ORDER OF THE MINISTER OF NATIONAL ECONOMY OF THE REPUBLIC OF KAZAKHSTAN
of February 27, 2015 No. 155
About approval of hygienic standard rates "Sanitary and epidemiologic requirements to ensuring radiation safety"
According to Item 6 of article 144 of the Code of the Republic of Kazakhstan of September 18, 2009 "About health of the people and health care system", PRIKAZYVAYU:
1. Approve the enclosed hygienic standard rates "Sanitary and epidemiologic requirements to ensuring radiation safety".
2. To provide to committee on consumer protection of the Ministry of national economy of the Republic of Kazakhstan in the procedure established by the legislation:
1) state registration of this order in the Ministry of Justice of the Republic of Kazakhstan;
2) within ten calendar days after state registration of this order its direction on official publication in periodic printing editions and in information system of law of Ad_let;
3) placement of this order on official Internet resource of the Ministry of national economy of the Republic of Kazakhstan.
3. To impose control of execution of this order on the supervising vice-minister of national economy of the Republic of Kazakhstan.
4. This order becomes effective after ten calendar days from the date of its first official publication.
Minister of national economy of the Republic of Kazakhstan
E.Dosayev
|
It is approved Minister of health and social development of the Republic of Kazakhstan March 4, 2015 |
________ T. Duysenova |
|
It is approved Minister of Energy of the Republic of Kazakhstan March 10, 2015 |
________ V. Shkolnik |
Approved by the Order of the Minister of national economy of the Republic of Kazakhstan of February 27, 2015 No. 155
Hygienic standard rates "Sanitary and epidemiologic requirements to ensuring radiation safety"
1. General provisions
1. These hygienic standard rates "Sanitary epidemiological requirements to ensuring radiation safety" (further - standard rates) are intended for legal entities and physical persons is not dependent on patterns of ownership, departmental accessory of forms of business, and also for local executive authorities, citizens of the Republic of Kazakhstan, the foreign citizens and persons without citizenship living in the territory of the Republic of Kazakhstan activities of which is connected with the address of sources of ionizing radiation, for ensuring radiation safety.
2. Standard rates are applied to safety of the person in all conditions of impact on it ionizing radiation of artificial or natural origin and are the fundamental document regulating requirements of the Law of the Republic of Kazakhstan "About radiation safety of the population" in the form of the main limits of doses, admissible levels of impact of ionizing radiation and other requirements for restriction of radiation of the person.
3. Physical persons and legal entities, bear responsibility for violation of requirements of ensuring radiation safety, according to the Code of the Republic of Kazakhstan "About administrative offenses" and the Law of the Republic of Kazakhstan "About radiation safety of the population".
4. In these hygienic standard rates the following concepts are used:
1) activity minimum significant (further - MZA) - activity of the opened or closed source of ionizing radiation in case of excess of which the source is subject to accounting and control and which requires the sanitary and epidemiologic conclusion issued according to Item 8 of article 62 of the Code of the Republic of Kazakhstan of September 18, 2009 "About health of the people and health care system" (further - the Code);
2) activity minimum significant specific (further - MZUA) - specific activity of open source of ionizing radiation in case of excess of which the source is subject to accounting and control and which requires the sanitary and epidemiologic conclusion issued according to Item 8 of article 62 of the Code;
3) personnel - the persons working with technogenic sources of ionizing radiation (group A) or being under the terms works in the sphere their impacts (group B).
5. Standard rates extend to the following types of impact of ionizing radiation per capita:
1) in the conditions of normal operation of technogenic sources of radiation;
2) as a result of radiation accident;
3) from natural sources of radiation;
4) in case of medical radiation.
Requirements for ensuring radiation safety are formulated for each type of radiation. The total dose from all types of radiation is used for assessment of radiation situation and the expected medical consequences, and also for reasons for protective measures and assessment of their efficiency.
6. Requirements of standard rates do not extend to the radiation sources creating under any conditions of the treatment of them:
1) individual annual effective dose no more 10th microsievert (further - μSv);
2) individual annual equivalent dose in skin no more than 50 millisieverts (further - mzv) and in crystalline lens no more than 15 mzv;
3) collective effective annual dose no more than 1 cheloveko-sievert (further - persons Stars) or when in case of collective dose more than 1 persons Stars assessment by the principle of optimization shows inexpediency of decrease in collective dose.
Requirements of standard rates do not extend also to space radiation on the Earth's surface and the internal radiation of the person created by natural potassium which it is impracticable to influence.
7. For reasons for expenses on radiation protection in case of realization of the principle of optimization is accepted that radiation in collective effective dose in 1 persons Stars is resulted in the potential damage equal to loss by about 1 persons Stars of year of life of the population. The size of cash equivalent of loss 1 persons Stars of year of life is established in the amount of at least 1 annual per capita national income.
8. The individual and collective lifelong risk of emergence of stochastic effects is determined respectively.
where: r,
R - individual and collective lifelong risk respectively;
Е - individual effective dose;
pi (E) dE, - probability for i-go of individual to receive annual effective dose from E to E+dE;
rE - coefficient of lifelong risk of reducing duration of the period of full-fledged life on average for 15 years on one stochastic effect (from fatal cancer, serious heritable effects and not the fatal cancer given on harm to consequences from fatal cancer), equal:
|
for production radiation: |
rE = 5,6h10-2 1/persons Stars in case of E <200 millisieverts a year (further – mzv / year); rE = 1,1h10-1 1/persons Stars in case of E3 200 mzv / year; |
|
for radiation of the population: |
rE = 7,3h10-2 1/persons Stars in case of E <200 mzv / year; rE = 1,5h10-1 1/persons Stars in case of E і 200 mzv / year. |
9. For the purposes of radiation safety in case of radiation within year the individual risk of reducing duration of the period of full-fledged life as a result of emergence of serious consequences from the determined effects conservatively is accepted by equal:
where: Pi [D> D], - probability for i-go of individual to be irradiated with dose more than D in case of the address with source within year;
Д - threshold dose for the determined effect.
10. For the most complete assessment of harm which can be caused to health as a result of radiation in small doses the concept of the radiation damage which is quantitatively considering as the effects of radiation of separate bodies and tissues of body differing in radio sensitivity to ionizing radiation and all organism in general is used. According to the commonly accepted linear nonthreshold theory of dependence of risk of stochastic effects of dose, the size of risk is pro rata to dose of radiation and is connected with dose through linear coefficients of radiation risk, according to appendix 1 to these standard rates.
The average size of coefficient of risk used for establishment of limits of doses of personnel and the population is accepted by equal 0,05 of Stars-1.
In the conditions of normal operation of nuclear radiation and electrophysical installations limits of doses of technogenic radiation within year are set proceeding from the following values of individual lifelong radiation risk for personnel 1x10-3 and for the population 5x10-5. Level of negligible risk constitutes 10-6.
In case of reasons for protection against sources of potential radiation within year the following values of the generalized risk (the work of probability of the event leading to radiation, and probability of death connected with radiation) are accepted: personnel of 2,0x10-4, year-1; 1,0x10-5, population year-1.
