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The document ceased to be valid since  September 19, 2015 according to Item 1 of the Order of the Government of the Republic of Kazakhstan of September 8, 2015 No. 754

ORDER OF THE GOVERNMENT OF THE REPUBLIC OF KAZAKHSTAN

of February 3, 2012 No. 202

About approval of Health regulations "Sanitary and epidemiologic requirements to ensuring radiation safety"

According to the subitem 2) of article 6 of the Code of the Republic of Kazakhstan of September 18, 2009 "About health of the people and health care system" the Government of the Republic of Kazakhstan DECIDES:

1. Approve the enclosed Health regulations "Sanitary and epidemiologic requirements to ensuring radiation safety".

2. This resolution becomes effective after ten calendar days after the first official publication.

Prime Minister of the Republic of Kazakhstan

K. Masimov

Approved by the Order of the Government of the Republic of Kazakhstan of February 3, 2012 No. 202

Health regulations "Sanitary and epidemiologic requirements to ensuring radiation safety"

(SETORB-2012)

1. General provisions

1. These Health regulations (further - Health regulations) establish sanitary and epidemiologic requirements to ensuring radiation safety when designing, commissioning and content of radiation objects, conclusion from operation of radiation objects, the address with the sources of ionizing radiation (closed and the open radio nuclide sources, radioactive materials, radio isotope devices, devices generating ionizing radiation), the treatment of radioactive waste, use of the materials and products polluted or containing radionuclides, implementation of production radiation supervision on objects including oil and gas complex and scrap metal, use of individual protection equipment and personal hygiene, in case of medical radiation, impact of natural sources of radiation and radiation accidents.

2. In these Health regulations the following concepts are used:

1) activity (further - And) - measure of radioactivity of any amount of the radionuclide which is in this energy condition at present of time:

Формула 1 к ПП РК от 03.02.2012 №202

dN - the expected number of the spontaneous nuclear transformations from this energy condition happening for period - dt. Unit of activity is the Becquerel (further - Bq). The used earlier stand-alone unit of activity of curie (further - Ki) constitutes 3,7x1010 of Bq;

2) activity minimum significant (further - MZA) - activity of the opened or closed source of ionizing radiation in case of excess of which is required the sanitary and epidemiologic conclusion issued by bodies of Gossanepidnadzor. Unit of measure of MZA - becquerel (Bq);

3) activity minimum significant specific (further - MZUA) - specific activity of open source of ionizing radiation indoors in case of which excess the sanitary and epidemiologic conclusion issued by bodies of Gossanepidnadzor is required.;

For the closed radiation sources the decision on need of receipt of permission to the address is determined by comparison of its activity with MZA, without MZUA. Unit of measure of MZUA becquerel on gram of Bq/g;

4) specific (volume) activity - the relation of activity And radionuclide in substance to the mass of m (amount of V) of substance:

Формула 2 к ПП РК от 03.02.2012 №202 

6) radioactive material - the substance in any aggregate state containing radionuclides with activity, conforming to hygienic standard rates "Sanitary and epidemiologic requirements to ensuring radiation safety (further - GN) and these health regulations;

7) intervention - the action directed to decrease in probability of radiation, or dose or adverse effects of radiation;

8) group critical - group of persons from the population (at least ten people), uniform in one or several signs (to sex, age, social or professional conditions, the place of residence, food allowance) which is exposed to the greatest radiative effects from radiation source;

9) deactivation - removal or decrease in radioactive pollution from any surface or from any circle;

10) the dose absorbed (further - D) - the size of energy of ionizing radiation transferred to substance:

Формула 3 к ПП РК от 03.02.2012 №202

de - the average energy transferred by ionizing radiation to the substance which is in elementary amount, a dm - the mass of substance in this amount.

Energy can be average on any certain amount, and in this case the average dose will be equal to the total energy transferred to amount divided into the mass of this amount. In terms of the International System of Units the absorbed dose is measured in the joules divided into kilogram (J/kg), and has the special name - heat (further - Gr). The used earlier stand-alone unit I am glad 0,01 of Gr is equal;

11) dose in body or fabric (further - DT) - the average absorbed dose in certain body or tissue of human body:

Формула 4 к ПП РК от 03.02.2012 №202

mt - the mass of body or fabric, a D - the absorbed dose in element of mass of DM;

12) dose equivalent (further - HT, R) - the absorbed dose in body or fabric increased by the corresponding weighing coefficient for this type of radiation, WR:

Формула 5 к ПП РК от 03.02.2012 №202

D tr - the average absorbed dose in body or fabric T, Wr the weighing coefficient for R radiation.

