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Rules On Protection Against Ionising Radiation

Original Language Title: Noteikumi par aizsardzību pret jonizējošo starojumu

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Clarifies 14.11.2003, Latvian journal Nr. 161 (2926) Cabinet of Ministers Regulations No 149 in 2002 Riga, April 9 (pr. No 15, § 11) rules concerning protection against ionizing radiation Issued in accordance with the law "on radiation safety and nuclear safety" the third paragraph of article 3 and the first subparagraph of article 17 of the General questions 1.  The rules define the requirements for protection against ionizing radiation according to radiation safety and nuclear safety, as well as ionizing radiation dose limits for the public.
2. the provisions do not apply to the effects of ionizing radiation on tissues, organs and human body or to the environment (hereinafter referred to as the irradiation), resulting from: 2.1 the potassium isotope 40 k human body;
2.2. the cosmic rays of the Earth's surface level;
2.3. radionuclides Earth's crust.
3. it is prohibited to distribute food products, animal feed, toys, jewelry, jewelry and cosmetic products, adding the radioactive substances or that is irradiated, causing those radionuclides. The following food products, animal feed, toys, jewelry, jewelry and cosmetic products are allowed to use only for scientific research.
4. in order to optimize the radiation safety and nuclear safety, multiple sources in a single operator or owned property in the object or the object's territory (the area controlled by the operator), considered one of the sources.
5. If the person establishes that non-compliance with radiation safety and nuclear safety requirements, or has a reasonable suspicion that they are met partly, she informed the foreman and the radiation safety Centre (hereinafter referred to as the Centre).
 
2. Radiation safety and nuclear safety measures 6. Natural and legal persons involved in activities with ionizing radiation sources or activities of a sealed source in the vicinity, the following radiation safety and nuclear safety requirements: 6.1 precautions when carrying out activities with ionizing radiation sources;
6.2. for more information on the sources of ionising radiation;
6.3. the operator of a controlled area specific radiation safety and nuclear safety measures (safeguards);
6.4. the radiation safety and nuclear safety related information exchange between all users of the information in question;
6.5. the expected exposure of ionizing radiation source, if its probability and size can be calculated in advance or set (the expected exposure). The expected exposure, as well as to the risks for man and the environment to ensure the evaluation operator;
6.6. priority protection measures, compared with other measures of the operator in a controlled area.
7. the Operator-controlled area and the estimated probability of exposure shall be calculated: 7.1 foreman operator controlled area;
7.2. a medical physics expert in the relevant medical institution;
7.3. the radiation safety expert-a person whose qualifications to perform physical, technical and radioķīmisko measurements, to assess doses from ionizing radiation and radiation safety, as well as, properly using the protection features effectively protect people from ionizing radiation;
7.4. the radiation safety and nuclear safety expert-a person whose qualifications to perform physical, technical and radioķīmisko measurements, assess the dose of ionizing radiation and radiation safety, and nuclear safety, as well as, properly using the protection features effectively protect people from ionizing radiation.
8. Radiation safety expert and radiation safety and nuclear safety expert requires appropriate education to manipulate ionizing radiation sources, and such execution or the operation of the driving experience: 8.1. persons with secondary vocational education, at least 17 years;
8.2. a person who holds a Bachelor's degree or higher professional education, at least 13 years;
8.3. a person who holds a master's degree, at least 10 years;
8.4. persons who are PhD degree and at least 7 years.
9. Radiation safety expert and radiation safety and nuclear safety experts list by radiation safety and nuclear safety expert of the attestation Commission approved environmental protection and regional development Minister. Radiation safety and nuclear safety expert of the attestation Commission approved environmental protection and regional development Minister. The Commission shall consist of at least nine members representing educational institutions providing professional training, professional associations, environmental protection and regional development Ministry, Center, and radiation safety tips.
10. Operator controlled area needs at least one radiation safety expert or radiation safety and nuclear safety expert (after checking with Center operator can ask the foreman to take the said expert features), if the operator of a controlled area: 10.1 take action with radioactive substances;
10.2. operating with ionizing radiation equipment operator civil liability insurance in the minimum amount is larger than the smallest the statutory sum insured;
10.3. actions carried out with ten and more ionizing radiation equipment: 10.3.1.  which is the smallest operator civil liability policyholders the minimum amount;
10.3.2. which operation is required the employee direct participation;
10.4. operating with ionizing radiation sources consistently performs more than five workers.
11. Operator controlled area needs at least one radiation safety and nuclear safety expert, if the transactions with nuclear materials permanently made more than five workers.
12. Operator creates a radiation safety department or radiation safety and nuclear safety Department, which is responsible only for activities with ionizing radiation sources, if the operator of a controlled area: 12.1. operates a national ionizing radiation;

12.2. handling of radioactive substances, which is located in a hermetically sealed capsule or in a solid state and tied up to prevent the spread of radionuclides into the environment under normal conditions of use (hereinafter referred to as the closed source), and the total radioactivity of which more than one million times greater than the Cabinet on July 3, 2001, Regulation No 288 of the "provisions on the handling of ionizing radiation sources, which do not require a special permit (license) or permit" the limits that require a special permit (license) or permit activities with ionizing radiation sources (hereinafter law limitations, which need a special permit (license) or permit);
12.3. handling of radioactive substances, which do not have the source (open source) and total radioactivity more than 104 times exceeds the legal limits that require a special permit (license) or permission, and there are environmental, material, surface, or an external or internal contamination with radioactive substances (radioactive contamination);
12.4 in the event of a radiological emergency could be endangered human life. Radiological emergency is not a planned event, for example, if the employee (also apprentice and student who is older than 18 years), operator controlled area permanently or temporarily performs operations with ionizing radiation sources (the worker), made a mistake in the operation, the source of ionising radiation or unplanned activity, the consequences or possible consequences are defined in these provisions to ionizing radiation dose limit is exceeded or the creation of radioactive contamination as a result of which the relevant limits be exceeded;
12.5. use mobile radiation equipment;
12.6. using ten and more ionizing radiation equipment in operation, the workers participate in directly.
13. Radiation Safety Department is made up of foreman and radiation safety expert, radiation safety and nuclear safety expert or medical physics expert (if institution there is one). Radiation safety and nuclear safety Department is the foreman and radiation safety and nuclear safety expert.
14. Foreman operator controlled area: 14.1.  is responsible for radiation safety and nuclear safety requirements;
14.2. involve all employees in the implementation of measures;
14.3. designate employees responsible for specific activities with ionizing radiation sources;
14.4. If the circumstances which may adversely affect the radiation safety and nuclear safety, immediately ensure research and prevention.
15. Failure to comply with any of the radiation safety and nuclear safety requirements, foreman: 15.1 establish violations the reasons, circumstances and consequences;
15.2. appropriate protection measures due to the relief of the infringement, as well as preventing the recurrence of such violations. Implementation of measures financed by the operator.
16. in order to ensure that the protective measures, the operator in cooperation with the foreman and a radiation safety expert or radiation safety and nuclear safety experts develop radiation safety and nuclear safety quality assurance program source testing, usage, storage and inspection (hereinafter referred to as the quality assurance program), including the requirements and their enforcement in relation to: 16.1.  records and registration records, the record identification, collection, indexing, updating and correction of the information;
16.2. the order and control of the procurement, the supplier assessment and selection, the requirements of the laws of procurement, order and procurement documentation and quality supporting documents, as well as procurement;
16.3. measuring instruments for use in testing;
16.4. test equipment, calibration, adjustment and repair;
16.5. the test material and product labelling;
16.6. the inspection and test records;
10.4. non-compliance with quality requirements and documentation;
16.8. the labelling of non-conforming items, their removal from the system and repair or substitution with other elements;
16.9. employee training, including training and employee proficiency tests;
16.10. monitoring of service providers;
16.11 operating independent of regular inspection (by the institutions or independent institutions experts);
16.12.16.1.16.11. these provisions and referred it to the drafting, execution, registration, approval, tracking, storage and archiving, as well as amendments thereto.
17. in order to carry out quality assurance program requirements, the operator will provide the necessary financial resources for implementation of the measures of protection and regularly and check the materials in the Phys. Invt.
18. Center: 18.1.  promote the education of the population on radiation safety and nuclear safety issues and disseminate information on the latest findings by radiation safety and nuclear safety;
18.2. the control of the quality assurance program;
18.3. participates in radiation safety expert, radiation safety and nuclear safety expert, a medical physics expert and driver training.
19. The Operator's quality assurance program aligned with the Center. Additional reconciliation necessary in the following cases: 19.1. If the operator operates a national nuclear facilities required by the local Government agreed a plan for the radiological emergency preparedness and radiological emergency situations, as well as with the security police agreed measures of physical protection and physical protection project;
19.2. If the operator operation with high power source that the total radioactivity is 106-109 times greater than laws and limits set, which need a special permit (license) or permit the operator shall develop and coordinate with local authorities plan for the radiological emergency preparedness and radiological emergency situations, as well as develop and coordinate with the security police physical protection measures;

