COMMISSION OF THE EUROPEAN COMMUNITIES 
C0M(93) 349 final 
Brussels, 20 July 1993 
Amended proposal for a 
COUNCIL DIRECTIVE 
LAYING DOWN THE BASIC SAFETY STANDARDS 
FOR. THE PROTECTION OF THE HEALTH 
OF WORKERS AND THE GENERAL PUBLIC 
AGAINST THE DANGERS ARISING FROM I ON IZING RAD I AT I ON 
Jsp 
(presented by the Commission pursuant to Article 149(3) 
of the EEC-Treaty) 
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EXPLANATORY MEMORANDUM 
Article 2(b) of the Euratom Treaty provides for the establishment 
within the Community of uniform basic safety standards to protect 
the health of workers and of the general public against the dangers 
of ionizing radiation. These basic safety standards were first 
adopted in 1959 by means of a Council Directive*1* and have 
subsequently been amended on several occasions to take account of 
developments in scientific knowledge in the field of radiation 
protection. The version of the basic standards currently in force 
dates back to 1980, with amendments mainly affecting their 
technical annexes being made in 1984(2). 
(1) Directives laying down the basic safety standards for the health 
protection of the general public and workers against the dangers of 
ionizing radiation (0J of 20.2.1959). 
(2) Council Directive 80/836/EURATOM of 15.7.1980 amending the 
Directives laying down the basic safety standards for the health 
protection of the general public and workers against the dangers of 
ionizing radiation (0J L 246 of 17.9.1980, p.1). 
Council Directive 84/467/EURATOM of 3.9.1984 amending Directive 
80/836/Euratom as regards the basic safety standards for the health 
protection of the general public and workers against the dangers of 
ionizing radiation (0J L 265 of 5.10.1984. p. 4). 
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2. Until 1986, the only legal instruments adopted by the .Community in 
the radiation protection field, based on Article 31 of the EURATOM 
Treaty, were these basic safety standards together with a 
Directive laying down basic measures for the protection of persons 
undergoing medical examination or treatment*3*. Since then, 
following the accident at Chernobyl, a number of additional 
measures have been introduced to reinforce and complement existing 
Community provisions for the protection of health against ionizing 
radiâtion<4>. 
(3) Council Directive 84/466/EURATOM of 3.9.1984 laying down basic 
measures for the radiation protection of persons undergoing medical 
examination or treatment (OJ L 265 of 5.10.1984, p.1). 
(4) Council Decision 87/600/EURATOM of 14.12.1987 on Community 
arrangements for the early exchange of information in the event of 
a radiological emergency (OJ L 371 of 30.12.1987, p.76). 
Council Directive 89/618/EURATOM of 27.11.1989 on informing the 
general public about health protection measures to be applied and 
steps to be taken in the event of a radiological emergency (OJ L 
357 of 7.12.1989, p. 31). 
Council Directive 90/641/EURATOM of 4.12.1990 on the operational 
protection of outside workers exposed to the risk of ionizing 
radiation during their activities in controlled areas (0J L 349 of 
13.12.1990, p. 21). 
Council Directive 92/3/EURATOM of 3.2.1992 on the supervision and 
control of shipments of radioactive waste between Member States and 
into and out of the Community (0J L 35 of 12.2.1992). 
Council Regulation 87/3954/EURATOM of 22.12.1987 laying down 
maximum permitted levels of radioactive contamination of foodstuffs 
and of feedingstuffs following a nuclear accident or any other case 
of radiological emergency (OJ L 371 of 30.12.1987, p. 11). 
- 4 -
(4 continued) 
Commission Regulation 89/944/EURAT0M of 12 April 1989, laying 
down maximum permitted levels of radioactive contamination in 
minor foodstuffs following a nuclear accident or any other case 
of radiological emergency (OJ L 101 of 13.4.1989, p. 17). 
Council Regulation 89/2218/EURAT0M of 18.7.1989 amending 
Regulation 87/3954/EURATOM laying down maximum permitted levels 
of radioactive contamination of foodstuffs and of feedingstuffs 
following a nuclear accident or any other case of radiological 
emergency (OJ L 211 of 22.7.1989, p.1). 
Council Regulation 89/2219/EEC of 18.7.1989 on the special 
conditions for exporting foodstuffs and feedingstuffs following 
a nuclear accident or any other case of radiological emergency 
(OJ L 211 of 22.7.1989, p.4). 
Council Regulation 90/737/EEC of 22 March 1990 on the 
conditions governing imports of agricultural products 
originating in third countries following the accident at the 
Chernobyl nuclear power station (OJ L 82 of 29.3.1990, p. 1). 
Commission Regulation 90/770/EURATOM of 29 March 1990 laying 
down maximum permitted levels of radioactive contamination of 
feedingstuffs following a nuclear accident or any other case of 
radiological emergency (0J L 83 of 30.3.1990, p. 78). 
Council Regulation 93/1493/EURATOM of 8 June 1993 on shipments 
of radioactive substances between Member States (0J L 148 of 
19.6.1993, p. 1). 
Commission Regulation 93/1518/EEC of 21 June 1993 (replacing 
C.R. 92/598/EEC of 9 March 1992) establishing a list of 
products excluded from the application of Council Regulation 
90/737/EEC on the conditions governing imports of agricultural 
products originating in third countries following the accident 
4t the Chernobyl nuclear power station (0J L 150 of 22.6.1993, 
p. 30). 
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There is also a Commission Recommendation issued in 1990 which 
draws the attention of the Member States to the risks of exposure 
to radon inside dwelIings*5>. 
(5) Commission Recommendation 90/143/EURATOM of 21.2.1990 on the 
protection of the public against indoor exposure to radon (OJ L 80 
of 27.3.1990, p. 26). 
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3. The Community's basic safety standards have always taken into 
account to a large extent the ICRP's recommendations, which 
represent the state-of-the-art as regards radiation protection and 
also form the basis for the recommendations of other international 
organisations with responsibilities in this area. The ICRP 
published its latest recommendations at the beginning of 1991 in 
its Publication 60 (replacing Publication 26, which appeared in 
1977). The Commission, for its part, has reviewed the provisions in 
the existing Directive in the light not only of the ICRP's 
recommendations but also of the experience gained in implementing 
those provisions. The revision is, moreover, in line with the 
undertaking made to the Council in 1987 at the time of the adoption 
of Regulation 87/3954 (see footnote 4). While the basic structure 
of the existing Directive has been retained, the following aims 
have been pursued in the revision: 
to provide radiation protection based on the most up-to-date 
scientific Knowledge, which should be utilised to the benefit 
of workers and the general public; 
to provide a sound technical and scientific basis and a uniform 
approach to radiation protection, and to ensure technical 
consistency with the recommendations of international 
organisations, such as IAEA, NEA-OECD, WHO and ILO; 
to update the provisions of the existing Directive, bearing in 
mind the basic structure on which the regulations in the Member 
States are modelled; 
- with a view to the completion of the Single Market, to preserve 
a high degree of harmonisation in the radiation protection 
measures provided for under the Euratom Treaty; 
to strengthen the provisions on control of radioactive 
materials in accordance with the undertaking made to the 
Council in 1992, at the time of the adoption of Directive 
92/3/EURATOM on the supervision and control of shipment of 
radioactive waste between Member States and into and out of the 
Commun i t y. 
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4. Taking into account all these factors, the most - important 
amendments contained in the proposal for a new Directive are as 
fol lows: 
use of the definitions, quantities and units as well as the 
radiation and tissue weighting factors set out in the latest 
ICRP recommendations; 
the inclusion of more restrictive dose limits taken from the 
latest ICRP recommendations, which take account of the most 
recent estimates of cancer risk associated with exposure to 
ionizing radiation, together with the complex concept of health 
detriment; 
the introduction of provisions concerning radiation protection 
in certain cases of occupational exposure to natural radiation 
sources ; 
the prohibition of certain unjustified uses of radioactivity; 
expansion of the provisions concerning protective measures to 
be taken in the event of a radiological accident; 
introduction of the Mdose constraint" concept in relation to a 
given source; 
changes to the radioactivity levels associated with the 
authorisation/reporting provisions laid down In the Directive; 
5. The impact of the proposed modifications on business is expected to 
be limited, as a consequence of their evolutive character with 
respect. to an existing Directive. The introduction of provisions 
concerning radiation protection in certain cases of occupational 
exposure to natural radiation sources is made in a flexible way, 
especially to allow their progressive application. 
6. The following section consists of comments on the various Titles in 
the proposed new Directive, explaining its rationale, scope and 
aims. 
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6.1 Compared with the existing Directive, the- scope of the proposed 
Directive is to be widened (Title II). It now covers' expI icitly 
the placing on the market and the exportation of radioactive 
substances as well as the operation of electrical equipment 
emitting ionizing radiation and containing components operating at' 
a potential difference of more than 5 kV. It also covers exposure 
to natural radiation sources at work. 
6.2 The system of reporting and prior authorisation of practices (Title 
III) has been modified: the requirements for the application of 
this system have been laid down more explicitly than in the 
existing Directive, and in particular, the conditions in which 
these requirements may be waived have been thoroughly reconsidered. 
This will contribute to a further harmonisation of authorisation 
procedures within the Community, which will also have an impact on 
the achievement of the Community's internal market. 
6.3 Title IV maintains the three basic principles of radiation 
protection (Justification, optimisation (ALARA) and dose 
limitation), specifying that the dose limits shall not apply to 
medical, accidental or emergency exposures or, in general, to 
exposures from natural radiation sources at work. 
As regards the dose limits, the following steps have been taken: 
- for workers, the new limit on effective dose is 20 mSv per year 
averaged over five consecutive years (100 mSv in five years) 
with the further provision that the effective dose shall not 
exceed 50 mSv in any single year). 
for members of the public, the new limit for the effective dose 
is 1 mSv per year. However, in special circumstances, a higher 
value may be authorised in a single year, provided that the 
average over five consecutive years does not exceed 1 mSv per 
year. 
i 
- Member States will be allowed to introduce exceptional 
derogations from the dose limits in accordance with the 
procedure laid down in Title X. 
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As regards-the protection of pregnant women exposed at work, the 
relevant provisions have been modified in order to protect the 
foetus as if it were a member of the public. 
