Instructions on labor protection during radiation monitoring in areas contaminated with artificial radionuclides

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Instructions on labor protection during radiation monitoring in areas contaminated with artificial radionuclides

Occupational Safety and Health

Occupational Safety and Health / Standard instructions for labor protection

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Abstract

The Instruction describes the fundamental approaches and solutions for conducting radiation monitoring at enterprises and organizations of the Russian fuel and energy complex located in radioactively contaminated areas resulting from various radiation accidents and disasters at the Chernobyl nuclear power plant.

The instruction was developed on the basis of federal normative and technical documents and departmental documents of the Ministry of Fuel and Energy of the Russian Federation and finalized in accordance with the requirements of the "NRB-96 Radiation Safety Standards".

The instruction was approved by the State Committee for Sanitary and Epidemiological Supervision of Russia (ref. No. 01-6/1530-11 dated December 09.12.94, 17) and the Gosatomnadzor of Russia (ref. No. 10-282/30.11.94 dated November XNUMX, XNUMX).

This Instruction is a guiding document of the Ministry of Fuel and Energy of Russia, taking into account the requirements of which specific instructions should be developed for conducting radiation monitoring in industries and at facilities of the Russian fuel and energy complex.

1. General provisions

1.1. Purpose of radiation monitoring

Radiation monitoring (RK) is designed to obtain information about the radiation situation and its changes at the facilities of the fuel and energy complex industries exposed to sources of ionizing radiation (IRS), including radioactively contaminated areas (REM), and in the places of residence of workers.

Radiation control is carried out in order to:

assessment of radiation exposure of radiation sources on people and determination of exposure doses for workers and the public;
solving the issues of ensuring radiation protection;
implementation of measures to reduce radiation exposure to people;
development of measures to reduce possible radioactive contamination of technical products, vehicles, industrial premises, equipment, environment and manufactured products;
establishing appropriate benefits for the imposed restrictions on the mode of work and residence.

1.2. The content of radiation monitoring

Radiation control includes:

determination of the exposure dose rate (EDR) of gamma radiation on the ground, in working and residential premises;
determination of the levels of general radioactive contamination of working surfaces of equipment, buildings, machinery and vehicles, overalls and skin of workers, as well as their places of residence;
determination of the specific activity and radionuclide composition of soil contamination in radioactively contaminated areas (SEM) (in the absence of such data from official bodies or as a verification of their reliability);
determination of the content of radionuclides in food products, drinking water and vegetation, gifts of nature;
determination of the volumetric activity of the air in the working area (if necessary), as well as samples of air masses during the wind transfer of radionuclides to the SEM;
control of individual exposure doses of workers;
control of individual exposure doses of family members of workers living at the REM.

1.3. Persons conducting radiation monitoring

Radiation control is carried out by specialists of the regular or freelance radiation safety service (RSS).

2. Determination of the dose rate of external gamma radiation

2.1. Determining the exposure dose rate of gamma radiation on the ground and at the facilities of enterprises is intended to assess the radiation situation, control its changes and predict the annual dose of external exposure to people.

2.2. The frequency of mandatory monitoring of the dose rate depends on the zone of radioactive contamination of the soil in which the object is located, and is:

for zone 1 - 5 Ci/sq. km for cesium-137 (zone A) - 2 times a year (in winter and summer);
for zone 5 - 15 Ci/sq. km (zone B) - once a month;
for zone 15 - 40 Ci/sq. km (zone B) - weekly.

If objects are located in a zone with higher soil pollution densities (> 40 Ci/sq. km) (zone D), the frequency of control is established by the management of the enterprise in agreement with the local bodies of the State Sanitary and Epidemiological Supervision (GSEN) of the Ministry of Health of Russia.

For individual objects, where places are identified where the exposure dose rate of gamma radiation exceeds the EDR in the surrounding area, control is carried out more often, but at least once a week.

2.3. The exposure dose rate of gamma radiation is measured by devices such as DBG-06T, DRG-01T, RKSB-104, Pripyat, MKS, etc., which have passed metrological certification or state verification and have unexpired verification certificates.