2. Standard rates to restriction of technogenic radiation in controlled conditions
11. For categories of the irradiated persons (personnel of group "A", "B" and the population) three classes of standard rates are established:
1) the main limits of doses (further - PD);
2) the admissible levels of monofactorial impact (for one radionuclide, way of receipt or one type of external radiation) which are derivative of the main limits of doses: limit of annual receipt (further - PGP), admissible annual average volume activities (further - DOA), annual average specific activities (further - DUA), capacity of equivalent dose (further - MED);
3) reference levels (doses, levels, activities, density of flows. Their values consider the level of radiation safety reached in the organization and provide conditions under which the radiative effects will be lower than admissible.
12. The main limits of doses of radiation do not include dose from natural and medical radiation, and also dose owing to radiation accidents. On these types of radiation special restrictions are set.
13. The effective dose for personnel shall not exceed for the period labor activity (50 years) - 1000 mzv, for the population for the period of life (70 years) - 70 mzv.
14. The administration of the company transfers the expectant mother to the work which is not connected with radiation sources from the date of receipt of information on the pregnancy fact, for pregnancy and breastfeeding of the child.
15. The annual effective dose of radiation of personnel due to normal operation of technogenic sources of ionizing radiation shall not exceed PD established in appendix 2 to these standard rates.
The annual effective dose is understood as the amount of the effective dose of external radiation received for calendar year, and expected the effective dose of internal radiation caused by receipt in organism of radionuclides for the same year.
16. Values of dose coefficients, limit of annual receipt with air and admissible annual average volume activity in air of separate radionuclides for personnel, intake of radionuclides through respiratory organs and annual average volume activity them in the inhaled air shall not exceed the PGP and DOA numerical values given in appendices 21 and 22 to this to standard rates where limits of doses are taken equal 20 mzv in year for personnel and 1 m3v in year for the population.
In non-standard conditions the MED admissible levels, annual average DOA of personnel and EROA of radon are determined in the settlement way taking into account time of stay of personnel in radiation-hazardous zone. The values of dose coefficients, and also sizes PGP of personnel, PGP of the population, DOA of personnel and DOA of the population given in appendices 21 and 22 (further - Pgppers, Pgpnas, Doapers and Doanas) Pgppers, Pgpnas, Doapers and Doanas for air are calculated for aerosols with logarithmic normal distribution of particles on activity with aerodynamic diameter, median on activity, 1 micrometer and the standard geometrical deviation equal to 2,5.
17. For personnel of group A of PGP and DOA value of affiliated products of disintegration of isotopes of radon (222Rn and 220Rn) - 218Po (RaA), 214Pb (RaB), 214Bi (RaC), 212Pb (ThB), 212Bi (ThC) in terms of equivalent equilibrium activity (for PGP) and equivalent equilibrium volume activity (for DOA) is constituted:
PGP: PRAA 0,10 + PRAB 0,52 + PRAC 0,38 = 3, 0 MBK
0, PTHB + + + + PTHC 0,09 = 0, 68 MBK
DOA: ARAA 0,10 + ARAB 0,52 + ARAC 0,38 = 1200 Bq/m3
0, ATHB + + + + ATHC 0,09 = 270 Bq/m 3,
where:
Pi and Ai - annual receipts and annual average volume activities in zone of breath of the corresponding affiliated products of isotopes of radon.
18. For students and pupils 16 years undergoing professional training with use of sources of radiation are more senior, annual doses shall not exceed the values established for personnel of group B.
19. The planned increased radiation of personnel of group A at liquidation or prevention of accident is allowed only in case of need rescuing of people and (or) prevention of their radiation. The planned increased radiation is allowed for men 30 years only in case of their voluntary written consent are more senior, after informing on possible doses of radiation and risk for health.
20. The planned increased radiation in effective dose to 100 mzv in year and equivalent doses of no more double values given in appendix of 2 these standard rates is allowed in case of coordination with territorial subdivision of department of state body in the sphere of sanitary and epidemiologic wellbeing of the population (not below regional level), radiation in effective dose to 200 mzv in year and quadruple values of equivalent doses it is allowed with the permission of the Chief state health officer of the Republic of Kazakhstan.
21. The increased radiation is not allowed:
1) for the workers who are earlier already irradiated within year as a result of accident or the planned increased radiation with effective dose 200 mzv or with the equivalent dose exceeding four times the corresponding limits of doses;
2) for persons having medical contraindications for work with radiation sources.
22. Persons which underwent to radiation in the effective dose exceeding 100 mzv within year during the further work shall not be exposed to radiation in dose over 20 mzv in year.
Radiation by effective dose over 200 mzv within year is considered as potentially dangerous. Persons which underwent to such radiation are immediately removed from zone of radiation and go for physical examination. The subsequent work with radiation sources is allowed to these persons in individual procedure taking into account their consent according to the decision of competent medical commission.
23. The persons which are not belonging to personnel, attracted to carrying out the emergency, rescue and other operations which are carried out on it is radioactive the polluted territories, are drawn up and allowed to works as personnel of group A.
3. Standard rates to protection against natural radiation under production conditions
24. The effective dose of radiation by natural sources of radiation of all workers, including personnel, shall not exceed 5 mzv in year under production conditions (any professions and productions).
25. The average values of radiation factors within year corresponding in case of monofactorial impact to effective dose 5 mzv in year in case of employment duration of 2000 hours in year (further - h/year), the average speed of breath of 1,2 cubic meter an hour (further - m3/h) and radioactive balance of radionuclides of uranium and thorium ranks in production dust, make:
1) capacity of effective dose of gamma radiation on 2,5 workplace microsievert hour (further - μSv/h);
2) Equivalent equilibrium volume activity (further - EROARN) in breath zone air the 310th becquerel on cubic meter (further - Bq/m 3);
3) EROATN in air of zone of breath of 68 Bq/m3;
Specific activity in production dust of uranium-238, of the row 40/f which is in radioactive balance with members kilobekkeret 4) on kilogram (further - kBq/kg) where f - annual average general dust content of air in zone of breath, milligram on cubic meter (further - mg/m 3);
5) specific activity in production dust of thorium-232, of the row which is in radioactive balance with members, 27/f, kBq/kg.
In case of multiple-factor impact the amount of the attitudes of the influencing factors towards the specified values shall not exceed 1.
26. In case of the choice of sites of the territories under construction of buildings and constructions of production appointment, sites with gamma background not of 0,6 of μSv/h, and radon flow density from the surface of soil 250 millibekkerel on square meter a second are allocated (further - (мБк/m2*s).
27. Impact of space radiations on crews of planes is normalized as natural radiation under production conditions and shall not exceed 5 mzv in year.
4. Standard rates to restriction of technogenic and natural radiation of the population in normal conditions
28. The admissible values of content of radionuclides in foodstuff, drinking water and atmospheric air corresponding to limit of dose of technogenic radiation of the population 1 mzv / year and to quotas from this limit are calculated based on values of dose coefficients in case of intake of radionuclides through digestive organs taking into account their distribution on components of food allowance and drinking water, and also taking into account intake of radionuclides through respiratory organs and external radiation of people. Values of dose coefficients for critical national groups, DOA and PGP through respiratory organs and PGP through digestive organs, are given in appendix 23 to these standard rates.
