values of monitored variables.
(5) Emergency level must be determined so that when
and legally) effluent could be taken to prevent
exceeding the authorized limits, or non-compliance with permit conditions and
(b)) the monitoring of deviations from the normal operation of the workplace can be adopted
corrective measures resulting from the condition and prevent its unwanted
development.
§ 74
Monitoring around the workplace
[To section 81, paragraph 3 (b) and (c))) up to the Atomic Act]
(1) monitoring around the workplace, from which they are discharged or in other
paths released radioactive substances, must be carried out by monitoring,
measurement, evaluation, and noting the variables and parameters
characterizing the radiation field and the occurrence of radionuclides in
around the workplace, in particular
and 3-d) of the dose equivalent,
(b) the activities of radionuclides and volume)
(c) the activities of radionuclides) by weight.
(2) the Recording level must be determined to meet the requirements for
the smallest detectable value, according to the Decree on the monitored variables
monitoring the radiation situation.
(3) the inquiry level has to be set as the upper bound is usually
present values of monitored variables.
(4) the Emergency level must be determined in accordance with the requirements of
optimization of the exposure of the population.
Part 8
Medical exposure
§ 75
Workplace equipment for x-ray Diagnostics and radiotherapy
[To section 86, paragraph 3 (a)) of the Atomic Act]
(1) a workplace for radiotherapy must be equipped with, if
and brachyterapeutické, the display device) specified for localization
applicators, the planning unit and dozimetrickým equipment for testing
properties of ionizing radiation sources,
(b)) with the x-ray equipment dozimetrickým radiotherapeutic equipment for
testing for properties of sources of ionizing radiation, or
(c)) with radionuclide particulate ozařovačem or an
1. the planning unit,
2. the Simulator,
3. dozimetrickým equipment for testing properties of ionizing sources
radiation,
4. If the radical radiotherapy, verifikačním system,
5. If the radical radiotherapy, running for
dosimetric verification of the administered dose, which is the in-vivo dosimetry
or her full-sized alternative, and
6. techniques with modulated intensity the volume system for the area, and
space dosimetry verification batch distribution.
(2) laboratory for x-ray Diagnostics and radiotherapy must have
posted in a conspicuous position on the necessity of communication to announce pregnancy
workers healthcare providers before making a
exposure to radiation.
(3) workplace Equipment for x-ray Diagnostics and radiotherapy must
take into account the special needs and the nature of the medical exposure
If done on it
and) medical exposure of children,
(b) the search or examination)
c) exposure is associated with a high dose of a patient during radiotherapy,
Interventional Radiology and computer tomography.
(4) the Radiotherapy departments must have access to tools for
testing operational stability.
Requirements on source of ionizing radiation used in medical exposure
§ 76
[To section 86, paragraph 3 (a)) of the Atomic Act]
Source of ionizing radiation used in medical exposure
and) intended for radiodiagnostiku or for the purposes of planning, management and
authentication in radiotherapy must be equipped with a device, or
appropriate means, which will provide quantitative information on the
the exposure of the patient; If it is technically feasible, it must be this
information is automatically transferred to the record of the examination of the patient,
(b)) for Interventional Radiology must
1. after the examination to provide quantitative information on exposure to the patient,
2. indicate the total product of kermy and area and cumulative reference
kermu in the air, is a fluoroscopy and-fluoroscopic or fluoroscopic,
3. be equipped with a Telecoil-implementation of operational stability tests with
monthly frequency or higher,
4. to provide structured reports of radiation dose, which is
automatically transmitted to the record of the examination of the patient, and
5. during the examination, notify the natural person conducting the examination
about the accumulated radiation of the patient load and
(c)) for computing tomography must
1. after the examination to provide quantitative information on exposure to the patient,
2. have the investigative protocols that are adapted to the investigation of children,
If snímkovány are children,
3. be equipped with a Telecoil-implementation of operational stability tests with
the frequency is higher than the monthly,
4. to provide information on the product of the length and kermy
5. to provide information on the weighted index computed tomography kermovém
or solid kermovém index computed tomography,
6. provide structured reports of radiation dose, which is
automatically transmitted to the record of the examination of the patient, and
7. be equipped with automatic exposure.
§ 77
[To section 86, paragraph 3 (a)) of the Atomic Act]
(1) the source of ionizing radiation used in medical exposure
and skiagrafický)
1. must not allow photography of the shield,
2. stationary with a digital receptor of the image, with the exception of the device
intended solely for the imaging of limbs, must be equipped with exposure
Automatics,
3. must be equipped with a Telecoil-implementation of operational stability tests with
monthly frequency or higher,
4. stationary, with the exception of a device intended solely for photography
the limbs must be equipped with automatic exposure and orgánovými
presets and
5. you must provide information about the product and area kermy
b) fluoroscopic
1. must not allow viewing of direct skiaskopií,
2. must be equipped with automatic control of the batch input,
3. you must set the size of the x-ray volume automatically according to the
the image receptor size and distance of the outbreak from the image receptor
4. must be equipped with a sound after 5 minutes total
fluoroscopic guidance prior to the time
5. must be equipped with the function of preserving the last image on the monitor after
the end of exposure,
6. with the image receptor shall not have a rectangular primary aperture,
7. must be equipped with a Telecoil-implementation of operational stability tests with
monthly frequency or higher and
8. you must provide information about the product and area kermy
c) mammography
1. must be equipped with automatic exposure,
2. with the film the image receptor or with indirect digitisation must be
equipped with a protirozptylovou grid
3. you must provide information about the compression strength and thickness after compression,
4. must be equipped with the function of automatic exchange of the filter, depending on the
thickness after compression,
5. must be equipped at least with the dimensions of the image receptor 18 x 24 cm,
If it is not intended to be stereotaxi, and
6. must be equipped with a Telecoil-implementation of operational stability tests with
monthly frequency or higher and
d) dental intraoral
1. must have a nominal voltage of at least 60 kV,
2. must have a distance to outbreak since the end of the tube at least 20 cm,
3. must be equipped with a Telecoil-implementation of all operational tests
stability,
4. must have a kolimaci volume corresponding to the shape and size of the receptor
the image,
5. must be equipped with a corresponding image receptor and holder
6. may not be portable.
(2) the source of ionizing radiation used in medical exposure, which is
Dental panoramic x-ray equipment, dental computing
tomografem or bone densitometer, must be fitted with hearing aids
the implementation of all operational stability tests.
§ 78
Therapeutic and diagnostic application of the radionuclide
[To section 86, paragraph 3 (b)) to (d)) of the Atomic Act]
(1) the therapeutic and diagnostic application of the radionuclide shall be measured
open activity of the source applied to the patient, and
prior to its administration.
(2) the Therapeutic application of the radionuclide shall be conducted in Ward
medical equipment providers of health services, especially
modified and equipped for this purpose. This condition does not apply if
the exposure of individuals living in the same household with the patients after
therapeutic application of an open undertaking cannot exceed
batch optimization limit laid down in § 64 para. 1 (b). a) nuclear
the law. This therapeutic application of the radionuclide must be ensured that the
the patient did not use its own lingerie.
(3) upon the entry of the patient after treatment application of the radionuclide according
paragraph 2, shall be all of his personal effects examined
in terms of the possible pollution of the radionuclides and, where such
pollution decontaminated or disposed of as radioactive waste.