In the case of nursing mothers, the competent authorities must, if 
necessary, establish dose constraints so as to provide the child 
with better protection against radioactive contamination. 
6.4 Title V deals with methods used for the calculation of 
effective dose and refers to Annexes II and III. 
6.5 In the proposed Directive, as in the existing version, the 
fundamental principles governing operational protection of 
exposed workers are set out in Title VI. They are also 
applicable to apprentices and students, since these two groups 
may engage in activities involving exposure. Compared with the 
existing Directive, the classification of areas (controlled and 
supervised) according to the level of risk associated with them 
has been preserved, whilst the criteria for making this 
classification have been simplified and additional 
responsibilities have been assigned to the employer/operator. 
As regards the classification of exposed workers into category 
A and category B workers, this is no longer found in the latest 
ICRP recommendations but the Commission's proposal has retained 
it since it has proved its value over a period of several 
years, particularly where the organisation of radiation 
protection is concerned. 
6.6 There are special provisions in the proposed Directive (Title 
VII) concerning exposure to natural radiation sources at work. 
Title VII requires that the Member States should first carry 
out surveys to identify in which areas of their territory and 
for which practices and working conditions workers are exposed 
in a significant manner to gamma radiation or. radon from 
natural sources. On the basis of the results of these surveys, 
the measures described in the new Directive must be taken. As 
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examples of activities to be the object of such surveys, and as 
a result of which measures may need to be taken, the proposal 
mentions operations in mines or other underground workplaces, 
operations with materials containing significant traces of 
natural radionuclides, and the operation of Jet aircraft in' 
flight. 
6.7 Title VIII sets out the fundamental principles governing 
operational protection of the population in normal 
circumstances. Among other things, this Title provides for the 
establishment in the Member States of a system of inspection to 
keep under review the radiation protection of the population 
and check compliance with the national regulations implementing 
the new Directive. In this connection, a number of obligations 
are placed on the operator/employer. 
6.8 Title IX represents an expansion of its earlier counterpart, 
owing to the experience gained from the accident at Chernobyl. 
It now covers potential, accidental and emergency exposures. 
The Member States are required to consider the development of 
all radiological emergencies on their territory before, during 
and after the event. 
The Member States must also establish relations with other 
Member States and with third countries to ensure that they are 
better prepared for any«eventuality and that measures taken to 
deal with any emergency are harmonised. 
6.9 Title X contains the final provisions, the main points of which 
are as fol lows: 
- A procedure has been laid down for modifying the lists of 
practices included in Articles 3 and 4 and for allowing 
exceptional derogations from the dose limits. 
- Each Member State shall report to the Commission every two 
years on the implementation of the Directive, so enabling 
the Commission to prepare reports for the European 
Parliament, the Council and the Economic and Social 
Committee; 
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Member States must transpose the Directive into national 
law within the deadline specified; 
the above deadline is meant to be a single time'limit, any 
time limits appearing in the previous Directives being 
superseded. 
6.10 Annexes 
The proposal for a Directive refers to values set out in 
its three annexes, which have been revised in line with the 
provisions of the proposed Directive. 
As regards Annex I, in the existing Directive the 
exemptions from the system of reporting/authorisation have 
been defined in terms of total activity (values ranging 
between 5 x 103 and 5 x 106 Bq spread over four 
radiotoxicity categories, as set out in Annex I to the 
existing Directive) and in terms of mass specific activity 
(100 Bq/g for artificial radionuclides and 500 Bq/g for 
solid natural radionuclides). It was recognised that this 
type of classification did not fully reflect the potential 
hazard to workers and to members of the public associated 
with the use, misuse and disposal of radioactive 
substances. Consequently, the revised version of Annex I 
sets out nuclide-specific activity levels and mass specific 
activity values, on a provisional basis at this stags. 
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Annex II .includes the radiation and tissue weighting 
factors in accordance with the latest recommendations of 
the ICRP. However, re-examination of relationships between 
dosimetric quantities and progress in radiation research' 
may lead to modification of these values in the future. 
The derived limits which appeared in .Annex III to the 
existing Directive need to be revised to take account of 
the new tissue weighting factors and new metabolic data and 
to achieve greater consistency with the proposed dose 
limits. Nevertheless, since a re-assessment of metabolic 
models is in progress, and it would not be appropriate to 
suspend the revision of the Basic Standards, nor to embark 
upon a revision of the tables at this moment. Annex III 
indicates provisionally the methods to be applied. 

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Amended proposal for a 
COUNCIL DIRECTIVE 
laying down the basic safety standards for the protection of the 
health of workers and the general public against the 
dangers arising from ionizing radiation 
THE COUNCIL OF THE EUROPEAN COMMUNITIES 
Having regard to the Treaty establishing the European Atomic Energy 
Community, and. in particular Articles 31 and 32 thereof, 
Having regard to the proposal from the Commission, drawn up after 
obtaining the opinion of a group of persons appointed by the Scientific 
and Technical Committee from among scientific experts in the Member 
States, 
Having regard to the opinion of the European Parliaments1^, 
Having regard to the opinion of the Economic and Social Committee*2*, 
Whereas the Treaty provides in Article 2b that uniform basic safety 
standards to protect the health of workers and of the general public 
shaII be laid down ; 
(1) O.J. n* ... 
(2) O.J. n* C 108, 19.4.1993, p. 48 
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Whereas Article 30 of the Treaty defines the basic standards for the 
protection of the health of workers and the general public"against the 
dangers arising from ionizing radiation as: 
(a) maximum permissible doses compatible with adequate safety; 
(b) maximum permissible levels of exposure and contamination; 
(c) the fundamental principles governing the health surveillance of 
workers; 
- 15 -
Whereas each Member State is required by Article 33 to lay down the 
appropriate provisions,- whether by legislation, regulation or 
administrative action, to ensure compliance with the basic standards 
which have been established and shall take the necessary measures with 
regard to teaching, education and vocational training; 
Whereas in order to perform its task the Community laid down basic 
standards for the first time in 1959 pursuant to Art. 218 of the Treaty 
(3)f and has since revised*4) 
(3) O.J. n" 11, 20.2.1959, p. 211/59 
(4) - Council Directive of 5.3.1962 (O.J. of 6.7.1962); 
Council Directive 66/45/EURATOM of 27.10.1966 (O.J. of 
26.11.1966); 
Council Directive 76/579/EURATOM of 1.6.1976 (O.J. L-187 of 
12.7.1976); 
Council Directive 79/343/EURATOM of 27.3.1979 (O.J. L-83 of 
3.4.1979); 
Council Directive 80/836/EURATOM of 15.7.1980 (O.J. L-246 of 
17.9.1980); 
Council Directive 84/467/EURATOM of 3.9.1984 (O.J. L-265 of 
5.10.1984). 
16 -
and supplemented them*5*; 
Whereas the development of scientific knowledge concerning radiation 
protection makes it necessary to revise the basic standards and to lay 
them down in a new legal instrument, replacing Directives 
76/579/Euratom and 80/836/Euratom; 
(5) - Directive 84/466/EURATOM of 3.9.1984 laying down basic measures 
for radiation protection of persons undergoing medical 
examination or treatment (O.J. L-265 of 5.10.84); 
- Directive 89/618/EURATOM of 27.11.1989 on informing the general 
public about health protection measures to be applied and steps 
to be taken in the event of a radiological emergency (O.J. L-
357 of 7.12.89); 
Directive 90/641/EURATOM of 4.12.1990 on the operational 
protection of outside workers exposed to the risk of ionizing 
radiation during their activities in controlled aresas (O.J. L-
349 Of 13.12.90); 
Regulation 87/3954/EURATOM of 22.12.1987 laying down maximum 
permitted levels of radioactive contamination of foodstuffs and 
feedingstuffs following a nuclear accident or any other case of 
radiological emergency (O.J. L-371 of 30.12.87); 
- Directive 92/3/EURATOM of 3.2.1992 on the supervision and 
control of shipments of radioactive waste between Member States 
and into and out of the Community (O.J. L-35 of 12.2.92); 
Regulation 93/1493/EURATOM of 8.6.1993 on shipments of 
radioactive substances between Member States (O.J. L-148 of 
19.6.93); 
Recommendation 90/143/EURATOM of 21.2.1990 on the protection of 
the public against indoor exposure to radon (O.J. L-80 of 
27.3.90); 
Council Decision 87/600/EURATOM of 14.12.1987 on Community 
arrangements for the early exchange of information in the event 
of a radiological emergency (O.J. L-371 of 30.12.87). 
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Whereas this development has given rise to a reappraisal of the risks 
involved in the usé of ionizing radiation, to the recognition of the 
need to reinforce the protection of health at the workplace against the 
dangers arising from exposure to natural radiation sources and to an 
increased awareness of the need to provide for precautionary measures 
to be applied in the event of an accident; 
Whereas the basic standards to be laid down within the Community have 
to take due account of the requirements of the nuclear common market as 
set out in Title Two, Chapter IX of the Treaty and the internal market 
created under the Treaty establishing the European Economic Community, 
subject to Art. 232 (2) of that Treaty; 
Whereas, in order to attain the objectives set out above, it is 
necessary to define the scope of the basic standards by including the 
placing on the market of radioactive substances, the operation of 
certain electrical equipment and exposure to natural radiation sources 
at the workplace; 
Whereas the Member States, in order to ensure compliance with the basic 
standards, are required to prohibit certain practices involving a 
hazard from ionizing radiation or, according to the degree of hazard 
involved, to submit them to a system of reporting and prior 
authorization; 
Whereas a system of radiation protection for practices should be based 
on the principles of Justification of exposure, optimisation of 
protection and dose limitation taking into account the particular 
situation of the different groups of persons exposed such as workers, 
nursing and pregnant women, apprentices, students and members of the 
public; whereas to this end limitations of doses and limits derived 
therefrom must be fixed; 
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Whereas the operational protection of exposed workers, apprentices-and 
students requires the implementation of measures at the' workplace; 
whereas these measures must include the prior evaluation of the hazard 
involved, the classification of workplaces and workers, monitoring of 
areas and working conditions as well as medical surveillance-. 
