Law fifteen/thousand nine hundred and eighty. On 22 April, the Council established the Nuclear Safety Council as the only body responsible for nuclear safety and radiation protection, with the task of proposing to the government the necessary regulations in this field.

On the other hand, the need for a Regulation on Radiological Protection that came to replace the existing regulations, dispersed and inadequate to the present circumstances was leaving to feel for some time in effect the The development of nuclear and radioactive activities made it essential to have the standards. on the basis of those issued by the competent international bodies, which have already been adopted by the most advanced countries, make it possible to regulate radiation protection by establishing the objective criteria to be based on to determine the bodies of the State responsible for the implementation of its provisions, which in accordance with the legislative changes in recent years are, in addition to the said Nuclear Safety Council, the Ministries of Industry and Energy and Health and Consumer Affairs.

It is their virtue, in accordance with the regulations proposed by the Nuclear Security Council, on the proposal of the Ministers of Industry and Energy and of Health and Consumer Affairs, according to the State Council, after deliberation of the Council of Ministers at its meeting on the 12th of August of a thousand nine hundred and eighty-two, I have:

Article 1.-The Deputy Regulation on Health Protection against Ionising Radiation is hereby approved.

Article 2. The provisions contained in the Orders for Protection against Radiation of 22 December of one thousand nine hundred and fifty-nine and ten of July of one thousand nine hundred and sixty-two, as well as the precepts of equal or equal, are hereby repealed. the lower range affect the matters covered by this Regulation.

FINAL DISPOSITION

In the context of the special conditions under which the activities carried out in the facilities referred to in the Regulation on Health Protection against Lonising Radiation by the Ministry of Health are carried out The proposal referred to in Article 6 (2) of the Workers ' Statute will be formulated in the context of work and social security.

Given in Palma de Mallorca to twelve of August of one thousand nine hundred and eighty two. -JUAN CARLOS R.-The Minister of the Presidency, Matias Rodríguez Inciarte.

REGULATION ON HEALTH PROTECTION AGAINST IONISING RADIATION

TITLE FIRST

General provisions

CHAPTER FIRST

Object and Scope

Article 1. This Regulation aims to establish protection rules to prevent the production of non-stochastic biological effects and to limit the likelihood of the incidence of stochastic biological effects to be considered acceptable. for the staff of nuclear and radioactive installations and the general public as a result of the activities carried out in those facilities.

The regime for measures to protect against ionising radiation provided for in Law 25/1984 of 29 April on Nuclear Energy will be governed by the provisions of this Regulation and those of this Regulation.

Art. 2. This Regulation shall apply to all types of nuclear and radioactive installations including the holdings of radioactive minerals to be processed. the use of storage for the storage of natural or artificial radioactive materials and the use of ionising radiation as well as the disposal of such substances and in general any activity involving them a risk arising from ionising radiation.

For the purposes of this Regulation the definitions contained in Appendix I shall be used.

CHAPTER II

Authorities and Administrative Bodies

Art. 3. The application of the provisions of this Regulation corresponds to the Ministry of Industry and Energy and to the Ministry of Health and Consumer Affairs and in particular to the Nuclear Safety Board without prejudice to the specific competence of other Ministries and authorities.

TITLE II

Basic protection rules

CHAPTER FIRST

General rules

Art. 4. The number of people exposed to ionising radiation will be as low as possible. The holder of the activity shall take the necessary measures to ensure that the doses received are as small as is reasonably possible taking into account social and economic factors and always lower than the dose limits set out in Appendix II.

Art. 5. For the purposes of this Regulation, persons are classified as:

a) Persons professionally exposed

b) Members of the public.

c) Population as a whole.

Art. 6. People who are exposed to the risk of ionizing radiation exposure are considered to be professionally exposed. Students and apprentices who, during the period of study or learning and in a normal way, are exposed to ionizing radiation are considered to be included in this category.

Members of the public are the people of the population considered individually who are professionally exposed.

Population as a whole is the collectivity of professionally exposed people and members of the public.

Art. 7. No person under the age of 16 may participate in activities where he may be subject to the risk of exposure to ionising radiation.

CHAPTER II

Protection rules for professionally exposed persons

Art. 8. The work shall be carried out in such a way as to ensure that, under normal working conditions, the doses received are the lowest possible taking into account social and economic factors and in any case lower than the dose limits set.

For the determination of the total doses the doses due to the internal and external sources of ionising radiation will be taken into account. In their computation, however, the doses due to the natural radioactive background should not be included as a result of medical examinations or treatments (as patients) or those received individually as members of the public.

Art. 9. The limits derived from the concentration of radionuclide activity in the inhaled air shall be those set out in Appendix III.

The annual intake limits per ingestion will be the same as for members of the public.

Art 10. As a general rule, any person under the age of 18 shall be prohibited from participating in activities in which they may normally be exposed to ionising radiation. By way of derogation or if other provisions allow for reasons of study or learning, the persons under this age may be admitted to such activities provided that they are more than sixteen years old and under the conditions laid down in Appendix II.