Indicator (qualitative) determination of gamma radiation levels in order to identify contaminated areas, but not to measure the exposure dose rate, can be carried out with SRP-68-01, SRP-88N and the like devices.

2.4. Measurements are carried out at a height of 1 m above the ground (floor) and on the surface of the equipment at least 5 times at each point with the calculation of the average result. Measurement of DER of gamma radiation on the territory of the object is carried out at points on the coordinate grid with the appropriate step depending on the area of the object. The number of measurements should be such as to cover points along the perimeter of the object and its diagonals. In addition, the measurement is carried out in characteristic places of constant and periodic stay of people (in cabins, interiors and bodies of vehicles, in the cabins of earth-moving equipment, at the entrances to the premises, at the controls, etc.). On these objects, measurements are taken at a distance of 5 cm from the surface. Inside each room (vehicle), measurements are carried out at a minimum of 5 points. The measurement results are recorded in the radiation monitoring log with the calculation of the average result and the measurement error.

The method for measuring the dose rate of gamma radiation is described in detail in the Guidelines "Radiation Monitoring and Sampling at Oil and Gas Production Facilities of the Russian Fuel and Energy Complex". M. 1996. 31 p.

3. Determination of levels of general radioactive contamination of working surfaces

3.1. Determining the levels of contamination of surfaces with beta- and alpha-active nuclides is carried out in order to timely detect and prevent the spread of radioactive substances through objects, equipment, protective equipment, overalls, skin and prevent their entry into the body.

3.2. Control over the level of contamination of surfaces is carried out using instruments (direct measurements) or by the method of taking smears.

3.3. Direct measurements are carried out with instruments such as MKS, "Beta", KRB-1, KRA-1, CRAB-2, CRAB-3, etc., which have passed metrological certification or state verification.

3.4. The frequency of control depends on the level of pollution of the territory where the facility is located, and the nature (purpose) of the facility:

If necessary, the frequency of control can be increased according to the recommendations of the SRB and the decision of the management of the enterprise, as well as the bodies of the SSES of the Ministry of Health of Russia.

3.5. Control of surface contamination levels by smearing is carried out in the following cases:

with an increased gamma background that interferes with direct measurements using portable radiometers;
when the shape of the measured surface limits the use of radiometers;
when removable (non-fixed) pollution is not allowed.

3.6. Smears can be dry and wet, as well as acidic or alkaline. A dry smear is taken with a material or filter paper; wet - material moistened with water; acidic material soaked in 1 - 1,5 normal nitric acid solution.

The smear removal rate depends on the nature of the surface being smeared and the type of smear. Average smear removal rates for aluminum, metlakh tiles and glass surfaces are as follows:

3.7. Smears are taken on a 100 x 100 mm stencil from a surface of 100 square meters. see each. If a smear cannot be taken from a surface of 100 sq. cm, then it is taken from a smaller area, but then the pollution level is recalculated for an area of 100 sq. cm.

3.8. After taking a swab, the swab is folded with a contaminated surface inside, placed in an envelope made of tracing paper (polyethylene film) and transferred for measurement on radiometric devices in the laboratory: alpha activity is determined on counting devices with an alpha counter; beta - activity - on counting installations with a beta - counter.

3.9. When measuring smears using a dosimeter radiometer of the MKS 01R-01 type with an appropriate sensor, a shipborne alpha - beta radiometer of the CRAB-2, CRAB-3 types, etc., the measurement results will be less accurate compared to measuring the same activity on a counting unit.

4. Determination of the density of radioactive contamination of soils

4.1. The determination is made in the territories surrounding industrial premises and places of residence, in order to determine (clarify) the social status of the territory in accordance with the Law of the Russian Federation "On Amendments and Additions to the Law of Russia" On the Social Protection of Citizens Exposed to Radiation as a Result of the Chernobyl Nuclear Power Plant Disaster, measures to limit the use of territories and determine benefits for employees and their families living on the REM.

4.2. The determination is carried out before carrying out work related to the movement of soil during the construction and repair of underground utilities, in order to determine the necessary personal protective equipment.

4.3. Periodically, the level of radioactive contamination of soils is determined on the personal farmsteads of workers, on subsidiary plots.