19.3. If the operator operation with heavy-duty equipment of ionizing radiation, radioactive substances and ionizing radiation dose resulting from the power of one meter away from the source of ionising radiation are 0.1 – 10 Sv/h required by security police a consistent physical protection measures;
19.4. If the operator operation with medium power sources that the total radioactivity is 103 – 106 times the legislation limits set, which need a special permit (license) or permit the operator shall develop and coordinate with the security police physical protection measures, as well as develop and coordinate with local authorities plan for the radiological emergency preparedness and radiological emergency situations, if an activity with open source or inform the municipality on relevant plans, if carried out the operation with the closed source.
3. calculation of the dose of ionising radiation absorbed dose 20 (D) is weight of absorbed radiation energy. Absorbed dose is the average dose of ionising radiation tissue or organs and environmental objects, its unit of measurement is the gray (Gy), which corresponds to one joule per kilogram.
21. the Equivalent dose (HT, R) is the absorbed dose in a single organ or tissue (T) according to the type of ionising radiation energy range (R) and (quality). The equivalent dose is calculated using the following formula: HT, R = R, where at wRD DT, R – absorbed the (R) ionizing radiation dose rate in tissue or organ (T) individual;
WR – the type of ionizing radiation (R) impact factor for a given energy range. 1. These provisions are set out in annex wR.
22. If the radiation field is composed of different types of ionizing radiation with different values of wR, the total equivalent dose (HT) is calculated using the following formula: HT = ² at wRD, R 23. effective dose (E) are all the tissues and organs of the body in external irradiation (if the source is outside the body) and internal irradiation (if source is located inside the body) of the equivalent dose amount, taking into account the influence of ionizing radiation on tissues. The effective dose is calculated using the following formula: E = ² ² ² wTH = wT at wRD, R, where T T R HT-tissue or organ (T) of the equivalent dose is absorbed;
WT-ionizing radiation impact factor on tissue or organ (T) individual. The relevant values are set in the WTO rules in annex 2.
24. the committed equivalent dose (HT (t)) is the integral dose period (t) of the equivalent dose in a separate capacity in organ or tissue (T). It calculates the time t0 when radionuclides from the external environment, caught up in the human body. The calculation uses the following formula: t0 + t HT (t) = ½ HT (t) dt where t0 HT (t) – the equivalent dose in a separate capacity in organ or tissue t at time (T);
t-years period, which will be gone after the reception and the radioactive substances which this integration. If t is not known, it is assumed to be 50 year adult 70-child.
25. the committed effective dose (E (t)) is the expected tissue or organ (T) of the equivalent dose amount that each dose of ionizing radiation multiplied by the appropriate tissue or organ impact factor wT. The expected effective dose is calculated using the following formula: E (t) = (t) ² wTH, where T t-years period has elapsed after the reception and the radioactive substances which the aggregation.
26. The equivalent dose, effective dose, dose rate and the estimated equivalent effective dose rate expected in the unit of measure is joules per kilogram, the name sievert (Sv).
27. The effective dose (ET) received by a certain age (g) a person shall be determined using the following formula: ET = e + Eārēj ² (g) j, ing, ing + ² e Ij (g) j, inh inh that J J Ij, Eārēj effective dose from external exposure;
(e) (g) j, ing and e (g) j, inh committed effective dose for unit intake for radionuclide j (Sv/Bq) taken through the digestive tract or inhaling the age (g) a person;
IJ, Ij, inh ing and ingestion or inhalation captured radionuclide j (Bq).
28. The estimated total effective dose equivalent is calculated by adding the dose from external radiation sources during the year and estimated equivalent dose from the intake of radioactive substances inside the invoices of the entire quantity of the radionuclide, which captures an adult 50 years, 70 years of children.
4. the radiation dose limits 4.1 ionizing radiation dose limits for workers and the 16 to 18 year old disciples and students 29.  The effective dose rate pamatlimit staff is 20 mSv per year. Clerk pregnant woman and mother is breastfeeding, the effective dose shall be 1 mSv in a year pamatlimit.
30. in addition to the effective dose rate pamatlimit (20 mSv per year) has the following limit on equivalent dose for children: 30.1. equivalent dose for the lens of the eye 150 mSv in a year;
30.2. the equivalent dose to any 1 cm2 of the surface of the skin 500 mSv in a year;
30.3. the equivalent dose to the hands, forearms, feet and ankles 500 mSv in a year.
31. The effective dose pamatlimit of 16 to 18 year old disciples and students (apprentices and students) is 6 mSv in a year.
32. in addition to the effective dose for apprentices and students, pamatlimit has the following limit on equivalent dose for children: 32.1. equivalent dose for the lens of the eye 50 mSv in a year;
32.2. the equivalent dose to any 1 cm² of skin surface 150 mSv in a year;
32.3. the equivalent dose to the hands, forearms, feet and ankles 150 mSv in a year.
33. According to the expected exposure foreman distributed officers in two categories: 33.1.  Category a staff, of which the committed effective dose may exceed, 6 mSv per year or an equivalent dose may be about 3/10 of more than 30 of these regulations provided for in point limit on equivalent dose for children;
33.2. Category B employees whose committed effective dose may not exceed 6 mSv per year or this rule laid down in paragraph 30, the equivalent dose limits for the child.
34. in addition to the provisions laid down in point (B) 33.2. category be divided into the following persons: 34.1. workers who do not carry out activities with ionizing radiation sources, but for which regular radiological investigation to uncover illegal acts in relation to the employer's property, if provided for in the contract of employment and has received the consent of the Trade Union;
21.3. the persons who carry out the procedure of the Court of radiodiagnostisk the medical examiner's or insurance needs, to detect illegal activity.
4.2. the dose limits of ionising radiation in particular allowed the exposure of the employee