Art. 11. Where a situation is present in a facility, the solution of which makes it necessary to expose persons to the risk of receiving a higher dose than one of the annual dose limits set for the exposed workers specified in the Appendix 11 the operation involving this risk shall be considered as a planned special operation and shall be programmed in such a way that no exposed person receives a dose exceeding one year twice the annual dose limits fixed in the Appendix II and under the conditions specified in Section 1.4 of Appendix II.

Any dose received as a result of a planned special operation should be recorded as such in the dosimetric record specifying where appropriate. The incorporation of radionuclides in the organism.

Women with the capacity to procreate and those under the age of eighteen cannot be admitted to these operations.

Art. 12. Where in the event of an accident and exceptionally there are situations giving rise to exposures involving the receipt of doses higher than the dose limits set for normal working conditions, these exposures shall be consideration of exceptional exposures and shall be classified as:

1. Emergency exposure.-Those on a voluntary basis where the annual dose limits set out in Appendix II are exceeded and which are justified in the case of providing assistance to individuals in danger of avoiding exposure of a large number of staff or save a valuable installation. Persons who are to be provided for this purpose must be informed of the risks involved before they are involved in such operations.

2. Accidental exposures.-Those of a fortuitous and involuntary nature in which one of the annual dose limits set out in Appendix II is exceeded.

If the doses received as a result of these exceptional exposures exceed twice the corresponding annual dose limits, the case will be brought to the attention of:

-Medical services who, in view of the dose received ilosymetric history. The age of the worker and the result of the additional medical examination shall take the appropriate immediate measures and shall propose appropriate measures in relation to the continuity of the worker in his post and to his possible medical care.

-The Nuclear Security Council

-The affected worker.

CHAPTER III

Protection rules for members of the public

Art. 13. The dose limits for the individual members of the public are those set out in Appendix II.

For the determination of the total doses the doses due to the internal and external sources of ionising radiation shall be taken into account not included, however the doses due to the natural radioactive substance or those derived from medical examinations or treatments.

Art. 14 The annual intake limits per ingestion if the annual inhalation incorporation limits for members of the public are as set out in Appendix III

CHAPTER IV

Protection rules, for the population as a whole

Art. 15. The total of the doses received by the population as a whole and in particular the resulting genetic dose will be as low as reasonably possible taking into account social and economic factors. For the estimation of the genetic dose, account should be taken of all activities involving a risk of exposure to the population as a whole.

TITLE III

Fundamental surveillance measures for the protection of professionally exposed persons.

CHAPTER FIRST

General rules

Art. 16. In the case of activities whose importance is required by the Nuclear Security Council, there shall be a Technical Service or Unit for Protection against ionising radiation in charge of compliance with the provisions of this Regulation. Regulation.

In such a case, the applicant for the administrative authorization necessary for the exercise of such activities shall propose the Service or Technical Unit either own or contracted to whom the functions provided for in the paragraph will fall. previous.

Art. 17 In the administrative authorizations necessary for the exercise of such activities, it shall be stated whether these functions shall be borne by the operator of the installation or if the existence of a Technical Service or Unit of Protection against Ionising Radiation.

Art 18. In any event, the Head of the Technical Service or Unit for the Protection against Ionising Radiation shall be in possession of a specific title issued by the Nuclear Safety Board.

Art 19. Before starting their activity, the persons professionally exposed must be informed and instructed, to a person who is not appropriate to their responsibility and to the risk of exposure to ionising radiation from their position of work:

a) Risks of ionizing radiation and its biological effects.

b) General rules for the protection against radiation and precautions to be taken under normal working conditions and in the event of an accident.

c) Specific rules and methods of working for their protection in the operations to be performed

(d) Types and use of the instruments for the dissection and measurement of radiation and the means and equipment of personal prosection.

e) The need to undergo medical examinations to determine their health status and specific examinations to assess possible internal contamination.

f) Acting in emergency situation.

g) Responsibilities arising from his/her job with respect to radiation protection.

CHAPTER II

Prevention of explosion

Art. 20. The surveillance of persons professionally exposed as regards the incidence of ionising radiation on their health shall be based on the following measures:

-Classification of persons professionally exposed in different categories according to their workplaces.

-Classification of workplaces in different zones.

-Extension of the rules and control measures in the different areas and the different categories of people professionally exposed.

Art. 21. For the purposes of surveillance and control, professionally exposed persons shall be classified as two categories:

Category A: These persons belong to those persons who, by the conditions under which their work is performed, are not unlikely to receive doses higher than 3/lo of any of the annual dose limits set in the Appendix II.

Category B: Those persons who, by the conditions in which their work is performed, are highly unlikely to receive doses higher than 3/10 of any of the annual dose limits set in the Appendix II.

Art 22. In 109 workplaces where there is a risk of exposure to ionising radiation, surveillance shall be carried out with appropriate equipment of the type and sensitivity to determine existing levels of radiation and environmental pollution. especially at points where these levels can be the maximum. In the case of contamination, the overall assessment of the surface concentrations and densities of activity and, if necessary, the identification of the most significant radionuclides shall be carried out.