(4) if the patient is undergoing therapeutic application of the radionuclide, the holder must
the authorisation to provide to the patient or his legal representative before the
leaving the medical equipment
and written information about the risks of) ionizing radiation and
(b) written instructions how) to limit the benefits of a natural person, which comes with a
the patient into contact, at such a low level, what can reasonably be achieved.
(5) if the patient is undergoing the diagnostic application of the radionuclide, you must
the authorisation holder shall provide the patient before leaving the health care
facility written instructions referred to in paragraph 4 (b). (b)) in the case that the
the exposure of individuals, that comes into contact with the patient, could
approximate values of the General limits for residents.
(6) in the workplace, which performs therapeutic or diagnostic
application of the radionuclide, must be posted in a visible place of the communication on
the need to notify staff of providers of health services
pregnancy or breast-feeding before performing the medical exposure.
(7) the equipment of workplaces in which therapeutic or diagnostic
application of the radionuclide shall be in accordance with the special needs and
the nature of the medical exposure.
§ 79
Diagnostic reference levels
(§ 84 (6) of the Atomic Act)
(1) the national diagnostic reference levels provided for in annex 22 to this
the Decree.
(2) a record of the outcome of the examination of the continuous diverting from the local
diagnostic reference levels must contain
and) period during which this diverting,
(b)) the approximate number of patients involved in this diverting,
(c)) the scope of this diverting,
(d)), the reasons for diverting,
e) progress and results of the optimization in the case that was based on the
the examination is made, and
(f) revision of local) recording of diagnostic reference levels in
If it was on the basis of the examination carried out.
(3) the record of the outcome of the examination of an important crossing of the local
diagnostic reference levels must contain
and) the date and time when this significant overrun has occurred,
(b) identify patient), this significant overrun was concerned, and
(c)) whether this significant overrun radiological event.
§ 80
Incorrect exposure of the patient's
[To section 60, paragraph 4 (a)) of the Atomic Act]
(1) Exposure of the patient, that is considered bad for the purposes of the definition of
radiological event, you
and the exposure that may) when the medical exposure endanger the life of the patient in
as a result, tissue reactions,
(b) the exposure incurred by reason of)
1. unintended events in medical exposure involving human error
or failure of the device, or
2. other events when the medical exposure, the consequences of which cannot be
omitted from the point of view of radiation protection,
(c)) in radiotherapy
1. radiation of the patient during the confusion,
2. therapeutic irradiation of tissue or organ other than planned,
3. the application of the total dose, or the dose on the fraction that differs significantly
from the indicated dose,
4. application erroneously prescribed dose, or
5. exposure that causes the radiobiologický effect of therapy does not match
originally planned, caused by the interruption or early termination
planned treatment, which is not due to the medical condition of the patient,
(d)), in nuclear medicine
1. application of other radiopharmaceuticals, than it was planned,
2. application activity, significantly different from the prescribed activity,
3. exposure in the confusion of the patient, or
4. application activity or radiopharmaceuticals, which have been incorrectly prescribed,
e) in radiodiagnostic medicine
1. the exposure times higher than needed,
2. radiation of the patient during the confusion,
3. the exposure of another organ or tissue than planned, or
4. in the performance conducted by the exposure of the fetus in a pregnant woman or the fetus
direct volume that has not been indicated, and
(f)) in the Interventional Radiology
1. the exposure times higher than needed,
2. radiation of the patient during the confusion,
3. the exposure of another organ or tissue than was planned,
4. in the performance conducted by the exposure of the fetus in a pregnant woman or the fetus
direct volume that has not been indicated, or
5. in case when the tissue response because of the incorrect implementation
performance.
(2) applications activities significantly different from the prescribed activity is in
nuclear medicine for the purposes of the definition of the wrong exposure for
and therapeutic application of the radionuclide) application activity that differs from the
prescribed activities by more than 20%, or
(b) application of the radionuclide) diagnostic application activity that is different
from the prescribed activities by more than 40%.
§ 81
Radiological events
(§ 87 para. 5 of the Atomic Act)
(1) the radiological events must be classified according to their
severity into categories A, B, or c. Criteria for the classification of radiological
events in the categories set out in Annex 23 to this Decree.
(2) a Radiological event category A or B is a serious radiological
event.
(3) Annex 23 to this Decree shall lay down the
and) procedures for case of radiological event, or in the case where the
radiological events could occur, if not the causes in a timely manner
detected and removed,
(b)) the contents and the retention period of the records of the examination of the radiological events
or in the case where the radiological events may occur, if they have not
the causes identified and resolved in a timely manner, and
(c) information about the fatal range) radiological events and deadlines to
implementation.
§ 82
Determination of the distribution of the population doses from medical exposure
(Section 85, paragraph 4, of the Atomic Act)
(1) the range of data on health services, which has been used
ionising radiation and health services provider that has been
reported and paid health insurance, provided by the Office of
health insurance provided for in annex 24 to this Decree.
(2) the information referred to in paragraph 1 shall be made available to the Office electronically in
machine readable format.
Part 9
Non-medical exposure
section 83
Records of nelékařském exposure of medical radiological equipment
(§ 83 para. 7 of the Atomic Act)
Records of nelékařském exposure of medical radiological equipment must
contain
and identification of the natural person) that is undergoing non-medical exposure,
(b) the rationale for each non-medical exposure),
(c)) date and time of each medical exposure,
d) record the exposure parameters that can be used to estimate the dose of
-medical exposure,
(e) identification of the source of ionising radiation), which is a non-medical
the exposure made,
(f) medical benefits) a comparison of the exposure with a local diagnostic
the reference level used for the examination in the framework of the medical exposure with
a similar procedure and the source of ionizing radiation and
g) information about the non-medical exposure without the approval of irradiation
natural persons if it is in accordance with other legislation as follows
followed.
§ 84
Nelékařském records of exposure by source of ionizing radiation
(§ 83 para. 7 of the Atomic Act)
Nelékařském records of exposure by source of ionizing radiation must
contain
and identification of the natural person) that is undergoing non-medical exposure,
(b)) age and sex of the individual who is undergoing non-medical exposure,
(c) the rationale for each non-medical exposure),
(d) information on the case,) where the natural person who had non-medical
the exposure experience, it refused,
(e) the date and time of execution) of each medical exposure,
f) record the exposure parameters that can be used to estimate the dose of
-medical exposure,
g) identify the source of ionizing radiation, which is a non-medical
the exposure made,
(h) medical benefits) a comparison of the exposure with batch optimization limits
and
I) information about the non-medical exposure without the approval of irradiation
natural persons if it is in accordance with other legislation as follows
followed.
Episode 10
Radiation protection in activities linked to obtaining radioactive
the mineral
§ 85
Site with activities linked to obtaining the radioactive mineral
(§ 88 para. 6 of the Atomic Act)
(1) activities linked to obtaining radioactive mineral must
be ensured by definition of radiation protection
and the reference zone)
1. a pond,
2. the decontamination station
3. mine water treatment plant and
4. wastewater treatment plant of industrial waste water from the workplace, which is part of the
treatment technology of radioactive minerals, and
(b) the controlled area)
1. the underground workplace where it is quarried by a radioactive mineral,
2. the technological unit on the surface of the building on the initial work of mine,
where is quarried by a radioactive mineral,
3. uranium concentrate in the oven,
4. in the warehouse of the uranium concentrate and
5. in the comprehensive chemical treatment technology section of uranium ore.