35. specific permitted the irradiation is irradiation, if elective which specific activities for employees exceed the effective doses of pamatlimit (20 mSv per year), or radiation, radiological emergency in order to save lives, prevent much of the population exposure or keep great material value.
36. specific permitted exposure may not be longer than five years.
37. specific permitted exposure may be subject only to A category.
38. specific permitted the irradiation need foreman justified and consistent with the employee or his representative.
39. In each particular case of specific work, if specially authorized exposures need is justified (except in the event of radiological emergency), the Centre, together with the authorized Ministry of welfare of the employees, apprentices and students for health care treatment services (hereinafter referred to as the medical establishment) certified occupational physician may allow an employee for a specified period exceed the effective doses of pamatlimit (20 mSv per year) for the specific job, if the dose of ionising radiation does not exceed 50 mSv per year and 100 mSv per year for five consecutive years.
40. specific permitted radiation is prohibited to subject it to category A employees in the five previous years, have already received a dose of ionizing radiation that is more than 100 mSv in a year.
41. the Director may allow an employee in the event of radiological emergency relief or receive an additional dose of ionizing radiation to 50 mSv of exposure time. Exposure above 50 mSv of exposure time may be allowed exceptionally to save human life, if in addition the received dose of ionising radiation does not exceed 200 mSv of exposure time.
42. The Operator shall ensure that information on the particular employees of the risk of exposure and allow the necessary protection, as well as ensure that radiation doses and the number of workers exposed in appropriate economic and social conditions is minimum.
4.3. the dose limits of ionising radiation for the population effective dose pamatlimit 43. citizens shall not exceed 1 mSv in a year, not including exposure from natural sources of ionizing radiation and medical exposure.
44. in addition to the effective dose rate pamatlimit (1 mSv per year) population has the following limit on equivalent dose for children: 44.1. equivalent dose for the lens of the eye 15 mSv in a year;
44.2. equivalent dose any 1 cm² of skin surface-50 mSv in a year;
44.3. the equivalent dose to the hands, forearms, feet and ankles – 50 mSv in a year.
45. If protective measures are not possible to prevent the increased exposure of the population (including radiological emergency), the effective doses of pamatlimit citizens (1 mSv per year) can be exceeded, but the dose of ionising radiation must not be greater than 5 mSv in a year and the average radiation dose may exceed 1 mSv per year for five consecutive years.
5. workers, apprentices and students for protection against ionizing radiation exposures 5.1. assessment of the expected 46. prior to the employee, apprentice or student initiated activities with ionizing radiation sources, the foreman is assessed the nature and estimated the size of the exposure, and determine the appropriate employee, apprentice or student protection measures.
47. the committed effective dose is defined: 29.3. This provision in annex 3 population, apprentices and students, radionuclides (except radon isotopes and the daughter nuclide 220Rn up) take with food or water, 4. population in annex, apprentices and students, radionuclides (except radon isotopes and the daughter nuclide 220Rn up) inhalation;
47.2. in annex 5 of these rules — employees, radionuclides (except radon isotopes and the daughter nuclide 220Rn up) when inhaled and take with food or water.
48. These provisions are set out in annex 6. factor (f1) chemical elements connection transfer through the intestinal tract, employees and citizens taking them with food or water. These rules are laid down in annex 7 factors (f1) chemical elements connection transfer through the intestinal tract, the employees inhaled.
49. in order to assess the exposure from radon isotope and nuclide 220Rn daughter up, apply the following conditional to the effective dose conversion factors to the expected exposure to the alpha energy units (Iu to J. h. m-3): 30.5. up home-1.1;
30.6. work up – 1.4;
30.6. at work – 0.5 220Rn. 50. Expected Alpha energy is the total energy of the Alpha emitting nuclides up and the radioactive daughter 220Rn decay, up to the daughter nuclides decay and ultimately 220Rn daughter nuclides to the common stable 220rn. Alpha energy is the joule (J), but the dose of ionising radiation power measurement of the concentration of a specific radionuclide in air, is the J. (h). m-3.51. This provision is laid down in annex 8 of the committed effective dose to employees and residents, inhaled soluble or chemically active gases and vapors.
52. This provision is laid down in annex 9 to the effective dose of power and population exposure of employees of inertaj gases.
5.2. Area classification, demarcation and labelling 53. Operator controlled area foreman distribution areas and sub-areas are evaluated according to the dose of ionizing radiation and of radiation accidents in the year the possible consequences.
54. the Operator-controlled area has the following areas: 54.1. control zone – the area around each source of ionising radiation or around a compact territory of ionizing radiation source group in which ionizing radiation dose may exceed 3/10 of these rules laid down in point 30. ionizing radiation dose limits;
54.2. monitoring zone – an area outside the control zone in which ionizing radiation dose effective dose may exceed 1 mSv per year pamatlimit.
55. in determining the boundaries of the zones and Subzones, take into consideration the room, building or area of physical boundaries.
56. The control area is intended to: 56.1. control of exposure that is received from the source of ionising radiation under normal operating conditions;
56.2. prevent radioactive contamination;
56.3. prevent or limit the expected exposure.
57. The control area, the following requirements shall be met: 57.1. it is fenced off and access the control area and escape from the work Manager in accordance with the procedure laid down in writing;
57.2. If the control zone is a sub-area of quite different requirements of radiation safety and nuclear safety, foreman down sub-areas border crossing procedures.

