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Amendment Of The Decree On Radiation Protection

Original Language Title: změna vyhlášky o radiační ochraně

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499/2005 Coll.
DECREE


Dated 6 December 2005

Amending Decree of the State Office for Nuclear Safety no.
307/2002 Coll., On radiation protection

The State Office for Nuclear Safety, pursuant to § 47 par. 7 to perform
§ 2. h) Point 4, § 2. gg), § 4 para. 4, 5, 6, 7, 11 and 12
, § 6 para. 2, 3, 4, 5 and 6, § 7 para. 3, § 8. 1, § 9 paragraph. 1
point. h), i), j) ar), § 13 par. 3 point. d) § 17 para. 1 point. d) §
18 paragraph. 1 point. a) and c), § 18 par. 4 and 5, § 22 letter. e) § 24 para. 4 and
points I.6, I.7, I.8, I.12 and I.13 Annex to the Law no. 18/1997 Coll., on
peaceful use of nuclear energy and ionizing radiation (atomic Act)
and amending and supplementing certain acts, as amended by Act no. 83/1998 Coll. and
Act no. 13/2002 Coll., (hereinafter the "Act")
Article I


Decree no. 307/2002 Coll., On radiation protection, as follows:

First In footnote no. 1 at the end of the text on a separate line
sentence "Council Directive 2003/122 / Euratom of 22 December 2003 on
control of high-activity sealed radioactive sources and orphan sources
.".

Second In § 1, at the end of the text of letter i) the words "including
high activity and orphan sources".

Third In § 1, paragraph 3 shall be added:

"(3) This decree was notified in accordance with Directive
European Parliament and Council Directive 98/34 / EC of 22 June 1998 on the procedure
providing information in the field of technical standards and regulations and rules for services
information society, as amended by Directive 98/48 / EC. ".

Fourth In § 2, letter b) including footnote no. 2 reads:

"B) Practitioner - doctor, dentist or other health worker
in the extent of their qualifications given special legal regulations
^ 2) has clinical responsibility for medical exposure

2 ) Act no. 95/2004 Coll., on conditions for the acquisition and recognition of professional
and specialized competencies to perform medical
professions of doctor, dentist and pharmacist, as amended by Act no. 125/2005 Coll
. ".

Fifth In § 2, letter e) including footnote no. 5a reads:

"E) indicating a doctor - a doctor indicating medical exposure by
special legislation 5a)

5a) Decree no. 424/2004 Coll., Activities of medical personnel
and other professionals. ".

6th In § 2 letter f) reads:

"F) Clinical responsibility - responsibility for clinical medical exposure
under a special legal regulation 5a)."

7th In § 2, letter r) reads:

"R) the practical tasks of medical exposure - Practical medical
exposure in terms of special legislation 5a)."

8th In § 2 letter u), including footnotes. 5b reads:

"U) radiological physicist - healthcare worker with a professional
competence to pursue the profession of radiological physicist under special legislation
^ 5b)

5b) Act no. 96/2004 Coll. on conditions for the acquisition and recognition
competence to engage in paramedical professions and to carry
activities of providing health care and amending
some related laws (Act on paramedical professions
), as amended by law no. 125 / 2005 Sb.

Decree no. 424/2004 Coll., laying down
activities of health workers and other professionals. ".

9th In § 2 letter ff) reads:

"Ff) Health screening - a diagnostic procedure that utilizes
radiological installations for early diagnosis in
risk population groups."

10th In § 2, the following points jj) to mm), added:

"Jj) abandoned emitter - sealed radionuclide source that is not under the supervision
required by law and whose activity at the time of its discovery
is above the exemption level of activity according to § 5. Forsaken
source is particularly source, who supervised
laid down in legal regulations have never been, or has been abandoned, lost, stolen or transferred without informing the recipient
or without notice to the Office

kk) high-activity sources - sealed radionuclide sources, which
activity at the time of manufacture or, if no time is known, at the time of his
first launch is equal to or higher than the corresponding level
activities listed in Annex no. 14

ll) the unused resource - a source of ionizing radiation, which is already

Activity for which the Office has issued a permit under § 9. 1 point.
I) of the Act, does not use and which no further use for this activity is not expected
,

Mm) recognized stock - authorized by the department in terms of the authorization
accordance with § 9. 1 point. d) or i) of the Act to collect or
term storage of radionuclide sources, including high-
emitters, or to rework them. ".

11th in § 3, at the end of subparagraph j) the full stop is replaced a comma and
letter k), which reads:

"k) photon dose equivalent, which is the exposure ^ 7) multiplied by a factor
38.76 Sv.C-1.kg." .

12th in § 4 para. 1 at the end of the text of letter g) the words "
unauthorized use or improper use."

13th in § 5. 2, after the word "represent" the word "also".

14th in § 6 letter g) reads:

"g) a consumer product with radionuclides, including ionization detectors fire
, not covered by the provisions of § 7. e) if within
permit to manufacture or preparation or their importation or exportation
accordance with § 9. 1 point. s) of the Act otherwise stated. ".

15th in § 7 letter e) reads:

" e) ionization smoke detectors, where the sum of the activities emitters more than ten
relevant exemption levels of activity, located
simultaneously in one building held by one person. ".

16th in § 9 point. e) the words" feed or other equipment containing sealed radionuclide
emitters, including irradiators for food irradiation
and other stationary industrial irradiators "is replaced
" Radioisotope irradiator for the irradiation of food and raw materials or other
stationary industrial irradiator. "

17th in § 9 at the end of letter f) is replaced by a comma and a letter
g), added:

"g) high-level emitter.."

18th in § 11 para. 1 the introductory part of the word "insignificant"
words "or type-approved minor."

19th in § 12 letter.), after the word "small" words "unapproved type
. "

20th in § 12 letter d) be deleted.

existing letters e) to g) shall be designated letters d) through f).

21st In § 12, at the end of the text in subparagraph d) the words "on which
character of radiation activity requires definition of controlled
zone".

22nd In § 13 point. g) after the word "meets" the word "appropriate".

23rd In § 13 at the end of subparagraph g) is replaced by a comma and
letter h), which reads:

"H) workspace with a compact extracorporeal blood irradiator closed
radionuclide source.".

24th In § 14 point. a) the words "the treatment of these irradiators" are deleted.

25th In § 14 letter c) reads:

"C) recognized the warehouse."

26th In § 14 point. e) the word "food" is replaced by "
food and raw materials."

27th In § 15 point. a) the words "§ 2. h) of the Act" is replaced by "§ 2
point. h) of section 1 of the Act".

28th In § 15 point. c) the words "Category III" is replaced by "lower
category."

29th In § 15, at the end of subparagraph c) is replaced by a comma and
letter d), which reads:

"D) storage of spent or irradiated nuclear fuel.".

30th In § 16 para. 2 the words "point. A) to c)" is replaced by "point. C)
to e)."

31st In § 23 para. 4, third sentence after the word "previous"
insert the word "demonstrable" and the last sentence is deleted.

32nd In the title of Part Two, Title I, the words "workplace where
perform radiation activity" is replaced by "
sources of ionizing radiation and workplaces with."

33rd In § 24 para. 1 introductory part, the words "workplace, where
perform radiation activities" is replaced by "sources of ionizing radiation and workplaces
with them."

34th In § 24 para. 1 point. d) the words "to ensure"
replaced by "ensuring".

35th In § 24 par. 3, second sentence, the words "radiation workers"
replace the words "members of the public."

36th In § 24 para. 4, at the beginning of the letter a) the words "
equipment and personal dosimeters."

37th In § 24 at the end of paragraph 4 is replaced by a comma and
letter d), which reads:

"D) medical supervision in accordance with § 28.".

38th In § 24, paragraphs 7 to 10, including note below
fn. 9 added:

"(7) Sources of ionizing radiation to be stored securely so that it

Ensure that they do not deal with unauthorized persons, and was prevented
loss or theft of the source or its damage.

(8) Unused radionuclide sources and devices containing them
without undue delay transmit to another authorized user returns
manufacturers or suppliers, transmit in a recognized warehouse or disposed of as radioactive waste
.

(9) Manufacturers, importers and distributors of radionuclide sources
create permanent conditions for the return of their manufactured, imported or distributed
radionuclide sources and devices containing
radionuclide source.

(10) At work I to IV. category as part of the quality system documentation
create operating rules, which include
written procedures for safe handling of ionizing radiation, including
procedures to prevent unauthorized use of resources, loss, theft or
damage, and emergency instructions ^ 9)
for action in case of deviations from normal operation, and permanent access
workers at least the intervention instructions, for example, by posting
accessible location.

9a) § 12 of Decree no. 318/2002 Coll., On details to ensure
emergency preparedness at nuclear installations and workplaces with sources of ionizing radiation and
requirements for the content of the internal emergency plan and emergency
Regulations as amended by Decree no. 2/2004 Coll. ".

39th in § 26 par. 2, first sentence, the word" operator
monitored or controlled area "is replaced by" Each holder of an authorization pursuant to § 9 | || paragraph. 1 point. d) i) of the Act, "and the word" situation "the words" and
were familiar with the operating regulations and other documentation.
For all radiation workers working in the controlled area of ​​a nuclear power plant
education must include an understanding of the regulations and
approved documentation for the controlled zone. ".

40th in § 27 par. 1, the second sentence is replaced by the phrase "systematic supervision
radiation protection is ensured by persons with direct responsibility for
radiation protection and supervisors.".