In case of impact of different types of radiation with various weighing coefficients which are specified in the table 1 of appendix 1 to these health regulations equivalent the dose is determined as the amount of equivalent doses for these types of radiation:

Формула 6 к ПП РК от 03.02.2012 №202

Unit of equivalent dose is the sievert (further - Stars);

13) dose effective (further - E) - the size used as measure of risk of emergence of the remote consequences of radiation of all body of the person and his separate bodies and fabrics, taking into account their radio sensitivity. It represents the amount of works of equivalent dose in bodies and fabrics on the corresponding weighing coefficients which are specified in the table 2 of appendix 1 to these health regulations:

Формула 7 к ПП РК от 03.02.2012 №202

Nt - equivalent dose in body or fabric T, Wt - the weighing coefficient for body or fabric T.

Unit of effective dose - sievert (3v);

Формула 7(1) к ПП РК от 03.02.2012 №202

15) dose effective (equivalent) annual - the amount of the effective (equivalent) dose of external radiation received for calendar year, and expected the effective (equivalent) dose of internal radiation caused by receipt in organism of radionuclides for the same year;

16) dose effective collective - measure of collective risk of emergence of stochastic effects of radiation, it is equal to the amount of individual effective doses. Unit of effective collective dose cheloveko-sievert (further - the people - Stars);

17) the dose prevented - the predicted dose owing to radiation accident which is prevented by protective measures;

18) pollution radioactive - presence of radioactive materials on surface, in material, in air, in body of the person or in other place, in the quantity exceeding the levels established by requirements of GN and these health regulations;

19) pollution of surface not dischargeable (fixed) - radioactive materials which are not transferred in case of contact to other objects and are not removed in case of deactivation;

20) pollution of surface dischargeable (unstable) - radioactive materials which are transferred in case of contact to other objects and are removed in case of deactivation;

21) waste disposal of radioactive - safe placement of radioactive waste without intention of subsequent their extraction;

22) observation zone - the territory outside the sanitary protection zone on which radiation control is carried out;

23) zone of radiation accident - the territory, on which established fact of radiation accident;

24) source of ionizing radiation (further - III or source of radiation) - the radioactive material or the device which is letting out or capable to emit the ionizing radiation conforming to requirements of GN, these health regulations and other regulatory legal acts of the Republic of Kazakhstan;

25) the radiation source closed is source of radiation which device excludes intake of the radionuclides containing in it to the environment in the conditions of application and depreciation which it is expected;

26) radiation source opened - source of radiation when which using intake of the radionuclides containing in it to the environment is possible;

27) radiation source natural - the source of ionizing radiation of natural origin conforming to requirements of GN and these health regulations;

28) the radiation source technogenic is the source of ionizing radiation which is specially created for its useful application or being by-product of these activities;

29) category of object radiation - the characteristic of object on degree of its potential danger for the population in the conditions of possible accident;

30) quota - the part of limit of dose established for restriction of radiation of the population from specific technogenic source of radiation and way of radiation (external, receipt with water, food and air);

31) class of works - the characteristic of works with open sources of ionizing radiation on degree of potential danger for personnel determining requirements for radiation safety depending on radio toxicity and activity of nuclides;

32) control radiation - receipt of information on radiation situation in the organization, in the environment and about levels of radiation of people (includes radiation and radiometric control);

33) workplace - the place of permanent or temporary stay of personnel for accomplishment of production functions in the conditions of impact of ionizing radiation during more than a half of working hours or two hours continuously;

34) capacity of dose - radiation dose for unit of time (second, minute, hour);

35) the population - all persons, including personnel out of work with sources of ionizing radiation;

36) radiation - impact per capita ionizing radiation;

37) radiation emergency - radiation as a result of radiation accident;

38) radiation medical - radiation of patients as a result of physical examination or treatment;

39) radiation the planned raised - the planned radiation of personnel in the doses exceeding the set main limits of doses for the purpose of the prevention of development of radiation accident or restriction of its consequences;

40) radiation potential - radiation which can result from radiation accident;

41) radiation natural - radiation which is caused by natural sources of radiation;

42) radiation production - radiation of workers from all technogenic and natural sources of ionizing radiation in the course of productive activity;

43) radiation professional - radiation of personnel in the course of its work with technogenic sources of ionizing radiation;

44) radiation technogenic - radiation from technogenic sources as in normal, and in an emergency, except for medical radiation of patients;