58. If necessary, the operator will set up a control zone of one or more subzones: 58.1. radiation area, room or area in which the employee can receive an ionizing radiation that is greater than 0.05 mSv/h. labelling used subareas radiation warning sign with the words "control zone. RADIATION ";
58.2. high radiation area, room or area in which the employee can receive an ionizing radiation that is greater than 0.1 mSv/h. labelling used subareas radiation warning sign with the words "control zone. THE HIGH RADIATION AREAS ";
58.3. very high radiation area, room or area in which the employee can receive an ionizing radiation that is greater than 5 mSv/h. labelling used subareas radiation warning sign with the words "control zone. VERY HIGH RADIATION AREA ";
58.4. other sub-areas, if it is necessary to use different individual and collective protective equipment.
59. the location of the control area, which is used or stored radioactive materials, shall be marked with a radiation warning sign (a radiation symbol and the words "radioactive material"). If radioactive materials storage site is located more than five days, the choice of the place of storage and equipment aligned with the Center.
60. The monitoring zone controls radioactive contamination and ionizing radiation, in order to assess the effectiveness of the quality assurance program and the estimated exposure in the event of a radiological emergency.
61. The Operator shall ensure that: 61.1. monitoring areas, control areas and, if necessary, the separation of the subarea barriers;
61.2. monitoring areas, control areas and sub-areas labelling indicating the zones and subzones types and doses of ionising radiation capacity;
38.1. Control access to areas and sub-areas and escaping from them, as well as conditions that do not allow unauthorised access to areas and sub-areas.
62. Foreman: 62.1. prepare employees working place according to distribution areas and sub-areas, taking into account the expected probability of exposure, the nature of the sources, risks, requirements of the safeguard measures and the possible radiological emergency nature and extent;
62.2. ensure the monitoring and control of the zone, as well as sub-areas of the zone (if any);
38.7. develop instructions according to the expected probability of exposure and monitoring activities to be carried out in the area and control area, as well as sub-areas (if any);
38.8. organise the monitoring of radiation monitoring and control area, as well as sub-areas (if any).
5.3. workers, apprentices and students for health care Operator supports 63. employees the following health care: 39.2. investigation of the medical workers before hiring them;
39.3. the medical examination prior to the employee's allocation category (A) or (B) to determine the employee's eligibility for a position;
63.3. compulsory health checks to determine the employee's compliance with the relevant job duties.
64. The Operator shall ensure apprentices and students in health care – medical examinations before the apprentice or student launched a training course for operator controlled area.
65. Category A employee health checks at least once a year, but a category B employee health – at least every two years to determine the employee's compliance with the relevant job duties.
66. the starting staff, apprenticeship or student health examination, the medical establishment is requesting statement of his outpatient or hospital patient's medical record, including all known earlier received exposure in the workplace, as well as medical exposure, if it had been, as well as environmental radiation monitoring assessment.
67. with regard to staff, students or trainees fit work uses the following medical classification: 67.1. State of health corresponds to the work to be carried out with ionizing radiation sources;
67.2. State of health corresponds to work with sources of ionizing radiation, if the specified conditions are met;
67.3. the health situation does not correspond to the work to be carried out with ionizing radiation sources.
68. If an employee found signs of occupational or work-related illness, of a general nature and he ended with ionizing radiation sources, the medical establishment continues his health care for as long as necessary to ensure the health of the person concerned. In that case, the expenses related to the health check, continues to bear the employer.
69. the information about employee health checks include: 69.1. experience with ionizing radiation sources;
EB 69.2. health testing results prior to employment or classification as category A or B;
69.3. compulsory health testing results;
69.4. ionizing radiation dose received.
70. Information on employee health medical establishment maintained until a person reaches or would have reached the age of 75, but not less than 45 years after the termination of ionizing radiation sources. After the expiry of that time-relevant information shall be referred to the archives of the law "on the archives".
71. If an employee has exceeded the effective dose rate pamatlimit (20 mSv per year) or the equivalent dose limit for the child during the year, the operator shall ensure the employee's extraordinary medical examination and, if the disease is detected signs or with work-related illness, of a general nature, the appropriate treatment. In that case, as well as in any case of an occupational disease requires medical institutions physician's permission to continue working with ionizing radiation sources.
72. If a radiological emergency: 72.1. operator provides the radiation emergency staff, while the irradiated apprentices and students for special health checks;
72.2. the medical establishment, if necessary, eliminates or minimizes internal radioactive contamination;
72.3. operator, taking into account the hospital's doctor's instructions, ensure the availability of medicines, as well as performing other necessary actions irradiated workers, apprentices and students for health care.
 
5.4. workers, apprentices and students evaluation of measures and implementation of 73. To ensure that workers, apprentices and students for protection against ionizing radiation, as well as to prevent radiological emergency, operator: 73.1. ensure workers, apprentices and students for control and accounting of irradiation operator controlled area;

73.2. designate the appropriate numbers of trained personnel to work with ionizing radiation sources;
73.3. provide managers and staff appropriate training and briefing to all employees, apprentices and students be aware of radiation safety and nuclear safety requirements and trained for protection against ionizing radiation;
45.6. ensure workers, apprentices and students for information on the possible damage to health that can lead to work with ionizing radiation sources;
73.5. additional safety information provided about the potential damage to their reproductive health and the effects of ionizing radiation on pregnancy;
73.6. provides a source of service and work instructions development, approval and issuance of staff;
45.8. controlled and recorded for each employee, the apprentice and student preparedness for the work assigned to him;
73.8. provides tracking and log and other checks with sources of ionizing radiation-related document processing and storage as well as the opportunity to test the protective measures;
73.9. stop operation with ionizing radiation sources, if it detected a fault or breach the laws into action with ionizing radiation sources, and removing relevant deficiencies.
74. The Operator is responsible for the insurance of employees against accidents at work and occupational diseases. Workers, apprentices and students for measures of protection against ionising radiation is determined by the foreman.
75. The Operator shall ensure that the employee is expected to include radiological emergency relief work, adequate information, instruction and training.
76. in order to assess the measures of protection of the quality and effectiveness of implementation, the operator provides: 76.1.  radiation safety and nuclear safety, used for accessories and material efficiency, as well as the correct use of the darbderīgum and regular checks;
76.2. ionizing radiation source and disposition;
76.3. new or modified sources darbderīgum of the approval;
76.4. technical effectiveness check;
76.5. regular calibration the instrument, as well as the correct use of the darbderīgum and regular checks.
6. Radiation safety and nuclear safety requirements for sources 6.1. sources for the construction of 77. Latvia is prohibited to import and use of ionizing radiation sources that are not certified or otherwise authorized to use legislation in Latvia, in the order, except that the sources are imported for testing, to verify the possibilities of using it in Latvia.
78. Ionizing radiation sources shall be so designed that it cannot be used for other purposes, which may increase the risk of exposure of human or cause radioactive contamination of the environment.
79. the source manufacturer considered: 79.1.  operator, which produced and distributed a (put) ionizing radiation source;
79.2. operator, highlighting the source of it, on its packaging, technical documentation or in the technical passport indicated his name, trade mark or other distinctive sign;
79.3. operator, which update the source to distribute.
80. the sources of the manufacturer is not responsible for the reliability of the sources. It is the responsibility of the manufacturer: 80.1. produce and distribute safe, human life, health and property of the person, as well as environmentally sound sources;
80.2. to take all precautionary measures ionizing radiation source safety guarantee (such as ionizing radiation source marking and examination of samples for source verification of complaints submitted, the source of ionising radiation recall).
81. the source manufacturer, so designed and constructed that sources of ionising radiation take account of the appropriate source probable operating conditions and, if necessary, provide the ability to use additional personal protective equipment.
82. the source manufacturer, so designed and constructed that sources, ensure that: 82.1. it would be possible to immediately identify the source of ionising radiation damage, which can result in unintended exposure;
82.2. the individual components of the system failure cannot cause unintended exposures;
82.3. should minimize the exposure of employees unplanned transactions in error;
82.4. to avoid the possibility of ionizing radiation equipment parts clogging up from the outside;
82.5. ionizing radiation sources should be easy to purification of the radioactive contamination;
82.6. source control and maintenance of the site should be located outside the influence of ionising radiation area (if possible);
82.7. often bits of source elements be replaced easily and safely;
82.8. source materials used in construction, as well as products used or created this source would be safe.
83. Source: the manufacturer provides 83.1. with collective means of protection against ionizing radiation and the special equipment and accessories to be ionizing radiation equipment to regulate, maintain in working order and used without the risk of exposure;
51.7. ionizing radiation source and its ingredients safe operation;
83.3. to sources should be designed or packaged so that it can be stored safely and without damage, and to be sufficiently stable.
84. Ionizing radiation equipment shall be so designed and constructed that: 84.1. to operate it only with actuation of the control devices provided for and the source of ionising radiation monitoring devices alerted immediately about deviations in the operation of the equipment;
52.3. it would be appropriate for the intended functions and safe, and repairable is adjustable according to the manufacturer's instructions, without causing radiological emergencies throughout the equipment during use (including Assembly and disassembly phase), even if the risk of a radiological emergency occurs in may, in an emergency;
84.3. warning devices and alarm devices being accidentally damaged.
85. Ionizing radiation sources shall be equipped with one or more of the radiation emergency stop devices, to ensure the machine's stopping by ionizing radiation in the event of radiological emergency, and prevent real or imminent danger.