41st in § 27 paragraph 2, including footnotes fn. 10 reads:

"(2) to ensure systematic supervision establishes a permit holder pursuant
§ 9 paragraph. 1 point. d) i) of the Act supervising person and at all workplaces
II. and higher category ensures the presence of the corresponding
number of people with direct responsibility for radiation protection ^ 10).
Presence of at least one person with direct responsibility for radiation protection
provides for activities in the controlled zone also
permit holder pursuant to § 9. 1 point. r) of the Act to services within the scope
according to § 59 para. 1 point. d) or a customer of this service.
Any person with direct responsibility for radiation protection and supervising
person must have special competence ^ 10)
corresponding operating activities and sources of ionizing radiation. If
operated by a natural person who has the appropriate special competence, may
supervising the activities of the person or persons with direct responsibility for radiation protection
exercise alone.

10) Decree no. 146/1997 Coll., Specifying activities that have
immediate impact on nuclear safety and activities especially important
terms of radiation protection requirements for qualification and professional
preparation, method of verification of special professional competence and granting authorizations to selected personnel
and
way be approved documentation for licensing of training of selected personnel, as
Decree no. 315/2002 Coll. ".
|| | 42nd in § 27 paragraph 7 reads:

"(7) Persons with direct responsibility for radiation protection at
ensure continuous supervision over radiation protection primarily involved
that constantly oversee that all workers in their work
satisfy the requirements of health protection as well as technical and administrative requirements
to ensure radiation protection. ".

43rd in § 28 para. 6 of the last sentence, the words"
handling sources of ionizing radiation "is replaced by" and employers ".

44th in § 29 paragraph 1 reads:

" (1) the monitored zone is defined wherever it is expects
effective dose could be higher than 1 mSv per year or an equivalent dose
could be higher than one tenth of the dose limit for eye

Lens, skin and extremities laid down in § 20 para. 1 point. c) to e). ".

45th in § 29 para. 2 of the first sentence after the comma, including commas deleted.

46th in § 29 para. 2 in the second sentence the word "also" be deleted.

47th in § 29 paragraph 3 reads:

"(3) the monitored zone is defined as a comprehensive and clearly defined part
workplace, usually structurally separate. At the entrances or border with
monitored zone indicates the warning "Followed zone with sources of ionizing radiation
", possibly a sign of radiation danger ^ 16) and
data on the nature and sources of risk associated with them. ". || |
48th in § 30. 1, the first sentence is replaced "Controlled zone is defined
wherever the effective dose could be higher than 6 mSv per year or
where the equivalent dose could be higher than three tenths
dose limit for the lens of the eye, skin and extremities laid down in § 20 paragraph
. 1 point. c) to e). ".

49th in § 30. 6, the second sentence is replaced by the phrase" other persons may
controlled area to work or reside only in the event that an operator controlled
band the conditions are such that their
exposure does not exceed the general limits. ".

50th in § 30 paragraph 7 reads:

" (7) in order to stay within the controlled area each equips
protective working aids adequately their activities or
reasons for their stay in the zone. ".

51st in § 30. 8 last sentence, the word" equivalent ", the following words
"in the controlled zone" and the words "radiation workers"
words "entering a controlled area."

52nd in § 32 at the end of paragraph 5 sentence "Generator radiation at || | which expired shelf life, or if no time is specified by the manufacturer
can be used if its parameters and operating characteristics
meet the manufacturer's intended purpose, test requirements
long-term stability and, in the case of radiological equipment and requirements
national radiological standards. ".

53rd In the heading of § 33, the words "workplaces with closed radionuclide emitters
" is replaced by "sealed sources, devices and
workplaces with them."

54th In § 33 para. 2 first sentence, the word "may" the words "
be passed only and may do it."

55th In § 33 at the end of paragraph 5 sentence "After a period
usability, or if no time is specified by the manufacturer, can
sealed radionuclide sources used under the conditions specified in § 82 paragraph
. 5. ' .

56th In § 33 at the end of paragraph 6 the sentence "
equipment containing sealed radionuclide sources for which expired shelf life,
, or if no time is specified by the manufacturer, can be used if its
parameters and operating characteristics comply with the manufacturer's intended purpose
use, test requirements and long-term stability in case
radiological equipment and the requirements of national radiological
standards. ".

57th In § 33, paragraphs 7 to 11 are added:

"(7) A person dealing with high-emitter, periodically verifies
whether high-level emitter, or a device containing
located on the site of use or storage and in apparently good condition
.

(8) High-level emitter provides the manufacturer, or in the case of imported
supplier of radiators, unmistakable identification number. If
This number shall be engraved or stamped on the radiator. This number || | will also be engraved or stamped on the packaging emitters. If this is not feasible or in the case
shipping containers for multiple uses, at least
packaging information on the nature of the emitter. the manufacturer, or in the case of imported
emitters supplier also ensure that the packaging and radiators, if
feasible, and emitter are marked and labeled
sign of radiation hazards, and each part of the documentation produced or imported
type of a high-emitters were even photos or other similar
representation emitters and of the typical source container.

(9) A person who has held high-level emitter, ensure that this
emitter and its packaging was always accompanied by written information to identify
source and its nature and that, if practicable,
marked and labeled with a sign of radiation hazards and that the markings and signs
remain readable. Identification and labeling should be in accordance with
identification and labeling in accordance with paragraph 8. The relevant documentation

Also contains photographs or other illustrations similar source package
resources, transport packaging, device or equipment. Photographs or other illustrations
similar resource is not necessary if it can not acquire or obtain
without removing the device. The provisions of this paragraph shall not apply to
radioactive waste repository or a recognized warehouse.

(10) A person who holds sealed radionuclide sources, besides
which is insignificant or type-approved minor sources, at least once annually
conducted an inventory of the sources and the results sent in writing or
another agreed form Office.

(11) A person who has held high-level emitter, without undue delay, notify the Office
theft, loss or unauthorized use of spotlights and
ensure long-term stability of the test in accordance with § 71 after each
event that could damage the radiator. About this event and the measures taken
Office informs.. "

58th in § 36 para. 1 point. B) Section 1 reads:

" 1. radiation generators. "

59th in § 36 para. 1 point. b), point 2 is deleted.

The present point 3 becomes point second

60 . In § 36 para. 1, at the end of subparagraph c) is replaced by a comma and
following point 3 is added:

"3. radiation generators. "

61st in § 36 para. 1 point. d) Section 1 reads:

" 1. radiation generators. "

62nd in § 36 para. 1 point. d) at the end of the text of point 2, the words"
except ionization fire detectors, subject to the provisions of § || | 7 point. e) ".

63rd in § 36 par. 2 point. e) the words" nuclear installation or radioactive waste repository
operated "are replaced by" workplace
implementation '.

64th in § 36 par. 3, second sentence, the word "instruction" is replaced
'intervention instructions. "

65th in § 37 paragraph 3 reads:

" (3) the manufacturer of radionuclide sources or appliances with them, except
insignificant or type-approved minor sources, adds
made sources of ionizing radiation a person who is entitled to them
deal, at least store them. " .

66th in § 38 par. 2 ", and sources of ionizing radiation delivers a
person who is entitled to dispose of them, at least at the store."
replaced by " and radionuclide sources or appliances with them, except
insignificant or type-approved minor sources, gives a person
who is authorized to dispose of them, at least at the store. ".

67th In § 38 par. 3, after the words "ionizing radiation" is inserted
words "which are radionuclide sources or contain".

68th In § 38, the following paragraph 4 is added:

"(4) Permission to ionizing radiation
specific way in which the import of ionizing radiation sources, must be the one who
in the course of his business imports those resources in the Czech Republic
. '.

69th In § 39 par. 3, after the words "ionizing radiation" is inserted
words "which are radionuclide sources or contain".

70th In § 40 para. 1 the words "and creating conditions for" deleted.

71st In § 40 par. 1 a) and b) are deleted.

72nd In § 40 par. 2, "and the long-term stability tests in accordance with § 71
with open radionuclide sources accompanying letter, with sealed radionuclide sources
valid certificate sealed radionuclide emitters
issued by an authorized person and minor sources of instruction
use approved by the Authority. " replaced by "long-term stability tests
according to § 71 and constancy tests according to § 72, with open radionuclide sources
accompanying sheet for sealed radionuclide sources
certificate sealed radionuclide source issued by an authorized person and small
resources and consumer products with added
radioactive substances whose production or importation was approved by the Office
accordance with § 9. 1 point. a) of the Act, including instructions for use
guidelines for the safe use of these products by the user, with
small type-approved sources with a user manual approved by the Authority. ".

73rd In § 40 para. 4, the words ", and sources of ionizing radiation delivers a
person who is entitled to dispose of them, at least store them."
Replaced by "and radionuclide sources and devices with them, except
insignificant or type-approved minor sources, gives a person
who is authorized to dispose of them, at least at the store.".


74th In § 41 paragraph. 2 point. a) the words "proven to conform to the approved type
" are replaced by "documentation of compliance with the approved pattern or with
requirements of technical regulations that apply to them."

75th In § 42 par. 3 of the word "instruction" is replaced by "intervention
instruction."

76th In § 43 at the end of the text of paragraph 2, the words "except
non-destructive X-ray equipment and facilities with well logs
sealed radionuclide source".

77th In § 43 par. 3, the words "paragraph 1" are deleted.

78th In § 44 para. 1 point. b) the words "and verification of performance
sources of ionizing radiation to the approved type" are deleted.

79th In § 44 para. 1 subparagraph b) a new point c), which reads:

"C) the verification of the properties of ionizing radiation sources is approved
type, or".

Existing letters c) and d) shall be designated Letters d) and e).

80th In § 44 par. 2 point. e) the words "professional representatives"
replaced by "individuals with appropriate special professional competence
representing the licensee".