Whereas it has become apparent that workers should be protected against 
exposure to natural radiation sources at their workplace; whereas to 
this end the Member States should be required to carry out surveys to 
identify the areas, practices and working conditions where workers are 
exposed, in a significant manner, to such sources; whereas, on the 
basis of such surveys, the Member States should take the appropriate 
protective measures-. 
Whereas the operational protection of the population in normal 
circumstances requires the establishment of a system of inspection to 
keep under review the radiation protection of the population and to 
check compliance with the basic standards; 
Whereas, owing to the experience gained from the Chernobyl accident, 
the Member States should consider the development of all radiological 
emergencies on their territory before, during and after an accident and 
should take all necessary measures to reduce their consequences; 
whereas cooperation between Member States and with third countries has 
proved capable of assuring increased preparedness; 
HAS ADOPTED THIS DIRECTIVE: 
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TITLE I 
DEFINITIONS 
Article 1 
For the purpose of this Directive, the following terms have the meaning 
hereby assigned to them. 
Absorbed dose (D): the energy absorbed per unit mass 
D - de 
dm 
Where - de is the mean energy imparted by ionizing radiation to the 
matter in a volume element 
- dm is the mass of the matter in this volume element. 
in this Directive, absorbed dose denotes the dose averaged over a 
tissue or an organ. The unit for absorbed dose is the gray. 
Accelerator: apparatus or installation emitting ionizing radiation with 
an energy higher than 1 Mev. 
Accident: an unintended event that causes damage to a source or that 
results or could result in exposure of members of the public in excess 
of the appropriate intervention level or in exposure of workers above 
the appropriate dose limits. 
Accidental exposure: a fortuitous and involuntary exposure of 
individuals as a result of an accident. 
- 20 -
Activation: process through which a stable nuclide is transformed into 
a radionuclide by irradiating with particles or high-energy gamma rays 
the material in which it is contained. 
Activity(A): the activity A, of an amount of a radionuclide in a' 
particular energy state at a given time, is the quotient of dN by dt, 
where dN is the expectation value of the number of spontaneous nuclear 
transitions from that energy state in the time interval dt: 
dN 
dt 
The unit for activity is the becquerel. 
Apprent ice: a person receiving training for employment involving 
exposure to ionizing radiation and instruction within an undertaking. 
Approved medical practitioner: a medical practitioner responsible for 
the medical surveillance of workers of category A as defined in Article 
21, whose capacity to act in this respect is recognised by the 
competent authorities. 
Approved occupational health services: a body or bodies responsible for 
the radiation protection and medical surveillance of exposed workers as 
defined in Article 21 whose capacity to act in this respect is 
recognised by the competent authorities. 
Becquerel (Ba): the special name of the unit of activity. One 
becquerel is equivalent to one transition per second: 
1 Bq - 1 s -1 
- 21 -
Committed effective dose (Efjc)): the sum of the committed organ or 
tissue equivalent doses resulting from an intake, each multiplied -by 
the appropriate tissue weighting factor W_. It is defined by: 
E(x) - 2 wTHT(-c!) 
T 
In specifying E(rC). -c is given in the number of years over which the 
integration is made. The unit for committed effective dose is the 
sievert. 
Committed equivalent dose (Hyf/tr)): the integral over time (t) of the 
equivalent dose rate in tissue or organ T that will be received by an 
individual resulting from an intake. It is given by: 
h^Cx) - \ ÎLf(t)dt 
for an intake at time t0 where 
H—(t) is the relevant equivalent dose rate in organ or tissue T 
at time t 
t is the time over which the integration is performed. 
In specifying HT it), t is given in years. When is not given, a 
period of 50 years is assumed for adults and up to age 70 for children. 
The unit for committed equivalent dose is the sievert.. 
Consignee: any natural or legal person to whom a radioactive substance 
is shipped. 
- 22 -
Controlled area: an area subject to special rules for the purpose of 
protection against ionizing radiation or of preventing the spread of 
radioactive contamination, to which access is controlled and restricted 
to workers who have received appropriate instructions. 
Dose constraint: a restriction on the doses to individuals resulting 
from defined sources for the purposes of optimisation of protection. 
Dose I imits: the limits laid down in Title IV for the doses resulting 
from the exposure of workers, apprentices and students, and members of 
the public to ionizing radiation from the practices covered by this 
Directive. 
Effective dose (E): the sum of the weighted equivalent doses in all the 
tissues and organs of the body specified in Annex II from internal and 
external irradiation. It is defined by the expression: 
E «2wTHT -SwTJwR DT>R 
T T "ft 
where 
Dj R is the organ absorbed dose from radiation R, 
- WR is the radiation weighting factor and 
- Wj is the t issue weight ing factor for tissue or organ T. 
The appropriate w-j- and WR values are specified in Annex I I .The unit 
for effective dose is the sievert. 
- 23 -
Emergency exposure: an exposure Justified in abnormal conditions in 
the interests of bringing help to endangered individuals, preventing 
exposure of a large number of people or saving a valuable undertaking 
or source, whereby one of the dose limits laid down for exposed workers 
could be exceeded. 
Equivalent dose (Hj): the absorbed dose, in tissue or organ T 
weighted for the type and quality of radiation R. It is given by: 
HT,R " WR DT.R 
where 
~ DT,R is the absorbed dose in tissue or organ T from radiation R 
and 
wR is the radiation weighting factor. 
When the radiation field is composed ofv types and energies with 
different values of wR, the total equivalent dose, HT, is given by 
HT -S WR DT.R 
The appropriate wR values are specified in Annex II. The unit for 
equivalent dose is the sievert. 
Exposed workers: persons, aged 18 years or more, subject to an exposure 
incurred at work from practices covered by this Directive and liable to 
result in doses exceeding one or other of the dose limits for members 
of the pub Iic. 
- 24 -
Exposure: the process of being exposed to ionizing radiation 
Gray (Gy): the special name of the unit of absorbed dose. One gray is 
equal to one Joule per kilogram: 
-1 1 Gy - 1 J kg 
Harm: clinically observable deleterious effects that are expressed in 
individuals or their descendants. It includes the probability of such 
effects. 
Holder : any natural or legal person who, before carrying out a shipment 
of radioactive substances, has the legal responsabiIity under national 
law for such materials and intends to carry out a shipment to a 
consignee. 
Intake: the activities of radionuclides entering the body from the 
external environment. 
Intervention: a human activity that decreases the overall exposure of 
individuals to radiation by removing existing sources, modifying 
existing exposure pathways or reducing the number of individuals 
exposed to an existing source. 
.Intervention level: a value of equivalent dose, effective dose or a 
derived value, at which intervention measures should be considered. The 
dose or derived value is solely that associated with the exposure 
pathway to which the intervention measure is to be applied. 
- 25 -
Ionizing radiation: the transfer of energy in space in the form-of 
electro-magnetic waves or particles with quantities of energy higher 
than 12.4 eV corresponding to a wavelength of 100 nanometer or a 
frequence of 3x10(15) Hertz. 
Members of the public: individuals in the population, excluding exposed 
workers, apprentices and students during their working hours. 
Natural radiation sources: sources of ionizing radiation from natural 
terrestrial or cosmic origin. 
Other relevant sources: any radioactive substance not being a sealed 
source intended for direct or indirect use of the ionizing radiation it 
emits for medical, veterinary, industrial, commercial, research or 
agricultural applicat ions. 
Placing on the market: any supply, whether in return for payment or 
free of charge, other than for storage followed by exportation from the 
territory of the Community or by disposal. Importation of a radioactive 
substance or products containing such substances into the territory of 
the Community shall be deemed to constitute placing on the market for 
the purposes of this Directive. 
Potential exposure: exposure which has a probability of occurrence and 
magnitude that may be predicted for an event such as an accident or 
failure of equipment. 
Practice: a human activity that can increase the overall exposure of 
individuals to radiation from a source. 
Ï>7 -
- 26 -
Quai if led expert: a person having the knowledge and training needed to 
carry out physical, technical, or radiochemical tests and to assess 
doses, and to give advice in order to ensure effective protection of 
individuals and correct operation of protective equipment, whose 
capacity to act as a qualified expert is recognised by the competent' 
authorities. 
Radiological emergency: the consequence of an accident for which Member 
States decide to take measures of a widespread nature in order to 
protect the public. 
Radioactive contamination: the contamination of any material, surface 
or environment or of an individual by radioactive substances. In the 
specific case of the human body, this radioactive contamination 
includes both external skin contamination and internal contamination, 
irrespective of route of intake. 
Radioactive substance: any substance that contains one or more 
radionuclides, the activity or the concentration of which cannot be 
disregarded as far as radiation protection is concerned. 
Reference group of the population: a group comprising individuals whose 
exposure to a source is reasonably uniform and representative of that 
of the individuals in the population who are the most highly exposed to 
that source. 
Sealed source: a source whose structure is such as to prevent, under 
normal conditions of use, any dispersion of the radioactive substances 
into the environment. 
- 27 -
Shipment: the transport operations from the place of origin to -the 
place of destination, including loading and unloading, of radioactive 
substances. 
Sievert (Sv): the special name of the unit of equivalent and effective 
dose. One sievert is equivalent to one Joule per kilogram: 
1 Sv - 1 J Kg"1 
Source: an apparatus, substance or installation capable of emitting 
ionizing radiation or radioactive substances, other than natural 
radiation sources. 
Supervised area: an area in which the working conditions are kept 
under review but special arrangements such as those enforced in 
controlled areas are not normally needed. 
- 28 -
TITLE II 
SCOPE 
Article 2 
This Directive shall apply to any practice or intervention which 
involves a hazard from ionizing radiation, notably: 
a) the production, processing, handling, use, holding, storage, 
transport, placing on the market, exportation and disposal of 
radioactive substances; 
b) the operation of any electrical equipment emitting ionizing 
radiation and containing components operating at a potential 
difference of more than 5 kV; 
c) exposure to natural radiation sources at work 
(i) in uranium mines; and 
(ii) in other workplaces as specified in Title VII. 
- 29 -
TITLE III 
REPORTING AND AUTHORISATION 
Article 3 
Reporting 
1. Each Member State shall make it compulsory for each person who or 
undertaking which carries out the practices referred to in Article 2 to 
report those practices. 