86. Heavy-duty equipment, ionizing radiation, of which the total radioactivity is 106-109 times greater than laws and limits set, which need a special permit (license) or authorization, or where the dose of ionising radiation power of one meter distance from the source is greater than 10 Sv/h: 53.5. provide at least two independent stop device, which is dominant in relation to the actuating devices;
86.2. Security blockers used in the design of physical protection systems, codes and keys, which guarantees that a device's repairs or calibration ionizing radiation sources operation with the lock is possible only under the direct control of the employees using the lock two mutually independent systems that shut off the two employees at the same time.
87. in order to prevent dangerous situations from occurring, the ionizing radiation source control device according to the label. It designs and manufactures to: 87.1. the device should be safe, convenient, secure from external factors, and without an external force to drive would not be possible;
87.2. the control device of human error probability would be minimal;
101.8. error control devices in use does not cause dangerous situations;
87.4. control device would be simple, unambiguous and appropriate for the purpose.
6.2. requirements for sources for the operation and maintenance of 88. Ionizing radiation source supplier is operator who, in the course of business, sells, supplies or otherwise distribute source without compromising on safety, as well as radiation safety and nuclear safety.
89. the supplier sources must not sell, supply or otherwise distribute the source, if it does not comply with the radiation safety and nuclear safety requirements, as well as the sources on which the safety of the delivered does not contain sufficient information.
90. The location of the source of ionising radiation, the operator shall take into account the factors that can affect: 90.1. ionizing radiation source safety;
90.2. the employees, apprentices, students and residents of irradiation.
91. The location of the open source, which the total radioactivity more than 103 times exceeds the legal limits that require a special permit (license) or permit and the closed source that the total radioactivity more than 106 times exceeds the legal limits that require a special permit (license) or permit, the operator shall take into account: 91.1. parameters that may affect the radiation safety and nuclear safety;
91.2. parameters that can affect the ionizing radiation source;
91.3. to plan for radiological emergency preparedness and radiological emergency situations.
92. Before starting the activity with sources of ionizing radiation, the operator shall carry out preparatory work to: 57.2.  prevent possible radiation leak that could occur in appropriate work conditions;
92.2. could limit any radiological emergency (if it has taken place);
92.3. it would be introduced in the procedures, which provides sources and any possible radiological emergency;
92.4. it would be possible to regularly perform radiation safety and nuclear safety checks and tests the system concerned, the element and equipment any time by detecting changes that may lead to unintended circumstances, job characteristics and the risk;
92.5. wherever possible, automatic system ionizing radiation beam disconnecting or ionizing radiation exposure reduction when operating conditions no longer match the defined work mode;
57.5. with a quick-responding systems make it possible to discover the unplanned operational conditions that may significantly affect radiation safety and nuclear safety, and to take timely preventive measures.
93. The Operator shall ensure: 93.1. ionizing radiation ionizing radiation generating equipment by ionizing radiation beam start-up and disconnect indicators and mechanisms of control and kolimēšan;
93.2. sources of supply with blocking devices that prevent ionising radiation facilities unintentional actuation;
93.3. sources of supply with protective devices against scattered radiation;
93.4. radiographic examination equipment supply with devices that automatically disconnects the ionizing radiation at a certain time or a certain dose of ionizing radiation to achieve;
93.5. the installation source automatically transfer from the working position to the storage position, if the power supply is interrupted, and the beam control mechanism starting again just from the machine controller.
94. The Operator is responsible for creating a tiered system of protection for ionizing radiation sources according to the expected size and probability of exposure to ionizing radiation source operating errors on one level to be compensated or corrected for the following levels of protection. Multistage protection system aims to: prevent radiological emergency 94.1. that may cause unintended exposures;
94.2. If in the event of radiological emergency, which created unintended exposure, however, reduce its effects;
58.6. restore source after the safe use of radiation emergency.
95. the source is stored in a special work rooms or in certain storage facilities to prevent unauthorised persons from gaining access to a place of storage containers and ionizing radiation sources. If you need to store: 95.1. closed source, the total radioactivity of which 103 times exceeds the legal limits that require a special permit (license) or permission, stored in a container that does not allow any illegal activities by the ionizing radiation source;
95.2. open source that the total radioactivity of more than 103 times in the laws and limits which need a special permit (license) or permission, stored in a container that does not allow a leak of radioactive content in any of the storage conditions.