81st In § 46 para. 1, second sentence, the words "at their originator, which
is entitled to be treated as open radionuclide sources"
replaced by "a person who is entitled to be treated as a
unsealed radionuclide sources, and even processing and treatment of radioactive waste
performed by such a person on the basis of a contractual relationship with
holder of a radioactive waste management "and
third sentence, the words" § 56 to § 57 " the words "and § 89".

82nd In § 48 at the end of paragraph 7 of the sentence "Its design, or
combined with the technical design and equipment of the place in which they are placed
, ensure that the waste is placed in them is protected against undesirable devaluation
, misuse, theft or leakage
threatening environment. ".

83rd In § 51 at the end of paragraph 2 is replaced by a comma and
letter d), which reads:

"D) radioactive waste can be safely handled throughout
duration of storage, including radioactive waste in packaging
files.".

84th In § 53 par. 2, first sentence, the word "permissible amount
radionuclide sources for storage" is replaced by "acceptable
activity radionuclide sources" and in the second sentence, the words "permissible amount
" is replaced by "permissible activities ".

85th In § 55 paragraph. 2, after letter b) the following point c) is added:

"C) the number and activity of stored
disused sealed radionuclide sources for high-emitters and their registration, or
. Identification numbers in accordance with § 33 para. 8".

Existing letters c) to l) shall be designated Letters d) through m).

86th In § 57 par. 1 point. c) the words "public sewer"
replace the words "public sewerage system".

87th In § 57 par. 1 at the end of letter c) the words "unless
Sewerage Rules 22a ^) provides otherwise".

Footnote. 22a reads:

"22a) § 14 par. 3 of Law no. 274/2001 Coll., On Water Supply and Sewerage
for public use and amending some laws (Act on Water Supply and Sewerage
), as amended. ".

88th In § 57 par. 2, the words "water and air pollution from nuclear installations or to use aggregate
heaps of uranium mines." replaced by "environmental
environment from nuclear facilities, mining and processing of uranium ore from
workplaces where there may be a significant increase in exposure from natural sources
nor on an aggregate heaps of uranium mines.".

89th In § 57 at the end of paragraph 2, the sentence "The release level is
apply also to the means of transport in accordance with Annex no. 4 of Decree no.
317/2002 Coll., On type approval and transport.".

90th In § 58 par. 2 first sentence, the word "use" the words "
, including information on how to safely dispose of the product or its
leftovers, after the user becomes a waste."

91st In § 58 para. 2 last sentence, the word "object" is replaced by
"product".

92nd In § 58, the following paragraph 4 is added:

"(4) The manufacturer or importer of a consumer product with added
radioactive substances create conditions for the return him
manufactured or imported products and allow him takeback
produced or imported products from them the scrap." .


93rd In § 59 para. 1 at the end of the introductory part of the words
"the following activities provided as a service to other natural or legal persons
".

94th In § 59 para. 1, letter d) be deleted.

Existing letters e) to g) shall be designated Letters d) through f).

95th In § 59 para. 1 point. d) after the word "departments" the words "IV.
category".

96th In § 59 para. 1 point. e) the word "assessment" the words
'exposure to natural radionuclides, including measurement and evaluation ".

97th In § 59 para. 1, at the end of letter f) is replaced by a comma and
subparagraph g), added:

"G) the import, export and distribution of radiation generators, except
radiation generators, which are insignificant resources.".

98th In § 59 para. 2 point. a) and b), the words "Annex no. 6"
added the words "or 15".

99th In § 59 para. 2 point. c) the words "professional representatives"
replaced by "individuals with appropriate special professional competence
representing the licensee".

100th In § 59 par. 3 of the second sentence deleted.

One hundred and first In the 59 paragraph. 4 words' to e) "are replaced by" or d) "and the words
" the holder of the authorization, which is the operator of the controlled area, where
to perform these services there. " is replaced
"Client service, unless he is authorized to perform an activity that is subject
services.".

102nd In § 62 paragraph. 1 introductory part, the words "be achieved"
replaced by "implementing procedures under § 17 and achieves it."

103rd In § 63 para. 1 first sentence, the word "audit" the words "[§
2 point. G)]."

104th In § 64 para. 1, "where, for technical reasons
possible" is replaced by "if possible".

105th In § 64 at the end of the text of paragraph 2, the words "for
radionuclide irradiators and linear accelerators and without adequate
X-ray equipment for brachytherapy."

106th In § 66 paragraph 1 and 2 added:

"(1) In radiotherapeutic practices must work closely
radiological physicist with the appropriate specialized qualifications by
special legislation 5b). For other radiological practices
must be provided with appropriate radiological physicist specialized | || competence, as appropriate, for consultation on
optimization including patient dosimetry and quality assurance including
quality control, if necessary
advice on matters relating to radiation protection concerning medical exposure. || |
(2) Radiological physics is carrying out its activities
responsible for implementing the physical and dosimetric activities necessary for its
and safe application of ionizing radiation in clinical practice and
assessment of the physical and dosimetric aspects of implementation
new radiological equipment or new physical methods into clinical practice
. It is also responsible for the implementation and evaluation of the quality system in
its scope, particularly for securing and evaluation of test results
sources of ionizing radiation and for the management of tests
sources of ionizing radiation and other medical devices which may affect
exposure of patients or other individuals undergoing medical exposure, and
application and optimization of radiation protection in clinical practice
medical equipment. ".

107th In § 66 para. 3, "Special attention must be paid to the training of practitioners
" is replaced by "permit holder
provides training of practitioners."

108th In § 67 par. 3 first sentence, the words "Special attention must be paid to the choice
medical devices and selecting" replaced
"permit holder ensures appropriate selection of medical devices and
option".

109s. In § 67 paragraph 4 reads:

"(4) Every medical exposure is recorded variables and parameters
allowing the dosage of any examination or treatment for a person elected
specific radiological procedure (§ 63 para. 1).".

110th In § 68 at the end of the text of paragraph 1, the words "or in
description of the monitoring pursuant to § 36 para. 3".

111th In § 68 par. 2 letter d) reads:

"D) the parameters and characteristics of other products and equipment that are intended for immediate
activities with ionizing radiation
whose structure can influence the level of radiation protection, for example,

Planning systems, developing process, the quality of X-ray films and intensifying
quality films. "

112th in § 68 par. 2 point. E) the words" declaration of conformity carried
the manufacturer or importer of the device or written assurance that
declaration of conformity has been issued "are replaced by" proof of type approval
. "

113th in § 68 par. 2 point. f) section 1, "including external
workers" are deleted.

114th in § 69 par. 1 at the end of the text of letter a) the words "or
requirements of relevant technical regulations." || |
115th in § 69 par. 2, "a quality assurance program or by
this program" is replaced by "quality system documentation."

116th in § 69 para. 6 for the word "record" the words
"way" and the word "monitoring program" is replaced
"monitoring program approved by the Office, or in the description
monitoring in accordance with § 36 para. 3".
| || 117th in § 69 par. 7, the word "regulation" is replaced by "prescription-24a)."

Footnote. 24a reads:

"24a) Decree no. 419/2002 Coll., On personal radiation passport.".

118th In § 70 para. 1 point. d) point 1 the words' letter b) "shall be
words" paragraph c) "and the word" manufacturing "the words"
or identification. "

119th In § 70 para. 1 point. d) Section 2, the words "or other
mechanical and operational systems laid down in the decision on type approval
," are deleted.

120th In § 70 para. 1 point. e) point 1 the words "or other mechanical systems
specified in the certificate of approval" shall be deleted.

121st In § 70 paragraph 2 reads:

"(2) Acceptance tests are carried out at least to the extent specified
Czech technical standards, on a proposal by a manufacturer, importer or distributor
or the extent specified in the type approval.
During the acceptance test the permit holder the performing, down
scope and frequency measurement and verification of properties of ionizing radiation
intended type of use in the tests
long-term stability and constancy tests. ".

122nd In § 70 par. 3 first sentence, the words "under special legal regulations
^ 10)" the words "and when it comes to providing health care
also appropriate specialized competence by special laws
^ 5b) ".

123rd In § 70 at the end of paragraph 3 the sentence "copy of the record
sent licensee of the performing, writing or in another agreed form
Office within one month from the test.".

124th In § 71 paragraph 1 reads:

"(1) The test long-term stability for each source of ionizing radiation
performing at least to the extent specified by Czech technical standards
^ 26), on a proposal by a manufacturer, importer or distributor and
or the extent specified for type approval. The range of tests
states permit holder carrying out the acceptance test and the first test
long-term stability (hereinafter referred to as "initial test of the long-term stability
"). ".

125th In § 71 para. 2 point. c) after the word "radiation", the word
"repeatedly".

126th In § 71 para. 2 point. d) Section 1 reads:

"12.1 months for radiodiagnostic cabin
X-ray equipment destined for human medicine and material resources".

127th In § 71 par. 3, second sentence, the words "under special legal regulations
^ 10)" the words ", and when it comes to providing health care
also relevant specialist qualification according to special legal
regulations ^ 5b) ".

128th In § 71 para. 3 last sentence after the word "test" the words
"in writing or in another agreed form".

129th In § 71 para. 4, a sentence added after the first sentence "Tests
long-term stability also not covered by the simple sources of ionizing radiation
, where it was stated in terms of a permit to dispose of them or
conditions decision on type approval. ".

130th In § 74 par. 3, the last sentence is replaced by the phrase "For the ingestion of water
other persons is expected that a person younger than two years old ingests
0.25 m3 of water per year in liquid form, a person from 2 to 17 years swallows 0.45 cubic meters of water per year
in liquid form and a person older than 17 years ingests 1 m3 of water per year, of which 0.7 m3
in liquid form. ".