45) the treatment of radioactive waste - all types of activity connected with collection, transportation, conversion, storage and (or) burial of radioactive waste;

46) the address with sources of ionizing radiation - the activities connected with production, delivery, obtaining, possession, storage, use, transfer, conversion or burial, import, export, transportation, maintenance of sources of ionizing radiation;

47) object radiation - the organization where the address with technogenic III is performed;

48) radioactive waste - the substances which are not intended for further use in any aggregate state in which content of radionuclides exceeds the levels established by requirements of GN and these health regulations;

49) personnel - the persons working with technogenic sources of the radiation (group A) or being under the terms works in the sphere their impacts (group B);

50) dose limit (further - PD) - the size of annual effective or equivalent dose of technogenic radiation which shall not be exceeded in the conditions of normal work. Observance of limit of annual dose prevents emergence of the determined effects, and the probability of stochastic effects remains at the same time at the acceptable level;

51) limit of annual receipt (further - PGP) - the admissible level of intake of this radionuclide in organism within year which in case of monofactorial impact leads to radiation of the conditional person the expected dose equal to the corresponding limit of annual dose;

52) radiation accident - the loss of management of source of ionizing radiation caused by defect of the equipment, the wrong actions of workers (personnel), natural disasters or other reasons which could give or led to radiation of people above of the established regulations or to radioactive environmental pollution;

53) radiation safety of the population - condition of security of these and future generations of people from impact of ionizing radiation, harmful to their health. Ensuring radiation safety - implementation of complex of the organizational, technological, technical, sanitary and epidemiologic and medico-preventive actions directed to decrease in levels of radiation of personnel and the population;

54) radiation and hygienic the passport of the organization - the document characterizing condition of radiation safety in the organization and containing recommendations about its improvement;

55) radiation - hygienic the passport of the territory - the document characterizing condition of radiation safety of the population of the territory and containing recommendations about its improvement;

56) work with III - all types of the address with radiation source on workplace, including radiation control;

57) work with radioactive materials - any kinds of the treatment of radioactive materials on workplace, including radiation control;

58) risk - probability of origin at the person or his posterity of any harmful consequence as a result of radiation;

59) sanitary propusknik - complex of the rooms intended for change of clothes, footwear, sanitary processing of personnel, control of radioactive pollution of integuments, individual protection equipment, special and personal clothes of personnel;

60) sanitary lock - the room between zones of radiation object intended for preliminary deactivation and change of additional resources of individual protection;

61) individual protection equipment - personnel remedy from external radiation, intake of radioactive materials in organism and radioactive pollution of integuments;

62) intervention level (further - UV) - the size of the prevented dose in case of which achievement, in cases of emergence of situations of chronic or emergency radiation, protective or postemergency measures are taken;

63) reference level - the value of controlled size of dose, capacity of dose, radioactive pollution established for operating radiation control, for the purpose of fixing of the reached level of radiation safety, ensuring further decrease in radiation of personnel and the population, radioactive environmental pollution;

64) the device (source) generating ionizing radiation - the electrophysical device (for example, the x-ray device, the accelerator, the generator) in which ionizing radiation arises due to change of speed of charged particles, their annihilation or nuclear reactions;

65) the effects of radiation determined - clinically revealed harmful biological effects caused by ionizing radiation concerning which existence of threshold below which the effect is absent is supposed and above - weight of effect depends on dose;

66) effects of radiation stochastic - the harmful biological effects caused by ionizing radiation, which do not have dose threshold of origin which probability of origin is pro rata to dose and for which weight of manifestation does not depend on dose;

67) natural radionuclides - radioactive elements of ranks of uranium-238 and thorium-232;

68) production waste of objects of oil and gas complex - the salt deposits and slime taken from processing equipment in case of its repair and cleaning, the elements of processing equipment and designs which are not intended for further use on their appointment, the soil and soil in the territory of the companies in which natural radionuclides in the course of productive activity of the companies of oil and gas complex can accumulate;

69) scrap metal (scrap of non-ferrous and ferrous metals) are the production wastes and consumption containing the non-ferrous or ferrous metals formed from the products of industrial and household purpose which became useless or lost consumer properties and suitable only for conversion;

70) scrap metal batch - separately warehoused amount of scrap metal (amount of scrap metal, loaded into one or several transport units - platform, the car, cars, cargo container);

71) local source - the subject having radioactive pollution, creating capacity of equivalent dose (further - MED) gamma radiation at distance of 10 centimeters (further - cm) is higher than microsievert 0,2 in hour (further - μSv/h), or the having MED, exceeding natural radiation background of the area, or density of flow of beta particles exceeding 0,4 of Bq/cm2 and (or) 0,04 of Bq/cm2 of alpha particles having on surface;

72) radioactive pollution of scrap metal - the separate fragment of scrap metal containing or polluted by radionuclides exceeding values established by hygienic standard rates of radiation safety.