96. The Operator shall ensure the sealed source storage locations, which is not possible with other materials, flammability, as well as the necessary fire protection measures, taking into account the peculiarities of the territory where the source is stored or used, and the source of ionising radiation safety requirements listed in the page.
97. the sources of ionising radiation is prohibited be stored in cardboard packaging.
98. Ionizing radiation sources stored in a fireproof location away from flammable material.
99. installing the ionizing radiation equipment, the operator shall ensure that equipment from the main control position can see ionizing radiation equipment. If this is not possible, the operator shall ensure that, before nuclear plant start-up would be visible or audible alarms and staff or other persons which can endanger the machine, following the exposure of the alarm time to leave the danger zone or take other protective measures.
100. The Operator and foreman shall immediately take the necessary measures and radiation safety investigations in such cases: 100.1. If an ionizing radiation source operating parameter, which has a relationship with radiation safety and nuclear safety, in excess of the permitted level or does not match the intended operating conditions;
100.2. in the event of radiological emergency, which can lead to radiation dose limit being exceeded.
101. The Operator shall ensure: 101.1. ionizing radiation equipment metālkonstrukcij and weld connection state control at least once a year in order to detect defects in time which may threaten the safe use of the equipment, such as cracks, deformation, corrosion, changes in wall thickness;
101.2 metālkonstrukcij status. control several times a year, if the ionizing radiation equipment is used in circumstances in which the work environment has a negative impact on the equipment;
101.3. for source control, maintenance, repair and other services during operation source, are not running (if it is possible). These service operations are carried out only by suitably authorised institutions.
102. The Operator shall ensure that all his property or possession of the existing sources of ionizing radiation calibration. Calibration is made by ionizing radiation source at the beginning of the operation, at least once a year and after each such operational procedures that affect radiation parameters.
103. Calibration the following conditions shall be satisfied: 103.1. ionizing radiation equipment is calibrated according to the type of ionising radiation energy and absorbed dose or dose the absorbed power specified distance;
103.2. closed source close exposure is calibrated according to the total radioactivity absorbed dose in determining power vacuum or a specific distance away in the air.
6.3 sources of radiation safety and nuclear safety rating 104.  Reliable sources under normal or foreseeable conditions of use (taking account of the expected service life) will not risk or cause radiation safety and nuclear safety requirements the minimum risk. Higher levels of safety or the existence of sources of ionising radiation, which is the lowest level of risk, can not be grounds for other sources or activities with them as unsafe.
105. The Operator and foreman provides a continuous source of control and immediately inform the Center and security police if source is lost, not allowed to move or use.
106. If the source of the manufacturer, the supplier or another operator that operates a relevant source, becomes aware that the source or it may be dangerous to human life, health, property or the environment of the person, he immediately: 106.1.  directly or through the Centre informed of unsafe sources or activities with it, as well as on other sources of disadvantage other operators that perform actions with the appropriate type of ionizing radiation sources;
106.2. interference – eliminates the shortcomings in question passes the non-secure sources of radioactive waste disposal or management company (if the source contains radioactive substances) or eliminates radioactive substances-unsafe nuclear facilities;
106.3. take measures to non-secure sources out of circulation;
106.4. inform the Centre on the measures that have been taken and will be taken to ensure the sealed source or the safety of the activity in question or for non-secure sources, the withdrawal or suspension of the activities concerned with the unsafe sources.
107. The Operator in cooperation with the foreman and a radiation safety expert or radiation safety and nuclear safety experts take the source of the radiation safety and nuclear safety assessment (SSA) to get the population to ionizing radiation dose does not exceed the dose limits of ionising radiation for the population. Security assessment shall indicate the following information: 107.1. the estimated size of the irradiation facilities, features and the emergence of probability;
107.2. ionizing radiation source working conditions and technical boundaries;
107.3. and radiation nuclear safety related structures, systems and procedures of an element (or all together), which can lead to the expected exposure, as well as its consequences;
107.4. change in the environment that may affect radiation safety and nuclear safety;
107.5. safety and nuclear safety with radiation-related operating procedures the alleged error and its consequences.
108. the security assessment shall take into account: 108.1. possible year environment distributed quantity of radioactive substances if the operator controlled area is taken with radioactive substances. 10. This provision is laid down in annex levels of radionuclide by year may be spread in the environment;
108.2. factors that may cause such a quantity of emissions of radioactive substances in excess of the provisions laid down in annex 10 limits the quantities of radionuclides emission prevention or control features, as well as each of the radioactive substances maximum total radioactivity, which cover corruption may come into the environment;

108.3. factors that may cause lasting a quantity of emissions of radioactive substances, which is less than the rules laid down in annex 10 levels for radionuclides and emission prevention and control;
108.4. factors which may contribute to ionizing radiation beam unexpected fires, and radiological emergency detection, prevention and control;
108.5. various independent radiation safety and nuclear safety assurance funds need to one failure does not lead to another failure and to prevent the expected probability of exposure and size.
109. If the contact zone of two operators, which perform actions with radioactive substances, or the appropriate source impact zones overlap, the foreman in evaluating the radioactive substances dispersed in the environment, take into account the allowable emissions of radioactive substances from the other operator of the controlled area to get the population to ionizing radiation dose does not exceed the dose limits of ionising radiation for the population.
110. The Operator shall ensure the safety assessment documentation. Security assessment can make an independent analysis, if one is provided for by the relevant quality assurance program.
111. The Operator shall arrange for the assessment of the safety of repeated, clarified radiation safety and nuclear safety instructions and technical specifications in the following cases: 111.1.  If it is essential to transform the source or the battery or the crew procedures;
111.2. If the operator has obtained information about the last radiation accidents that are caused by environmental exposure or radioactive contamination exceeds the relevant dose limits of ionising radiation, or have found that the estimated radiation dose may exceed the appropriate limits;
111.3. If the laws are changed, which may affect the safety assessment.
112. If the security assessment shows that the probability of radiation emergency remains, foreman prepares radiological emergency response plan. Radiation emergency plans approved by the operator. If a radiological emergency affect the population and environmental safety, operator readiness plan for the radiological emergency and radiological emergency situations into line with the relevant authorities and the Centre.
7. the protection of the population against ionising radiation of 113.  The Centre carries out population received ionizing radiation dose monitoring with indirect method-uses and controls the monitoring data on radioactive pollution of the environment (hereinafter referred to as the environmental radiation monitoring) and food (food radioactive contamination) in the territory of Latvia: 113.1. identify populations that are equally exposed to any source of ionizing radiation exposure and exposure from this source is the greatest (hereinafter referred to as the critical population group);
113.2. collects information received from operators of environmental radiation monitoring, operator controlled areas;
113.3. collect information on environmental radiation monitoring of radioactive contamination of foodstuffs and of results;
113.4. continuously exploring and assess the radiation exposure of the population;
113.5. evaluate critical population groups received doses of ionising radiation national ionizing radiation in the impact zone of objects.
114. If the expected transactions with ionizing radiation sources are associated with the risk of exposure, the operator before the start of the activities in question carried out potential risk analysis.
115. the monitoring of environmental radiation monitoring zone provides the operator who performs transactions with: 115.1. National ionizing radiation;
115.2. the open source, which the total radioactivity 103 times in the laws and limits which need a special permit (license) or permit;
115.3. the closed nature of the sources that the total radioactivity 106 times the legislation limits which need a special permit (license) or permission.
116. Operator: 116.1. ensure environmental radiation monitoring programme development and coordination with the Centre, as well as under the environmental radiation monitoring programme to ensure control of the quantity of radionuclides in the air, soil, plants and water, taking into account the expected specific radioactivity of radioactive substances in the air, soil, plants, water, and the size of the possible changes, through the various steps in the control zone;
116.2. at least once a year and submitted to the local Council report on environmental radiation monitoring results.
117. the environmental radiation monitoring programme provides: 117.1. parameters measured;
117.2. area measurements and measuring regularity;
117.3. measurement method, radioactive contamination and dose rate ionizing radiation power measurement of control procedures and equipment used;
117.4. residue levels of ionising radiation and the measures taken, if the level is exceeded.
118. the environmental radiation monitoring results shall include the following information: 118.1. the area in which the environmental radiation monitoring;
118.2. date and time of measurement;
118.3. measured values;
the name of the instrument concerned 118.4.;
118.5. calculated or estimated values: 118.5.1. possible internal radiation;
118.5.2. possible external exposure;
responsible for the measurements of 118.6. employee's name and title.
119. the environmental radiation monitoring programme at least once a year, review to assess whether it meets the operator zone and in the zone of the nature of the operations to be undertaken with ionizing radiation sources.
120. The population received ionizing radiation dose assessment include: 120.1.  external radiation dose measurement results for marginalised groups of citizens;
120.2. the internal assessments of population exposure marginalised groups;
120.3. radioactive contamination of the results of the measurements of environmental objects and foodstuffs.
121. The Center shall inform the citizens and employers if: 121.1. population exposures critical group dose from external radiation long periods of 5 mSv in a year or more;
121.2. natural sources of radiation beyond the eighth chapter of this provision limits.
122. in order to assess the population received a dose of ionizing radiation exposure, internal use: this provision 3.122.1. in annex, the expected effective doses when ingested radionuclides to food or water;