The documents relating to the assessment and the results of such surveillance must be filed by the owner of the installation who will be available to them, from the competent authority.

Art. 23. The Sr workplaces shall be classified according to the risk of exposure in the following areas:

Controlled area: This is where it is not unlikely to receive doses higher than 3/10 of the annual dose limits set in Appendix II.

Monitored area: This is where it is not unlikely to receive higher doses 3 1/10 of the annual dose limits set in Appendix II, with doses higher than 3/10 of these annual dose limits being highly unlikely.

Art. 24. The classification of workplaces within the established areas should always be up to date in accordance with the actual conditions.

Art. 25. The controlled and monitored areas shall be adequately demarcated and marked in such a way as to show the risk of exposure to them. This signalling shall be carried out in accordance with the requirements of Appendix IV.

Art. 26. Access to controlled and monitored areas shall be limited to persons authorised for this purpose.

Art. 27. At the exit of the controlled and monitored areas where there is a risk of contamination there shall be adequate detectors to check for possible contamination and where appropriate to take appropriate measures.

Art. 28. The use of individual dosimeters and in the gas that there is a risk of contamination the use of personal protective equipment appropriate to the existing specific risk shall be mandatory in the controlled areas.

Art. 29. In the monitored areas, an estimation of the doses that can be received should be performed by area dosimetry. If there is a risk of contamination, the use of appropriate personal protective equipment shall be mandatory.

CHAPTER III

Determination of doses

Art. 30. The doses received by the professionally exposed persons must be determined when the working conditions are normal with a periodicity not exceeding one month for the external dosimetry and with the periodicity that is established in each case. for the internal dosimetry of those exposed to the risk of the incorporation of radionuclides. All this in order to keep the metered record of the same and check compliance with the basic standards of protection laid down in Title II.

The dosimetric system used for the determination of individual doses will be appropriate for both external and internal radiation classes and energies to which people are exposed.

Individual dosimetry, both external and internal, shall be performed by Entities or institutions expressly authorized and supervised by the Nuclear Security Council.

Art. 31. For professionally exposed persons belonging to category A it shall be compulsory:

a) Use individual dosimeters to measure the representative external dose of the entire body throughout the working day.

(b) In the case of risk of exposure where some parts of the body may receive doses higher than the whole of the body, use appropriate dosimeters in the potentially affected parts.

c) In the case of internal exposure risks, carry out the appropriate measures or analyses to assess the corresponding doses.

Art. 32. For professionally exposed persons belonging to category B, the use of personal dosimeters shall not be required, provided that the area dosimetry is available in the workplaces to control the doses received. are less than 3% of the annual dose limits set in Appendix II.

Art 33. Professionally exposed persons who have been able to receive doses higher than the annual dose limits set out in Appendix II as a result of exceptional exposures or planned operations shall be the subject of a study to assess as accurately as possible the doses of the whole body or the doses received in the affected organic regions.

CHAPTER IV

Record individual doses

Art. 34. It will be compulsory to register all the doses received during the working life of the persons professionally exposed in an individual dose history which will be at all times the worker's own disposition. In the event that the installation operator ceases to be employed, the operator must provide a certified copy of that record.

Art. 35. The dose history for persons in category A shall record at least the monthly doses and the cumulative doses during each 12-month period. In the case of persons in category B, the specified or estimated annual doses shall be recorded.

Art. 36. The doses received by exceptional exposures shall be recorded in the case of a separate dose recorded separately from those received during the work under normal conditions. In the same way, they will be due to planned special operations.

Art. 37. Persons who are professionally exposed in more than one installation shall be obliged to give express account of that fact to those in charge of the protection of each of the centres in which they work in order to be It is updated and has completed its individual dosimetric history. To this end, the worker must communicate in each facility the dosimetric results provided to him in the others.

When in the same place of work, professionally exposed persons who are dependent on more than one holder will be obliged to agree on how to determine and communicate the doses received as consequence of this activity.

Art. 38. Both the dosimetric history of the persons professionally exposed and the documents relating to the assessment of the doses and the measures of the surveillance equipment must be archived by the holder of the activity where they provide services have been provided by such persons who shall have them at the disposal of the competent authority but may not bring them to the attention of other persons without the express consent of the worker himself.

Art. 39. The dosimetric history of any professionally exposed person must also be included in their individual health care documentation.

CHAPTER V

Medical surveillance

Art. 40. The medical surveillance of the persons professionally exposed shall be carried out by a specialized or contracted medical service with capacity officially recognized for these purposes by the Ministry of Health and Consumer Affairs. Nuclear Security Council without prejudice to the legislated on Services of Medical and Professional Diseases.

Art 41. Any person who is to be assigned to a job who is at risk of exposure must be subject to a prior health examination to enable him to prove that he is not in any of the incompatibilities that are legally present. determined and decide on their suitability for the work to which they are intended.