3. Sources of radiation are subject to obligatory accounting and control. Are completely exempted from radiation control and accounting:

1) the electrophysical devices generating ionizing radiation with the maximum energy no more than 5 kev;

2) other electrophysical devices generating ionizing radiation in the conditions of which normal operation capacity of equivalent dose in any available point at m 0,1 distance from the surface of the equipment does not exceed μSv/h 1,0;

3) products, goods containing radionuclides on which there is sanitary and epidemiologic conclusion that the doses of radiation created by them do not exceed the values given in GN;

4) the opened and closed sources with activity below MZA given in the operating GN;

5) the radiating radioactive sources closed gamma, capacity of dose from which at distance of 0,1 of m does not exceed μSv/h 1,0;

6) sources of radiation are completely exempted from radiation control and accounting based on the sanitary and epidemiologic conclusion of state body in the sphere of sanitary and epidemiologic wellbeing of the population in the corresponding territory.

4. The work permit with sources of radiation is not required if:

1) products, goods listed in Item 3 of these health regulations are used;

2) on workplace specific activity of radionuclide is less than MZUA, or activity of radionuclide in open source is less than MZA given in GN or the amount of the attitudes of activity of separate radionuclides towards their tabular values less than 1;

3) in the organization general activity of radionuclides in open form does not exceed MZA more than ten times or the amount of the attitudes of activity of several radionuclides towards their tabular values given in GN does not exceed unit;

4) capacity of equivalent dose in any point which is at meter 0,1 distance from surface of the closed radio nuclide source of radiation does not exceed μSv/h 1,0 over background.

2. Sanitary and epidemiologic requirements to ensuring radiation safety

5. Radiation safety of personnel, the population and the surrounding environment is provided in case of respect for the basic principles of radiation safety: reasons, optimization, regulation.

The principle of reasons is applied at stage of decision making by authorized bodies when designing new sources of radiation and radiation objects, issue of licenses, development and approval of rules and hygienic standard rates on radiation safety, and also in case of change of conditions of their operation according to appendix 2 to these health regulations.

In the conditions of radiation accident the principle of reasons belongs not to sources of radiation and conditions of radiation, and to protective measure. As the size of advantage it is necessary to estimate the dose prevented by this action. The actions directed to recovery of control over radiation sources are held without fail.

The principle of optimization provides maintenance at perhaps low and achievable level as individual (below the limits set by GN), and collective doses of radiation, taking into account social and economic factors according to appendix 2 to these health regulations.

In the conditions of radiation accident when instead of limits of doses higher levels of intervention are effective, the principle of optimization is applied to protective measure taking into account the prevented dose of the radiation and damage connected with intervention.

The principle of regulation is provided with all persons on whom the level of radiation of people depends and provides not excess established by the Law of the Republic of Kazakhstan of April 23, 1998 No. 219-I "About radiation safety of the population" and GN of individual limits of doses of radiation of citizens from all III.

For control of the effective and equivalent doses of radiation regulated by GN the admissible levels of monofactorial impact (for one radionuclide depending on way of receipt or one type of external radiation) which are derivative of the main limits of doses are entered: capacities of dose, annual receipt of radionuclides in organism and other indicators.

Derivative standard rates in case of technogenic radiation are calculated for monofactorial impact and each of them exhausts all limit of dose, their use is based on condition not of excess of unit by the amount of the attitudes of all controlled sizes towards their admissible values.

Quotas for the main technogenic sources of radiation are applied to the prevention of use of the dose limit set for the population only on one technogenic source of radiation or on their limited quantity.

Reasons for values of quotas shall contain in projects of radiation objects. Recommendations about establishment of quotas are given in appendix 3 to these health regulations.

6. Assessment of radiation safety on object and in each region is performed on basis:

1) characteristics of radioactive environmental pollution;

2) the analysis of providing actions for radiation safety and accomplishment of regulations, rules and hygienic standard rates in the field of radiation safety;

3) probabilities of radiation accidents and their scale;

4) degrees of readiness for effective liquidation of radiation accidents and their consequences;

5) the analysis of doses of radiation of personnel of group "A" by results of the regulated DOZ forms No. 1, No. 2 DOSES, and also III received by separate national groups from all;

6) numbers of persons which underwent to radiation above the set limits of doses of radiation.