122.2. This provision in annex 4 of the expected effective dose, radionuclide inhalation;
122.3. This provision 6. the coefficients set out in annex (f1) chemical elements connection transfer through the intestinal tract, taking them with food or water;
8. these provisions 122.4. Annex estimated effective dose inhaled soluble or chemically active gases and vapours;
9. these provisions 122.5. in annex to the effective dose of radiation of the inertaj capacity of gases.
8. protection against natural ionizing radiation sources 8.1. Natural sources of ionizing radiation building 123. Center the places, where the building is elevated natural radiation level. That place research at the national or local order accredited laboratory, in cooperation with other competent authorities.
124. by building or apartment owner or tenant order radon level buildings accredited laboratory determines or Center.
125. Where it is established that the average specific radon radioactivity in buildings is greater than 200 Bq/m3 per year, building or apartment owner shall inform the tenant and the Center (where the radon level defined by the accredited laboratory). The Center shall inform the citizens about the expected harm to their health and, together with the building or apartment owner or tenant decides on safeguard measures of the harmful effects of radon reduction.
126. Where it is established that the specific radioactivity of radon in buildings larger than 1000 Bq/m3 during the measurement or 600 Bq/m3 on average per year, the building or apartment owner or tenant shall immediately take the measures of protection.
127. the Centre, together with the building or apartment owner or tenant decides on the necessary building or apartment protection measures based on radon and its decay products of continuous or periodic measurements, radon radioactivity specific seasonal change, geological data and information on the building or housing construction.
128. The construction contractor, designer and artist is responsible for the new building or apartment radon average specific activity does not exceed 200 Bq/m3 per year.
129. The external gamma radiation dose equivalent sources of power limits are as follows: the new building – 0.5 µSv 129.1./h;
129.2. buildings-1 µSv/h;
129.3. frequently used areas outside buildings, such as yards, playgrounds, palīgbūv, 1 µSv/h 8.2. Natural sources of ionizing radiation in the workplace 130. this subsection shall apply to existing places of work the natural ionising radiation sources that do not take action, but which have an exposure exceeding 43. This provision and paragraph 44 limits employees who do not carry out activities with ionizing radiation sources, or the public. The employer shall ensure appropriate protection measures, if the following actions are taken: 130.1. activities related to the increase of the radon isotope and nuclide 220Rn daughter up the specific radioactivity, elevated gamma radiation or any other exposure in workplaces such as minerālavoto, caves, mines, underground workplaces and aboveground workplaces in the individual;
130.2. the storage of materials, which are not regarded as radioactive but which contain significant quantities of natural radionuclides, as well as transactions with them;
130.3. the activities that produce waste, which are not regarded as radioactive but which contain such a quantity of natural radionuclides that may exceed this provision in paragraph 43 and 44. limits;
130.4. in their operational jet aircraft in flight.
131. If the employee who does not perform transactions with ionizing radiation sources, the work can get a dose of ionizing radiation that is greater than 1 mSv in a year, the employer shall take the work environment research to determine which areas, carrying out of an activity and the circumstances in which the person concerned is subject to exposure and preventive measures to reduce the dose of ionizing radiation.
132. If the employee who does not perform transactions with ionizing radiation sources, the workplace can get ionizing radiation dose greater than 6 mSv in a year, the employer shall apply these rules his employees under certain protection measures.
133. If the committed effective dose exceeding 1 mSv, but less than 6 mSv in a year, the employer shall ensure that a pregnant woman employed by ionizing radiation dose, you could get the fetus throughout pregnancy, does not exceed 1 mSv.
134. the employer, in cooperation with the Centre controlled jet plane crew received doses of ionizing radiation. If the radiation dose received is greater than 1 mSv, but less than 6 mSv in a year, the plane crew members pregnant women the employer shall ensure that the dose of ionising radiation, which could get the fetus throughout pregnancy, does not exceed 1 mSv.
135. Where surface and underground work places average specific radon radioactivity is greater than 400 Bq/m3 per year, the employer shall ensure protection measures to reduce the harmful effects of radon in the workplace and to prevent the employment of pregnant women in these jobs throughout the pregnancy.
136. If it is not possible to reduce the specific radioactivity of radon to 400 Bq/m3, shall be assimilated to the point where an activity with sources of ionizing radiation, and the employer the employee concerned apply these provisions in certain protective measures for employees.
8.3. Natural sources of ionizing radiation in water 137. the Centre shall inform the population and the local authorities of the anticipated harm human health and protection measures of the harmful effects of radon reduction, if the specific radioactivity of radon in drinking water is 100 Bq/l-1000 Bq/l drinking water, in which radon radioactivity is more specific about 1000 Bq/l, may not be used, if no protective measures are the harmful effects of radon reduction.
138. Long-lived radionuclides (238, 234, 226Ra, and ultimately the 210P) the specific radioactivity in drinking water, expressed as an annual effective dose must not exceed 1 mSv.
8.4. Natural sources of ionizing radiation and būvizstrādājumo of būvmateriālo 139. If būvmateriālo and būvizstrādājumo are specific 226Ra which radioactivity exceeds 100 Bq/kg, the works contractor provides appropriate safeguards to prevent this provision 8.1. section limit being exceeded for radon concentration in buildings that will be used in the construction of these building materials and construction products.