(2) in the definition of the reference band and controlled zone
paragraph 1, and in ensuring radiation protection shall be
followed by analogy pursuant to § 46 to 51.
§ 86
Special requirements for ensuring radiation protection in the activities
related to obtaining of the radioactive mineral
(§ 88 para. 6 of the Atomic Act)
Review of surface contamination of natural persons when it leaves the
controlled zone workplace where activities are carried out by
related to obtaining of the radioactive mineral, pursuant to section 47 (a). (e))
is not performed.
Part 11
Natural sources of ionizing radiation
§ 87
Workplace materials with increased content of natural radionuclides
[To section 93, paragraph 4 (a)) of the Atomic Act]
Workplace materials with increased content of natural radionuclides is
site at which is done
and mining, transport pipelines) or processing of oil and gas,
b) coal mining,
(c)), mining of metal ores
(d) processing of niobium or tantalum) ore,
(e) the processing of material containing rare) soil
f) primary production of iron,
g) tin smelting, lead or copper
h) manufacture of cement clinker, including maintenance of furnaces,
I) production of phosphate fertilisers, the manufacture of phosphoric acid, or thermal
manufacture of phosphorus,
j) production of pigment titanium dioxide-based,
to zirconium or zirconium processing),
l) the production, processing or use of the materials containing thorium and uranium,
m) coal burning in plants with a thermal power of over 5 MW, including maintenance
boilers,
n) acquisition of geothermal energy,
about) the operation of the device on the property-editing or dealing with groundwater
"water treatment sludge from an underground source,
p) treatment of materials, for which it has been shown that the content of
natural radionuclide in it exceeds the release level or increasing the
3-d dose equivalent power consumption of more than 0.5 mikroSv/h,
q) mining activity,
r) activities carried out using mining techniques in the underground, or
s) activities related to the management of mining waste.
§ 88
Determination of the personal benefits of the worker in the workplace with the possibility of an increased
exposure from natural sources of radiation
[To section 93, paragraph 4 (b)) of the Atomic Act]
(1) the method of measurement for the purpose of determining personal doses
and the worker who treated) with material with enhanced content
the nature of the radionuclide in the workplace with the material with enhanced content
natural radionuclide, you must include
1. measurement of the spatial dose equivalent,
2. measurement of the average volume of activities of radionuclides in the air,
3. measurement of surface contamination in the workplace and
4. the registration period of residence, or
(b)) a worker who is a member of the air crew on board the aircraft when
flight at a height of over 8 km, must include a determination
1. worker participation rates on individual years,
2. the flight characteristics and
3. the parameters relevant to the calculation of the effective dose, and that repeatedly for
each calendar year.
(2) in the workplace with the material with increased content of natural
the radionuclide measurements must be carried out to assess whether they are exceeded
the level of
and 300 Bq/m3) for the average volume activity of radon in air
the performance of the work, or
(b)) 1 mSv per year for an effective dose that does not include the dose received from
radiation from natural background radiation and radon and its products
conversion.
(3) in the workplace with the material with increased content of natural
the radionuclide, on which is recorded as exceeding the level provided for in paragraph 2,
must be on the basis of repeated measurements and the period of stay in the workplace
set the personal benefits of a worker. In the case of work on multiple sites
with the possibility of increased radiation exposure from natural sources of radiation must be personal
benefits of a worker will be totaled. Provided for the personal benefits of a worker must be
assessed according to the values listed in paragraph 4 (b). (b)).
(4) determination of individual doses, the worker may not be carried out on the
work with the material with increased content of natural radionuclides,
There is a change in working conditions, production methods or
raw materials and
and the overrun level) not in accordance with paragraph 2, or
(b)), with repeated measurements under paragraph 3 have not been encountered
exceeding the
1.6 mSv per year for an effective dose, or
2.1/3 of the limits set on the calendar year, in section 4, paragraph 4. 1 (b). (b)) to
(d)).
(5) in the workplace, on which may be exceeded by the value of personal
benefits the worker referred to in paragraph 4 (b). (b)), it must be personal benefits
the worker identified repeatedly in each calendar year.
§ 89
Information about the site with the possibility of increased radiation exposure from natural sources
radiation and their transfer to the Office
[To section 93, paragraph 4 (b)), and (c)) of the Atomic Act]
(1) the data obtained by measurement in accordance with § 88 para. 2 and the data on the set
individual doses must be kept for the duration of the work
the activities of the worker and to the time when the worker has or would
reached 75 years of age, but at least for a period of 30 years from the termination of the work
activity.
(2) the information referred to in paragraph 1 and the information on exceeding the values under section 88
paragraph. 2 (a). 4 (b). (b)) must be reported to the Office within one month from the
to obtain them.
(3) the authority must be about the site with the possibility of an increased exposure of
natural radiation sources reported the following information:
and) identification of persons engaged in an activity in which it is
powered by: the workplace, the
(b)) the name and address of the workplace,
(c) the classification of the workplace) under section 93 para. 1 the Atomic Act and section
87,
(d) details of the raw material used) in the workplace and technology description
used in the workplace,
(e) a description of the workplace, the Organization), the method and mode of operation, and the period of stay
a worker at the workplace,
(f)) the way the release of radioactive substances from the workplace with the possibility
the increased exposure from natural sources of radiation,
g) an indication of whether the radioactive substance used being freed for the production
building material, and
h) description of the optimization of radiation protection in the workplace, a description of the measures
taken to ensure radiation protection and a description of the collateral requirements
According to § 94 paragraph. 2 the Atomic Act in the workplace.
(4) the information referred to in paragraph 3 shall be notified to the authority for the first time before
the start of operation of the workplace and whenever they change.
(5) the information referred to in paragraph 3 shall be kept for at least 30
years from the end of operation of the workplace with the possibility of an increased exposure of
natural sources of radiation.
§ 90
Optimization of radiation protection in the workplace with the possibility of an increased
exposure from natural sources of radiation
[To section 66 paragraph 6 (b), (c)) and section 93 para. 4 (b). (d)) of the Atomic Act]
(1) the optimization of radiation protection in the workplace with the possibility of an increased
exposure from natural sources of radiation must be carried out when crossing the
levels in accordance with § 88 para. 2.
(2) measures to implement the optimization of radiation protection referred to in paragraph
1 are in particular
and) change
1. the raw materials used,
2. technology, or
3. the Organization, method or mode of operation and
(b) workplace with the option) the adjustment of the increased exposure from natural sources
radiation, including adjusting the ventilation.
§ 91
The release of radioactive substances from the workplace with the possibility of increased radiation exposure
from natural sources of radiation
[To section 95 para. 6 (a)) to c) Atomic law]
(1) the measurement and evaluation of the content of radionuclides in radioactive substance
released from the workplace with the possibility of increased radiation exposure from natural
radiation sources must be carried out in the case of workplaces with material
increased content of natural radionuclides in particular for
and) deposits,
(b)) of sludge,
c) applied filters
(d)) of the waste and the waste water released outside the workplace and
e) materials from this site intended for reuse or
recycling.
(2) the measurement and evaluation referred to in paragraph 1 shall be carried out for the first time when
the commissioning of this work and then when you change that could
influence the content of radionuclides in radioactive substance, at least once every 12
months.