7. Radiation safety on object and around it is provided for the account:

1) qualities of the project of radiation object;

2) the reasonable choice of the area and the platform for placement of radiation object;

3) physical protection of sources of radiation;

4) zonings of the territory around the most dangerous objects and in them;

5) service conditions of technological systems;

6) licensing of all types of activity with radiation sources;

7) sanitary and epidemiologic assessment of activities with radiation sources;

8) availability of system of production radiation supervision;

9) planning and holding actions for ensuring radiation safety of personnel and the population during the normal work of object, its reconstruction and conclusion from operation, and also in case of radiation accidents;

10) advanced trainings and knowledge of rules of work with radiation sources.

8. The operating organization provides:

1) receipt of the sanitary and epidemiologic conclusion on the right of works with sources of radiation and to the products containing radioactive materials or the equipment working at basis of sources of radiation;

2) development of reference levels of radiation factors in the organization and zone of observation for the purpose of fixing of the reached level of radiation safety, and also instructions on radiation safety;

3) approval of the list of persons belonging to personnel of groups A and B;

4) creation of the working conditions with sources of ionizing radiation conforming to requirements of these health regulations, rules for labor protection, safe engineering, industrial safety and other health regulations which action extends to this organization;

5) planning and implementation of actions for providing and enhancement of radiation safety in the organization;

6) systematic control of radiation situation on workplaces, in rooms, in the territory of the organization, in controlled areas, and also behind maximum permissible emissions and maximum permissible dumpings of radioactive materials into the environment;

7) carrying out regular control and accounting of individual doses of radiation of personnel with provision of the summarized information in state body in the sphere of sanitary and epidemiologic wellbeing of the population in the corresponding territory;

8) regular informing personnel on levels of ionizing radiation on their workplaces and about the size of the individual doses of radiation received by them;

9) preparation and certification for questions of ensuring radiation safety of heads and contractors, specialists of services of radiation safety, other faces, constantly or temporarily performing works with radiation sources;

10) briefing and examination of personnel in the field of radiation safety;

11) carrying out preliminary (in case of revenues to work) and periodic medical examinations of personnel;

12) timely informing state bodies, authorized to exercise public administration, the state supervision and control in the field of ensuring radiation safety, about emergence of emergency, about the violations of production schedules creating threat of radiation safety;

13) accomplishment of the conclusions, resolutions and instructions of officials of the state bodies exercising public administration, the state supervision and control in the field of ensuring radiation safety;

14) receipt of special permission (license) for activities in the field of use of atomic energy;

15) accounting of radioactive sources (radioactive materials), radio isotope devices and installations generating ionizing radiation, excluding possibility of their loss or uncontrolled use and storage.

9. The personnel working with sources of the radiation (group A):

1) fulfills the requirements for ensuring radiation safety established by these health regulations;

2) uses individual protection equipment;

3) fulfills the established requirements for the prevention of radiation accident and the rule of conduct in case of its origin;

4) timely has periodic medical examinations;

5) without delay informs the head (shops, the site, laboratory) and service of radiation safety (person responsible for radiation safety) of all found defects in work of the installations, devices and devices which are radiation sources;

6) follows the instructions of service of radiation safety concerning ensuring radiation safety in case of performance of works;

7) upon termination of change leaves the workplaces if other is not provided by business necessity.

10. Radiation safety of personnel is ensured:

1) restrictions of the admission to work with radiation sources on age, sex, the state of health, level of the previous radiation and other indicators;

2) knowledge and observance of rules of work with radiation sources;

3) sufficiency of protective barriers, screens and distances from radiation sources, and also restriction of operating time with radiation sources;

4) creation of the working conditions meeting the requirements of GN and these health regulations;

5) application of individual remedies;

6) respect for reference levels of radiation factors in the organization;

7) organization of radiation control;

8) organization of system of information on radiation situation;

9) holding effective actions for protection of personnel when planning of the increased radiation in case of threat and emergence of accident;

10) organization of accounting and control of sources of ionizing radiation.

11. Radiation safety of the population is ensured:

1) creation of conditions of activity of people, according to requirements of these health regulations;

2) establishment of quotas for radiation from different sources of radiation;

3) organization of radiation control;

4) efficiency of planning and holding actions for radiation protection in normal conditions and in case of radiation accident;

5) organization of system of information on radiation situation.

12. In case of development of actions for decrease in doses of radiation of personnel and the population proceed from the following basic provisions:

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