131st In § 74 the following paragraph 5 is added:

"(5) For the calculation of the effective dose due to inhalation transformation products

Radon from the air in areas affected by mining and processing of uranium ores
the background value equivalent radon concentration contemplating
10 Bq / m3, if no other in the area is not known. ".

132. In § 76 par. 3 first sentence, the words "surface contamination with radionuclides
" is replaced by "radioactive contamination" and the second sentence is deleted
.

133rd in § 76 par. 4 words ", which works with open
radionuclide sources, and workplaces IV. category. "
replace the words" IV. category and those workplaces with unsealed sources III.
Category in which it is required by permit conditions. ".

134th in § 77 par. 1, second sentence deleted.

135th in § 77 par. 2 the words "including external workers" are deleted.

136th In § 77 at the end of paragraph 2 the following sentence "for workers
category a is a control period for evaluation of personal dosimeter 1
month. Evaluation of personal dosimeters carried out by authorized dosimetric service
.. "

137th in § 77 par. 3, third sentence, the words" or intervention "are deleted.

138th in § 77 par. 5, the first sentence the words "loss of control over
source of ionizing radiation" is deleted and the word "may" is replaced by
"are able".

139th in § 78 paragraph 1 reads: | ||
"(1) Monitoring discharges and other respiratory
release of radioactive substances into the environment is performed by monitoring, measurement, recording and evaluation
variables and parameters characterizing
be released, in particular their total, mass
volume or activity. Is introduced in all workplaces where there is a
disposal of materials contaminated with radionuclides of controlled release or where there is a possibility of leakage
significant amount of radionuclides into the environment.
Used to monitor compliance with the authorized outlet or permit conditions and
early identification and evaluation of potential leaks and their consequences on the population
around the workplace and the environment. ".

140th in § 78 para. 2 first sentence, the words "into the air and waterways"
replaced by "and other paths of release of radioactive substances into the environment
."

141st in § 79 para. 1, second sentence after the word "departments" are inserted
words "IV. categories and on those workplaces III. category, where the
required by permit conditions. "

142nd in § 79 par. 3 first sentence, the words" very significant sources of ionizing radiation
"is replaced by" workplace ".

143rd in § 79 para. 4 the word "regulation" is replaced by "prescription-26a)."

Footnote. 26a reads:

"26a ) Decree no. 319/2002 Coll., on function and organization of the national radiation monitoring network
.

Decree no. 11/1999 Coll., On emergency planning zone. ".

144th in § 80 par. 2 letter f) reads:

'f) Protocol on the acceptance test, the test
long-term stability if such tests are required, and records the results of measurements carried out within
constancy tests ".

145th in § 80 at the end paragraph 2 is replaced by a comma and a letter
j) is added:

"j) for high activity sources also photograph or other similar
representation in cases where it is required according to § 33 paragraph .
8 or 9th. "

146th in § 80 paragraph 3 reads:

" (3) If the Office provides otherwise, keep logs of acceptance tests after
for use of equipment, the test
long-term stability for at least three years and records the results of measurements carried out within
constancy tests for at least one year.
Other data pursuant to paragraphs 1 and 2 shall be kept for at least 10 years from completion
dealing with the source of ionizing radiation. ".

147th in § 80 paragraph. 4 of the introductory part of the words "
records of ionizing radiation sources," the word "data" and the words "
otherwise specified" word "and".

148th in § 80 paragraph. 4 at the end of subparagraph c ) replaces the comma and full stop
letter d) shall be deleted.

149th in § 80 paragraph. 5, the words "by the end of January and the end of July of the current year
summary for the previous half-year" are replaced the words "collectively
for the previous quarter, at the latest one month after its expiry".

150th in § 82 par. 2 point. b) the word "manufacturing" the words "|| | or identification. "

151st In § 82 at the end of paragraph 3 the sentence 'This provision shall not apply to high-level
emitters.".


152nd In § 82 para. 4 of the last sentence, the words "
classified as insignificant sources" are deleted and the words "sealed source" is inserted
words "to the authorized person to verify his tightness and used."

153 above. In § 82 para. 5, "but it has expired certificate,"
deleted.

154th In § 82 at the end of the text of paragraph 5, the words "on the basis
to the condition of the test results confirmed the long-term stability when
tightness test was conducted using the direct method."

155th In § 83 paragraph. 4 first sentence, the words "produced radionuclides"
words "or leads to their concentration."

156th In § 84 paragraph 1, including footnote no. 26b reads:

"(1) A licensee leads to records of personal doses of workers
category A following documents and information:

a) the name, place and date of birth,

b) personal identification number, if assigned a personal identification number wearer to use his
gave written consent under a special legal regulation 26b)

c) personal contributions and other data to characterize the exposure set by the Office in terms
authorized or approved by the Authority as part of the monitoring program
.

26b) § 13c of the Act no. 133/2000 Coll., on register of population and birth
numbers and on amendments to certain acts (register of population Act) in
amended. ".

157th In § 86 par. 2, the words "monitoring program" is deleted.

158th In § 87 point. d) the number "1000" is replaced by "400".

159 aircraft. In § 87 letter e) reads:

"E) work on which is carried

first management of solid coal combustion products to plants with a thermal
capacity of over 5 MW,

second production of building materials coal combustion products,

third extraction, transport pipelines and oil and gas processing,

fourth processing phosphate materials,

fifth production and processing of materials based on titanium minerals ,

sixth production and processing of materials based on mineral zirconium

seventh processing of raw materials containing rare earths

eighth metallurgical production of metals,

9. the production, processing and use of materials containing thorium and uranium

10th disposal of sludge from water supply treatment water from underground sources,

11th of waste materials, which have been shown,
the content of natural radionuclides in them exceeds the clearance levels or increases power
photon dose equivalent of more than 0.5 microSv / h. ".

160th § 88-91, including footnotes. 26c and 26d added:

"§ 88

investigative standards and guidance values ​​for exposure from natural sources

(1) for the workplace, where it may be a significant increase in exposure
from natural sources, the Subject to these levels of inquiry

a) 400 Bq / m3 for the average volume activity of radon in the air is
work for the department referred to in § 87 point. b), c), d) and e) || |
b) 1 mSv per year for the effective dose of natural background, except
radon and its decay products, for the office specified in § 87 point. e).

(2) for persons mentioned in § 89 para. 1 point. a) and b) at workplaces
listed in § 87 point. b), c), d) and e) target is 6 mSv per year
for the effective dose. If you can be this guideline value is exceeded,
it is a workplace with a significantly increased exposure from natural sources
and radiation protection at these sites provide in accordance with the provisions of §
90. at the same time implementing optimization of radiation protection procedures
according to § 17 and take measures to reduce exposure
consistent with the results of this optimization.

(3) For aircrew members who are working on board aircraft in
height above 8 km, is a guideline value of 1 mSv per year for an effective dose.
If this target can be exceeded, members of airline crews
must be informed about the size of exposure, health risks and
measures adopted and assesses the exposure of individual crew members and
on the basis of these assessments are being prepared and in order to reduce exposure
adjusting flight plans.

(4) Working conditions of pregnant women in workplaces listed in § 87
adjusted in accordance with the requirements of § 23 para. 2nd

§ 89

Range assessing, recording and transmission

(1) Measurement in the workplace, including the determination of effective doses, performs
authorized dosimetric service in accordance with the terms of the relevant

Authorization under § 9. 1 point. r) of the Act. The effective dose is determined

A) for individuals engaged in work on workplaces listed in §
87 point. b), c), d) and e), on which the expected exposure to radon and its decay products
due to their inhalation by measuring
average values ​​of radon activity concentration in the workplace and records
residence time, and to the extent provided for in paragraph 3,

B) for individuals who manage or residues of substances at the workplace
listed in § 87 point. e) based on the measurement of dose
input gamma, the average volume activities of radionuclides in
air, surface contamination of the workplace and residence time of registration,
to the extent provided for in paragraph 3,

C) for aircrew members working on board the aircraft at an altitude
over 8 km by establishing their participation in individual years,
flight characteristics and other parameters important for calculating
effective dose, repeatedly for each calendar year,

D) for other persons designated by the audit work and the way
in the frequency set by the Authority.

(2) measurements under paragraph 1 shall apply mutatis mutandis requirements
monitoring during radiation activities specified in § 73 to 79.

(3) At workplaces specified in § 87 point. b), c), d) and e)

A) where the total working time of persons performing work on these sites
demonstrably exceed 100 hours a year, exceeded the guideline values ​​
according to § 88 para. 2 does not consider possible a measurement or determination of the effective dose
Do not carry out

B) other than those referred to in subparagraph a), the measurements are performed to assess whether
exceeded investigative or guide values ​​in accordance with § 88

C) have been found when either of
investigation levels according to § 88 para. 1 point. a) or b) on the basis of repeated measurements and determine the effective dose
assesses whether it can be for people performing here
work exceeded the target value according to § 88 par. 2

D) have not been found to exceed any of investigation levels
according to § 88 para. 1 point. a) and b), or which were not repeated during
measurements, the possibility of exceeding the guideline values ​​of § 88 par. 2
may not be in the years to measurement or determination of an effective dose of conduct,
unless there is a change of work conditions, manufacturing processes or materials
,

E) for which it has been demonstrated that it may be for some people
exceeded the target value according to § 88 par. 2, the effective dose
all persons performing work in these workplaces repeatedly determined for each calendar
year.