4.4. The content of radionuclides of cesium-137, -134, strontium-90, -89 (if necessary - plutonium-239, -240) or other radionuclides is determined in the soil.

4.5. Sampling, processing and analysis is carried out in specialized laboratories certified by the State Standard in accordance with the Guidelines for the determination of radioactive substances in aerosols, water, soil and food (Government Headquarters, 1991, M .: - 158 p.).

4.6. Determination of the density of radioactive contamination of soils is carried out once a year in the spring and summer.

4.7. Sampling "from the area" is carried out using the "envelope" method, i.e. by taking "point" samples in the corners and in the center of the surveyed area. In this case, an average sample is used for analysis.

"Point" soil samples are taken with standard metal rings with a diameter of 140 mm and a height of 50 - 200 mm or a shovel measuring 150 x 200 mm to a depth of 50 - 200 mm. Before sampling, vegetation is cut within the intended square.

4.8. The average sample ("from the area") is made up of dry "point" samples by the "quartering" method. To do this, "point" samples are combined and thoroughly mixed.

The combined sample is laid out in an even layer 1,5–2 cm thick so that a square is obtained, cut diagonally into 4 triangles, the contents of the two opposite ones are discarded, and the remaining two are combined. "Quarting" is continued until the next portion after combining will not be equal in weight to about 500 - 600 g. The resulting average sample is treated as a "dot".

4.9. The average sample is placed in a double plastic bag, a "Passport" is inserted between the bags, in which the sample number, administrative region, place of sampling, MED, time of sampling, weather conditions are indicated. The sample is then placed in a container that keeps it immobile inside the container during transport.

4.10. All selected samples are measured on a gamma, beta or alpha spectrometer in accordance with the method of analytical control of radionuclides.

4.11. For radiochemical analysis, a sample is chosen that is closest in total gamma activity or content of cesium-137 (or another most dangerous radionuclide) to the average value.

4.12. The results of spectrometric and radiochemical analyzes should be issued with indication of the measurement error and confidence level.

5. Determination of the specific activity of food products, drinking water, vegetation and gifts of nature

5.1. Radiation control of food products and water is carried out by specialized laboratories in order to assess their suitability for food in accordance with Russian and regional control levels according to standardized indicators established by the SSES of the Ministry of Health of Russia in the event of a specific accident.

5.2. The content of normalized radionuclides in products grown by those living on the REM in farmsteads or summer cottages, as well as in forest gifts in the summer-autumn period, is subject to control.

5.3. Control over the specific activity of drinking water in water supply sources is carried out 2 times a year (in autumn and after floods). The use of water for drinking and cooking from unknown sources is prohibited without verification.

5.4. Control over the specific activity of food products of local production is carried out after harvesting.

5.5. If necessary, additional radiation monitoring of food and water can be performed at any time of the year.

5.6. In the case of radiation monitoring of food products and water in a period not exceeding 3 months after the end of the formation of SEM, as well as in the case of information on the possible additional formation of SEM, control of the content of iodine-131 is important.

5.6. Control of exposure doses of employees of enterprises and members of their families living at the REM is carried out in accordance with the instructions for monitoring individual exposure doses.

5.7. The results of all types of radiation monitoring are recorded in the radiation monitoring log (Appendix 1) and stored at the enterprise for 30 years.

5.8. On the basis of this Standard Instruction, instructions for radiation monitoring at the enterprise are developed, which should contain sections 1, 2, 3, 4, 5 and 6 of this Standard Instruction, as well as Section 7, which includes the following issues in accordance with the requirements of the Basic Sanitary Rules OSP-72 / 87":

general provisions for ensuring radiation safety during radiation monitoring;
radiation safety requirements before starting work under SEM conditions;
requirements of the Republic of Belarus during work;
radiation safety requirements at the end of work.

Application. Journal of Radiation Monitoring

Notes

1. Type of sample - air, water, food, soil, soil, biological objects, products, etc.

2. According to column 13, a map must be attached to the journal - a diagram of the places of radiation monitoring and sampling.

In column 13, enter data on GOST or TU for the sample material, a list of scientific and technical documentation for determination methods and the equipment used for measurements, indicating the number and date of the license, who issued it, the number and date of the verification certificate.

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