Professionally exposed persons will also be subject to periodic health examinations to check their general health status and especially to determine the status of the exposed organs and their functions. This surveillance shall be supplemented by additional medical examinations adapted to the importance of exposure and ionising radiation and their frequency shall be determined at the same time by the health status of the worker and for any incidents that may occur.

Art. 42. The medical examination of any person's prior health to be assigned to a post involving risk of exposure shall be aimed at obtaining a complete medical history which also includes:

The knowledge of the type of work performed previously and the risks to which it has been exposed as a result of it and in its case of the dosimetric history to be contributed by the worker.

-Possible exposures incurred as a result, either of the functions exercised or of treatments and medical diagnoses with specification of their causes doses received zones surveys and type of clinical manifestations observed.

-The result of a general clinical examination completed by dermatological and ophthalmic haematological investigations, in addition to those deemed necessary to judge the condition of the organs or devices that may be affected to a higher degree for the risk arising from the specific work to be carried out.

Art. 43. The periodic medical examinations of the professionally exposed persons shall be carried out at least once a year.

These medical examinations shall include a general clinical examination including in addition to the hermatological study the investigations deemed necessary to judge the state of the organs or tissues that may be potentially affected by radiation: Ionising

Any additional medical examinations shall be carried out on all the examinations deemed necessary in relation to the characteristic I of the exposure or of the internal or external contamination.

Art. 44. From the medical point of view and according to the result of the appropriate recognition, the professionally exposed persons shall be classified in the following categories:

Suitable: Those that can perform activities that involve the risk of exposure associated with the job.

Under observation: Those who are subject to medical studies to check their fitness to return to jobs that involve a certain risk of exposure.

Unfit: Those that must be kept separate from positions that involve a certain risk of exposure. The declaration of people's inability will be based on the existing rules on disability and occupational diseases.

Art. 45. Each professionally exposed person shall be opened a medical protocol which shall contain at least the results of his or her prior medical examination of his or her periodic medical examinations and of his/her examinations. of all of his or her professional life and an additional dosimetric record in which the estimates of the doses received by that person are recorded as a result of medical diagnosis and treatment.

These protocols will be closed for at least thirty years after the cessation of activity in the medical services corresponding to the centres in which those persons provide or have provided their services and will be the provision of the competent authority and the worker himself.

Art. 46. The specialised medical service may determine whether it may be extended for as long as it deems necessary for the medical surveillance of persons having been professionally exposed to have been declared unfit or to have ceased to be in that professional activity.

TITLE IV

Fundamental surveillance measures for the protection of the public

Art. 47. The protection of members of the public and of the population as a whole shall be carried out by means of a series of measures and controls in order to ensure that the operations of production and use of ionising radiation are carried out with the adequate guarantees.

Art. 48. Surveillance shall be based primarily on the assessment of the doses that may be received under normal operating arrangements and in the case of an accident and shall be appropriate to the risk involved in the activities.

Art. 49. In order to obtain the administrative authorization which may be used for the exercise of nuclear or radioactive activities, the applicant shall provide the appropriate studies to determine the risk of exposure to which he may be the population as a result of such activities, both in normal operation and in the event of an accident.

Art. 50. In those activities where the results of the safety study advise it, an emergency plan should be proposed, where the rules of action in the event of an accident of the staff of the activity are specified. Such an emergency plan will follow the General Standards established by the Nuclear Security Council.

Art. 51. The administrative authorisation for the studies referred to in the previous Article shall specify whether a specific surveillance system should be available to monitor during the course of the activity the doses which the could be received by the public.

In this case, the dose estimates shall be carried out at a frequency not exceeding one year and their results shall be archived by the holder of the activity together with the data that served as the basis for their determination.

TITLE V

Radioactive waste

Art. 52. The activities falling within the scope of this Regulation should be designed to prevent or minimise the spread of radioactive materials to the environment, whether or not they are in normal operation. as in the case of an accident. As a minimum, such activities shall comply with the rules of this Title without prejudice to the application of the legal and regulatory provisions on those provisions in force or to be issued in the future.

Art. 53. Activities which may give rise to radioactive waste or waste of significant amounts must be equipped with the necessary storage and disposal storage systems. These systems will be independent of other storage and disposal systems. The operation of those will be subject to appropriate reviews to avoid escapes.

Art. 54. The limits for the emission of radioactive waste to the environment must be such that the concentrations of radionuclide activity in them and the doses likely to be received by the population to which they are potentially affect the lowest possible taking into account social and economic factors. Those levels shall always be lower than the limits specified in Appendices II and III of this Regulation respectively.

Art. 55. Any disposal of waste and radioactive waste into the environment shall require express administrative authorisation and shall be carried out under the conditions specified in that authorisation.

For this purpose, the applicant for the authorisation shall attach appropriate studies in each case concerning the discharge of radioactive tributaries into the environment and the capacity to receive radioactive pollutants from the area in question. function of its characteristics.