(4) Effective doses of persons performing work on multiple sites
listed in § 87 para. 1 are added.

(5) Measured data and data on effective doses intended for persons
performing at workplaces stipulated in § 87
kept for the duration of their work and continue until the person
or would have attained 75 years of age, but at least for 30 years after
termination of employment, and the Office shall be notified within one month from receipt
.

(6) The Office shall state system records exposure of individuals
notified in writing or another agreed form collectively once a year
directly or through a person who performs personal dosimetry names
surnames, birth numbers if you were assigned a personal identification number to the holders of its utilization
granted its consent under a special legal regulation
^ 26b), and data on effective doses destined for the calendar year
all persons performing work at workplaces with a significantly increased | || radiation from natural sources according to § 90

(7) A person required by § 6 par. 3 of the Act clearly informs
persons engaged in work on workplaces listed in § 87 point. b), c), d) and e
), where it was found exceeding investigation levels according to § 88
on the results of measurements in the workplace on designated
effective doses and radiation risks associated with them and made measures.

§ 90

Significantly increased exposure from natural sources

(1) For persons engaged in work on workplaces listed in § 87, at
which may be an effective dose greater than 6 mSv per year,
radiation protection shall be ensured to the extent and in the manner that applies to work

Controlled area workplaces which carry radiation
activity, especially

A) defining the workplace or in part, where the persons performing the work
exceed three tenths of the limits stipulated in § 20-23, marking its
and secured against unauthorized entry

B) determining the persons who may perform work here, and determining the manner and extent of their demonstrable
annual guidance on radiation risks
workplace

C) providing input, annually recurring, output,
eventually follow and emergency medical preventive examinations
for persons performing work in this workplace,

D) treatment guidelines for work in the workplace, including guidelines for its
out safely and guidelines for the entry of persons other than performing
work there,

E) the determination of protective gear, which will feature people
conduct the work

F) ensuring monitoring in accordance with § 89 para. 2 and 5, including processing
monitoring program and specifying the method of handling materials
contaminated with radionuclides

G) the guidance documentation for the above mentioned scope and method of securing
radiation protection, including accounting and reporting of the Office of
effective doses and evidence of other variables listed in § 84 and 85.

(2) Cases significantly increased exposure from natural sources, which are
under § 4 para. 7 point. b) the law applicable exposure limits, and it
limits specified in § 20-23, the exposure of persons performing work pursuant to paragraph 1.


§ 91

Release of natural radionuclides from the workplace, where it can be
significant increase of exposure from natural sources

(1) With the release of natural radionuclides from departments where may
significant increase of exposure from natural sources, especially watching

A) deposits and sludge in piping and storage systems, such as
pumps, fittings, valves, collectors and separators,

B) filters and separators from separated materials
installed in power plants, waterworks, chemical and petrochemical industries,

C) management of technological units produced during the renovation, demolition or disposal
,

D) waste and secondary raw materials from production, such as energy
products, phosphogypsum,

E) wastewater.

(2) a solid insoluble substance or substances with low leaching for
which can be assumed that the rows are long decay
radionuclides approximately in equilibrium, the level of release to release
natural radionuclides into the environment environment of workplaces where
may be a significant increase in exposure to natural sources specified in §
87 point. e) mass activity index value is 2.

(3) In the case of other types of substances, particularly soluble substances,
in which the decay in the ranks of the long-term radioactive equilibrium radionuclide
significantly impaired the clearance levels for release
natural radionuclides into the environment of the workplace where
may be a significant increase in exposure to natural sources specified in §
87 point. e), are as follows

A) the release of solids is in no way a kilogram of material released
combined share of average weight
activities of individual radionuclides and release levels of mass activities relevant
radionuclides listed in Table. 1 Annex no. 2 is greater than 2

B) waste water discharges into surface water in any
liter of water discharged, the total volume activity alpha-26c) in all
substances greater than 0.5 Bq / l or total volume activity of beta-26d)
after deducting the contribution of K-40 in all substances is not greater than 1 Bq / l

C) in the discharge of wastewater into the public sewerage system in any
liter of water discharged, the total volume activity alpha-26c)
in any substances greater than 50 Bq / l or total volume activity beta
^ 26d) after deducting the contribution of K-40 in all substances
not greater than 100 Bq / l, unless sewerage Rules 22a ^) otherwise stated

D) is landfilled waste ^ 23) storing material complies by
letter a) and saving is done in a way that does not cause
at a distance of 1 m from the surface of the landfill increasing the photon dose

Equivalent of more than 0.2 microSv / h over the original background
in the area and the total photon dose equivalent rate no higher than 0.4
microSv / h.

(4) The release of natural radionuclides into the environment from
workplaces where there may be a significant increase in exposure from natural sources
, is also progressing according to § 56 par. 1, 2 and 4 and § 57 paragraph . 3rd

26c) CSN 75 7611 Water quality. Determination of radionuclides. The total volume
alpha activity.

26d) CSN 75 7612 Water quality. Determination of radionuclides. The total volume
beta activity. ".

161st in § 96 paragraph 1-3 added:

" (1) Building materials, subject to the requirement of systematic measurements
and evaluation of natural radionuclides are given in table no. 1
Annex no. 10 of the building products and materials. Limit values ​​
natural radionuclides above which are not
construction materials put into circulation and for individual construction materials
set the appropriate values ​​of mass activities listed in Table
. 1 Annex no. 10.

(2) Approximate values ​​of natural radionuclide content in building materials
are determined by the index values ​​of mass activity [§ 3
point. h)], given by way of use of building materials in the construction
Table no. 2 of Annex no. 10. When they crossed the start
building materials, which are designed for direct installation in buildings can be put into
circulation only justified in cases where the costs associated with
intervention to reduce the content of radionuclides, particularly by changing
raw materials or their origin, sorting materials, changing technologies or other
appropriate intervention, would have been significantly higher than the risks of health | || injury. If you are building materials exceeded the target value
intended solely for use as raw material for production of other building materials
not required to implement other interventions than demonstrable
informing the customer about the content of natural radionuclides in the present building
material. In this case, the cost of intervention disregarded.

(3) for systematic measurement and evaluation of natural radionuclide content in building materials
is considered to measure the mass activities
Ra-226, Th-228 and K-40, performed during initial construction material into
circulation, additional measurements in frequency according to table no. 3 of Annex
no. 10 and comparing the results of these measurements and their respective threshold
key values. ".

162nd in § 97 para. 1, footnote. 27 and in the first sentence the words
" values ​​volume activities "are deleted.

163rd in the Annex no. 1 in the text under the heading of the table no. 1
after the word" represent "the word" also ".

164th Annex no. 1 in table. 1, the line
"Ga-67106102"



inserted line "Ga-68105102" and

line

"Ga-72105 10"

, the line

"Ga-105 68 + 10".

165th in the Annex. tables 1 no. 1 and no. 2, the words "natural Th '
replaced by" Th sec. "and the words" natural U "words" U sec. ".

166th in Annex . 1 table no. 2, the following first line
"Sr-90 Y-90."

167th Annex no. 2 table no. 2 reads:

" Table no. 2

Distribution of radionuclides into classes according to radiotoxicity and potential threats to external radiation


For selected radionuclides, marked with a + in the second column of the table and
listed in Table no. 2 of Annex no. 1, the value of the release
levels apply only to these radionuclides themselves, but also represent
these radionuclides in equilibrium with those of radioactive products
transformations which are listed in the second column of the table. 2 Annex No.1.
------------------ ------------------------------------------------ || | -------------------------------------------- Class radionuclides
----------------------
1 Na-22, Na-24, Mg 28 Al 26, Al-28, C-38, K-43, C-47
Sc-46, Sc-48, V-48, Mn-52, Mn-52 m, Mn-54, Mn-56, Fe-52
Fe-59, Co-55, Co-56, Co-58, Co-60, Co-62 m, Zn-65
Ga-68, Ga-72, Ge-68, As-74, Br-82, Rb-82 m, Sr-82
Sr-85, Sr-92, Y-88, Zr-95 Nb-94 Nb-95 Nb-98, Mo-90
Mo-101, Tc-96, Ru-106 +, Ag-108 m + 110 m-Ag, Sb-124,
Te-131 m, 132-Te, Te-133 meters, Te-134, I-130, I-132, I-134,
I-135, Cs-132, Cs-134, Cs-136, Cs-137 +, Ba-140 +
La-140, Eu-152, Eu-154, Tb-160, H-181, Ta-182,
Os-185, Ir-190, Ir-192, Tl-200, Bi-206, Bi-207,