(3) the internal rules for the handling of radioactive substance from uvolňovanou
workplace with the possibility of increased radiation exposure from natural radiation sources must
contain
a) enumeration of the radioactive substances occurring in the workplace, including
information about the content of radionuclides in them,
b) description of the waste radioactive substance in the workplace, including how
its disposal or release from the workplace,
(c)) the guidance on safe handling of radioactive substance in the workplace and
(d) the quantity of the evidence) how radioactive substances.
(4) protocols with the results of measurement and evaluation referred to in paragraph 1 shall be
The Office transmitted within 1 month from obtaining, directly or through
the holder of the authorization referred to in § 9 para. 2 (a). h) point 7 of the Atomic Act.
(5) the results of the measurements and the protocols referred to in paragraph 1 shall be
retained for a period of 5 years from the termination of the operation of the site, with the option
the increased exposure from natural sources of radiation.
TITLE III
THE EXISTING EXPOSURE SITUATION
§ 92
Workplace with possible increased exposure from radon
[To section 96, paragraph 3 (a)) of the Atomic Act]
The conditions for the inclusion of the site located in the basement or the first
floor of the building between the workplace with the potential increased exposure of
Radon laid down in annex 25 to this Decree.
§ 93
The effective dose of a worker in the workplace with the potential for increased exposure of
Radon
[To section 96, paragraph 3 (b)) of the Atomic Act]
(1) a workplace with possible increased exposure from radon shall be
measurements to assess whether the reference level is exceeded 300
Bq/m3 for the average volume activity of radon in the time of the stay
a worker at the workplace in the length 2 000 hours in 12 months. In the case of
different period of residence of the worker in the workplace must be used time
the integral of the radon activity concentration corresponding to the period of the stay.
(2) in the workplace with the potential increased exposure from radon, on which the
established that the reference levels referred to in paragraph 1 shall be on the
repeated measurements and the determination of the effective dose examined whether
can be any worker exceeded the value of the effective dose 6
mSv per 12 months. In the case of work on multiple sites with potential
increased exposure of radon shall be effective dose the worker added.
(3) in the workplace with the potential increased exposure from radon, on which no
established that the reference levels referred to in paragraph 1 or on which the
not when measured in accordance with paragraph 2 is detected option
exceeding the value of the effective dose of a worker 6 mSv per 12 months
in the following years may not be measuring and determining the effective dose
carried out, if there were no
and) to change the
1. working conditions
2. the organization or work mode, or
(b)) to adjust the workplace, including changes to the ventilation.
(4) in the workplace with the potential increased exposure from radon, on which it was
measurement in accordance with paragraph 2 established the possibility of exceeding
the values of the effective dose of a worker 6 mSv per 12 months, must be the measurement
and the determination of the effective dose is carried out in each calendar year.
§ 94
Information about the site, with the possible increased exposure from radon and their
transfer of Authority
[To section 96, paragraph 3 (b), (c) and (d))) the Atomic law]
(1) the data obtained by measurement under section 93 para. 1 and the data on the set
effective doses of workers at the workplace, with possible increased exposure
of radon shall be kept for the duration of the work
the worker and to the time when the worker reaches or would have reached 75 years of age
age, but at least for a period of 30 years after the end of work.
(2) the information referred to in paragraph 1 and the information on exceeding the values under section 93
paragraph. 1 and 2 shall be notified to the authority within one month of their
How to obtain.
(3) the authority must be about the site with the possible increased exposure from radon
reported the following information:
and) identification of persons engaged in an activity in which it is
powered by: the workplace, the
(b)) the name and address of the workplace,
(c)), pursuant to section 96 workplace type para. 1 the Atomic Act,
(d) a description of the site, organization), method and mode of work, ventilation
conditions and period of residence of the worker in the workplace,
e) description of the optimization of radiation protection in the workplace and
(f)) in case the condition is true, according to § 97 para. 1 the Atomic
the Act, a description of the measures taken to ensure the radiation protection and description
meet the requirements pursuant to § 97 para. 2 the Atomic Act in the workplace.
(4) the information referred to in paragraph 3 shall be notified to the authority for the first time before
the start of operation of the workplace with the potential increased exposure from radon and
whenever you change them.
(5) the information referred to in paragraph 3 shall be kept for a period of 30 years from the
closure of the workplace with the potential increased exposure from radon.
§ 95
Optimization of radiation protection in the workplace with the potential increased exposure
from radon
[To section 66 paragraph 6 (b), (c)) of the Atomic Act]
(1) the optimization of radiation protection in the workplace with the potential for increased
radiation from radon shall be carried out when exceeding the reference levels
under section 93 para. 1.
(2) measures to implement the optimization of radiation protection referred to in paragraph
1 are in particular
and organization, how) to change or mode of operation and
(b) workplace with possible adjustment) increased exposure from radon, including editing
the ventilation.
§ 96
Radon index land
(Section 98 (4) of the Atomic Act)
(1) to determine the radon index land must be
and representative file) used the measurement of 222Rn in activity concentration
soil air
b) evaluated by the plynopropustnost Foundation soil and
(c)) used by local and General characteristics of the geological bedrock
influencing the direction and speed of movement of radon in Foundation soils.
(2) the determination of the radon index land must be evaluated on the
basis of a common assessment of the
and the statistical characteristics of the activity concentration) of radon in soil
the air and
(b)) the characteristics of measurement or assessment of the identified plynopropustnosti
on the basis of professional experience and knowledge.
(3) how to evaluate the results to determine the radon index land
Annex No. 26 of this Decree.
(4) Radon index of land is low, if it is
and volume activity of radon) in the soil air less than
1.10 kBq/m3 for high permeable subsoils,
2.8 kBq/m3 for moderately permeable subsoils, or
3.30 kBq/m3 for low permeable subsoils, or
(b)), the numerical value of land determined by measuring radon index less than
10.
(5) land is a central index of Radon, if
and volume activity of radon) in the soil air
1. greater than 10 kBq/m3 and less than 30 kBq/m3 for high permeable
subsoils,
2. more than 20 kBq/m3 and less than 70 kBq/m3 for moderately permeable
subsoils, or
3. more than 30 kBq/m3 and less than 100 kBq/m3 for low permeable
subsoils, or
(b)), the numerical value of land determined by measuring radon index greater than
10 and less than 35.
(6) the land is a high index of Radon, if
and volume activity of radon) in the soil air greater than
1.30 kBq/m3 for high permeable subsoils,
2.70 kBq/m3 for moderately permeable subsoils, or
3.100 kBq/m3 for low permeable subsoils, or
(b)), the numerical value of land determined by measuring radon index greater than
35.
§ 97
The protection of natural persons before the natural radiation in the construction
[To section 66 paragraph 6 (a)), and (b)) and § 99 paragraph 2. 5 of the Atomic Act]
(1) the reference level for natural radiation inside the building with a residential or
tourist rooms
and) 300 Bq/m3 for volumetric activity of radon in indoor air of House
or residential room; This value applies to the average value of
When replacing the usual when using air, or
b) 1 mikroSv/h for maximum power consumption of the 3-d dose equivalent
in a residential or residential room at a height of 1 m above the floor and
a distance of 0.5 m from the wall.
(2) the value of the annual average activity concentration of radon in the air, when you
which is the owner of a building with a residential or tourist rooms
be required to take measures to reduce the level of exposure, it is 3 000 Bq/m3.