Art. 56. In order to ensure that the limits specified in Appendices II and III to this Regulation are not reached in the relevant administrative authorisations, the limits and conditions for the emission of radioactive tributaries shall be established on the basis of characteristics of the installation or activity in question. In addition, the total activity of the radioactive tributaries to be evacuated per year may be limited.

Art. 57. The storage of radioactive waste and waste must be carried out by confining them to vessels whose characteristics provide sufficient protection against non-ionizing radiation taking into account the conditions of the place of storage and possible dispersion or leakage of radioactive material.

Art. 58. Containers containing radioactive waste or radioactive waste shall be properly marked.

A duplicate record shall also be kept in two separate locations in which the most relevant physical-chemical data of content and at least the maximum values of the content of the data are to be recorded for each container. the level of radiation in contact and one meter away from the surface as well as the date of the last measurement and the possible activity.

TITLE VI

Inspection

Art. 59. All the activities referred to in Article 2. This Regulation shall be subject to an inspection regime from the point of view of the protection against ionising radiation. The inspection shall be carried out by optional staff officially designated by the Nuclear Safety Board without prejudice to the specific powers of other Departments or authorities. The persons responsible for the inspection shall be considered as agents of the authority for the purposes indicated in the Criminal Code in respect of the exercise of their duties.

Art. 60. Inspectors shall verify compliance with the provisions of this Regulation and shall in particular ensure that the limits laid down for persons professionally exposed by members of the public and the population as a whole are not exceeded. The inspectors shall also verify compliance with the specifications laid down by the Administration in the relevant regulatory authorisations.

Art. 61. The holder of an activity falling within the scope of this Regulation shall be obliged to:

by facilitating access to the inspectors to the places deemed necessary for the performance of their work.

b) Facilitate the installation of equipment or instrumentation that is required to perform the necessary tests and checks.

c) Make available to the inspectors the information, documentation, equipment and existing elements that are accurate for the performance of their mission.

d) Allow inspectors to take sufficient samples to perform the relevant tests and checks. At the request of the holder of the activity, a duly sealed and marked sample shall be allowed to be held.

Art. 62. The inspectors shall be entitled to require the immediate suspension of the work or activities carried out without observing the provisions of this Regulation, involving in the judgment of the inspector manifest danger to persons and property. Such actions shall be recorded in the minutes with the necessary details.

TITLE VII

Sanctions

Art. 63. Infringements of the provisions of this Regulation shall be sanctioned in accordance with Articles 91 et seq. of Law No 25/1964 of 29 April and in Article 2 (d) and the second provision of the Law. 15/1980 of 29 April by the appropriate administrative bodies.

2. Infringements of the provisions of this Regulation are classified as serious and very serious.

2.1 Are considered minor infractions

(a) Do not take the necessary steps to ensure that the number of people exposed and the doses received are as low as possible.

b) Not to archive the results of radioactive surveillance of workplaces.

c) Do not have updated the medical protocol for each professionally exposed person belonging to the installation template.

d) Do not have adequate signage in areas considered to be monitored or there is no personal regulation in their entry.

e) Do not archive the medical protocol without due review.

I) Do not make estimates of doses to the public with the required frequency or not to archive] calculations leading to the same.

g) Do not have updated the recorded or stored radioactivity data record.

2.2. Serious violations are considered:

(a) Allow activities to be carried out by persons covered by the prohibition laid down in Article 10 of this Regulation.

(b) Not to record the dose received as a result of planned special operations.

c) Not to report exceptional exposures to the medical services Conse jo de Seguridad Nuclear or the interested party.

(d) Not counting on the assumptions so determined with a Service or Technical Unit for the Protection against ionising radiations

e) Do not report and instruct professionally exposed personnel

f) Do not properly classify professionally exposed personnel

(g) Not to carry out the necessary surveillance to determine at least the maximum levels of radiation and pollution at workplaces located in a controlled or controlled area.

h) Do not have adequate monitoring of the doses that may be received by the public.

i) Do not have adequate signage in areas considered as controlled or there is no personal regulation in their entry.

(j) Not having adequate instrumentation to determine possible contamination at the exit of areas where there is a risk of contamination.

(k) Not to possess the equipment and instrumentation in radiation protection required and not to force its use to the professional exposed when the Service or Technical Unit of Protection so requires.

l) Carry out discharges of waste or radioactive waste that violate the limits of the emission conditions imposed.

m) Do not provide the worker with the required time history for the required time.

2.3. Very serious violations are considered:

(a) Allow minors of sixteen years or persons declared unfit as professionally exposed to remain in places where they may be exposed to ionising radiation.

b) Expose women in a position to procreate or under eighteen years of age in planned special operations.

(c) Exede the dose limits indicated in Appendix II or those imposed by the Nuclear Safety Board on the operating specifications. Doses produced by exceptional exposures or involuntary or haphazard accidents are excluded

(d) Give employment to personnel from another nuclear or radioactive facility or who has carried out work with ionising radiation without requiring an updated dose history and medical protocol.

e) Not to complete the dosimetric history of people who have worked at the facility as professionally exposed.

f) Do not have the medical protocol of the staff of your template

g) Prevent. Hide or obstruct the missions of the Inspection of the Nuclear Security Council.