Po-203, Po-205, Po-207, R-223 + R-224 + R-225
R-226 + R-228 +, Ac-227, Ac-228, Th-228 +, 229 + Th, Th
sec. +, PA-231, U-230 +, U-232 +, U +-235, U-236, U sec. +
Np-237 + Pu-236, Pu-238, Pu-239, Pu-240, Pu-242,
Pu-244, Am-241, Am-242 m-Am-243 +, Cm-243, Cm-244,
Cm-245, Cm-246, Cm-247, Cm-248, CF 248, CF 252, CF-254,
------------------- -----------------------------------------------
2 Be-7, C-11, F-18, K-42, Sc-47, Co-57, Cu-64, Ga-67
As-76, Se-75, Rb-83, Rb-86, Sr-85 m, Sr-90 + Y-90
Y-92, Zr-97 + Nb-97, Mo-93, Mo-99, Ru-97, Ru-103,
Rh-105, Cd-115, In-111, In-113 m, 114 m-In, In-115 m,
Sn-113, Sn-125, 122 Sb, 125 Sb, Te-123 meters, Te-133
I-125, I-126, I-129, I-131, Cs-129, Ba-133, Ce-139,
Ce-141, Ce-143, Ce-144 +, Nd-147, Nd-149, Eu-152 m,
Eu-155, Gd-153, Er-171, Sm-153, Yb-169, W-187, Ir-194,
Pt-191, Au-198, Au-199, Hg197, Hg-197 meters, Hg-203
Tl-201, Tl-202, Pb-203, Pb-210 +, 212 + Pb-Bi-212 +
Po-210, Ra-227, PA-233, Th-227, Th-230, Th-232, U-231,
U-234, U-237, U-238 + Np-239, Cm-242
--------------------------- ---------------------------------------
3 C-14, P-32 , C-36, C-41, Cr-51, As-77, Sr-89, Y-91
Y-93, Zr-93 +, Tc-96 m, 97 m Tc, Tc-99, Tc-99m, Pd-109,
Ag-111, Cd-109 Cd-115 m, 125 m-Te, Te-127 meters, Te-129
I-123, Cs-135, Pr-142, Pm-149, Dy-165, Dy-166, Ho-166,
Gd-159, Tm-170, Yb-175, Lu-177, W-181, W-188, Re-186,
Re-188, Os-191, Os-193, Pt-193, Pt-197, Pt-197 m,
Tl-204, Bi-210, At-211, Th-226 Th-231 Th-234 + U-239,
Pu-234, Pu-235, Pu-237, Pu-241, Pu-243, Am-242, Bk-249
CF-246, CF-253
---------------------------------------- --------------------------
4H-3, Si-31, P-33, S-35, C-45, Mn-53, Fe-55, Co-58 m,
Co-60M, Co-61, Ni-59, Ni-63, Zn-69, Ge-71, As-73,
Nb-93 m Tc-97, Rh-103 m, Pd-103, Te-127, Cs-131,
Cs-134 m, Pr-143, Pm-147, Er-169, Tm-171, W-185, Pt-193 "
------------------- -----------------------------------------------


168th Annex no. 3 in the text under the heading of the table no. 3, "from the lungs into the digestive tract
" replaced "in the digestive tract into the body fluids
."

169. Annex no. 6 reads:

"Annex no. 6 to Decree no. 307/2002 Coll.

Conditions for proper and qualified testing in the field of radiation protection


General requirements:

The methodology and the protocols to be used in the names of variables and their
units in accordance with applicable standards; as well as the terms used in
statistical evaluation of measurement results.
Sample methodology


First identification of the person applying for a permit testing in the field of radiation protection


Second the person who developed the methodology

Third test type

Fourth IRS, for which the methodology developed

Fifth Literature references to standards

6th lists of equipment

7th documentation for the equipment required to perform the test

8th for each test must be stated:

08.01 characteristics of the measured parameter

08.02 Apparatus

08.03 measurement procedure and method for obtaining measurement results (description of the measurement diagram
geometry measurement used variables, units)

08.04 calculation algorithm, interpretation

08.05 the tolerance of the measured parameter, the accuracy and reproducibility of measurements


08.06 evaluation

Sample measurement protocol

First Protocol number

Second identification of persons possessing a permit to conduct tests including
permit number and the duration of

Third nature and subject tests, identification methodology for measuring

Fourth who perform the test

Fifth date of testing

6th identification of the workplace where the test was performed, the location of the IRS


7th detailed identification test of the IRS (a component type, production
number, manufacturing date, installation date)

8th submit the required documentation

9th Used Equipment & Instruments (date of last calibration)

10th List of measured parameters

11th Part of each text:

11.1 Parameter name

11.2 measurement conditions

03.11 recording the results of measurements (number of measurements used
quantities and units)

11.4 The result of the measurement accuracy, reproducibility, tolerance and
detected deviation from tolerance

11.5 rating yes / no

12th summary of the results of the individual tests, tests (parameter
requirement, measured value evaluation yes / no)


13th draft scope of testing the long-term stability and operational stability,
case of acceptance test

14th date copy of the protocol

15th signature of the person conducting tests of a statutory body holder
permission. "

170th Annex no. 7 in Table no. 1 in the second column, third and fourth
line, the words" 20 years "shall be replaced "15 years."

171st Annex no. 9, including footnote no. 31 reads:

"Annex no. 9 of Decree no. 307/2002 Coll.

Diagnostic reference levels

Table. 1

Diagnostic reference levels for radiographic examination

----------------------------------------------- -------------------------------------------
Entrance examinations Projection surface kerma Ke *)
(Based on 1 image)
[MGy]
-------------------------------------------- ----------------------------------------------
Lumbar AP spine - anteroposterior projection 10
LAT - lateral projection 30
LSJ - projection
lumbosacral transition to 40 -------------------------------------------
-----------------------------------------------
abdomen, intravenous AP - anteroposterior projection urography and 10


Cholecystography ------------------------------ -------------------------------------------------- ----------
pan AP - anteroposterior projection 10
---------------------------- -------------------------------------------------- ------------
hip joint AP - anteroposterior projection 10
------------------------- -------------------------------------------------- ---------------
Chest PA - projections zadopřední 0.4
LAT - lateral projection of 1.5 ----------------------------------------
--------------------------------------------------
Thoracic spine AP - 7 anteroposterior projection
LAT - lateral projection 20
------------------------------------------ ------------------------------------------------ || | Skull PA - projections zadopřední 5
LAT - lateral projection 3
------------------------------------------ ------------------------------------------------ || | teeth intraoral image 5
radiovisiography 1
--------------------------------------------- ---------------------------------------------

*) Kerma in air volume at the point of entry into the patient
offsetting backscatter. Values, where used
intensifying screens, are subject to a combination of film - film
amplifying a relative gain 200. For combination with a higher gain
(400, respectively. 600), the values ​​should be reduced to 2- times, respectively.
3 times.

Table. 2

Diagnostic reference levels for computed tomography
------------------------------------- ---------------------------------
Examination kermový weighted index computed tomography CWA)
(On one tomographic examination)
[MGy]
-------------------------------------------- --------------------------

Chapter 60 ---------------- -------------------------------------------------- Lumbar spine
----
35 ------------------------------------- --------------------------------- Belly

35 --------- -------------------------------------------------- -----------

A) Cw = 01.03 C100, c + 2 / 3C100, p where

C100, c is CTDI100 according to the harmonized standard ^ 31) specified in the standard
Wednesday the head of body or phantom with a height of 15 cm and a diameter
16 cm (head) and 32 cm (lumbar spine and abdomen) but when using variable
kerma place variable dose and C100, p is CTDI100 by
harmonized standard ^ 31) determined as the average of four
subsurface dose measurements around the perimeter of the same phantom, but using
Kerma variables instead of variables dose. For spiral CT examination should
values ​​should be reduced by multiplying by a factor 1 / p, where p = CT
pitch factor according to harmonized standard ^ 31) (feed rate
patient table per revolution and the N-times the thickness section, where N is the number
tomographic cuts formed in one revolution of the radiation source).

Table. 3

Diagnostic reference levels for mammography examinations
-------------------------------------- ------------------------------------------
thickness of the PMMA Equivalent thickness of the breast Moderate dose dairy žlázeb)
[cm] [cm] in the cranio-caudal projection
[MGy]

----------------------------------------------- ---------------------------------

3.0 3.2 1.3 4.0 4.5 2.0 4.5 5.3

2.5 5.0 6.0 3.3 6.0 7.5 5.0


7.0 9.0 7.3 ---------------------------- -------------------------------------------------- -

B) Determined in phantom breast using standard film and foil

Table no. 4

Diagnostic reference levels for radioscopic examination
--------------------------------------
------------ Operating mode Input power kermový c)
[MGy / min]
------------------------------------------ Normal
-------- 25 ----------------------------------
----------------
High performance d) ----------------------- 100
---------------------------

C) Kermový power in the air at the point of entry into the patient volume
offsetting backscatter.

D) For X-ray fluoroscopy devices that have an optional working
mode "high performance".

Table no. 5

Diagnostic reference level for the digitally processed image for DSA system

------------------------------- --------------------------------------------------
------------- For the examination of the abdomen e) Projection Entrance surface kerma Ke f)
(Related to 1snímek)
[MGy]
-------------------------------------------- --------------------------------------------------
digitally processed image AP - 1
anteroposterior projection for the abdominal region
------------------------------ -------------------------------------------------- --------------

E) Default exposure machine for examination in the abdomen;
Measured on a water phantom with a thickness of 20 cm, the largest field size (no zoom
), 3 frames per second. In the case of manual settings at a voltage of 70 kV
largest field size (no zoom), 3 frames per second.

F) In the air, offsetting the backscatter in the patient's body.