29. When designing new buildings of residential and public appointment it is provided that annual average EROARN affiliated products of radon and toron in air of rooms EROARN + 4,6 EROATN did not exceed 100 Bq/m 3, and capacity of effective dose of gamma radiation did not exceed capacity of dose on the open area more than on μSv/h 0,2.
30. In the operated buildings annual average EROARN affiliated products of radon and toron in air of premises shall not exceed 200 Bq/m3. In case of higher values of volume activity the protective measures directed to decrease in intake of radon in air of rooms and improvement of ventilation of rooms are held. Protective measures are held also if capacity of effective dose of gamma radiation in rooms exceeds capacity of dose on the open area more than on μSv/h 0,2.
31. In case of the choice of sites of the territories under construction of apartment houses and buildings of social appointment sites with gamma background not exceeding 0,3 mkgr / and density of flow of radon from the surface of soil no more than 80 mbk / are allocated h (sq.m x c);
32. Effective specific activity (Aeff) of natural radionuclides in the construction materials (crushed stone, gravel, sand, rubble and sawn stone, cement and brick raw materials and others) got on their fields or which are industry by-product and also the waste of industrial production used for production of construction materials (ashes, slags), and finished goods shall not exceed:
1) for the materials used in the under construction and reconstructed residential and public buildings (the I class):
where:
And Ra and And Th – specific activities of 226Ra and 232Th which are in radioactive balance with other members of uranium and thorium ranks, AK – specific activity of K-40 (Bq/kg);
2) for the materials used in road construction within the territory of settlements and zones of perspective building. For exterior finish of residential, public and factory buildings, fountains, cultural and other constructions provided that the expected individual annual effective dose of radiation, in case of the planned type of their use shall not exceed 10 μSv, and the annual collective effective dose shall not exceed more than one persons Stars. Use for construction and internal finishing of residential and public buildings, nurseries, the teenage, medical organizations (the II class) is not allowed:
Aeff
740bk/kg;
3) for the materials used in road construction out of settlements (III class):
Aeff 1500bk/kg;
4) in case of 1,5 of kBq/kg <Aeff <the issue of use of materials is resolved by 4,0 of kBq/kg (the IV class) in each case separately in coordination with territorial subdivision of department of state body in the sphere of sanitary and epidemiologic wellbeing.
In case of Aeff> 4,0 of kBq/kg materials is not allowed to be used in construction.
33. The provisional estimate of admissibility of use of water for the drinking purposes on indicators of radiation safety is given on specific total alpha (Aa) and beta activities (Ab). In case of Aa and Ab values below 0,2 and 1, of Bq/kg, respectively, further researches of water are not obligatory. In case of excess of the specified levels the analysis of content of radionuclides in water is carried out. If in case of joint presence in water of several natural and technogenic radionuclides the condition is satisfied:
where Ai - specific activity of i-go of radionuclide in water, Bq/kg;
UVI - appropriate levels of intervention of value of dose coefficients
(mzv/Bq) in case of intake of radionuclides in organism of adults with water and levels of intervention of UV (Bq/kg) on content of separate radionuclides in drinking water according to appendix 24 to these standard rates, actions for decrease in radioactivity of drinking water are not obligatory.
34. Critical path of radiation of people for the account 222Rn, containing in drinking water, is transition of radon to air of the room and the subsequent inhalation receipt of affiliated products of radon to organism. Intervention level for 222Rn in drinking water constitutes 60 Bq/kg. Determination of specific activity 222Rn in drinking water from underground sources in case of the decentralized water supply is obligatory.
In case of possible presence at water 3H, 14C, 131I, 210Pb, 228Ra, 232Th, 232U (in zones of observation of radiation objects I and II of category on potential danger) determination of specific activity of these radionuclides in water is obligatory.
35. Sanitary and epidemiologic examination of foodstuff and restriction of radiation of the population is performed by regulation of content of admissible levels of radionuclides of caesium-137 and strontium-90 according to appendix 25 to these standard rates.36. Content of radionuclides in tea (black, green, tiled) shall not exceed on caesium 137 - 400 Bq/kg, to strontium of 90 - 200 Bq/kg.
37. Content of radionuclides in coffee (in grains, ground, soluble) shall not exceed on caesium 137 - 300 Bq/kg, to strontium of 90 - 100 Bq/kg.
38. Content of radionuclides in dietary supplements on vegetable basis, including flower pollen (dry teas), liquid (elixirs, balms, tinctures) shall not exceed on caesium 137 - 200 Bq/kg, to strontium of 90 - 100 Bq/kg".
39. Content of radionuclides in herbs (herbs, bark, rhizome, fruits) does not exceed on caesium 137 - 400 Bq/kg, to strontium of 90 - 200 Bq/kg.
40. Foodstuff, ready to the use, from fruit, vegetables, berries (tinned vegetables, mushrooms, jam, jams, syrups, concentrates, drinks, juice) pass researches on radiation safety.
41. Content of radionuclides in tobacco and tobacco products shall not exceed on caesium 137 - 120 Bq/kg, to strontium of 90 - 50 Bq/kg.
42. Assessment of radioactivity of solid fuel includes (coal):
1) indicators of capacity of dose of gamma radiation and determination of uniformity of the site. Sites of the field (layer) are considered uniform in case of difference of values of capacity of equivalent dose scale of radiation no more than 30% on all surface;
2) specific activity of natural radionuclides of coal and ashes.
The provisional estimate of radioactivity of solid fuel is made at stage of exploration or superficial shooting of the territory for open pit or layer in well face.
Individual annual effective dose shall not exceed 10 μSv, and collective effective annual dose - no more than 1 persons Stars.
Establishment of system of restrictions and type of safe use of fuel is made based on the analysis of specific activity of natural radionuclides. The amount of the attitudes of specific activity of radionuclides of uranium (radium) and thorium towards minimum significant specific activities (Sugol), is determined by formula:
where,
AU (Ra), ATH – specific activity of U (226Ra), 232Th, respectively, a Bq/kg who are in radioactive balance with other members of uranium and thorium ranks.
1000 – MZUA of natural uranium and thorium, Bq/kg.
Depending on value About coal the class of radiation hazard of coal is established.
43. On object of subsurface use on production of solid fuel in case of withdrawal of the parcel of land and in case of operation of solid fuel the population issues the sanitary and epidemiologic conclusion according to Item 8 of article 62 of the Code.
44. Establishment of class of radiation hazard of ashes and type of its safe use as construction material is performed on indicator of specific effective activity.
Assessment and forecasting of specific effective activity of the ashes which are formed in case of combustion of fuel can be carried out by results of radiation testing of coal and is determined by formula:
And coal eff.progn = And coal eff. x To to +
coal,
where,
And coal eff - specific effective activity of natural radionuclides in coal test;
coal - absolute error of determination And coal eff.
To - the coefficient of concentration of radionuclides in ashes, is determined by formula:
where,
Ad - ash-content of coal, %.
Depending on value of specific activity the class of radiation hazard and type of use is established.