2.4. Graduation from the fouls

The offences mentioned above will be graded the effects of their corresponding penalty on minimum degree and maximum degree infractions according to the results appreciated by the Security Council on 1 January. or.

2.4.1 The minor infractions will be sanctioned with a fine of at least 25,000 to 200,000 pesetas; in its average grade of 200,001 to 500,000 pesetas and in its maximum grade of 500,001 to 1,000,000 pesetas.

2.4.2. Serious infringements shall be punishable by a fine of at least 1,000,081 to 2,500,000 pesetas; in the middle grade of the pesetas to 5,000,000 pesetas and to a maximum of 5,000,001 to 7,000,080 pesetas.

2.4.3. Very serious infringements shall be punishable by a fine of at least 7,000,001 to 10,000,000 pesetas; in their average grade of 10,000,001 to 25,000,000 pesetas and to a maximum of 25,000,001 to 100,000 000 pesetas.

2.4.4. The recidivism in the infringement may result in a doubling of the fines previously provided for.

3. It is up to the Nuclear Safety Council in accordance with the provisions of Law 15/1980 of 22 April to propose the imposition of the penalties for infringements of the provisions of this Regulation, as well as for the annulment of the of licences. Permissions or authorizations.

ADDITIONAL DISPOSITION

The transport of radioactive material in everything not expressly regulated by its specific legislation shall be governed by the provisions of this Regulation as soon as it is applied to it and supplemented by technical standards. of protection contained in the last edition of the Regulation for the Non-Risk Transport of Radioactive Materials developed by the International Atomic Energy Agency.

APPENDIX I

Definitions

Activity A)

It is the number of spontaneous nuclear transformations that occur in an amount of a radionuclide in the time unit. The unit of activity in the International System is the Becquerel (Bq) which corresponds to a disintegration/second.

Due to its great diffusion in this Regulation, the activity in curios is also expressed.

I Ci = 3.7 X 10 10 Bq

1 Bq = 2 7027 X 10-ll Ci

radioactive contamination

It is the undesirable presence of radioactive substances in a matter a surface or any medium or a person for radioactive substances

In the particular case of the human organism, this contamination may be external or skin when deposited on the outer and inner surface when the radionuclides have penetrated the organism by any means (inhalation). percutaneous ingestion etc.).

Absorbed dose

It is the ratio between the energy communicated by the ionizing radiation to the matter in a volume element and the mass of matter contained in said volume. The unit of absorbed dose in the International System is the Gray equivalent to 1 J/kg.

Due to its wide diffusion in this Regulation, the dose absorbed in rads is also expressed.

1 rad = 10-Gy

1 Gy = 100 rads

Genetically significant annual dose

For a population it is equal to the average of the individual annual doses received in the gonads. Each individual dose will be weighted by one factor taking into account the likely number of children who may be fathered after exposure.

Integrated internal dose.

It is the dose that will be received in fifty years in an organ or tissue, as a consequence of the incorporation of one or several radionuclides.

Effective Dose (He)

It is the weighted sum of the (equivalent) doses received in] different organs. Its value is given by the expression

Formula omitted.

where Wi is the weighting factor for the organ and which represents the proportion of stochastic risk resulting from tissue irradiation with respect to total risk when the whole organism is irradiated uniformly, and H is the equivalent dose received by the fabric . Wi/son weight factor values:

Wt * Fabrics *

Gonadas * 0.25 *

Mom * 0.12 *

Bone Marrow * 0.12 *

Lung * 0.12 *

Thyroid * 0.03 *

Bone (surface) * 0.03 *

Rest (five organs) * 0.30 *

NOTE

The assessment of the rest of the body with a weighting factor of 0 30 is the result of multiplying the weighting factor assigned to each of the other organs (0.06) by a maximum of five organs that may be involved in a localised exhibition.

Equivalent dose (H)

It is the product of the dose absorbed by a number of factors (quality factor and modifying factors) that take into account the characteristics of the radiation and the distribution of the radionuclides when the word is used. is always the equivalent dose.

The equivalent dose unit in the International System is the Sievert (Sv) equivalent to 1 J/kilogram.

The equivalent dose in rems is also expressed in this Regulation due to its wide spread.

1 rem = 10-2 Sv

1 Sv = 100 rems

Genetic Dose

It is the dose that if it was actually received by each individual from conception to the average age of procreation (thirty years) would imply the same genetic burden for the population as a whole than the actual doses. received by the individuals of this population.

Stochastic biological effects

They are the ones that are characterized by a dose-effect relationship of a probabilistic nature. Properties of these stochastic biological effects are the lack of threshold doses and will always be severe once produced

Non-stochastic biological effects.

They are the ones that are characterized by a deterministic causal relationship between the dose and the effect. They are only manifested when the dose received reaches or exceeds a certain threshold dose, its severity depends on the dose received.

Exposure, irradiation

It is the action and effect of subjecting people to ionizing radiation.