Table. 6

Diagnostic reference levels for radiodiagnostic examinations with

indicator surface kerma ------------------------------- ------------------------------------------------- | Investigations || Projection Product of kerma and area PKA
[Gy.cm2]
------------------------------------------ --------------------------------------
Chest PA / LAT - projection zadopřední 1 | || and side
--------------------------------------------- -----------------------------------
pan AP - anteroposterior projection 5
--- -------------------------------------------------- ---------------------------
Belly AP - anteroposterior projection 8
----------- -------------------------------------------------- -------------------
Lumbar spine AP - anteroposterior projection 10
------------------ -------------------------------------------------- ------------ 40

Urography ------------------------------ -------------------------------------------------- Stomach 25

------------------------------------------ -------------------------------------- Irigiskopie 60
----
-------------------------------------------------- --------------------------

Table. 7

Diagnostic reference levels for nuclear medicine examinations
---------------------------------------------------------------------------------------------------------
Authority system, type testing, a group of radionuclide Substance Activity
chemical form of the disease applied
in one
examination
[MBq]
---------------------------------------------------------------------------------------------------------
Bone scintigraphy of Tc-99m phosphates, phosphonates 800
(Whole-body, three-phase, SPECT)
---------------------------------------------------------------------------------------------------------
Bone marrow scintigraphy of Tc-99m nanocolloid 550
(Whole body, SPECT)
---------------------------------------------------------------------------------------------------------
Brain dynamic scintigraphy of Tc-99m TcO4, DTPA 600
-------------------------------------------------- --------------------
static, Tc-99m TcO4, DTPA 600
planar

-------------------------------------------------- --------------------
SPECT Tc-99m TcO4, DTPA, HMPAO, ECD 800
-------------------------------------------------- --------------------
receptors I-123 Ioflupane, IBZM 200
-------------------------------------------------- --------------------
accumulation of glucose F-18 FDG 400
-------------------------------------------------- --------------------------------------
Cisternography 111 In-DTPA 40
-------------------------------------------------- -
Yb-169 EDTA 40
---------------------------------------------------------------------------------------------------------
Test thyroid accumulation of I-131 iodide 0.5
-------------------------------------------------- --------------------------------------
planar scintigraphy of Tc-99m TcO4 200
-------------------------------------------------- -
Tc-99m-MIBI, DMSA (V) 400
-------------------------------------------------- -
I-123 iodide 20
-------------------------------------------------- -
I-131 iodide 7 *)
-------------------------------------------------- -
Tl-201 chloride 80
-------------------------------------------------- --------------------
whole body Tc-99m MIBI, DMSA (V) 800
carcinoma ------------------------------------------------ ----
thyroid I-131 iodide 185
-------------------------------------------------- -
Tl-201 chloride 100
---------------------------------------------------------------------------------------------------------
Parathyroid scintigraphy planar Tc-99m TcO4 200
bodies ----------------------------------- -----------------
Tc-99m MIBI 800
-------------------------------------------------- -
Tl-201 chloride 80
---------------------------------------------------------------------------------------------------------
Lung scintigraphy planar Tc-99m aerosol Technegas 1000 **)
ventilation ------------------------------------------------- ---
Kr-81 m gas 6000 ***)
-------------------------------------------------- --------------------------------------
planar scintigraphy of Tc-99m MAA microspheres 200
perfusion ------------------------------------------------- ---------------------
SPECT Tc-99m MAA microspheres 3000
---------------------------------------------------------------------------------------------------------
Heart perfusion SPECT Tc-99m MIBI, tetrofosmin 900 ****)
1400 *****)
myocardial ------------------------------------------------- ---------------------
SPECT Tl-201 chloride 110
-------------------------------------------------- --------------------
SPECT (reinjekce) Tl-201 chloride 40
-------------------------------------------------- --------------------------------------
metabolic. PET imaging of F-18 FDG 500
(Viability)
-------------------------------------------------- --------------------------------------
Radionuclide ventriculography Tc-99m RBC 800
-------------------------------------------------- --------------------------------------
first flow scintigraphy of Tc-99m TcO4, Tc-99m-DTPA 900
-------------------------------------------------- --------------------------------------
adrenergic invervace I-123 MIBG 400
---------------------------------------------------------------------------------------------------------
Lymphatic endosonography radionuclide Tc-99m nanocolloid 150
system ----------------------------------- -------------------------------------------------- ---
detection of sentinel. nodes Tc-99m nanocolloid 150

---------------------------------------------------------------------------------------------------------
Vessels radionuclide venography Tc-99m MAA 200
(One limb) ---------------------------------------------- ------
Tc-99m-DTPA 300
-------------------------------------------------- --------------------------------------
radionuclide angiography Tc-99m erythrocytes, TcO4 800
DTPA HSA
-------------------------------------------------- --------------------------------------
scintigraphic thrombus detection Tc-99m thrombocytes 500
---------------------------------------------------------------------------------------------------------
Blood volume and blood components Tc-99m HSA 80
-------------------------------------------------- -
131 I-HSA 6
-------------------------------------------------- -
Cr-51 erythrocytes 6
-------------------------------------------------- --------------------------------------
survival and localization destruction Cr-51 in erythrocytes, platelets 6
Blood elements ------------------------------------------------ ----
In-111 platelet 10
-------------------------------------------------- --------------------------------------
ferokinetika Fe 59 Fe (III) citrate 3
---------------------------------------------------------------------------------------------------------
Spleen planar scintigraphy of Tc-99m altered erythrocytes 100
-------------------------------------------------- --------------------
SPECT Tc-99m altered erythrocytes 200
---------------------------------------------------------------------------------------------------------
Hepatobiliary scintigraphy planar Tc-99m colloids 150
system ----------------------------------- -----------------------------------
SPECT Tc-99m colloids 300
-------------------------------------------------- --------------------
Dynamic Tc-99m IDA derivatives 250
---------------------------------------------------------------------------------------------------------
Gastrointestinal scintigraphy of the salivary glands Tc-99m TcO4 100
nal tract -------------------------------- -------------------------------------------------- ------
esophageal Tc-99m colloids 70
-------------------------------------------------- --------------------------------------
gastroesophageal reflux Tc-99m colloids 50
-------------------------------------------------- --------------------------------------
gastric emptying Tc-99m colloids 60
-------------------------------------------------- --------------------------------------
scintigraphy div. Meckel's Tc-99m TcO4 500
-------------------------------------------------- --------------------------------------
gastrointestinal bleeding scintigraphy of Tc-99m RBC 700
-------------------------------------------------- --------------------------------------
determination of blood loss Cr-51 erythrocytes 4
and proteins in the GI tract ---------------------------------------------- ------
I-125 HSA 6
-------------------------------------------------- -
131 I-HSA 6
-------------------------------------------------- --------------------------------------
Schilling test Co-57 monocyanocobalamin 1
-------------------------------------------------- -
Co-58 monocyanocobalamin 1
---------------------------------------------------------------------------------------------------------
Kidneys renography simple I-131 hippurate 1
-------------------------------------------------- --------------------------------------
planar scintigraphy of Tc-99m DMSA (III) gluconate 150
-------------------------------------------------- --------------------
SPECT Tc-99m DMSA (III) gluconate 250

-------------------------------------------------- --------------------
Dynamic Tc-99m-DTPA, MAG3, EC 250
-------------------------------------------------- --------------------
rated Tc-99m-DTPA, MAG3, EC 500
perfusion
-------------------------------------------------- --------------------------------------
determination Epple, GFR Tc-99m MAG3, DTPA 20
-------------------------------------------------- -
I-131 hippurate 0.5
-------------------------------------------------- -
51 Cr-EDTA 3
---------------------------------------------------------------------------------------------------------
Bladder direct radionuclide Tc-99m DTPA, TcO4 50
cystography ------------------------------------------------- ---------------------
indirect Tc-99m MAG3 200
---------------------------------------------------------------------------------------------------------
Testicles, scrotum scintigraphy of Tc-99m TcO4 600
---------------------------------------------------------------------------------------------------------
Tumors scintigraphy of Tc-99m MIBI, depreotid 800
(Planar, SPECT) antibodies
-------------------------------------------------- -
In-111 antibody 190
pentetreotide
-------------------------------------------------- -
Ga-67 citrate 300
-------------------------------------------------- -
Tl-201 chloride 100
-------------------------------------------------- -
I-123 MIBG 400
-------------------------------------------------- -
F-18 FDG 750
-------------------------------------------------- --------------------------------------
scintimammography Tc-99m MIBI, tetrofosmin, 800
(Planar, SPECT) phosphonates
---------------------------------------------------------------------------------------------------------
Inflammation scintigraphy of Tc-99m leukocytes, HIG 600
(Planar, SPECT) --------------------------------------------- -------
Tc-99m antibody 800
-------------------------------------------------- -
In-111 leukocytes 30
-------------------------------------------------- -
Ga-67 citrate 150
---------------------------------------------------------------------------------------------------------

*) Just before the therapy I-131 **
) activity in the nebulizer; it is believed that less than one tenth
is deposited in the lungs
***) For one application
****) Activity for one application of the two-day protocol
*****) activity summary for day protocol

31) EN 60601-2-44 Medical electrical equipment - Part 2-44:
Particular requirements for the safety of X-ray equipment for computer tomography
.

172nd Annex no. 10 reads:

"Annex no. 10 of Decree no. 307/2002 Coll.