45. The technology of investigation, production, transportation and conversion of oil and oil-water suspension does not allow possibility of pollution by natural radionuclides of processing equipment and objects of the environment higher than the levels provided by these standard rates.
In case of content in oil of natural radionuclides in number of no more than 10 intervention levels (IL) for water (application 24) it is used without restriction. In case of content of radionuclides more than 10 levels of intervention for water oil is allowed to conversion only after its cleaning up to the specified size (10 UV).
46. Content of natural radionuclides in the reservoir waters pumped in the oil-and-gas horizon in the course of production of oil products is not normalized. When downloading in the water-bearing horizons or dumping on land relief of concentration of ERN into them shall not exceed them 10 UV for water.
47. Specific activity of natural radionuclides in mineral fertilizers and agrochemicals shall not exceed:
AU + 1,5 * ATH 1,0 of kBq/kg,
where AU and ATH - specific activities of uranium-238 (radium-226) and thorium-232 (thorium-228), the uranium and thorium ranks which are in radioactive balance with other members, respectively.
Admissible content 40K in mineral fertilizers and agrochemicals is not established. In case of the treatment of the materials containing 40K the requirements for restriction of radiation of the population at the expense of natural sources of radiation established in Items 26 and 27 are observed.
48. Specific activity of natural radionuclides in phosphoric fertilizers and ameliorants shall not exceed:
AU + 1,5 * ATH 4,0 of kBq/kg,
where AU and ATH - specific activities of uranium-238 (radium-226) and thorium-232 (thorium-228), the uranium and thorium ranks which are in radioactive balance with other members respectively.
49. For ensuring radiation safety of the population and employees of the organizations and planning of types and amount of radiation control in case of the treatment of materials with the increased content of natural radionuclides their following classification is entered:
1) I class: Aeff of 740 Bq/kg
2) II class: 0,74 <Aeff 1,5 of kBq/kg
3) III class: 1,5 <Aeff 4,0 of kBq/kg
4) IV class: Aeff_ 4,0 of kBq/kg
50. The treatment of materials I of class is under production conditions performed without any limit.
During the work with materials II, III, IV of class the sanitary and epidemiologic conclusion, according to Item 8 of article 62 of the Code is issued.
51. The company prior to mining of construction materials, mineral fertilizers, ameliorants and fuel and energy raw materials receives the sanitary and epidemiologic decision about degree of its radiation hazard and conditions of use of materials according to Item 8 of article 62 of the Code.
5. The standard rate on restriction of medical radiation
52. Radiation protection of patients in case of medical radiation is based on need of receipt of useful diagnostic information and/or therapeutic effect of the corresponding medical procedures in case of the smallest levels of radiation (for radiation therapy this requirement belongs to healthy, not intentionally irradiated, to bodies and fabrics). The principles of reasons for purpose of medical procedures and optimization of protection of patients are applied to ensuring radiation protection of patients. When carrying out preventive medical radiological researches and scientific research of almost healthy faces annual effective dose of radiation of these persons shall not exceed 1 mzv.
53. Persons (not personnel of X-ray radiological departments) giving help in support of patients (seriously ill patients, children) in case of accomplishment of X-ray radiological procedures shall not be exposed to radiation in the dose exceeding 5 mzv in year. The same requirements are imposed to radiation safety of the adult persons living together with the patients who completed course of radio nuclide therapy or brachytherapy with implantation of the closed sources and which are written out from clinic. For other adult persons, and also for the children contacting to the patients who are written out from clinic after radio nuclide therapy or brachytherapy, the limit of dose constitutes 1 mzv in year.
54. The patients taking course of radio nuclide therapy or brachytherapy with implantation of the closed sources can be written out from clinic provided that level scale - radiation emitted from body meets requirements of Item 60 of these standard rates. The statement of the patient after therapy by the radionuclides specified in appendix of 5 these standard rates is allowed if the entered or residual activity of radionuclides in body or the measured capacity of dose in air near the patient's body below the corresponding values given in appendix of 5 these standard rates. Before the statement patients should give written and oral instructions concerning precautionary measures which are accepted to protect from radiation of family members to whom they can come into contact. The same requirements are imposed to the mode of out-patient treatment of patients.
55. In case of the death of the patient in whose organism there is pacemaker with radio nuclide power source cremation of body is carried out after removal of source.
56. When planning and holding the procedures connected with radiation by ionizing radiation in the medical organization doses at all persons which are exposed to medical radiation are determined and registered.
6. The standard rate on restriction of radiation of the population in the conditions of radiation accident
57. The predicted radiation levels in case of which protective measures are necessary are held if the expected dose of radiation for the short term (2 days) reaches levels in case of which excess the determined effects (appendix 6 to these standard rates) are possible.
58. In case of chronic radiation during life protective measures are obligatory if the annual absorbed doses exceed the levels of chronic radiation creating risk of the serious determined effects specified in appendix 7 to these standard rates.
59. Intervention levels for temporary settling out of the population constitute: to start temporary settling out - 30 mzv in month, for the end of temporary settling out 10 mzv in month. If it is predicted that the dose which is saved up in one month will be above the specified levels within year, it is necessary to resolve issue of settling out of the population on the permanent residence.
60. When carrying out antiradiation interventions, limits of doses (appendix of 2 these standard rates) are not applied.
61. In case of the accident which entailed radioactive pollution of the extensive territory based on control and the forecast of radiation situation the zone of radiation accident is established. In zone of radiation accident control of radiation situation is carried out and actions for decrease in levels of radiation of the population are performed.
62. Criteria for adoption of urgent decisions in initial stage of radiation accident and decision making about population measures of protection in case of major radiation accident are given in appendix 8 to these standard rates. Criteria for decision making about restriction of consumption of the polluted food in the first year after emergence of accident, and also criteria for decision making about restriction of consumption polluted waters are given in appendices 9 and 10 to these standard rates.
63. At late stages of the radiation accident which entailed pollution of the extensive territories long-living radionuclides, decisions on protective measures are made taking into account the developed radiation situation and specific social and economic conditions (appendix 26 to these standard rates).
7. Values of admissible levels of radiative effects in normal service conditions of sources of ionizing radiation
64. For each category of the irradiated persons value of admissible level of radiative effects for this way of radiation is determined to the annual limit of dose (average in five years), specified in appendix of 2 these standard rates.
65. Values of admissible levels for all ways of radiation are determined for standard conditions which are characterized by the following parameters:
1) in amount of the inhaled air V with which radionuclide arrives in organism for calendar year;
2) time of radiation of t within calendar year;
3) geometry of external radiation by flows of ionizing radiation.
For personnel the following values of standard parameters are established: Vpers = m3 2,4x103 in year; tpers = 1700 h a year; Mpers = 0. For the population the following values of standard parameters are established: tnas = 8800 h a year; Mnas = 730 kg a year for adults. The annual amount of the inhaled air is established depending on age:
66. Numerical values of annual average admissible density of flows of particles in case of external radiation of all body, skin and crystalline lens of eye of persons from personnel monoenergetic electrons, beta particles, monoenergetic photons and monoenergetic neutrons, values of admissible radioactive pollution of surfaces of working rooms and the equipment which is in them, integuments, special clothes, special footwear and other individual protection equipment of personnel, admissible levels of dischargeable radioactive pollution of surface of vehicles are given in appendices 12 - 20 these standard rates.