Continuous exposure, continuous irradiation.

It is the permanent external exposure whose intensity can vary with the time or internal exposure resulting from a permanent incorporation whose importance can vary in time.

External exposure, external irradiation

It is the body's exposure to sources of radiation outside it.

Global exposure, global irradiation.

It is the exposure considered as homogeneous in the entire body.

Internal exposure, internal irradiation.

Exposure of the organism to sources of internal radiation to it.

Partial exposure, partial irradiation.

It is the exposure that affects essentially a part of the organism or one or more organs or tissues or exposure of the whole body considered as non-homogeneous.

Total exposure, total irradiation

Is the sum of the external and internal exposures.

Unique exposure, single irradiation

It is the external exposure of short duration or internal exposure resulting from the incorporation of radionuclides in a short time.

Natural radioactive background

It is constituted by the set of ionising radiations that come from natural terrestrial or cosmic sources.

Incorporation

This is the amount of activity taken by the outside body.

Dose limit

These are the limits set in this Regulation for the dose resulting from the exposure of professionally exposed persons, apprentices and students and members of the public, not taking into account the dose resulting from the natural radioactive background and the exposure suffered as a result of medical examinations and treatments. The dose limits are applied to the sum of the dose received by external exposure during the period considered and the integrated internal dose resulting from the incorporation of radionuclides during the same period.

Activity concentration derived limit

It is the maximum value of the concentration of activity of a radionuclide to be inhaled by the standard man during a two-thousand-hour working year or ingested throughout the calendar year, giving rise to the corresponding limits of annual equivalent doses.

Annual onboarding limit

It is the maximum activity of a radionuclide that can be incorporated annually into the human organism.

Ionising radiations

It is radiation composed of photons or particles capable of determining the formation of ions directly or indirectly.

Radiotoxicity

It is the toxicity due to ionising radiations emitted by a built-in radionuclide and its descendants-the radiotoxicity depends not only on its radioactive characteristics, but also on its physical-chemical or also of the metabolism of the element in the organism or in a certain organ.

Collective Effective Dose

It is the integral of the effective doses caused by an installation or activity on the population affected by it, and it is defined by the expression:

Formula omitted.

This magnitude is usable for optimization procedures and is expressed in Sv-man

Collective Dose

The collective dose (s) for a population or group is given by the summation

Formula omitted.

APPENDIX II

Dose limits

The limits set in this appendix shall be applied to the sum of the equivalent doses resulting from the external exposure for one year and at the equivalent dose for the entire life resulting from the incorporation of radionuclides. during that year. In the case of occupational exposure, the equivalent dose resulting from incorporation for one year shall be considered as the integrated internal dose.

The dose limits correspond to the values that should never be exceeded, and lower limits can be established according to the optimization and justification studies.

1. Annual dose limits for professionally exposed persons.

1.1. Annual limit for the case of total and homogeneous exposure of the body.-The annual dose limit for the whole body, for any period of 12 consecutive months, is 50 mSv (5 rems).

1.2. Annual limits for the case of partial exposure of the body.-In the case of total non-homogeneous or partial exposure of the body:

1.2.1. The annual effective dose limit, for any period of two consecutive months, is 50 mSv (5 rems).

12 2. The annual dose limit for the lens is 100 mSv (30 rems).

The annual dose limit for the skin is 500 mSv (so rems). When the exposure results from skin radioactive contamination, this limit applies to the average dose on a surface of 100 square centimeters in the region receiving the highest dose.

The annual dose limit for hands, forearms, feet, and ankles is 500 mSv (so rems).

The annual dose limit for any other organ or tissue, considered individually, is 500 mSv (50 rems).

13. Special limits.

1.3.1. Under the age of 18.-In the exceptional case that a person, under the age of 18 and over 16, is at risk of exposure to ionising radiation as an apprentice or student, the annual dose limits are three. we say of the annual dose limits for professionally exposed persons.

1.3.2. Women.

-For women with the ability to procreate, the dose in the abdomen should not exceed 13 mSv (1.3 rems) in one trimester

-For pregnant women, the working conditions must be such that the dose to the fetus from the diagnosis of pregnancy to the end of the pregnancy does not exceed 10 ms, (1 rem). In general, this limit is ensured by placing the woman in the working conditions of the professionally exposed, belonging to category B.

1.4. Planned special operations.

1.4.1. During the performance of any special operation. Planned involving only external exposure, no exposed person will receive a dose that exceeds in one year twice the annual dose limits set in this appendix.

When this operation involves only internal contamination, the activity of the incorporated radionuclides shall not be stopped in one year at the same time as the fixed entry limits, by inhalation fixed, in Tables I and II of the Appendix III.

In case of concurrency of both risks, for the calculation of the equivalent dose, the weighted participation of each of them must be taken into account.

1.4.2. The doses received as a result of this type of operation, throughout the life of the individual, will not exceed the five-fold of the annual dose limit.

In such operations, the smallest possible number of individuals will be sought, and the following conditions must be met:

-That for the purposes of these operations, and as a consequence of its realization, the professionally exposed person is considered as category A.