2. However, no reporting shall be required for the following practices: 
(a) the use of radioactive substances or their subsequent disposal if 
the quantities involved do not exceed in total the values given in 
column 2 of table A in Annex I ; or 
(b) the use of radioactive substances or their subsequent disposal if 
the concentrations of activity per unit mass do not exceed the 
values given in column 3 of table A in Annex I ; or 
(c) the use of apparatus containing radioactive substances exceeding 
the quantities or concentration values specified in (a) or (b), 
provided that: 
1. it is of a type approved by the competent authority of the 
Member State; and 
2. it is constructed in the form of sealed sources ensuring 
effective protection against any contact with the radioactive 
substances and against any leakage of them; and 
3. it does not cause, in normal operating conditions, a dose rate 
exceeding 1 /zSv h-1 at a distance of 0.1 m from any 
accessible surface of the apparatus; or 
- 30 -
(d) the operation of any electrical equipment to which this Directive 
applies, provided that: 
1. it is of a type approved by the competent authority of the 
Member State; and 
2. it does not cause, in normal operating conditions, a dose rate 
exceeding 1 j*Sv h_1 at a distance of 0.1 m from any 
accessible surface of the apparatus; or 
(e) the operation of any cathode ray tube intended for the display of 
visual images provided that it does not cause, in normal operating 
conditions, a dose rate exceeding 1 ftSv h-1 at a distance of 0.1 
m from any accessible surface of the apparatus; or 
(f) the occupancy of dwellings and other exposures to natural sources, 
without prejudice to Article 2 (c). 
3. The list of practices, laid down in paragraph 2, may be revised in 
accordance with the procedure laid down in Article 56. 
Article 4 
Authorization 
1. Prior authorization shall be required for the following practices: 
(a) the construction, operation and decommissioning of any undertaking 
of the nuclear fuel cycle; 
(b) the disposal of radioactive substances or the recycling of 
materials containing radioactive substances, arising from any 
industrial, medical, veterinary or research undertaking, unless 
conditions laid down by the competent authorities are met; 
- 31 -
(c) the deliberate addition of radioactive substances fn the product ion 
and manufacture of medicinal products and consumer goods and the 
placing on the market of such goods; 
(d) the deliberate administration of radioactive substances to persons 
and animals for the purpose of medical or veterinary diagnosis, 
treatment or research; 
(e) the use of X-ray sets or radiation sources containing radioactive 
substances for industrial radiography or processing of products and 
the use of accelerators except electron microscopes; 
(f) the use of accelerators, X-ray sets or radioactive sources for the 
exposure of persons for medical treatment or research. 
2. Prior authorization may be required for other practices than those 
listed in paragraph 1, to be determined in accordance with the 
procedure-laid down in Article 56. 
3. Authorizations may be issued for a continued practice and cover the 
use of several radiation sources over a specified period of time. They 
may be renewable. 
Article 5 
Prohibited practices 
The deliberate addition of radioactive substances in the production of 
foodstuffs, toys, personal ornaments and cosmetics, the deliberate 
activation of such goods and their placing on the market shall be 
prohibited. 
- 32 -
Article 6 
Shipment of radioactive substances 
1. Each Member State shall make arrangements to ensure that shipments 
of radioactive substances within its territory can be made only to 
consignees which have complied with all applicable provisions 
implementing this Directive and with relevant national requirements for 
use, treatment, handling, safe storage or disposal of such radioactive 
substances. 
2. A holder of sealed sources who intends to carry out a shipment of 
such sources to a consignee in another Member State, or to arrange for 
such a shipment to be carried out, shall obtain a prior written 
declaration by the consignee of the sealed sources to the effect that 
the consignee has complied, in the Member State of destination, with 
all applicable provisions implementing this Directive and with relevant 
national requirements for use, treatment, handling, safe storage or 
disposal of that class of source. 
The declaration shall be sent by the consignee to the competent 
authorities of the Member State to which the shipment is to be made. 
Receipt of the declaration shall be acknowledged thereon by the 
competent authority and the declaration shall then be sent by the 
consignee to the holder. 
- 33 -
3. A holder of sealed sources or other relevant sources who has carried 
out a shipment of such sources to a consignee in another Member State, 
or arranged for such a shipment to be carried out, shall, within 21 
days of the end of each calendar quarter, provide the competent 
authorities in the Member State of destination with the following 
information in respect of deliveries during the quarter: 
- names and addresses of consignees; 
- the total activity per isotope delivered to each consignee and 
the number of such deliveries made; 
- the highest single quantity of each isotope delivered to each 
consignee; 
the type of substance: sealed source or other relevant source. 

- 34 -
TITLE IV 
SYSTEM OF RADIOLOGICAL 
PROTECTION FOR PRACTICES 
CHAPTER I 
GENERAL PRINCIPLES 
Article 7 
1. Each Member State shall establish and require the application of a 
system of radiological protection for practices based on the following 
general principles: 
(a) all practices resulting in exposure to ionizing radiation shall be 
Justified in advance by, and kept under review as to the benefits 
which they produce;. 
(b) all exposures shall be kept as low as reasonably achievable, 
economic and social factors being taken into account; generic dose 
constraints for particular types of practice shall be established 
by the competent authorities; 
(c) without prejudice to Article 13, the sum of the doses from all 
relevant practices shall not exceed the dose limits laid down in 
this Title for exposed workers, apprentices, students and members 
of the pub Iic. 
2. The principles set out in paragraph 1 (a) and (b) shall apply to all 
exposures to ionizing radiation including medical exposures. The 
principle* set out in paragraph 1 (c) shall not apply to any of the 
following exposures: 
- 35 -
(a) the exposure of individuals as part of their own medical diagnosis 
or treatment; 
(b) emergency exposures, without prejudice to Article 55; 
(c) exposures from natural sources other than in uranium mines and as 
specified in Title VII; 
(d) the exposure of individuals knowingly and willingly helping (other 
than as part of their occupation) in the support and comfort of 
patients undergoing medical diagnosis or treatment, either in a 
hospital or at home, without prejudice to paragraph 3; 
(e) the exposure of volunteers participating in medical and biomedical 
research programmes, without prejudice to paragraph 3. 
3. Each Member State shall establish guidance on appropriate procedures 
to be applied to the individuals referred to at 2 (d) and 2 (e) above. 
It shall also establish appropriate constraints to be applied to the 
doses received by the volunteers referred to at 2 (e) above. 
CHAPTER II 
LIMITATION OF DOSES FOR EXPOSED WORKERS 
Article 8 
Age limit for exposed workers 
Without prejudice to Article 12 (2), persons under 18 years of age may. 
not be assigned to any work which would result in their being exposed 
workers. 
- 36 -
Article 9 
Dose limits for exposed workers 
1. The limit on effective dose for exposed workers shall be 20 mSv per 
year averaged over five consecutive years (100 mSv in five years), with 
the further provision that the effective dose shall not exceed 50 mSv 
in any single year. This limit applies to the sum of the relevant doses 
from external exposure in the specified period and the 50-year 
committed equivalent dose from intakes in the same period. 
2. Without prejudice to paragraph 1, the following limits for the lens 
of the eye, skin and extremities apply: 
- the limit for equivalent dose for the lens of the eye shall be 
150 mSv in a year; 
the limit for equivalent dose for the skin shall be 500 mSv in a 
year. This limit shall apply to the dose averaged over any area of 
1 cm2, regardless of the area exposed; 
the limit for equivalent dose for the hands, forearms, feet and 
ankles shall be 500 mSv in a year. 
Article 10 
Protection of pregnant women 
As soon as a pregnant woman, in accordance with national legislation 
and/or national practice, informs the management of her condition, the 
foetus shall be protected as far as possible as though it were a member 
of the public. The exposure of the pregnant woman in the context of her 
employment shall be as low as reasonably achievable and the conditions 
of her work shall be such as to ensure that the equivalent dose to the 
foetus does not exceed 1 mSv during the remainder of the pregnancy. 
- 37 -
Article 11 
Protection of nursing mothers 
1. Nursing mothers shall not be employed in work involving a risk of 
radioactive contamination. 
2. Special attention will be paid to the possibility of bodily 
radioactive contamination. If necessary, the competent authorities 
shall establish relevant dose constraints. 
CHAPTER III 
LIMITATION OF DOSES FOR 
APPRENTICES AND STUDENTS 
Article 12 
1. The dose limits for apprentices aged 18 years or over and students 
aged 18 years or over who, in the course of their studies, are obliged 
to use sources shall be the same as the dose limits for exposed workers 
laid down in Article 9. 
2. The limit for effective dose for apprentices aged between 16 and 18 
years and for students aged between 16 and 18 years who, in the course 
of their studies, are obliged to use sources, shall be 6 mSv per year. 
The dose limits for the lens of the eye, skin and extremities shall be 
equal to three-tenths of the dose limits for exposed workers laid down 
in Article 9 (2). 
3. The dose limits for apprentices and students who are not subject to 
the provisions of paragraphs 1 and 2 shall be the same as the dose 
limits for members of the public specified in Article 14. 
- 38 -
CHAPTER IV 
SPECIALLY AUTHORIZED EXPOSURES 
Article 13 
1. In exceptional circumstances, evaluated case by case, the competent 
authorities may, where some specific opération so requires, authorize 
individual occupational exposures of some identified workers exceeding 
the dose limits set out in Article 9, but within maximum exposure 
levels defined for the particular case by the competent authorities. 
The following conditions shall apply: 
a) only workers of category A defined in Article 23 may be subject to 
specially authorized exposures; 
b) pregnant and nursing women are excluded from such exposures; 
c) these exposures shall be carefully justified and thoroughly 
discussed with the management, the relevant workers, their 
representatives, the approved occupational health services or approved 
medical practitioner and the qualified expert; 
d) information about the risks involved and the precautions to be taken 
during the operation shall be provided; 
e) all closes related to such exposures shall be separately recorded in 
the health record. 
2. The exceeding of dose limits as a result of specially authorized 
exposures shall not necessarily be a reason for excluding the worker 
from his usual occupation. 
- 39 -
CHAPTER V 
LIMITATION OF DOSES FOR THE POPULATION 
Article 14 
Dose limits for members of the public 
1. Without prejudice to Article 15, the dose limits for members of the 
public shall be as laid down in paragraphs 2 and 3. 