67. Values of annual average admissible density of flows of particles are this for broad range of radiation energies and two most probable geometriya of radiation: isotropic (2p or 4p) fields of radiation and fall of parallel bunch of radiation on body in front (front-back geometry).
68. For integuments, special clothes and footwear, other individual protection equipment general is normalized (removed and not removed) radioactive pollution. In other cases only dischargeable pollution is normalized.
Levels of general radioactive pollution of integuments are determined taking into account penetration of share of radionuclide into skin and into organism. Calculation is carried out in the assumption that total area of pollution shall not exceed 300 cm2.
Appendix 1
to Hygienic standard rates "Sanitary and epidemiologic requirements to ensuring radiation safety"
Linear coefficients of radiation risk
|
The irradiated national group |
Coefficient of risk of malignant new growths, h10-2 Stars-1 |
Coefficient of risk of heritable effects, h10-2 Stars-1 |
Amount, h10-2 Stars-1 |
|
All population |
5,5 |
0,2 |
5,7 |
|
Adults |
4,1 |
0,1 |
4,2 |
Appendix 2
to Hygienic standard rates "Sanitary and epidemiologic requirements to ensuring radiation safety"
Main limits of doses
|
The normalized sizes 1) |
Limits of doses | |
|
personnel of group A 2) |
Population | |
|
Effective dose |
20 mzv in year on average for any consecutive 5 years, but no more than 50 mzv in year |
1 mzv in year on average for any consecutive 5 years, but no more than 5 mzv in year |
|
Equivalent dose in year in: eye crystalline lens 3) to skin 4) brushes and feet |
20 mzv 500 mzv 500 mzv |
15 mzv 50 mzv 50 mzv |
Note:
1) simultaneous radiation to the specified limits in all normalized sizes is allowed;
2) the main limits of doses, as well as all other admissible levels of radiation of personnel of group B, 1/4 values for personnel of group A are equal. Further all normative values for category "personnel" are given in the text only for group A;
3) treats dose at depth of 300 milligrams on square centimeter (further - mg/cm 2);
4) treats average on the area of 1 square centimeter (further - cm2) to value in basal layer of skin 5 mg/cm2 thick under integumentary layer 5 mg/cm2 thick. On palms thickness of integumentary layer - 40 mg/cm2. The specified limit allows radiation of all skin of the person provided that within average radiation of any 1 cm2 of the area of skin this limit will not be exceeded. The dose limit in case of radiation of face skin provides not excess of limit of dose on crystalline lens from beta particles.
Appendix 3
to Hygienic standard rates "Sanitary and epidemiologic requirements to ensuring radiation safety"
Classes of radiation hazard of coal
|
Class of radiation hazard of coal |
Amount of the relations of specific activity of radionuclides to MZUA, Sugol |
Coal use conditions |
|
I |
<1 - |
No restrictions for use of coal in economic activity are introduced |
|
II |
> 1 |
Use of coal in economic activity is not allowed |
Appendix 4
to Hygienic standard rates "Sanitary and epidemiologic requirements to ensuring radiation safety"
Classes of radiation hazard of ashes
|
Class of radiation hazard of ashes |
Specific effective activity of radionuclides, (And ashes eff. progn And ashes eff) Bq/kg |
Conditions of safe use of ashes |
|
I |
to 370 |
Ashes are used in the under construction and reconstructed residential and public buildings |
|
II |
from 370 to 740 |
Ashes are used in road construction within the territory of settlements and zones of perspective building, and also in case of construction of factory buildings |
|
III |
from 740-1500 |
Ashes are used in road construction out of settlements |
|
IV |
more than 1500 to 4000 |
The issue of use of ashes is resolved in each case separately in coordination with territorial subdivision of department of state body in the sphere of sanitary and epidemiologic wellbeing of the population |
Appendix 5
to Hygienic standard rates "Sanitary and epidemiologic requirements to ensuring radiation safety"
Activity of radionuclides in body of the adult patient (GBq) after radio nuclide therapy or brachytherapy with implantation of the closed sources and capacity of equivalent dose (μSv/h) at distance of 1 m from the surface of body in case of which the statement of the patient from clinic is allowed
|
Radionuclide |
Half-life period, days (further – days) |
Activity in body, GBq |
Capacity of dose, μSv/h |
|
125I1) |
60,1 |
4 |
10 |
|
131I |
8,0 |
0,4 |
20 |
|
153Sm |
2,0 |
9 |
100 |
|
188Re |
0,7 |
12 |
80 |
Note:
1) as a part of implants for prostate gland brachytherapy.
In case of repeated treatment within year activity in body and capacity of dose decrease in the number of times equal to number of courses of treatment in year.
Appendix 6
to Hygienic standard rates "Sanitary and epidemiologic requirements to ensuring radiation safety"
The predicted radiation levels in case of which protective measures are necessary
|
Body or fabric |
The absorbed dose in body or fabric in 2 days, Gr |
|
All body |
1 |
|
Lungs |
6 |
|
Skin |
3 |
|
Thyroid gland |
5 |
|
Eye crystalline lens |
2 |
|
Gonads |
3 |
|
Fruit |
0,1 |
Appendix 7
to Hygienic standard rates "Sanitary and epidemiologic requirements to ensuring radiation safety"
The levels of chronic radiation creating risk of the serious determined effects
|
Body or fabric |
The annual absorbed dose, Gr |
|
Gonads |
0,2 |
|
Eye crystalline lens |
0,1 |
|
Red marrow |
0,4 |
Appendix 8
to Hygienic standard rates "Sanitary and epidemiologic requirements to ensuring radiation safety"
Criteria for adoption of urgent decisions in initial stage of radiation accident
|
Measures of protection |
The prevented dose for the first 10 days, mGy | |||
|
on all body |
thyroid gland, lungs, skin | |||
|
level A |
level B |
level A |
level B | |
|
Shelter |
5 |
50 |
50 |
500 |
|
Iodic prevention: adults children |
- - |
- - |
2501) 2501) |
25001) 10001) |
|
Evacuation |
50 |
500 |
500 |
5000 |
Note:
1) only for thyroid gland.
Appendix 9
to Hygienic standard rates "Sanitary and epidemiologic requirements to ensuring radiation safety"
Criteria for decision making
|
Measures |
The prevented effective dose, mzv | |
|
level A |
level B | |
|
Restriction of consumption of the polluted foodstuff and drinking water |
5 for the first year 1/year in the years ahead |
50 for the first year 10/year in the years ahead |
|
Settling out |
50 for the first year |
500 for the first year |
|
1000 for all the time of settling out | ||
Note:
If the level of the radiation prevented by protective measure does not exceed the level A, measures of protection connected with violation of normal activity of the population, and also economic and social functioning of the territory can not be carried out.