140. The natural radionuclide (226Ra, 232Th) specific maximum limit of radioactivity in būvmateriālo and būvizstrādājumo is as follows: 140.1. būvmateriālo and būvizstrādājumo intended for residential and public building construction, repair and interior fittings,-270 Bq/kg;
140.2. būvmateriālo and būvizstrādājumo intended for civil and industrial buildings and premises for the construction, repair, reconstruction, as well as the residential and public buildings for external decoration and construction of roads in populated areas,-740 Bq/kg;
140.3. the būvmateriālo and būvizstrādājumo intended for civil and industrial buildings for external decoration and construction of roads outside built-up areas, – 1350 Bq/kg.
141. The building materials and construction products, gamma radiation source-specific radioactivity limit is 2 Bq/kg. If a specific radioactivity less than 1 Bq/kg, no protection measures. Radioactivity is determined using the following formula: mg = CK/3000 + CR/300/200 mg – which CTh gamma radiation source of radioactivity (Bq/kg);
CK, potassium 40 specific radioactivity (Bq/kg);
CR-radium 226 in the specific radioactivity (Bq/kg);
CTH-thorium 232 in the specific radioactivity (Bq/kg).
142. The building materials and construction products manufacturers, suppliers, and agents of the works is responsible for building materials and construction products the specific activity limits specified.
9. protection against artificial sources of ionizing radiation ionizing radiation sources 9.1 building 143. agents of the works selected building materials and materials containing no artificial sources of ionizing radiation or it is so substantial that the new building will: 143.1. external gamma radiation dose equivalent sources of power is less than 0.25 µSv/h;
143.2. buildings surrounding the external gamma radiation dose equivalent sources of power is less than 0.5 µSv/h;
143.3. frequently used areas outside buildings, such as yards, palīgbūv, playgrounds, surrounding external gamma radiation sources in doses equivalent to the capacity is less than 0.5 µSv/h; 9.2. Radioactive Substances in water 144. Centre the water radioactive pollution monitoring and control, to assess the radiation exposure of the population.
145. at least four times a year, drinking water supplies and acquisitions in places where water consumption is greater than 10000 m3, accredited laboratory determines the tritium, 90Sr and 137Cs specific radioactivity in water intended for consumption. Water intended for consumption is: 145.1. natural water or water after treatment and purification, intended for drinking, food preparation or other domestic purposes, regardless of the type of water supply;
145.2. water used in food production or food processing.
146. at least once a year according to the State environment monitoring program accredited laboratory determines the 90Sr and 137Cs specific activity in the Daugava, Gauja river Lielupe, Venta, in the middle of it, flow into the Salatsi seas and lakes, which area is more than 25 km2.
147. The Center shall inform the population and the local authorities of the anticipated harm human health and possible protective measures when specific radioactivity is: 147.1. the water intended for consumption: 147.1.1. more than 100 Bq/l for tritium;-
147.1.2. greater than 0.06 Bq/l – 90Sr;
147.1.3. greater than 0.1 Bq/l, 137Cs;
147.2. River and lake water: 147.2.1. greater than 0.6 Bq/l – total beta radioactivity, recalculated to 90Sr;
147.2.2. greater than 1.0 Bq/l-137Cs. 9.3. radioactive contamination of food. in Latvia the prohibited 148 to import, produce and distribute food which radioactive contamination exceeds the provisions set out in annex 11. The Centre carries out food monitoring of radioactive contamination of the product.
149. radioactive contamination of food is controlled by the food and veterinary service. The control results shall be transferred to the Center.
150. these provisions are established in annex 11, the limit is exceeded, the food manufacturer, eliminates the causes of radioactive contamination, such as decontamination, used in the production and processing methods to reduce radioactive contamination present where radioactive contamination of raw materials may not be reduced. If it is not possible to reduce radioactive contamination, radioactive contaminated food.
151. at least once a year, the food and veterinary service controls radioactive contamination of milk on the farm where the cow more than 200, and food companies where milk production exceeds 5000 tonnes per year (translation of milk equivalent). Milk control of 137Cs and 90Sr, but 40 k is used to assess the quality of the methods of measurement. If the specific radioactivity in milk 90Sr is greater than 0.2 Bq/l or 137Cs specific activity greater than 0.5 Bq/l, determined the other this provision 11. radionuclides listed in the annex.
152. for the control of radioactive contamination for foodstuffs in the total consumption per day per person (hereinafter referred to as the food basket) accredited laboratory at least annually 90Sr and 137Cs activity. Controlling food basket, also take account of imported food products. Radioactive contamination of food basket down, parallel with the following methods: 152.1. based on the statistics of certain food consumption per person per day, the amount of the individual food purchase in a shop and market (food purchase in a store or a market where day shopping at least 10000 people), determine the radioactivity in each individual food and the calculation of the total radioactivity in the whole food basket.
152.2. combining samples constitute one man for portions of breakfast, lunch and dinner (the food products purchased in the restaurant where is served the day of at least 1000 people). The resulting sample determines the quantity of radioactive substances and the food basket.
153. If the food basket 90Sr radioactivity is greater than 0.1 Bq or 137Cs activity greater than 0.2 Bq per day per person, the Centre, together with the food and veterinary service: 153.1. investigate and analyse the situation of food production and distribution;
153.2. Requests the food manufacturers and distributors to prevent radioactive contamination and, if necessary, to ensure the food processing to reduce radioactive contamination up to maximum residue levels;

153.3. If it is not possible to reduce radioactive contamination of food products in the basket, the relevant food legislation in the order withdrawn.
9.4. radioactive contamination of animal feed for 154. is prohibited to import, produce and distribute animal feed that radioactive contamination exceeds the provisions set out in annex 12.
155. radioactive contamination of animal feed is controlled by the food and veterinary service. The control results shall be transferred to the Center.
156. Where it is established that radioactive contamination in animal feed exceeds 12 this provision limits set out in annex, the animal feed producer and Distributor: 156.1. eliminates the causes of radioactive contamination;
156.2. If it is not possible to eliminate the causes of radioactive contamination is removed from the animal feed chain;
156.3. withdrawn from the circulation of animal feed processing or destroyed.
9.5. radioactive contamination of air 157. Center of radioactive contamination of the air surveillance and control, in order to assess population exposure and gamma radiation dose provides power monitoring, using the automatic gamma radiation monitoring system.
158. The accredited laboratory once a month is determined by the specific 137Cs and 7B radioactivity in air samples, using at least one of the Daugavpils district placed stationary air sampling aerosol filtration equipment, operating in continuous mode.
10. Protective measures for reducing exposure 159. Protection measures is to reduce the exposure to ionizing radiation source neutralization, ionizing radiation ionizing radiation or conversion subject to the reduction in the number of people (intervention). Intervention: 159.1. radiological emergency in order to reduce or eliminate the exposure of short duration;
159.2. chronic irradiation necessary to reduce or eliminate chronic irradiation. Chronic irradiation is irradiation of: 159.2.1. natural radiation sources;
159.2.2. radioactive substances, which have remained from previous radiation accidents after the completion of the measures of protection;
159.2.3. ionizing radiation sources that are not subject to the control of the Centre;
159.2.4. for activities with ionizing radiation sources, which do not require a special permit (license) or permit activities with ionizing radiation sources.
160. the interventions need to evaluate the work of Director and radiation safety expert or radiation safety and nuclear safety expert. The intervention is allowed if it reduces possible harm to health and the positive effect is greater than the intervention of injury, as well as any interference with the associated costs.
161. If necessary intervention, foreman prepares the intervention plan. Intervention type, scale and duration of the check to the optimal benefit of health harm reduction interventions with maximum exceeded costs. Intervention plan must be approved by the operator. If the measures in question affect the environment and population security, operator intervention plan coordinated with the local government and the Center.
162. Interference may refer to: 162.1. ionizing radiation source, to reduce or stop the direct radiation or radionuclide emissions;
162.2. environmental objects to reduce the transfer of radioactive substances to humans;
162.3. people to reduce unintended exposure and organize the treatment of victims.
163. Intervention radiological emergency is justified if a radiological emergency can cause serious damage to human health.
164. Intervention to prevent prolonged exposure due to radon, is justified if: 164.1. building or apartment radon concentration exceeds 200 Bq/m3, the intervention provides a building or apartment owner;
164.2. the workplace for radon concentration is greater than 400 Bq/m3, the interference by the employer.
165. Ionizing radiation dose at which receiving intervention required, determine the provisions of annex 13.
166. The Operator shall ensure any radiological emergency and of the effects of the evaluation of the effectiveness of interventions, and tracking. The Center collects the relevant information.
11. The final issue 167. Be declared unenforceable in the Cabinet of 26 May 1998, Regulation No 194 "rules on the control of radioactive contamination of food" (Latvian journal, 1998, 155./156.nr.).
Prime Minister a. Smith of environmental protection and regional development Minister v. Makarova in the Editorial Note: rules shall enter into force on 13 April 2002.
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