2. The limit for effective dose shall be 1 mSv in a year. However, in 
special circumstances, a higher effective dose may be authorized in a 
single year, provided that the average over five consecutive years does 
not exceed 1 mSv per year. This limit applies to the sum of the 
relevant doses from external exposure in the specified period and the 
50-year committed equivalent dose (to age 70 years for children) from 
intakes in the same period. 
3. in addition: 
The limit for the equivalent dose for the lens of the eye shall 
be 15 mSv in a year; 
- the limit for the equivalent dose for.the skin shall be 50 mSv 
in a year averaged over any 1 cm2 area of skin, regardless of 
the area exposed; 
- the limit for the equivalent dose for the hands, forearms, feet 
and ankles shall be 50 mSv in a year. 
- 40 -
Article 15 
Exposure of the whole population 
1. Each Member State shall ensure that the contribution to the exposure' 
of the whole population from each practice is kept as low as reasonably 
achievable, taking account of the principles set out in Article 7 (1) 
(a) and (b). 
2. The total of all such contributions shall be regularly assessed. 
3. Each Member State shall regularly transmit the results of these 
assessments to the Commission. 
CHAPTER VI 
Article 16 
If exceptional circumstances so require, dose limits different from 
those fixed in this Title may be authorised in accordance with the 
procedure laid down in Article 56. Such authorization shall be duly 
justified and limited in its scope, duration and geographical 
applicabiIity. 
TITLE V 
ESTIMATION OF EFFECTIVE DOSE 
Article 17 
For the estimation of effective dose the methods referred to in this 
Title or any other appropriate methods shall be used. 
41 -
Article 18 
1. For external radiation, the values given in Annex II may be used to 
estimate the relevant equivalent and effective doses. 
2. For internal exposure from a radionuclide or from a mixture of 
radionuclides, the methods given in Annexes M and III may be used to 
estimate the effective doses. 
- 42 -
TITLE VI 
FUNDAMENTAL PRINCIPLES GOVERNING OPERATIONAL PROTECTION 
OF EXPOSED WORKERS, APPRENTICES AND STUDENTS 
Article 19 
Operational protection of exposed workers shall be based on the 
following principles: 
a) prior evaluation to identify the nature and magnitude of the 
radiation hazard to exposed workers; 
b) classification of workplaces into different areas, where 
appropriate, by reference to an assessment of the expected annual 
doses and of the expected frequency and possible consequences of 
minor mishaps; 
c) classification of workers into different categories; 
d) implementation of control measures and monitoring relating to the 
different areas and to the different working conditions; 
e) medical surveillance. 

- 43 -
CHAPTER I 
MEASURES FOR THE RESTRICTION 
OF EXPOSURE 
SECTION 1 
CLASSIFICATION AND DELINEATION OF AREAS 
Article 20 
Arrangements in workplaces 
1. For the purposes of radiation protection and having regard to 
Titles M and VII, arrangements shall be made as regards all workplaces 
where there is a risk of exposure to ionizing radiation in excess of 
the relevant dose limits for members of the public. Such arrangements 
must be appropriate to the nature of the undertakings and sources and 
to the magnitude and nature of the hazards. The scope of the 
precautions and monitoring, as well as their type and quality, must be 
appropriate to the hazards associated with the work involving exposure 
to ionizing radiation. 
2. A distinction shall be made between controlled areas and supervised 
areas. 
3. Specific arrangements shall be made in controlled areas, wherever 
there is a significant risk of the spread of radioactive contamination. 
4. The competent authorities shall establish guidance on the 
classification of controlled and supervised areas which is relevant to 
the particular circumstances. 
- 44 
5. The management shall keep under review the working practices in 
controlled and supervised areas. 
Article 21 
Requirements for controlled areas 
The minimum requirements for a controlled area are that it shall be 
delineated and that access to it shall be controlled in accordance with 
written procedures provided by the management. 
Article 22 
Discretionary measures for control led and supervised areas 
Taking into account the nature and extent of radiation hazards in the 
controlled and supervised areas: 
a) signs indicating type of area, nature of the sources and their 
inherent hazards shall be displayed; 
b) working instructions appropriate to the radiation hazard associated 
with the sources and the operations involved shall be laid down; 
c) radiological environmental surveillance shall be organized in 
accordance with the provisions of Article 26. 
These duties shall be within the competence of qualified experts. 
- 45 -
SECTION 2 
CLASSIFICATION OF EXPOSED WORKERS. APPRENTICES AND STUDENTS 
Article 23 
Categorisation of exposed workers 
For the purposes of monitoring and surveillance, a distinction shall be 
made between two categories of exposed workers: 
category A: those who work routinely in controlled areas and those 
who are liable to receive an effective dose greater than 6 mSv per 
year or an equivalent dose greater than three-tenths of the dose 
limits for the lens of the eye, skin and extremities laid down in 
Article 9 (2); 
- category B: those exposed workers not classified as workers of 
category A, routinely working in supervised areas or occasionally 
in controlled areas. 
Article 24 
information and training 
Exposed workers, apprentices and students shall: 
(a) - be informed of the health risks involved in their work; 
- be informed of the general radiation protection procedures and 
precautions to be taken and, in particular, those involved with 
operational and working conditions in respect of both the 
undertaking in general and each type of work station or job; 
- 46 -
- .- be informed of the importance of complying with the technical, 
medical and administrative requirements; 
(b) - in the case of women, be informed about the specific health 
risks; this information shall be supplemented in the event of a 
pregnancy; 
(c) - be given training in the field of radiât ion .protect ion. 
SECTION 3 
ARRANGEMENTS FOR THE RADIOLOGICAL PROTECTION 
OF EXPOSED WORKERS 
Article 25 
1. An assessment of arrangements for the radiological protection of 
exposed workers shall be made by the management. 
2. The examination and testing of protective devices and measuring 
instruments shall be the task of qualified experts and shall comprise: 
a) prior critical examination of plans for sources from the point of 
view of radiation protection; 
b) the acceptance into service of new or modified sources from the 
point of view of radiât ion protection; 
c) regular checking of the effectiveness of protective devices and 
techniques; 
d) regular calibration of measuring instruments and regular checking 
that they are serviceable and correctly used. 
- 47 -
CHAPTER I I 
ASSESSMENT OF EXPOSURE 
SECTION 1 
MONITORING OF THE WORKPLACE 
Article 26 
1. The radiological environmental surveillance, mentioned in Article 
22, shall comprise: 
a) the measurement of dose rates, indicating if necessary the nature 
and the quality of the radiation in question; 
b) the measurement of the air concentration and surface density of 
contaminating radioactive substances, indicating if necessary their 
nature and their physical and chemical states. 
2. The results of these measurements snail be recorded and shall be 
used, where appropriate, for estimating individual doses, as required 
in section 2. 
- 48 -
SECTION 2 
INDIVIDUAL MONITORING 
Article 27 
Monitoring - General 
1. Individual monitoring shall be systematic for exposed workers of 
category A. This monitoring shall be based on individual measurements 
or, in cases where these are impossible or inadequate, on an estimate 
arrived at either from individual measurements made on other exposed 
workers or from the results of the surveillance of the workplace 
provided for in Article 26. 
2. The competent authority shall provide general guidance for 
identifying those workers of category A liable to receive significant 
internal contamination, in order to set up an adequate system for their 
mon i tor i ng. 
3. Category B workers shall be individually monitored when entering a 
controlled area. In other circumstances, where individual measurements 
have not been made, an estimate of individual doses shall be made from 
the results of the surveillance of the workplace provided for in 
Article 26. 
Article 28 
Investigations after accidental exposures 
In the case of accidental exposures an investigation shall be conducted 
with the aim of identifying the circumstances and assessing and 
recording the relevant doses and their distribution in the body. 
- 49 -
Article 29 
Recording of emergency exposures 
In the case of emergency exposures, the results of individual 
monitoring or dose assessments shall be separately and individually 
recorded. 
Article 30 
Reporting of results 
1. The results of individual monitoring required by Articles 27 to 29 
shall: 
- be made available to the competent authorities, to the management and 
to the worker as required by Article 41 (2); 
- be submitted to the approved occupational health services or 
approved medical practitioner. In the case of an accident or emergency 
the results shall be submitted as soon as possible. 
2. It shall be the responsibility of the management to ensure 
compliance with the requirements of this Article. 
- 50 -
SECTION 3 
MONITORING FOR THE PURPOSE OF OPTIMISATION 
Article 31 
Provision shall be made for monitoring, in addition to that required by 
Articles 26 to 29, whenever it is needed to confirm optimisation of 
radiation protection. 
SECTION 4 
RECORDING OF RESULTS 
Article 32 
1. A record, referred to as the radiation exposure section of the 
health record, and containing the results of the individual monitoring, 
shall be made for each exposed worker of category A. 
2. The following shall be retained during the working life involving 
exposure to ionizing radiation of exposed workers, and afterwards until 
the individual has or would have attained the age of 75 years, but in 
any case not less than 30 years from the termination of the work 
involving exposure: 
a) a record of the exposures measured or estimated, as the case may 
be, of individual doses in pursuance of Articles 27 to 29; 
b) in the case of exposures referred to in Articles 28 and 29, the 
reports relating to the circumstances and to the action taken-, 
- 51 -
c) any results oif workplace monitoring that have been specifically 
used in the assessment or estimation of the dose .to an individual 
for whom an exposure record is required by virtue of subparagraph 
(a) above, shall be annexed to that exposure record and retained 
accordingly. 
CHAPTER III 
MEDICAL SURVEILLANCE OF EXPOSED WORKERS 
Article 33 
Taking into account the specific features of radiation protection and 
without prejudice to Articles 34 to 39, the medical surveillance of 
exposed workers shall be based on the principles that govern 
occupational medicine generally. 
SECTION 1 
MEDICAL SURVEILLANCE OF CATEGORY A WORKERS 
Article 34 
Medical surveillance 
1. The medical surveillance of workers of category A shall be the 
responsibility of approved occupational health services or approved 
medical practitioners. 