-That the professionally exposed person has not received in the twelve months

above a dose higher than the annual dose limit.

-That the professionally exposed person has not previously received doses higher than five times the annual dose limit as a result of planned or exceptional special operations.

Exceeding the dose limits as a result of a planned special operation will not be a reason to exclude the professionally exposed person from their usual occupations, the conditions Subsequent work must be subject to the discretion of the specialised doctor.

2. Annual dose limits for members of the public.

2.1. Annual limit for the case of total homogeneous exposure of the body-The annual dose limit for the whole body, for any period of 12 consecutive months, is 5 mSv (0.5 rems).

2.2. Annual limits for the case of total non-homogeneous or partial exposure of the body.

2.2.1. The annual effective dose limit, for any period of 12 consecutive months, is 50 mSv (0.5 rems).

2.2.2. The annual dose limit for the lens is 30m/sV (3 rems)

The annual dose limit for the skin is 50 mSv (5 rems). When exposure results from skin radioactive contamination, this limit applies to the average dose on a surface of 100 square centimeters, in the region receiving the highest dose.

The annual limit for hands, forearms, feet, and ankles is 50 mSv (5 rems).

The annual dose limit for any other organ or tissue, considered individually, is 50 mSv (5 rems).

APPENDIX III

1. Annual incorporation limits by inhalation and limits derived from the concentration of radionuclides in the air inhaled for the professionally exposed persons and limits of the annual corporation by inhalation and by ingestion for the members of the public.

The values given in Tables I and II correspond to 8 the annual dose limits set out in Appendix ll for professionally exposed persons and members of the public.

2. Mixture of radionuclides.

(a) If the composition of the mixture is unknown, but the presence of certain radionuclides may be excluded with certainty, the lower of the limits set for radionuclides that may be present shall be used.

(b) If the detailed composition of the mixture is unknown but the radionuclides of the mixture have been identified, the lower of the limits set for the radionuclides present shall be used.

(c) If the concentration and toxicity of one of the radionuclides predominates in the mixture, the annual incorporation limits fixed for those radionuclides shall be used.

d) If the composition of the radionuclide mixture is known, one of the following conditions must be met:

Formula omitted.

Tables omitted.

APPENDIX IV

Zoning signage

The risk of irradiation shall be marked by using its international symbol, a symbol marked by a rectangular orla of the same color of the symbol and of the same width as the diameter of the inner circumference of the symbol. symbol.

1. Areas with rolling.

In the controlled areas, the clover will be green on a white background.

When there is only risk of external irradiation, the anterior clover bordered from radial tips will be used.

If there is a risk of contamination and the risk of external irradiation is negligible, the previous clover will be used in dotted field.

When there is a joint risk of contamination and irradiation, the anterior clover bordered from radial points in dotted field shall be used.

These signals will be placed in a visible manner at the entrance and in the significant locations of these controlled areas.

1.1. Limited stay area.-This is where there is a risk of receiving a higher dose than the annual dose limits set out in Appendix II.

In the areas of limited permanence, this clover will be yellow on white background.

When there is only risk of external irradiation, the anterior clover bordered from radial tips will be used.

If there is a risk of contamination and the risk of external irradiation is negligible, the previous clover will be used in dotted field.

When there is a risk of contamination and irradiation together, the anterior clover bordered from radial points in dotted field shall be used.

These signals will be clearly visible at the entrance and in the significant locations of these limited-stay zones.

1.2. Prohibited access area.-This is where there is a risk of receiving at a single exposure dose higher than the annual dose limits set out in Appendix II.

In the forbidden access zones, this clover will be red on white background.

When there is only risk of external irradiation, the anterior clover bordered from radial tips will be used.

If there is a risk of contamination, and the risk of external irradiation is negligible, the previous clover in dotted field will be used

When there is a joint risk of contamination and irradiation, the anterior clover bordered from radial points in dotted field shall be used.

These signals shall be placed in a visible manner at the entrance and in the significant places of such prohibited access zones.

2. Monitored areas.

In the ngiled areas the clover will be bluish gray on white background.

When there is only the risk of external irradiation, the anterior clover bordered from radial tips will be used.

If there is a risk of contamination and the risk of irradiation is negligible, the previous clover will be used but in dotted field

When there is a joint risk of contamination and external irradiation, the anterior clover bordered from radial points in dotted field will be used.

These signals will be placed in visible form at the entrance and in the significant locations of these monitored areas.

3. For all types of areas, the above signs shall be supplemented at the top with a legend indicative of the type of area, and at the bottom of the risk type.

4. Where the boundaries of an area are to be marked on a temporary basis, fences, articulated metal bars or supports for passing ropes, tape chains, etc., shall be used which shall have the colour corresponding to the area where they are treat.

5. In places of access between adjacent areas of different characteristics, the corresponding limits may be marked on the ground by lines clearly visible with the colours correlated to the areas concerned. Such signalling may be completed with illumination of the colour appropriate to the areas concerned.