Appendix 10
to Hygienic standard rates "Sanitary and epidemiologic requirements to ensuring radiation safety"
Criteria for decision making about restriction of consumption of the polluted food in the first year after emergence of accident
|
Radionuclides |
Specific activity of radionuclide in foodstuff, kBq/kg | |
|
level A |
level B | |
|
131I, 134Cs, 137Cs |
1 |
10 |
|
90Sr |
0,1 |
1,0 |
|
238Pu, 239Pu, 241Am |
0,01 |
0,1 |
Note:
If the radiation prevented by protective measure exceeds level A, but does not reach level B, the decision on accomplishment of measures of protection is made by the principles of reasons and optimization taking into account specific situation and local conditions.
If the level of the radiation prevented reaches and exceeds level B adequate measures of protection are carried out even if they are connected with violation of normal activity of the population, economic and social functioning of the territory.
Appendix 11
to Hygienic standard rates "Sanitary and epidemiologic requirements to ensuring radiation safety"
Annual amount of the inhaled air for different age groupes of the population
|
Age, years |
to 1 |
1-2 |
2-7 |
7-12 |
12-17 |
Adults (17 years are more senior) |
|
V, one thousand m3 a year |
1,0 |
1,9 |
3,2 |
5,2 |
7,3 |
8,1 |
Appendix 12
to Hygienic standard rates "Sanitary and epidemiologic requirements to ensuring radiation safety"
Values of equivalent dose and annual average admissible density of flow of monoenergetic electrons for persons from personnel in case of radiation of skin
|
Energy of electrons, MEV |
Equivalent dose in skin on single fluence, 10-10 Stars * cm2 |
Annual average admissible density of flow Dpppers, cm2 * with-1 | ||
|
IZO1) |
PZ2) |
IZO1) |
PZ02) | |
|
0,07 |
0,3 |
2,2 |
2700 |
370 |
|
0,10 |
5,7 |
16,6 |
140 |
50 |
|
0,20 |
5,6 |
8,3 |
150 |
100 |
|
0,40 |
4,3 |
4,6 |
190 |
180 |
|
0,70 |
3,7 |
3,4 |
220 |
240 |
|
1,00 |
3,5 |
3,1 |
230 |
260 |
|
2,00 |
3,2 |
2,8 |
260 |
290 |
|
4,00 |
3,2 |
2,7 |
260 |
300 |
|
7,00 |
3,2 |
2,7 |
260 |
300 |
|
10,0 |
3,2 |
2,7 |
260 |
300 |
Note:
1) FROM - the isotropic
(2) field of radiation, 2) PZ - radiation by parallel bunch in front-back geometry.
Appendix 13
to Hygienic standard rates "Sanitary and epidemiologic requirements to ensuring radiation safety"
Values of equivalent dose and annual average admissible density of flow of monoenergetic electrons for persons from personnel in case of radiation of crystalline lenses of eyes
|
Energy photons, MEV |
Equivalent dose in skin on single fluence, 10-10 Stars * cm2 |
Annual average admissible density flow Dpppers, cm2 * with-1 | ||
|
IZO1) |
PZ1) |
IZO1) |
PZ1) | |
|
1,0-2 |
6,17 |
7,06 |
1,31+04 |
1,16+04 |
|
2,0-2 |
1,66 |
1,76 |
4,96+04 |
4,63+04 |
|
3,0-2 |
0,822 |
0,880 |
1,00+05 |
9,25+04 |
|
5,0-2 |
0,462 |
0,494 |
1,81+05 |
1,63+05 |
|
1,0-1 |
0,549 |
0,575 |
1,50+05 |
1,42+0,5 |
|
1,5-1 |
0,827 |
0,851 |
9,74+04 |
9,74+04 |
|
3,0-1 |
1,79 |
1,81 |
4,53+04 |
4,53+04 |
|
4,0-1 |
2,38 |
2,38 |
3,38+04 |
3,38+04 |
|
5,0-1 |
2,93 |
2,93 |
2,80+04 |
2,80+04 |
|
6,0-1 |
3,44 |
3,44 |
2,40+04 |
2,40+04 |
|
8,0-1 |
4,39 |
4,39 |
1,88+04 |
1,88+04 |
|
1,0 |
5,23 |
5,23 |
1,55+04 |
1,55+04 |
|
2,0 |
8,61 |
8,61 |
9,57+03 |
9,57+03 |
|
4,0 |
13,6 |
13,6 |
6,08+03 |
6,08+03 |
|
6,0 |
17,9 |
17,9 |
4,57+03 |
4,57+03 |
|
8,0 |
22,3 |
22,3 |
3,66+03 |
3,66+03 |
|
10,0 |
26,4 |
26,4 |
3,13+03 |
3,13+03 |
Note:
1) FROM - isotropic (2) the field of radiation, PZ - radiation by parallel bunch in front-back geometry.
Fluence of particles F - dN/d relation
,
where dN - quantity of the particles falling on the sphere with the cross-sectional area of d F =dN/d, sq.m
Density of flow of particles of n - the relation of dN / (d dt), where dN - quantity of the particles falling on the sphere with d cross-sectional area for dt time interval:
n=dN / (d dt), sq.m with-1
Appendix 14
to Hygienic standard rates "Sanitary and epidemiologic requirements to ensuring radiation safety"
Values of equivalent dose and annual average admissible density of flow of beta particles for persons from personnel in case of contact radiation of skin
|
Average energy beta range, MEV |
Equivalent dose in skin on single fluence, 10-10 Stars * cm2 |
The annual average admissible density of flow Dpppers, cm2 * with-1 |
|
0,05 |
1,0 |
820 |
|
0,07 |
1,8 |
450 |
|
0,10 |
2,6 |
310 |
|
0,15 |
3,4 |
240 |
|
0,20 |
3,8 |
215 |
|
0,30 |
4,3 |
190 |
|
0,40 |
4,5 |
180 |
|
0,50 |
4,6 |
180 |
|
0,70 |
4,8 |
170 |
|
1,00 |
5,0 |
165 |
|
1,50 |
5,2 |
160 |
|
2,00 |
5,3 |
155 |
Appendix 15
to Hygienic standard rates "Sanitary and epidemiologic requirements to ensuring radiation safety"
Values of effective dose and annual average admissible density of flow of monoenergetic photons for persons from personnel in case of external radiation of all body
|
Energy of photons, MEV |
Effective dose on single fluence, 10-12 Stars * cm2 |
The annual average admissible density of flow, Dpppers, cm2 * with-1
|
Kerma in air on single fluence, 10-12 Gr cm2 | ||
|
IZO1) |
PZ2) |
IZO1) |
PZ2) | ||
|
1,0-2 |
0,0201 |
0,0485 |
1,63+05 |
6,77+04 |
7,43 |
|
1,5-2 |
0,0384 |
0,125 |
8,73+04 |
2,62+04 |
3,12 |
|
2,0-2 |
0,0608 |
0,205 |
5,41+04 |
1,62+04 |
1,68 |
|
3,0-2 |
0,103 |
0,300 |
3,24+04 |
1,08+04 |
0,721 |
|
4,0-2 |
0,140 |
0,338 |
2,31+04 |
9,65+03 |
0,429 |
|
5,0-2 |
0,165 |
0,357 |
1,99+04 |
9,12+03 |
0,323 |
|
6,0-2 |
0,186 |
0,378 |
1,77+04 |
8,63+03 |
0,289 |
|
8,0-2 |
0,230 |
0,440 |
1,42+04 |
7,44+03 |
0,307 |
|
1,0-1 |
0,278 |
0,517 |
1,18+04 |
6,33+03 |
0,371 |
|
1,5-1 |
0,419 |
0,752 |
7,79+03 |
4,33+03 |
0,599 |
|
2,0-1 |
0,581 |
1,00 |
5,61+03 |
3,28+03 |
0,856 |
|
3,0-1 |
0,916 |
1,51 |
3,54+03 |
2,17+03 |
1,38 |
|
4,0-1 |
1,26 |
2,00 |
2,59+03 |
1,63+03 |
1,89 |
|
5,0-1 |
1,61 |
2,47 |
2,02+03 |
1,32+03 |
2,38 |
|
6,0-1 |
1,94 |
2,91 |
1,69+03 |
1,12+03 |
2,84 |
|
8,0-1 |
2,59 |
3,73 |
1,26+03 |
8,73+02 |
3,69 |
|
1,0 |
3,21 |
4,48 |
1,01+03 |
7,33+02 |
4,47 |
|
2,0 |
5,84 |
7,49 |
5,63+02 |
4,38+02 |
7,55 |
|
4,0 |
9,97 |
12,0 |
3,28+02 |
2,73+02 |
12,1 |
|
6,0 |
13,6 |
16,0 |
2,38+02 |
2,05+02 |
16,1 |
|
8,0 |
17,3 |
19,9 |
1,89+02 |
1,64+02 |
20,1 |
|
10,0 |
20,8 |
23,8 |
1,56+02 |
1,38+02 |
24,0 |
Note:
1)IZO - the isotropic (4) field of radiation, 2) PZ - radiation by parallel bunch in front-back geometry.