2. Medical surveillance shall include: 
- 52 -
a) a-pre-employment medical examination 
The purpose of this examination shall be to determine the worker's 
fitness for the first post within the current employment for which 
he is being considered and for each new post involving a change in' 
type of risk. It shall include an inquiry into his medical history 
including all known previous exposures to ionizing radiation 
resulting either from his employment or from medical examination 
and treatment, a clinical examination and any other investigations 
necessary for assessing his general state of health; 
b) general medical surveillance 
The approved occupational health services or approved medical 
practitioner must have access to any relevant information they 
require in order to ascertain the state of health of workers under 
surveillance and to assess the environmental conditions existing in 
the working premises insofar as they might affect the fitness of 
workers for the tasks assigned to them; 
c) periodic reviews of health 
The health of workers shall be reviewed as many times as the 
approved occupational health services or approved medical 
practitioner consider necessary to determine whether they remain 
fit to perform their duties. The nature of this review shall 
depend on the type of work and on the individual worker's state of 
health. The state of health of each worker shall be reviewed at 
least once a year. 
3. The approved occupational health services or approved medical 
practitioner may indicate the need for medical surveillance to continue 
after cessation of work for as long as they consider it necessary to 
safeguard the health of the person concerned. 
- 53 -
Article 35 
Medical classification 
The following medical classification shall be adopted with respect to 
fitness for work as a worker of category A: 
- fit; 
fit, subject to certain conditions; 
unf it. 
Article 36 
No worker may be employed for any period as a category A worker if the 
medical findings are unfavourable. 
Article 37 
Medical records 
1. A medical section of the health record shall be opened for each 
worker of category A and kept up to date so long as he remains a worker, 
of that category. Thereafter it shall be retained until the individual 
has or would have attained the age of 75 years, but in any case not 
less than 30 years from the termination of the work involving exposure 
to ionizing radiation. 
2. The medical section of the health record shall include information 
regarding the nature of the employment, the results of the pre-
employment medical examinations and the periodic reviews of health. 
- 54 -
SECTION 2 
EXCEPTIONAL MEASURES OF MEDICAL SURVEILLANCE 
Article 38 
Spec 1a I med i caI survei11ance 
1. Special medical surveillance shall be provided in each case of 
exposure where the effective dose of 50mSv as laid down in Article 9 
(1), or any of the other dose limits laid down in Article 9 (2), have 
been exceeded. 
2., Subsequent conditions of exposure shall be subject to the agreement 
of the approved occupational health services or approved medical 
practitioner. 
Article 39 
Additional medical surveillance 
In addition to the medical surveillance of exposed workers provided for 
in Articles 33 and 34, provision shall be made for any further 
examinations, decontamination measures or urgent remedial treatment 
considered necessary by the approved occupational health services or 
approved medical practitioner and for any further action in relation to 
the health protection of the exposed individual. 
- 55 -
SECTION 3 
APPEALS 
Article 40 
Each Member State shall lay down the procedure for appeal against the 
findings and decisions made in pursuance of Articles 35, 36 and 38. 
CHAPTER IV 
TASKS OF MEMBER STATES IN RESPECT 
OF PROTECTION OF EXPOSED WORKERS 
Article 41 
1. Each Member State shall establish a system or systems of inspection 
to enforce the provisions introduced in compliance with this Directive 
and to initiate surveillance and intervention measures wherever 
necessary. 
2. Each Member State shall require that workers have access on their 
request to the results of their individual monitoring measurements or 
assessments of their doses made as a result of workplace measurements 
or biological monitoring. 
3. Each Member State shall make the necessary arrangements to recognise 
the capacity of: 
- the qualified experts-, 
- the approved medical practitioners and approved occupational 
health services. 
- 56 -
To this end, each Member State shall arrange for the training of such 
specialists. 
4. Each Member State shall require the management of an undertaking to 
provide the worker with the means necessary for proper radiation 
protection. If necessary a specialized radiation protection unit shall 
be set up. This unit, which may be shared by several undertakings, 
shall be the responsibility of the management and shall not be part of 
any production or operation unit. 
5. Each Member State shall facilitate the exchange within the European 
Community of all relevant information on the doses previously received 
by a worker, in order to control the further exposure of the worker and 
to perform the pre-employment medical examination required by 
Article 34. 
CHAPTER V 
OPERATIONAL PROTECTION OF APPRENTICES AND STUDENTS 
Article 42 
1. Articles 10 and 19 shall also apply to the apprentices and students 
referred to in Article 12 (1) and 12 (2). 
2. The operational protection of apprentices and students aged 18 years 
or over shall be equivalent to that of exposed workers of category A or 
B as appropriate. 
3. The operational protection of apprentices and students aged between 
16 and 18 years shall be equivalent to that of exposed workers of 
category B. 
- 57 -
TITLE VI I 
EXPOSURE TO NATURAL RADIATION SOURCES AT WORK 
Article 43 
Applicat ion 
1. This Title shall apply to exposures to natural radiation sources at 
work to the extent that the competent authority has declared, 
fol lowing.a survey carried out under Article 44 (1), that exposure to 
these natural radiation sources is subject to control. 
2. In particular this Title shall apply to: 
a) operations in identified workplaces where it has been declared 
that radon or gamma radiation needs attention such as: 
operations in spas, caves, mines (other than uranium mines) and 
other underground workplaces; 
b) identified operations with and storage of materials not usually 
regarded as radioactive, but which contain significant traces 
of natural radionuclides; 
« 
c) identified operation of jet aircraft in flight. 
3. Without prejudice to the above paragraphs, it does not apply to 
potassium-40 in the body, cosmic rays at ground level, and 
radionuclides in the earth's crust. 
- 58 -
Article 44 
Surveys and protective measures 
1. Each Member State shall require surveys to be carried out to' 
identify in which areas of its territory, and for which practices and 
working conditions, workers are likely to experience significant 
exposures due to gamma radiation or radon gas and its daughters, or due 
to operations with materials containing significant amounts of natural 
radionuclides. 
2. Member states shall, on the basis of such surveys and for each 
identified area, practice and working conditions, require, as 
appropriate: 
a) arrangements for measurements to assess the doses received by the 
workers; 
b) the application at the workplace of the principles laid down in 
Ar t i cIe 7 ; 
c) the establishment of regulations, standards or codes of practice 
for construction of new workplaces; 
d) the opening of a radon section of the health record for workers. 
Article 45 
Protection of Aircrew 
Each Member State shall make arrangements for the assessment of 
exposure of aircrew involved in the operation of jet aircraft, 
identified under Article 43 (2) (c), by their employers and shall, 
where appropriate, classify aircrew as exposed workers. 
- 59 -
TITLE VIII 
FUNDAMENTAL PRINCIPLES GOVERNING OPERATIONAL 
PROTECTION OF THE POPULATION IN NORMAL CIRCUMSTANCES 
Article 46 
Basic Principle 
Each Member State shall take all necessary measures to ensure the 
protection of the population. 
Article 47 
Conditions for authorization of practices 
involving a hazard from ionizing radiation 
for the population 
In cases decided upon by each Member State in the light of the extent 
of the exposure hazard involved, the competent authorities shall carry 
out the following tasks concerning practices subject to prior 
authorization: 
a) examination and approval of plans for undertakings involving an 
exposure hazard, and of the proposed siting of such undertakings 
within the territory concerned, from the point of view of radiation 
protection; 
b) acceptance into service of such new undertakings subject to 
adequate protection against any exposure or radioactive 
contamination liable to extend beyond the perimeter, taking into 
account, if relevant, demographic, meteorological, geological, 
hydro logical and ecological conditions; 
c) examination and approval of plans for the discharge of radioactive 
waste. 
- 60 -
Article 48 
Estimates of population doses 
The competent authorities shall: 
1. ensure that dose estimates from all sources are made for the whole 
population of the area concerned and for reference groups of the 
population in all places where such groups may occur; 
2. decide on the frequency of assessments and take all necessary steps 
to identify the reference groups of the population, taking into 
account the effective pathways of transmission of the radioactive 
mater ials*, 
3. ensure that, taking into account the radiological hazards, the 
estimates of the population doses include: 
a) assessment of the doses due to external radiation, indicating, 
where appropriate, the quality of the radiation in question; 
b) assessment of the intake of radionuclides, indicating the 
nature of the radionuclides and, where necessary, their 
physical and chemical states, and déterminât ion of the activity 
and concentrations of these radionuclides; 
c) assessment of the doses that the reference groups of the 
population are liable to receive and specification of the 
characteristics of these groups; 
4. require records to be kept relating to measurements of external 
exposure, estimates of intakes of radionuclides and radioactive 
contamination as well as the results of the assessment of the doses 
received by reference groups and by the population. 
- 61 -
Article 49 
Inspection 
1. Each Member State shall establish a system of inspection to: 
- keep under review the radiation protection of the population; 
check compliance with the national regulations implementing this 
Directive. 
2. Inspections of shipments of sealed sources and other relevant 
sources, pursuant to Community or national law, for the purpose of 
radiation protection shall be performed as part of the control 
procedures applied in a non-discriminatory manner throughout the 
territory of the Member State. 
- 62 -
Article 50 
Tasks within undertakings 
1. Each- Member State shall require the management responsible for 
practices as referred to in Article 2 to conduct them in accordance 
with the general principles of health protection of the population and 
in particular to carry out the following tasks within its undertaking: 
a) achieving and maintaining an optimal level of protection; 
b) checking the effectiveness of technical devices for protecting the 
environment and the population; 
c) acceptance into service, from the point of view of surveillance of 
radiation protection, of equipment and procedures for measuring 
exposure and radioactive contamination of the environment and the 
population; 
d) regular calibration of measuring instruments and regular checking 
that they are serviceable and correctly used. 
2. The tasks provided for in paragraph 1 shall be the responsabiIity of 
qualified experts. 
- 63 -
TITLE IX 
POTENTIAL. ACCIDENTAL AND EMERGENCY EXPOSURES 
Article 51 
Tasks of the competent authorities 
1. Each Member State shall require that the possibilities of accidents 
and the potential exposures due to those accidents affecting 
undertakings or sources within its jurisdiction are considered and that 
intervention plans are drawn up and are tested, to an appropriate 
extent, at regular intervals. 