(3) when exceeding the reference levels referred to in paragraph 1, the owner of the
to assess the effectiveness of the measures relating to buildings, in particular in the
and the use of the buildings), including adjusting the ventilation, or
(b)) or the execution of technological adjustment measures.
(4) the procedure referred to in paragraph 3, the owner of the building
and use procedures, mutatis mutandis) optimization of radiation protection in accordance with § 66
paragraph. 1, para. 2 (a). (c)) and paragraph 2. 5 of the Atomic Act and
(b)) use the information about the source of radon and its severity in a given situation
and the available types of radon reduction measures in the building,
including the cost of them.
Protection against natural radionuclides in water
§ 98
[To section 100, paragraph 3, point (a) to (c))) the Atomic law]
(1) the maximum permissible value of the activity concentration of radon in drinking water
for public use and for the supply of bottled water on the market laid down in annex
# 27 of this Ordinance.
(2) the level of reference content natural radionuclides in drinking water for
public use and for the supply of bottled water on the market provided for in annex No.
27 to this Decree.
(3) the method and scope of the systematic measurement and evaluation of the content of natural
radionuclides in the water as stipulated in Annex # 27 to this Decree.
(4) systematic measurement and evaluation of the content of natural radionuclides in
the water must be carried out in water from an underground source and in a mixture of water from
the underground resources and water surface
and for the first time before the start of supply) of drinking water for public use
(b)) for the first time before the start of the supply of bottled water on the market in the Czech Republic
and
(c)), then periodically throughout the supply of drinking water for the public
the need for, or bottled water on the market in the Czech Republic.
(5) the frequency of the systematic measurement and evaluation of the content of natural
radionuclides in the water as stipulated in Annex # 27 to this Decree.
(6) in the context of the systematic measurement and evaluation of the content of natural
radionuclides in water must be done fixing the indicative dose
If the level of investigation exceeded the total Alpha activity concentration
or the total beta activity concentration. Investigation levels laid down in annex
# 27 of this Ordinance.
(7) the establishment of indicative benefits under paragraph 6 shall be carried out with
using the results of additional analysis. How complementary analysis
# 27 as stipulated in annex to this Decree.
§ 99
[To section 100, paragraph 3, point (a) to (c))) the Atomic law]
(1) if the pre-trial level of total Alpha activity concentration
exceeded the total levels of inquiry and exceeding the activity concentration
the beta is only caused by the presence of 40 k, indicative dose according to § 98
paragraph. 6 may not be established and its reference level shall be considered
nepřekročenou.
(2) systematic measurement of the content of natural radionuclides in the water can be
done in the range of the basic analysis, if
and) found that the reference level indicative dose is not exceeded,
or
b) established that the reference level is exceeded, according to subparagraph (a))
radiation protection optimized.
(3) the scope of the basic analysis referred to in paragraph 2 shall set out Annex # 27 to
This Decree.
(4) if the results Exceed the 5 consecutive years of reference
levels laid down in § 98 para. 2, the systematic measurement and evaluation of the contents of the
natural radionuclides in the water must be carried out only if there is a
a change that could affect the content of natural radionuclides in
the water, with the exception of water treatment to reduce the content of natural radionuclides.
(5) comply with the values according to § 98 para. 1, 2, and 6 must be assessed
a) for water supplied from a water supply network in place, where the water flows out of
Withers,
(b)) for water supplied from a tanker to the point at which it emerges from the tanker,
c) in the case of water put into bottles or container, which are intended to
the sale, on the place of performance of the bottle or container and the
(d)) by the water used to prepare food in a food business on the
the place, where the water is used in the undertaking.
(6) water samples must be for the systematic measurement and evaluation of the contents of the
natural radionuclides in the water are taken to be representative
for
and water provided during the whole) of the calendar year and for the whole water
a large, well-stocked and region
(b)) all produced water stáčenou into the bottles or containers.
§ 100
Data relating to protection against natural radionuclides in water and
notifying Authority
[To section 100, paragraph 3, point b (d)) of the Atomic Act]
(1) registration of the results of measurements of the content of natural radionuclides in water and
other data shall in the case of the supply of drinking water for public use
include
and) the name or name, surname, date of birth and address of the place of
of residence, ID number, if assigned, the natural person who is
supplier of water,
b) name, address or the address of the location of the branch on the territory of the United
States, if it was established, the identification number, if assigned,
legal person, which is a supplier of water,
(c) the name of the water)
(d)) the water source identification data,
(e) data on source) water and the annual volume of water delivered,
f) supplied by the municipality and the enumeration of the population served,
g) data on the water treatment,
h) indication of the measures pursuant to § 100 para. 2 (a). (c)), and (d)) of the Atomic
the law,
I) details of the place, date and method of sampling,
j) protocols with the measurement results of the samples, and
k) registration number of the authorisation holder, which performs measurement.
(2) registration of the results of measurements of the content of natural radionuclides in water and
other data in the event of supply of bottled water on the market in the United
Republic include
and) identification of the extent referred to in paragraph 1 (b). a) and b)
1. the manufacturer of bottled water and
2. the importer of bottled water,
(b)) and the type of designation of bottled water,
(c)) the water source identification data,
(d)), the annual volume of manufacture or importation of bottled water,
e) details of water treatment,
(f)), details of measures pursuant to § 100 para. 2 (a). (c)), and (d)) of the Atomic
the law,
g) data on the location, date and method of sampling,
(h) the results of measurements) logs samples and
I) the registration number of the authorisation holder, which performs measurement.
(3) the information referred to in paragraphs 1 and 2 shall be kept for a period of 5 years from the
their supply of drinking water for public use or marketing of packaged
water on the market in the Czech Republic.
(4) the information referred to in paragraphs 1 and 2 shall be notified to the Authority
and for the first time before the start of supply) of drinking water for public use or
the supply of bottled water on the market in the Czech Republic and
(b)) in any calendar year.
(5) the data referred to in paragraph 1 (b). I) and (j)) and paragraph 2 (a). g) and (h)) can be
The Office communicated through the authorisation holder in accordance with § 9 para. 2
(a). (h)), section 6 of the Atomic Act.
(6) data on their supply of drinking water for public use or
the supply of bottled water on the market in the Czech Republic must be reported to the Office of
without delay.
§ 101
Optimization of radiation protection in the supply of drinking water for the public
the need for and delivery of bottled water on the market in the Czech Republic
[To section 66 paragraph 6 (b), (c)) of the Atomic Act]
When adopting the measures referred to in § 100 para. 2 (a). (c)), and (d)) of the Atomic
the law has the supplier of the water and the manufacturer and importer of bottled water to take into account
the effectiveness of these measures. These measures are in particular:
and select a different source of water),
(b)) in the case of imports of bottled water imports a similar bottled water with a lower
natural radionuclide content, or
c) installation of equipment to reduce the content of natural radionuclides.
§ 102
Protection against natural radionuclides in building materials
[To section 9, paragraph 2 (b) (j)) and § 101 paragraph. 4 (b). and atomic) to c)
the law]
(1) the Enumeration of building materials according to § 9 para. 2 (a). j) nuclear
the law set out in annex 28 to this Decree.
(2) the reference level for the building material is 1 mSv per year for
effective dose from external exposure, the representative person or gamma radiation
When you use the building with living quarters, or pobytovými rooms exclusive
the dose of radiation received from the natural background.