Kerma - the relation of the amount of initial kinetic energies of dEk of all loaded ionizing particles formed under the influence of indirectly ionizing radiation in elementary amount of substance to the mass of DM substance in this amount:
Kerma unit - heat (Gr).
Kerma and the absorbed dose are equal each other in that degree with what balance of charged particles is reached and with what it is possible to neglect the brake radiation and weakening of flow of photons on the way of run of secondary electrons.
Appendix 16
to Hygienic standard rates "Sanitary and epidemiologic requirements to ensuring radiation safety"
Values of equivalent dose and annual average admissible density of flow of monoenergetic photons for persons from personnel in case of radiation of skin
|
Energy photons, MEV |
Equivalent dose in skin on single fluence, 10-12 Stars cm2 |
Annual average admissible density flow Dpppers, cm2 with-1 | ||
|
IZO1) |
PZ1) |
IZO1) |
PZ1) | |
|
1,0-2 |
6,17 |
7,06 |
1,31+04 |
1,16+04 |
|
2,0-2 |
1,66 |
1,76 |
4,96+04 |
4,63+04 |
|
3,0-2 |
0,822 |
0,880 |
1,00+05 |
9,25+04 |
|
5,0-2 |
0,462 |
0,494 |
1,81+05 |
1,63+05 |
|
1,0-1 |
0,549 |
0,575 |
1,50+05 |
1,42+0,5 |
|
1,5-1 |
0,827 |
0,851 |
9,74+04 |
9,74+04 |
|
3,0-1 |
1,79 |
1,81 |
4,53+04 |
4,53+04 |
|
4,0-1 |
2,38 |
2,38 |
3,38+04 |
3,38+04 |
|
5,0-1 |
2,93 |
2,93 |
2,80+04 |
2,80+04 |
|
6,0-1 |
3,44 |
3,44 |
2,40+04 |
2,40+04 |
|
8,0-1 |
4,39 |
4,39 |
1,88+04 |
1,88+04 |
|
1,0 |
5,23 |
5,23 |
1,55+04 |
1,55+04 |
|
2,0 |
8,61 |
8,61 |
9,57+03 |
9,57+03 |
|
4,0 |
13,6 |
13,6 |
6,08+03 |
6,08+03 |
|
6,0 |
17,9 |
17,9 |
4,57+03 |
4,57+03 |
|
8,0 |
22,3 |
22,3 |
3,66+03 |
3,66+03 |
|
10,0 |
26,4 |
26,4 |
3,13+03 |
3,13+03 |
Note:
IZO1) - the isotropic (2) field of radiation, PZ - radiation by parallel bunch in front-back geometry.
Appendix 17
to Hygienic standard rates "Sanitary and epidemiologic requirements to ensuring radiation safety"
Values of equivalent dose and annual average admissible density of flow of monoenergetic photons for persons from personnel in case of radiation of crystalline lenses of eyes
|
Energy of photons, MEV |
Equivalent dose in crystalline lens on single fluence, 10-12 Stars cm2 |
Annual average admissible density of flow Dpppers, cm2 with-1 | ||
|
IZO1) |
PZ1) |
IZO1) |
PZ1) | |
|
1,0-2 |
0,669 |
2,23 |
3,66+04 |
1,08+04 |
|
1,5-2 |
0,749 |
2,06 |
3,29+04 |
1,16+04 |
|
2,0-2 |
0,622 |
1,53 |
3,97+04 |
1,60+04 |
|
3,0-2 |
0,375 |
0,865 |
6,55+04 |
2,85+04 |
|
4,0-2 |
0,275 |
0,571 |
9,07+04 |
4,27+04 |
|
5,0-2 |
0,239 |
0,459 |
1,03+05 |
5,33+04 |
|
6,0-2 |
0,234 |
0,431 |
1,06+05 |
5,67+04 |
|
8,0-2 |
0,264 |
0,476 |
9,05+04 |
5,16+04 |
|
1,0-1 |
0,326 |
0,568 |
7,26+04 |
4,34+04 |
|
1,5-1 |
0,545 |
0,857 |
4,59+04 |
2,88+04 |
|
2,0-1 |
0,762 |
1,16 |
3,31+04 |
2,11+04 |
|
3,0-1 |
1,20 |
1,77 |
2,09+04 |
1,39+04 |
|
4,0-1 |
1,59 |
2,33 |
1,54+04 |
1,06+04 |
|
5,0-1 |
2,00 |
2,86 |
1,24+04 |
8,64+03 |
|
6,0-1 |
2,39 |
3,32 |
1,04+04 |
7,34+03 |
|
8,0-1 |
3,10 |
4,21 |
7,90+03 |
5,87+03 |
|
1,0 |
3,76 |
4,96 |
6,53+03 |
4,91+03 |
|
2,0 |
6,64 |
7,93 |
3,68+03 |
3,09+03 |
|
4,0 |
11,1 |
12,1 |
2,20+03 |
2,00+03 |
|
6,0 |
15,1 |
15,6 |
1,62+03 |
1,57+03 |
|
8,0 |
19,1 |
19,1 |
1,29+03 |
1,29+03 |
|
10,0 |
23,0 |
22,3 |
1,06+03 |
1,10+03 |
Note:
IZO1) - the isotropic (4) field of radiation, PZ - radiation by parallel bunch in front-back geometry.