2. In particular, intervention plans shall take into account the 
following aspects: 
a) The general principles of radiation protection for intervention 
mentioned hereafter shall be respected: 
» 
- the reduction in health detriment due to radiation, resulting 
from the reduction in dose, should be sufficient to justify the 
harm and costs, including social costs, of the intervention; 
- the form, scale and duration of the intervention should be 
optimised so that the benefit of the reduction in health 
detriment, less the detriment associated with the intervention, 
will be maximised; 
- dose limits, as laid down in Articles 9 and 14, do not apply 
to intervention. However, guidance on the situations in which 
intervention is appropriate will be given by the intervention 
levels adopted under sub-paragraph (c) below. 
- 64 -
b) Each Member State shall require provision to be made for 
interventions related to: 
- the source, to reduce or stop the direct radiation and 
emission of radionuclides; 
- the environment, to reduce the transfer of radioactive 
substances to individuals; 
- individuals, to reduce the accidental exposure and organize 
the treatment of victims. 
c) Each Member State shall adopt intervention levels, taking 
account of any intervention levels established by Community 
legislation. 
d) Each Member State shall arrange, where necessary, for the 
designation of special teams for technical, medical and health 
interventions on a national basis and for their training in 
accordance with Article 7 of Directive 89/618/Euratom. If 
necessary, these arrangements shall be made in cooperation with 
competent organizations in other States. 
e) Each Member State shall provide for the organization of 
intervention in case of a major accident in or outside its 
territory. 
f) Each Member State shall assess and record the consequences of 
any accident and the effectiveness of the intervention. 
- 65 -
Article 52 
Cooperation with other States 
1. Without prejudice to relevant Community legislation and 
international agreements, each Member State shall, in the event of a 
radiological emergency at an undertaking on its territory or likely to 
have radiological consequences on its territory, establish relations to 
obtain cooperation with any other Member State or non-member State 
which may be involved. 
2. Each Member State shall require emergency plans to be drawn up in 
its territory in relation to possible radiological emergencies at 
undertakings outside its own territory, in accordance with the 
provisions of Article 51. 
3. Each Member State shall seek to cooperate with other Member States 
or non-member States in relation to possible radiological emergencies 
at undertakings on its own territory, in order to facilitate the 
organization of radiological protection in these States, in accordance 
with the provisions of Article 51. 
Article 53 
Potential exposures 
Each Member State shall, where appropriate: 
consider the probability and magnitude of potential exposures from 
practices carried out by persons and undertakings subject to the 
system of reporting or authorization laid down in Title III; 
- 66 -
seek to assess the spatial and temporal distribution of- the 
radioactive substances dispersed following possible accidents, 
recognizing the increasing difficulties when the probability of 
occurrence of the accident decreases; 
establish technical standards for the undertakings or sources, 
intervention plans for the different kinds of accident and training 
of special emergency teams. 
Article 54 
Tasks of management 
1. Each Member State shall require the management to draw up plans for 
intervention within the undertakings under its responsibility. 
2. Each Member State shall make provision for the immediate 
notification to its competent authorities, by the management 
responsible for the practice involved, of accidents occurring on its 
territory and require all appropriate actions to reduce the 
consequences. 
3. Each Member State shall require that in the event of an accident the 
responsible management shall make an initial provisional assessment of 
the consequences of the accident and successive assessments based on 
subsequent measurements of radioactive contamination. 
- 67 -
Article 55 
Emergency exposures 
1. Each Member State shall make provision for situations where workers 
or intervention personnel involved in different kinds of intervention 
are liable to. be subjected to emergency exposures resulting in doses in 
excess of the dose limits for exposed workers. To this end, each Member 
State shall establish exposure levels taking into account the technical 
obligations and the health risks; these levels shall be operational 
guides. An exposure above these special levels may be admitted 
exceptionally to save human lives and only for volunteers who are 
informed about the risks involved in their intervention. 
2. Each Member State shall require monitoring and medical surveillance 
of the persons exposed in the emergency teams. 
- 68 -
TITLE X 
FINAL PROVISIONS 
Article 56 
Accelarated procedure 
1. Where the procedure laid down in this Article is to be followed, the 
Commission shall submit to the Council a proposal, after consultation 
of the group of experts instituted under Article 31 of the Euratom 
Treaty. 
2. The Council shall, acting by a qualified majority, decide upon the 
proposal within three months. 
3. The Commission shall examine any request for a proposal made by a 
Member State. 
Article 57 
Reports on implementation 
1. Every two years, and for the first time on (date to be 
specified), each Member State shall forward to the Commission a report 
on the implementation of this Directive, including the results of the 
assessments made under Article 15. 
2. On the basis of these reports, the Commission shall prepare a 
summary report for the European Parliament, the Council and the 
Economic and Social Committee. 
- 69 -
Article 58 
Implementation in Member States law 
1. Member States shall bring into force the laws, regulations and 
administrative provisions necessary to comply with this Directive on 31 
December 1994. They shall immediately inform the Commission thereof. 
When Member States adopt these provisions, these shall contain a 
reference to this Directive or shall be accompanied by such reference 
at the time of their official publication. The procedure for such 
reference shall be adopted by Member States. 
2. Member States shall communicate to the Commission the main 
provisions of national law which they adopt in the field covered by 
this Direct ive. 
Article 59 
Repeals 
Directives 76/579/Euratom and 80/836/Euratom and Regulation 
93/1493/Euratom are repealed with effect from 31 December 1994. 
Article 60 
This Directive is addressed to the Member States 
Done at Brussels 199... 
For the CounciI, 
The President, 
- 70 
ANNEX I 
Values of quantities and concentrations of radionuclides to be used 
for the application of Article 3. 
1. Table A below presents the values of quantities and 
concentrations of activity per unit mass not to be exceeded in 
compliance with Articles 3 (a) and (b) respectively for the 
principal radioactive nuclides concerned. 
2. For radionuclides not listed in Table A, the competent authority 
shall assign appropriate values for the quantities and 
concentrations of activity per unit mass where the need arises. 
Values thus assigned shall be complementary to those in Table A. 
3. The values laid down in Table A apply to the total inventory of 
radioactive substances held by a person or undertaking at any point 
i n t i me. 
4. The values laid down in Table A column 3 for the concentration 
of activity per unit mass pertain to the use of moderate amounts of 
radioactive substances; they shall not be applied to other 
practices involving low levels of radioactivity unless it can be 
demonstrated that the same values 'are justified; levels laid down 
by the competent authorities for the general or specific 
authorization of waste disposal or of recycling shall be 
constrained so as to ensure that materials released to the 
environment shall not exceed the values specified in Table A. 
- 71 -
5. Nuclides carrying the suffix * + ' or 'sec' in Table A represent 
parent nuclides in equilibrium with their corresponding daughter 
nuclides as listed in Table B. In this case the values given in 
Table A refer to the parent nuclide alone but already take account 
of the daughter nuclide(s) present. 
6. In all other cases of mixtures of more than one nuclide the 
requirement for reporting may be waived if the sum of the ratios 
for each nuclide of the total amount present divided by the value 
listed in Table A is less than or equal to 1. This summation rule 
also applies to activity concentrations where the various nuclides 
concerned are contained in the same matrix. 
- 72 -
1. Table A: Values of quantities and of concentrations of activity 
per unit mass not to be exceeded in compliance with Article 3 
(2) (a) and (b) respectively, for the principal radioactive 
nuclides Iisted below: 
NucIi de Quantity (Bq) Concentrât ion 
(kBq/kg) 
H-3 
Be-7 
C-14 
0-15 
F-18 
Na-22 
Na-24 
Si-31 
P-32 
P-33 
S-35 
CI-36 
CI-38 
Ar-37 
Ar-41 
K-42 
K-43 
Ca-45 
Ca-47 
Sc-46 
Sc-47 
SC-48 
V-48 
Cr-51 
Fe-52 
Fe-55 
Fe-59 
Mn-51 
Mn-52 
Mn-52m 108 
108 
106 
109 
105 
105 
105 
105 
105 
10? 
10? 
105 
105 
1012 
109 
106 
105 
106 
105 
106 
106 
105 
105 
10? 
105 
106 
106 
105 
105 
105 106 
102 
104 
103 
10 
1 
1 
102 
102 
105 
105 
103 
1 
107 
103 
10 
10 
10* 
10 
1 
10 
1 
1 
102 
10 
104 
1 
10 
1 
1 
73 
\ 1 
Nuc1i de 
Mn-53 
Mn-54 
Mn-56 
Co-55 
Co-56 
Co-57 
Co-58 
Co-58m 
Co-60 
Co-60m 
Co-61 
Co-62m 
Ni-59 
Ni-63 
Ni-65 
Cu-64 
Zn-65 
Zn-69 
Zn-69m 
Ge-71 
Ga-72 
As-73 
As-74 
As-76 
As-77 
Se-75 
Br-82 
Kr-74 
Kr-76 
Kr-77 
Kr-79 
Kr-81 
Kr-83m 
Kr-85 Quantity (Bq) 
108 
106 
10* 
105 
10* 
105 
105 
107 
104 
10* 
105 
105 
10? 
10? 
105 
106 
105 
105 
10® 
109 
105 
106 
105 
105 
105 
106 
105 
10* 
10™ 
10« 
10™ 
ion 
ion 
10™ Concentrat Ion 
(kBq/kg) 
104 
10 
1 
1 
1 
10 
10 
104 
1 
103 
10 
1 
104 
105 
10 
10 
10 
102 
10 
103 
1 
103 
10 
10 
102 
10 
1 
103 
103 
103 " 
104 
105 
106 
106 
74 
Nuclide 
Kr-85m 
Kr-87 
Kr-88 
Sr-85 
Sr-85m 
Sr-87m 
Sr-89 
Sr-90+ 
Sr-91 
Sr-92 
Y-90 
Y-91 
Y-91m 
Y-92 
Y-93 
Rb-86 
Zr-93+ 
Zr-95 
Zr-97+ 
Nb-93m 
Nb-94 
Nb-95 
Nb-97 
Nb-98 
Tc-96 
Tc-96m 
Tc-97 
Tc-97m 
Tc-99 
Tc-99m 
Mo-90 
Mo-93 
Mo-99 
Mo-101 Quantity (Bq) 
10™ 
109 
10» 
106 
106 
106 
105 
104 
10* 
10* 
10* 
105 
107 
10* 
105 
105 
106 
106 
105 
107 
106 
106 
105 
105 
106 
108 
107 
106 
106 
107 
105 
10? 