Portfolios to reduce exposure to natural radionuclides

Table. 1

Construction materials and limit values ​​of mass activity at the crossing
is not a building material put into circulation
------------------------------ -------------------------------------------------- ------------
Construction material Mass activity of Ra-226
[Bq / kg]

use for construction use solely
residential or other buildings
sojourn than residential rooms or rooms

sojourn --------------------------------- -------------------------------------------------- ---------
bricks and other building products from clay 150,500

Building products of concrete, plaster, cement and lime


Building products aerated and škvárobetonu

----------------------------------------------- ---------------------------------------------
Building stone 300 1000

Building products made of natural and artificial
stone, artificial stone

Ceramic Tile

Sand, gravel, stones and clay

Fly ash, bottom ash, slag, gypsum arising
in industrial processes, tailings and sludge
for building, construction products nec them


Materials from waste heaps, dumps and tailings
for construction purposes in addition to radiation activities

Cement, lime, gypsum
--------------------------------------- -------------------------------------------------- ---

Table. 2

Guiding values ​​of natural radionuclide content in building materials
------------------------------------ --------------------------------------------
Construction material Index I
mass activity -------------------------------------------- ------------------------------------
Building materials intended for the construction of walls, ceilings 0.5
and floors in buildings with residential or sojourn
rooms especially walling units, prefabricated
products, blocks, bricks, concrete, drywall
--------------- -------------------------------------------------- ---------------
Other construction materials intended for use in 1
buildings with residential or sojourn rooms
------------ -------------------------------------------------- ------------------
Building materials intended for use other than 2
in buildings with residential or sojourn rooms,
all construction materials specifically designated || | for use as raw material for the production of building materials

----------------------------------- ---------------------------------------------

Table. 3

The range of analyzes of natural radionuclide content in building materials
------------------------------------ --------------------------------------------
Construction material Range ---------------------------------------------- analysis
----------------------------------
construction materials intended for construction of walls, ceilings, once a year || | and floors in buildings with residential or sojourn
rooms (especially walling units, prefabricated
products, blocks, bricks, concrete, plasterboard)
--------------- -------------------------------------------------- ---------------
Other construction materials intended to be used once every two years
in buildings with residential or sojourn rooms
--------- -------------------------------------------------- ---------------------
Building materials intended for use other than once every five years
in buildings with residential or sojourn rooms
- -------------------------------------------------- ----------------------------

Table no. 4

Guiding values ​​of volume activities in the water supply
------------------------------------- -------------------------------------------
indicator radionuclide content Indicative value volume activity

bottled drinking water, bottled
baby for public natural
water supply, mineral
bottled spring water
water and bottled
Drinking water
--------------------------------------------- -----------------------------------
radon concentration of 20 222 Bq / l of 50 Bq / l 100 Bq / l -------------------------------------------
-------------------------------------
total volume alpha activity of 0.1 Bq / l 0.2 Bq / l 0.5 Bq / l
----------------------------------- ---------------------------------------------
volume activity tritium 100 Bq / l
------------------------------------------ --------------------------------------
TID *) 0.1 mSv / year
--------------------------------------------- -----------------------------------
total volume beta activity of 0.1 Bq / l 0, 5 Bq / l and 1.0 Bq / l
after deducting the contribution 40K
----------------------------- -------------------------------------------------- -

*), The TID is an annual committed effective dose of
intake of radionuclides present in the water, except for tritium
potassium-40, radon 222 and its decay products;
value of TID is considered overrun, if
total volume alpha activity, while the total volume
beta activity not exceed the scales.

Table no. 5


Limits activity concentrations above which are not water supply


In the table below the limit values ​​do not reflect the chemical toxicity of uranium
which is assessed separately.
----------------------------------------------- -------------------
Radionuclide limits of volume activity [Bq / l]

bottled drinking water, bottled natural
baby public mineral water *)
* Water) supply
bottled spring
water, bottled
drinking water *) -------------------------------------------
-----------------------
Pb-210 0.2 0.7 1.4 ---------
--------------------------------------------------
------- After-210 0.1 0.4 0.8 -------------------------
-----------------------------------------
Rn-222 100 300 600
----------------------------------------------- -------------------
Ra-224 0.7 6 12
Ra-226 0.4 1.5 3
Ra-228 0 1 0.5 1
----------------------------------------- -------------------------
Th-228 0.5 6 12
Th-230 0.4 3 6
Th-232 0.4 3 6
--------------------------------------- ---------------------------
U-234 5 12 24
U-238 5 12 24
- -------------------------------------------------- --------------

*) Decree no. 275/2004 Coll., On requirements for quality and safety of bottled water
and the method of treatment.

Table. 6

The range of analyzes of the content of natural radionuclides in the water supply
------------------------------------ ------------------------------------
Kind of water delivered Drinking Bottled water Bottled water
Public children other than
Water supply baby
-------------------------------------------- ----------------------------
the analysis of volume activity of Rn-222, if it is a water
from underground sources

total volume activity alpha *)

Total volume beta activity **)
---------------------------------------- --------------------------------
Additional analysis analysis representation of the natural
radionuclides in water in which it was found
exceeding the guideline values, the following
procedure

uranium content, if the total volume activity
Alpha exceeds the reference value

volume activity of Ra-226, if the total
mass alpha activity after deducting the contribution
Uranium exceeds the reference value

volume activity of Ra-228, if the volume
activity of Ra-226 exceeds the reference value
total alpha activity

the identification of additional table no. 5 above
alpha-emitting radionuclides, if
total volume activity alpha after deducting
Post Ra-226 and uranium exceeds the target
value

potassium content, if the total volume
beta activity exceeds the reference value

the identification of additional table no. 5 above
beta-emitting radionuclides, if
Total volume beta activity after deducting
Post K-40 exceeds the reference value
---------------------------------------- --------------------------------
monitoring frequency once a year, once a year, once a year
- -------------------------------------------------- --------------------- *
) CSN 75 7611 water quality. Determination of radionuclides. overall
mass alpha activity. **
) CSN 75 7612 Water quality. Determination of radionuclides. overall
volume beta activity. "

173rd Annexes no. 14 and no. 15 are added:

" Annex no. 14 of Decree no. 307/2002 Coll.
High-level emitters


Table. 1

Activity levels defining high-level emitters. For radionuclides
not listed in the table but are presented in Table. 1 Annex
no. 1 of this Decree, the relevant activity level define high-level emitter
one hundredth of the A1 value given in Table 1 of Annex
no. 3 Decree no. 317/2002 Coll.
----------------------------------------------- ----------------------
element (atomic number) Radionuclide activity level defining
high-level emitter [Bq]
------------------------------------------ ---------------------------
Iron (26) of Fe-55 4 x 1011

----------------------------------------------- ----------------------
Cobalt (27) Co-60 4 x 109
------------ -------------------------------------------------- -------
Selenium (34) Se-75 3 x 1010 ---------------------------
------------------------------------------
Krypton (36) Kr -85 x 1
1011 ------------------------------------------ ---------------------------
Strontium (38) Sr-90a) at 3 x 109 ------
-------------------------------------------------- -------------
palladium (46) Pd-103a) 4 x 1011
-------------------- ------------------------------------------------- | || Iodine (53) I-125 2 x 1011
----------------------------------- ----------------------------------
Cesium (55) C-137a), 2 x 1010 || | ------------------------------------------------- --------------------
Prometheum (61) Pm-147 4 x 1011 --------------
-------------------------------------------------- -----
Gadolinium (64), Gd-153 1 x 1011
----------------------------- ----------------------------------------
Thulium (69) Tm-170 3 x 1010 --------------------------------------------
-------------------------
Iridium (77) Ir-192 1 --------- x 1010
-------------------------------------------------- ----------
Thallium (81) Tl-204 1 x 1011
------------------------ ---------------------------------------------
Radium ( 88) R-226b), 2 x 109
-------------------------------------- -------------------------------
Plutonium (94) Pu-238a) 1 x 1011
- -------------------------------------------------- -----------------
Americium (95) Am-241b) 1 x 1011 ----------------
-------------------------------------------------- ---
Californium (98) Cf-252 5 x 108
------------------------------- --------------------------------------

A) the activity level includes contributions from daughter radionuclides
half-life of less than 10 days.
B) Includes neutron sources with beryllium.

Annex no. 15 of Decree no. 307/2002 Coll.

Conditions for proper and qualified execution services important for radiation protection


General requirements:

The methodology and protocols are used names of variables and their units
according to current standards, as well as the terms used in the statistical evaluation
results.

Particulars of the sample methodologies

First identification of the person applying for a permit to conduct business (u
individuals name, surname and place of residence or place of business, at
legal entity name or business name and domicile)

Second identification of the person who developed a methodology (for individuals
name, surname and place of residence or place of business, for legal entities
name or business name and domicile)

Third type of measurement, for which the methodology developed

Fourth references, standards and recommendations

Fifth for each type of measurement shall be:

05.01 characteristic measured quantity

05.02 Apparatus

05.03 measurement procedure and the method of obtaining the results (description of the measurement diagram
measurements in situ, the quantities, units)

05.04 calculation algorithm, interpretation

05.05 measured value and measurement accuracy

06.05 evaluation of the results, compared with the indicative, respectively. limits

Particulars sample measurement protocol

First Protocol number

Second identification of the holder of the authorization to conduct business (for natural persons
name, surname and place of residence or place of business, for legal entities
name or business name and its headquarters), including the authorization number and the period of validity
|| |
Third the nature and object of measurement, specification methodology used in measuring

Fourth identification of the individuals who carried out measurements (name, surname and
permanent residence or place of business)

Fifth the measurement date

6th identification of the customer's measurements (for a natural person: name, surname and
permanent residence or place of business, for legal entities
name or business name and domicile)

7th specification of the place and conditions of measurement

8th sample description, time and place of collection

9th detailed identification of the sample

10th Used Equipment & Instruments (date of the last verification, respectively.
calibration)

11th of each measurement:

11.1. quantity name

2.11 Conditions during measurement

3.11 recording the results of measurements (number of measurements used
quantities and units)

11.4. measurement result, accuracy


12th summary of the results of individual parts measurement, overrun
indicative respectively. limit values ​​(yes / no)

13th date protocol processing

14th signature of the person with relevant authorization of special professional competence
a statutory body of the licensee. "Article II





Transitional Provisions first documentation at workplaces with ionizing radiation
processed under the existing legislation is brought into conformity with this decree
no later than 31 December 2006.

second provisions of § 33 para. 8 and 9, second sentence, as amended effective date of || | entry into force of this regulation shall not apply to high-reflectors
manufactured before the effective date of this decree. Article III





effectiveness this Decree shall take effect on 1 January 2006.

Chair:

Ing. Drábová vr