(3) Index is a measure of the mass activities and quantity specified by the relationship
I = aK/3 000 Bq.kg-1 + aRa/300 Bq.kg-1 + aTh/200 Bq.kg-1 based on
by weight of activities expressed in Bq.kg-1 radionuclide 40 k, 226Ra and
228Th.
(4) the index value for the building material activity concentration is 1. When
This value has exceeded the reference level provided for in paragraph 2 for
the excess.
(5) the systematic measurement and evaluation of the content of natural radionuclides in
building materials must be carried out by determining the index weight
things to do
and for the first time, before placing the building) of material on the market and
(b)), at least once per calendar year.
(6) the effective dose of a person from the use of representative for the building
material from external radiation, or gamma radiation must be determined from the results of the
measurement by weight of 40 k, 226Ra activity and 228Th established in accordance with
paragraph 5 and assessed by comparison with the reference levels referred to in paragraph 2.
(7) If a construction material or components of radioactive substance with
broken balance of long-term natural radionuclides being freed from
workplace materials with increased content of natural radionuclides,
determination of the index of the activity must be replaced by the measurement pursuant to §
95 para. 1 (b). (b)) of the Atomic Act. The results of this measurement shall be
evaluated by comparison with the reference levels referred to in paragraph 2. Effective
representative person of the use of the dose for the building material from the external
gamma radiation exposure must be determined from the results of this measurement and
evaluated by comparison with the reference levels referred to in paragraph 2.
§ 103
Data relating to protection against natural radionuclides in the construction
material and their notification of the Office
[To section 101, paragraph 4 (b), (d)) of the Atomic Act]
(1) registration of the results of measurements of the content of natural radionuclides in
construction material and other data shall include
and) the name or name, surname, date of birth and address of the place of
of residence, ID number, if assigned, the natural person who is
the manufacturer or importer of building materials,
b) name, address or the address of the location of the branch on the territory of the United
States, if it was established, the identification number, if assigned,
legal person, who is a manufacturer or an importer of building materials,
(c) the designation or type) of building materials and raw materials for its production and
an indication of their origin,
(d)) the indication of the annual volume of manufacture or importation of building materials,
e) an indication of the origin of imported building materials,
(f) characterizing the range and) details how to use building materials
in construction,
(g)), the indication of the date and method of sampling,
(h) the results of measurements) logs samples and
I) the registration number of the authorisation holder, which performs measurement.
(2) the information referred to in paragraph 1 must be kept for at least 5 years from the
their supply of building materials on the market in the Czech Republic.
(3) the information referred to in paragraph 1 must be notified to the Authority
and for the first time before the delivery of the building) of material on the market in the Czech Republic and
(b)) in any calendar year.
(4) the information referred to in paragraph 1 (b). g) and (h)) can be notified to the Authority
by the holder of the authorization referred to in § 9 para. 2 (a). h) point 6
the Atomic Act.
(5) indication of their supply of building materials on the market in the United
the Republic must be notified to the Authority without delay.
TITLE IV
The GARBAGE COLLECTOR
§ 104
Clearance levels for workplaces with sources of ionizing radiation
(§ 76 para. 6 of the Atomic Act)
(1) the release level for workplaces with sources of ionizing radiation
considered to be exceeded
and when the subject or release) of the solid, if
1. in the emitted by the subject or in the quantity of emitted by solids is
the sum of the shares of the average weight of the activities of individual radionuclides
and their release levels of activity concentration is greater than 1;
the release levels of activity set out in annex # 7 to this
the Decree, or
2. anywhere on the desktop of 300 cm2 of the surface of the subject is the reclaimed surface
contamination is higher than the release level of the surface; release
the level of surface activity laid down in annex # 7 to this Decree,
(b)) when the discharge of waste water into surface water, if the sum
the average volume of the products of each of the activities discharged
radionuclides and their maximum conversion factors hing to receive
the ingestion of an adult individual of the population is greater than 0.1 mSv/m3;
the maximum conversion factor of hing to receive the ingestion of an adult
individual members of the public laid down in annex 3 to this Decree,
(c)) in the discharge of waste water into the sewer system for public use,
If the sum of the products of the average volumetric activity in each
discharges of radionuclides and their maximum conversion factors hing
to receive the ingestion of an adult individual of the population is greater than 10
MSV/m3,
(d)) in a discharge of radionuclides into the air, if the sum of the products of
the average volume of radionuclides discharged and the activities of individual
their conversion factors for inhaled intake hinh adults
an individual of the population referred to in annex 3 to this Decree is larger
than 0.1 mikroSv/m3; conversion factor for inhalation intake hinh
an adult individual of the population set out in annex 3 to this
the Decree,
(e)) in the landfill of waste, if
1. in the emitted by the subject or release by a solid is the sum of the shares
the average weight of the individual activities of radionuclides and their
the release levels of activity concentration is greater than 1, or
2. input the spatial dose equivalent at a distance of 1 m from the
the surface of the landfill is in place on disposal greater than 0.4 mikroSv/h,
and
(f)) during combustion in an incinerator, if
1. combustion gases emitted into the atmosphere exceeds the clearance levels
referred to in subparagraph (d)), or
2. ash generated by burning crosses clearance levels under (a))
or (e)).
(2) the average concentration referred to in paragraph 1 (b). and) and (e))
applies to a single released by the subject or the quantity released
homogeneous solids. Released quantities of solids is considered
homogeneous, if the density of the solid is in any part of the volume does not differ from
its average density of more than 30% and mass activity of the solid
in any part of the volume does not differ from the average activity concentration of
more than 30%.
(3) the average quantity of liquid volume activity generated or
gaseous substances referred to in paragraph 1 (b). b) to (d)) shall be determined from the
a representative sample of the substance taken prior to its release, or
to be removed during the release.
§ 105
Clearance levels for the workplace with the possibility of an increased exposure of
natural sources of radiation
[To section 95 para. 6 (b), (d)) of the Atomic Act]
(1) the clearance levels for the release of solid materials from the workplace with
the possibility of increased radiation exposure from natural sources of radiation, including their
landfill of waste, garbage collection for reuse, recycling
or burning, are
and activity of natural radionuclides by weight) of a series of Group 1 kBq/kg,
(b) the activity of natural radionuclides by weight) of a series of 232Th 1 kBq/kg,
or
(c)) mass activity 40 k 10 kBq/kg.
(2) the clearance levels referred to in paragraph 1 shall not be considered excess,
If the average concentration of any radionuclide is not greater than
the value of the clearance levels.
(3) the clearance levels for the discharge of waste water into surface waters
are
and the total volume activity) the average Alpha for all substances, 0.5 Bq/l and the
(b) the average total volume activity) beta, after deduction of the contribution of 40 k in the
all the substances of 1 Bq/l.
(4) the clearance levels referred to in paragraph 3 shall not be considered excess,
If the average density of Alpha activity or average bulk activity
Beta after deducting the contribution of 40 k is not greater than the value of the release
level.
(5) the clearance levels for discharges of wastewater into the drains for
public use are
and the total volume activity) the average Alpha in all substances 50 Bq/l and the
(b) the average total volume activity) beta, after deduction of the contribution of 40 k in the
all fabrics 100 Bq/l.
(6) the clearance levels referred to in paragraph 5 shall not be considered excess,
If the average density of Alpha activity or average bulk activity
Beta after deducting the contribution of 40 k is not greater than the value of the release
level.