Appendix 18
to Hygienic standard rates "Sanitary and epidemiologic requirements to ensuring radiation safety"
Values of effective dose and annual average admissible density of flow of monoenergetic neutrons for persons from personnel in case of external radiation of all body
|
Energy of neutrons, MEV |
Effective dose on single fluence, 10-12 Stars cm2 |
Annual average admissible density of flow, Dpppers, cm2 with-1 | ||
|
IZO1) |
PZ1) |
IZO1) |
PZ1) | |
|
thermal neutrons |
3,30 |
7,60 |
9,90+2 |
4,30+2 |
|
1,0-7 |
4,13 |
9,95 |
7,91+2 |
3,28+2 |
|
1,0-6 |
5,63 |
1,38+1 |
5,80+2 |
2,37+2 |
|
1,0-5 |
6,44 |
1,51+1 |
5,07+2 |
2,16+2 |
|
1,0-4 |
6,45 |
1,46+1 |
5,07+2 |
2,24+2 |
|
1,0-3 |
6,04 |
1,42+1 |
5,41+2 |
2,30+2 |
|
1,0-2 |
7,70 |
1,83+1 |
4,24+2 |
1,79+2 |
|
2,0-2 |
1,02+1 |
2,38+1 |
3,20+2 |
1,37+2 |
|
5,0-2 |
1,73+1 |
3,85+1 |
1,89+2 |
8,49+1 |
|
1,0-1 |
2,72+1 |
5,98+1 |
1,20+2 |
5,46+1 |
|
2,0-1 |
4,24+1 |
9,90+1 |
7,71+1 |
3,30+1 |
|
5,0-1 |
7,50+1 |
1,88+2 |
4,36+1 |
1,74+1 |
|
1,0 |
1,16+2 |
2,82+2 |
2,82+1 |
1,16+1 |
|
1,2 |
1,30+2 |
3,10+2 |
2,51+1 |
1,05+1 |
|
2,0 |
1,78+2 |
3,83+2 |
1,84+1 |
8,53 |
|
3,0 |
2,20+2 |
4,32+2 |
1,49+1 |
7,56 |
|
4,0 |
2,50+2 |
4,58+2 |
1,31+1 |
7,13 |
|
5,0 |
2,72+2 |
4,74+2 |
1,20+1 |
6,89 |
|
6,0 |
2,82+2 |
4,83+2 |
1,16+1 |
6,76 |
|
7,0 |
2,90+2 |
4,90+2 |
1,13+1 |
6,67 |
|
8,0 |
2,97+2 |
4,94+2 |
1,10+1 |
6,61 |
|
10 |
3,09+2 |
4,99+2 |
1,06+1 |
6,55 |
|
14 |
3,33+2 |
4,96+2 |
9,81 |
6,59 |
|
20 |
3,43+2 |
4,80+2 |
9,52 |
6,81 |
Note:
IZO1) - the isotropic (4) field of radiation, PZ - radiation by parallel bunch in perednezadny geometry.
Appendix 19
to Hygienic standard rates "Sanitary and epidemiologic requirements to ensuring radiation safety"
Admissible levels of radioactive pollution of surfaces of working rooms and the equipment which is in them, integuments, overalls, special footwear and other individual protection equipment of personnel, it is frequent / (sm2min)
|
Object of pollution |
Alpha-active nuclides 1) |
Beta and active nuclides 1) | |
|
Separate 2) |
others | ||
|
Uninjured skin, special linen, towels, internal surface of front parts of individual protection equipment |
2 |
2 |
2003) |
|
Main overalls, internal surface of additional resources of individual protection, external surface specialist of footwear |
5 |
20 |
2000 |
|
The surfaces of rooms of permanent stay of personnel and the equipment which is in them |
5 |
20 |
2000 |
|
The surfaces of rooms of periodic stay of personnel and the equipment which is in them |
50 |
200 |
10000 |
|
External surface of the additional resources of individual protection withdrawn in dignity locks |
50 |
200 |
10000 |
Note:
1) for integuments, special clothes and footwear, other individual protection equipment general is normalized (dischargeable and not dischargeable) radioactive pollution. In other cases only dischargeable pollution is normalized;
2) alpha-active nuclides which annual average admissible volume activity in air of working rooms of DOA <0,3 of Bq/m3 belong to separate;
3) for 90Sr + 90Y - 40 it is frequent / (cm2 of mines).
Appendix 20
to Hygienic standard rates "Sanitary and epidemiologic requirements to ensuring radiation safety"
Admissible levels of dischargeable radioactive pollution of surface of the vehicles used for transportation of radioactive materials and materials it is frequent / (cm2 of mines)
|
Object pollution |
Pollution type | |||
|
Dischargeable (unstable) |
Not dischargeable (fixed) | |||
|
alpha-active radionuclides |
beta and active radionuclides |
alpha-active radionuclides |
beta and active radionuclides | |
|
External surface of the vehicle and security container of container |
It is not allowed |
10 |
It is not regulated |
2001) |
|
Internal surface of security container and external surface of the shipping container |
1,0 |
100 |
It is not regulated |
2000 |
Note:
1) for 90Sr + 90Y - 40 it is frequent / (cm2 of mines).
Appendix 21
to Hygienic standard rates "Sanitary and epidemiologic requirements to ensuring radiation safety"
Values of dose coefficients, limit of annual receipt with air and admissible annual average volume activity in air of separate radionuclides for personnel
|
Radionuclide |
Period half-decay |
Type Connections in case of inhalation [1] |
Dose coefficient of impact Persian , Stars/Bq |
Limit of annual receipt PGPPERS, Bq a year |
Admissible annual average volume activity DOAPERS, Bq/m3 |
|
1 |
2 |
3 |
4 |
5 |
6 |
|
H-3 |
12,3 of years |
G1 |
1,8-11 |
1,1+09 |
4,4+05 |
|
|
|
G2 |
1,8-15 |
1,1+13 |
4,4+09 |
|
|
|
G3 |
1,8-13 |
1,1+11 |
4,4+07 |
|
Be-7 |
53,3 of days |
P |
4,8-11 |
4,2+08 |
1,7+05 |
|
|
|
M |
5,2-11 |
3,8+08 |
1,5+05 |
|
Be-10 |
1,60+06 |
P |
9,1-09 |
2,2+06 |
8,8+02 |
|
|
|
M |
3,2-08 |
6,3+05 |
2,5+02 |
|
S-11 |
0,340 hour |
G1 |
3,2-12 |
6,2+09 |
2,5+06 |
|
|
|
G2 |
2,2-12 |
9,1+09 |
3,6+06 |
|
|
|
G3 |
1,2-12 |
1,7+10 |
6,7+06 |
|
S-14 |
5,73+03 |
G1 |
5,8-10 |
3,4+07 |
1,4+04 |
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The document ceased to be valid since August 16, 2022 according to the Order of the Minister of Health of the Republic of Kazakhstan of August 2, 2022 No. KR DSM-71