(7) the average value referred to in paragraphs 1, 3 and 5 shall apply to the quantities of
released materials, which can be used to weight or volume
the activity can be considered as homogeneous.
TITLE V OF THE
EMERGENCY EXPOSURE SITUATIONS
Section 106
Reference levels for emergency exposure situations
[To section 66 paragraph 6 (a)) of the Atomic Act]
The reference level for exposure of individuals in an emergency exposure
the situation is for the sum of 100 mSv of effective dose from external exposure and
the committed effective dose from internal exposure.
§ 107
Protective measures in an emergency exposure situation
[To § 104 paragraph 9 (a)) of the Atomic Act]
(1) when the justification and optimization in the context of deciding on the introduction of
protective measures in an emergency exposure situation must be taken into account
and feasibility considerations) of the protective measures, in particular
1. population density,
2. the traffic situation,
3. the existence of a large settlement units,
4. the time required to prepare the evacuation of the population, or
5. the current meteorological situation,
(b)) the size of the exposure of individuals, which would have been averted by the introduction of
protective measures, and
(c) the consequences of the implemented protection measures).
(2) Urgent protective measures must be introduced, should always
absorbed dose in the bodies in the course of less than 2 days for any
natural persons may not exceed the levels laid down in annex # 29 of this
the Decree.
(3) it is justified by the emergency safeguard measures
and hide, if dark) the effective dose is greater than 10 mSv per
period lasting a maximum of 2 days of scorching,
(b) following administration of prophylaxis if)
1. There is a risk of internal contamination with radioactive iodine and
2. the other full-time equivalent dose in the thyroid gland caused by
radioactive isotopes of iodine is greater than 100 mSv, or
(c)) evacuation, if the sum of the effective dose has not yet received in an emergency
exposure situation is by offsetting the effect of the ongoing trade
measures and the effective dose that could be averted by the evacuation, it is
more than 100 mSv during the first 7 days.
(4) a reasoned subsequent protective measures is
and restricting the use of radionuclides contaminated) food, water and
feedingstuffs, retrograde annual time effective dose is greater than 1 mSv,
and
(b) resettlement of the population) is impossible to ensure an effective dose of the population in the
the return of the affected territory less than 20 mSv over a period of the next 12
months.
(5) when deciding the appeal introduced protective measures must be
take into account the exposure, which occurred after the revocation of the protective
measures.
(6) the appeal is justified by the protection measures, evacuation and sheltering
the resettlement of the inhabitants, if the effective dose over a period of the next 12
months after the revocation of the measure less than 20 mSv.
(7) while the occurrence of the emergency exposure situations and extraordinary
the situation after another disaster must be taken can increase damage from
emergency situation after another crash as a result of introduction of a safeguard
measures in the range of greater than the benefit from the reduction of the exposure.
Informing people about the risk of extending the intervention and data on
the intervention of
section 108
[To § 104 paragraph 9 (b)), and (c)) of the Atomic Act]
(1) Hitting a person whose posting to intervene in advance assumes
must in the context of their regular education may receive general and regularly
updated information about
and) effects of ionizing radiation and related potential health
the risks and
b) precautionary measures to avert or radiation protection reduction
exposure to radiation.
(2) the person sending the person hitting it must intervene before the intervention
to inform about the
and radiation situation and) current estimates of effective dose, which may
hitting a person may receive during the intervention, and
(b)) all safeguard measures, which is in the course of the intervention required
follow.
(3) Affecting a person whose posting is not expected to intervene in advance,
must be within a reasonable range, you may receive the information referred to in paragraphs 1 and 2.
The provision of information must be affecting the person confirmed in writing.
(4) the person sending a person to intervene must hitting after performing the intervention
to inform the intervening person about the size of the evaluated the effective dose,
the hitting has been received.
(5) Hitting a person, who is a member of the fire rescue
the Corps of the Czech Republic, police of the Czech Republic or the Czech Army
States must, before the provision of a service promise or oath
informed that within the framework of the classification may be
sent to the intervention, which can be exceeded the reference level 100
mSv.
section 109
[To § 104 paragraph 9 (b)) to (e)) of the Atomic Act]
(1) the consent of hitting people with participation in the intervention must be recorded
in writing signed by hitting people. The consent of a person who is trespassing
a member of the fire brigade of the United States, the police
The United States, or the army of the Czech Republic, is considered to have been
composition of the staff promise or oath.
(2) personal protective equipment and equipment intervening persons must in what
as far as possible to limit the surface and internal contamination of people.
(3) the list of persons involved and the records and information concerning the facts under section
108 and paragraph 1 must keep a broadcasting person for a period of 10 years from the
their intervention.
(4) the records of the monitoring and evaluation of the size of the exposure affecting persons
the person must keep a broadcasting for a period of 30 years after the end of the intervention.
(5) the identification of the person and her affecting the received dose must
sending a person to forward to the Office, immediately after their intervention.
§ 110
Procedures for optimizing measures to direct the lasting exposure in
as a result of an emergency exposure situation
[To section 66 paragraph 6 (a)), and (c)) of the Atomic Act]
(1) when optimizing measures to direct the lasting exposure in
as a result of an emergency exposure situation must be in an existing exposure
situation taken into account
and exposure as a result of) the external contamination of the environment and
(b) the exposure as a result of) the internal intake of contaminated food or
contaminated water.
(2) the reference level to avoid distortion of the lasting exposure as a result of
an emergency exposure situation is not more than 20 mSv per 12 months.
(3) Measures to direct the lasting exposure to manage
contaminated sites resulting from an emergency exposure situation
must include the
and) the definition of contaminated areas in their degree of contamination,
(b) restrictions on the movement of natural persons),
(c)) the conditions for livestock and crop production,
d) establishing conditions for use in contaminated areas,
(e) the conditions for decontaminating) in the contaminated area, and
f) conditions for the storage and processing of contaminated waste.
(4) if they are not aware of more accurate data on the period of stay in the buildings and in the
open terrain, it is considered that the representative spends inside buildings
person 7 000 hours per calendar year.
(5) when optimizing measures to direct the lasting exposure
caused by the radioactive contamination of the food chain must be
taken into account
and the degree of contamination of items) of the food chain and
(b)) the representation of the contaminated items of the food chain in the food
a basket of representative person.
PART THREE
SECURITY OF RADIOACTIVE SOURCES
§ 111
Security practices of the source
(§ 164 (2) of the Atomic Act)
(1) the permit holder must make the security of the source
1. up to 3. security categories so that
and, determine the information important) in terms of security of
resources and ensure their protection against abuse and
(b)) will take measures to detect and delay both the access to
radionuklidovému the source and the response to it, in particular
1. preventing unauthorized transfer, in the case of radioactive source 1.
security categories, and
2. reduce the likelihood of unauthorized transfer to the lowest
attainable peace, if it is a radioactive source 2. or 3. category
Security.
(2) the security of the source 1. up to 3. security categories
must include the
and both the detection system) access to the radionuklidovému sources 1.
up to 3. category security, which must ensure that
1. detect unauthorised transfer of resources 3.
security categories,
2. detection of any unauthorized access attempt to radionuklidovému
source 1. and 2. security categories,
3. the unveiling of an unauthorized access attempt to radionuklidovému sources 1.
category security unauthorized worker authorisation holder and
4. obtaining information necessary to pursue without delay the evaluation found
both the access,
(b)) a system of barriers to the transfer of the source, which
must ensure
1. reduce the likelihood of unauthorized transfer of
source 3. security categories,
2. reduce the likelihood of unauthorized transfer of
source 2. the Security category at the lowest achievable level, and
3. delay sufficient to begin intervention and preventing unauthorized
the relocation of the source 1. security categories, and
(c)) the system response to an unauthorized access is detected, which must include
1. the adoption of measures in the event of unauthorized transfer of
source 3. security categories,
2. the immediate adoption of measures to prevent the unauthorized transfer
of the source 2. security categories or interrupted
and
3. the immediate implementation of the intervention, which prevents unauthorized repositioning
of the source, and ensure that adequate human and
material resources for such action for source 1. category
Security.
§ 112
Elements of the system security
(§ 164 (2) of the Atomic Act)
The elements that the security system of the source include,
are
and) technical resources and organisational measures which obviously make it difficult for
access to the radionuklidovému resources and discourage such unauthorised physical
person from unwanted conduct,
(b)) the technical means and the organizational measures to ensure the timely
the recognition of both the access to the radionuklidovému source,
c) mechanical and other barriers, which extends as far as possible the time required
unauthorized transfer of the source,
d) organisational measures that ensure the response to attempts to access
radionuklidovému resources, and
e) rules for working with individuals, information and technical
means to ensure the security of the source.
§ 113
Security plan
(Section 24 para. 7 of the Atomic Act)
Security plan must include
and a description of the source), categorization and description of how to
its use,
(b) a description of the site and use) the imposition of the source, its surroundings
and its location in the buildings and campuses,
(c) the location of the buildings and sites) due to publicly available sites,
(d)) the objective of a security plan for buildings and facilities, taking into account
1. the specific conditions and risks and
2. the procedures for the prevention of the adverse consequences of the wrongful act,
e) description of the security measures of the source, including the
1. radionuklidovému controlling access to resources,
2. detection of both the access to the radionuklidovému source,
3. both the access to the radionuklidovému source,
4. intervention in nepovolaném access to radionuklidovému resources,
5. methods of communication between persons who are evaluating deliverables
the alarm system, and affected persons, and
6. assessment of the effectiveness of the measures referred to in points 1 to 5,
f) description of the security measures of the administrative
resources, including
1. the rights and duties of workers,
2. standard and emergency operations with radionuclide source, maintenance
and repair of technical means of hampering access to radionuklidovému
resources and to ensure early detection of both the access to
radionuklidovému resources
3. how to ensure the protection of information relevant for the
security of radioactive sources,
4. methods of controlling access to resources and radionuklidovému
5. the training of personnel, and
(g) a description of the measures to increase).
section 114
Protection of information relevant for the security of the
resources
(§ 164 (2) of the Atomic Act)
(1) the information important in terms of security of
resources are
and radionuclide data sources) and their location,
(b)) planned means of transportation and its route,
(c)) the information contained in the security plan,
d) details of the security system,
e) data on the surveillance,
(f) data on administrative measures) within the security
of the source and
g) details of the intervention, which prevents unauthorized repositioning
of the source 1. security categories.
(2) the information referred to in paragraph 1, the holder of the authorisation to provide only
persons who need them for the performance of their activities, and only in the
the extent to which this performance they need.
(3) the permit holder must appoint a natural person is required to ensure
security of radioactive sources and the coordination of activities within the
security of radioactive sources.
(4) the holder of the authorisation shall ensure that any natural person involved in the
security of radioactive sources and physical self
accessing the radionuklidovému sources 1. Security category
selected and continuously assessed having regard to the risk of
security that can represent.
PART FOUR
FINAL PROVISIONS
section 115
Notification
This Decree was notified in accordance with the directive of the European Parliament
and of the Council (EU) 1535 of 9 June. September 2015, the procedure for the provision
information in the field of technical regulations and of rules on services,
the information society.
§ 116
Transitional provisions
(1) the test of long-term stability to be implemented under section 27 para. 1 (b). and)
After the entry into force of section 6 of this order on a simple source
ionizing radiation, which is
and with an intraoral dental x-ray equipment), on which the previous
long-term stability test conducted in 2015, must be made
within 24 months of the test of long-term stability,
(b)) with an intraoral dental x-ray equipment manufactured before the year 2005,
on which the previous long-term stability test carried out in
2016, must be made within 24 months after this test, the long-term
stability,
(c) dental panoramic x-ray) equipment manufactured before the year
2009, must be made within 12 months from the previous test of the long-term
stability,
d) dental panoramic x-ray equipment manufactured in 2009
up to 2011, must be made within 24 months from the previous test
long-term stability, or
e) veterinary x-ray equipment manufactured before 2006, you must
be made within 24 months from the previous tests of long-term stability.
(2) the requirements for sources of ionising radiation used for medical
exposure referred to in
§ 76 (a)). and (b)). (b) paragraphs 3 and 4), and (b). (c)), paragraphs 3 to 6 shall
apply to the sources of ionizing radiation that are installed after the effective date of
of this order and
(b)) § 76 (a). (b) point 5 (a)). c) section 7 shall apply to the source
ionizing radiation installed after 1. February 2018.
(3) the requirements for sources of ionising radiation used for medical
exposure referred to in
and § 77 para.) 1 (b). and (3) (a)). (b) point 7 (a)). (c) point 6)
(a). (d)), paragraphs 3 to 6 and para. 2 shall apply to the sources of ionising
radiation installed after entry into force of this order,
(b)) § 77 para. 1 (b). and) point 4 shall apply to the sources of ionising
radiation installed after 1. February 2018 and
(c) section 77 para.) 1 (b). and section 5 (a)). (b)) point 8 shall apply to the source
ionizing radiation installed after 1. April 2012.
(4) Hitting a person, who is a member of the fire rescue
the Corps of the Czech Republic, police of the Czech Republic or the Czech Army
States before the date of entry into force of this Decree, it is considered
an informed pursuant to § 108 paragraph. 4 the date of entry into force of this
the Decree.
(5) the consent of the persons referred to in paragraph 4 that spans within the meaning of § 109 paragraph. 1
It is considered a given composition of the staff promise or oath before
entry into force of this Decree.
§ 117
The effectiveness of the
This Decree shall enter into force on 1 January 2000. January 2017, with the exception of
and section 75 para.) 4, § 76 (a). (b) point 2 (a)). c) point 2 and § 77 para. 1
(a). (b)) points 4 and 6 (a). d) points 1 and 2, which will become effective 1.
February 2018, and
(b)) § 77 para. 1 (b). and that paragraph 2) shall take effect on 1. January 2021.
Chair:
Ing. Drábová, Ph.d., v. r.
Annex No 1-29 Decree No 422/2016 Sb.
_________________
*) Note. ASPI: the attachments are available on the website http://ftp.aspi.cz/opispdf/2016.html#castka_172
1) Council Directive 2013/51/Euratom of 22 December 2003. October 2013, the
laying down the requirements for the protection of the health of the population, in terms of
radioactive substances in water intended for human consumption.
Council Directive 2013/59/Euratom of 5 December. December 2013, which
laying down the basic safety standards for protection against the dangers of
exposure to ionising radiation and the directives 89/618/Euratom,
90/641/Euratom Directive 96/29/Euratom, 97/43/Euratom and Directive 2003/122/Euratom.