105 
105 Concentrat ion 
(kBq/kg) 
104 
103 
103 
10 
10 
10 
102 
10 
10 
1 
10 
102 
10 
10 
10 
10 
103 
10 
10 
103 
1 
10 
10 
1 
1 
102 
103 
103 
104 
10 
10 
103 
10 
1 
75 
Nuclide 
Ru-97 
Ru-103 
Ru-105 
RU-106+ 
Rh-103m 
Rh-105 
Pd-103 
Pd-109 
Cd-109 
Cd-115 
Cd-115m 
Ag-105 
Ag-110m 
Ag-111 
ln-111 
ln-113m 
ln-114m 
ln-115m 
Sn-113 
Sn-125 
Sb-122 
Sb-124 
Sb-125 
1-123 
1-125 
1-126 
1-129 
1-130 
1-131 
1-132 
1-133 
1-134 
1-135 Quantity (Bq) 
107 
10* 
10* 
105 
108 
106 
107 
105 
106 
105 
105 
106 
106 
105 
106 
105 
105 
105 
106 
105 
105 
105 
106 
107 
105 
105 
104 
105 
105 
105 
105 
105 
105 Concent rat ion 
(kBq/kg) 
10 
10 
10 
10 
103 
102 
103 
102 
103 
10 
102 
10 
1 
102 
10 
10 
102 
10 
102 
10 
10 
1 
10 
10 
102 
10 
102 
1 
10 
1 
10 
1 
1 
- 76 -
Nue Ii de 
Cs-129 
Cs-131 
Cs-132 
Cs-134m 
Cs-134 
Cs-135 
Cs-136 
CS-137+ 
Cs-138 
Te-123m 
Te-125m 
Te-127 
Te-127m 
Te-129 
Te-129m 
Te-131 
Te-131m 
Te-132 
Te-133 
Te-133m 
Te-134 
Xe-131m 
Xe-133 
Xe-135 
Ce-139 
Ce-141 
Ce-143 
Ce-144+ 
Ba-131 
Ba-140+ 
La-140 
Pr-142 
Pr-143 Quantity (Bq) 
106 
106 
106 
105 
105 
106 
105 
105 
104 
106 
106 
105 
106 
105 
105 
105 
106 
106 
105 
105 
105 
1010 
1010 
1010 
106 
106 
TO5 
105 
106 
105 
105 
105 
106 Concentrât ion 
(kBq/kg) 
10 
102 
10 
102 
1 
104 
1 
10 
1 
10 
102 
102 
103 
10 
102 
10 
1 
10 
10 
1 
10 
105 
104 
104 
10 
102 
10 
10 
10 
1 
1 
10 
102 
77 
Nuclide 
Pm-147 
Pro-149 
Nd-147 
Nd-149 
Sm-151 
Sm-153 
Eu-152 
Eu-152m 
Eu-154 
Eu-155 
Gd-153 
Gd-159 
Tb-160 
Dy-165 
Dy-166 
Ho-166 
Er-169 
Er-171 
Tm-170 
Tro-171 
Yb-175 
Lu-177 
Ta-182 
Hf-181 
W-181 
W-185 
W-187 
Re-186 
Re-188 
Os-185 
Os-191 
0s-191m 
Os-193 
lr-190 Quantity (Bq) 
10 
ios 
105 
10* 
107 
105 
10* 
105 
10* 
10* 
10* 
105 
105 
105 
10* 
105 
10* 
10* 
10« 
107 
106 
10® 
10* 
105 
107 
10« 
10* 
10* 
105 
10© 
10* 
10® 
1Q5 
106 Concentration 
dcBq/kg) 
10< 
102 
10 
10 
10s 
102 
1 
10 
1 
102 
10 
102 
1 
102 
102 
10 
10« 
10 
102 
10^ 
102 
102 
1 
10 
102 
104 
10 
102 
10 
10 
102 
103 
102 
1 
78 
Nuclide 
Jr-192 
lr-194 
Pt-191 
Pt-193m 
Pt-197 
Pt-197m 
Hg-197 
Hg-197m 
Hg-203 
Au-198 
Au-199 
TI-200 
TI-201 
T1-202 
T1-204 
Bi-206 
Bi-207 
Bi-210 
BJ-212+ 
Pb-203 
Pb-210+ 
Pb-212+ 
Po-203 
Po-205 
Po-207 
Po-210 
At-211 
Rn-220+ 
Rn-222+ 
Ra-223+ 
Ra-224+ 
Ra-225 Quantity (Bq) 
10* 
105 
106 
106 
10* 
105 
10® 
105 
10» 
105 
10* 
106 
106 
10« 
105 
105 
106 
10* 
105 
io6 : 
103 
105 
105 
10* 
106 % : 
103 
10» • 
107 
108 
104 
104 
104 Concentration 
(kBq/kg) 
10 
10 
10 
102 
102 
102 
102 
102 
10 
10 
102 
1 
10 
10 
102 
1 
1 
102 
1 
10 
10 
1 
1 
1 
1 
10 i 
102 
104 
1 
10 
1 
102 
79 
Nuclide 
Ra-226+ 
Ra-227 
Ra-228+ 
Th-226+ 
Th-227 
Th-228+ 
Th-229+ 
Th-230 
Th-231 
Th-232sec 
Th-234+ 
AC-227+ 
Ac-228 
Pa-230 
Pa-231 
Pa-233 
U-230+ 
U-231 
U-232+ 
U-233 
U-234 
U-235+ 
U-236 
U-237 
U-238+ 
U-238sec 
U-239 
U-240 
U-240+ 
Np-237+ 
Np-239 Quantity (Bq) 
103 
105 
104 
106 
104 
104 
103 
103 
107 
102 
10* 
103 
105 
106 
103 
106 
104 
106 
103 
104 
104 
104 
104 
105 
104 
103 
105 
106 
105 
103 
106 Concentration 
(kBq/kg) 
1 
10 
10 
102 
10 
1 
10 
10 
102 
1 
10 
10 
10 
10 
10 
10 
102 
102 
1 
102 
102 
102 
102 
10 
10 
1 
102 
103 
1 
10 
10 
80 
Nuclide 
Np-240 
Pu-234 
PU-235 
PU-236 
Pu-237 
Pu-238 
Pu-239 
Pu-240 
Pu-241 
Pu-242 
Pu-243 
Pu-244 
Am-241 
Am-242 
Am-242m+ 
Am-243+ 
Cm-242 
Cm~243 
Cn-244 
Cm-245 
Cm-246 
Cm-247 
Cm-248 
Bk-249 
Cf-246 
Cf-248 
Cf-249 
Cf-250 
Cf-251 
Cf-252 
Cf-253 
Cf-254 Quantity (8q) 
105 
108 
108 
10* 
107 
103 
103 
103 
105 
103 
106 
103 
103 
106 
103 
103 
10s 
103 
10* 
103 
103 
103 
103 i 
106 
106 
104 
103 
10* 
103 
10* 
106 
103 Concentration 
(kBq/kg) 
1 
102 
102 
102 
102 
10 
10 
10 
103 
10 
102 
10 
10 
102 
102 
10 
103 
10 
102 
10 
10 
10 
10 
10« 
103 
102 
10 
102 
10 
102 
10* 
10 
- 81 -
Nuclide Quantity (Bq) Concentration 
(kBq/kg) 
Es-253 105 103 
Es-254 104" 102 
Es-254m 10s 10 
Fm-254 107 104 
Fm-255 106 103 
- 82 
Table B: List of nuclides in secular equilibrium as referred to in 
pt. 5 
Parent 
nucIi de Daughter nucI ides 
Sr-80+ 
Sr-90+ 
Zr-93+ 
Zr-97+ 
RU-106+ 
CS-137+ 
Ce-134+ 
C6-144+ 
Ba-140+ 
B1-212+ 
Pb-212+ 
Rn-220+ 
Rn-222+ 
Ra-223+ 
Ra-224+ 
Ra-226+ 
Ra-228+ 
Th-226+ 
Th-228+ 
Th-229+ 
Th-232sec Rb-80 
Y-90 
Nb-93m 
Nb-97 
Rh-106 
Ba-137 
La-134 
Pr-144 
La-140 
TI-208,Po-212 
Bi-212,TJ-208,Po-212 
Po-216 
Po-218,Pb-214,BI-214 
Rn-219,Po-215.Pb-211.Bi-211 
Rn-220,Po-216,Pb-212tBi-212,TI-208, 
Po-212 
Rn-222,Po-218fPb-214tBi-214,Pb-210, 
Bi-210,Po-210 
Ac-228 
Ra-222,Rn-218, Po-214 
Ra-224,Rn-220,Po-216,Pb-212,Bi-212, 
TI-208,Po-212 
Ra-225,Ac-225,Fr-221,At-217,B i-213, 
Po-213,Pb-209 
Ra-228,Ac-228,Th-228,Ra-224,Rn-220, 
Po-216,Pb-212,Bi-212,TI-208,Po-212 
- 83 -
Parent Daughter nucI ides 
nucIi de 
Th-234+ Pa-234m 
AC-227+ Fr-223,Ra-223,Rn-219,Po-215,Pb-211, 
Bi-211 
U-230+ Th-226,Ra-222,Rn-218,Po-214 
U-232+ Th-228,Ra-224,Rn-220,Po-216,Pb-212, 
Bi-212,TI-208,Po-212 
U-235+ Th-231 
U-238+ Th-234,Pa-234m 
U-238sec Th-234,Pa-234m,U-234,Th-230,Ra-226, 
Rn-222,Po-218,Pb-214,Bi-214,Pb-210, 
Bi-210,Po-210 
U-240+ Np-240 
Np-237+ Pa-233 
Am-242m+ . Am-242 
AB1-243+ Np-239 
- 84 -
ANNÇ* I» 
A. Definitions of terms used in this ANNEX 
Effective quality factor (0): average value of the quality factor where 
the dose absorbed is delivered by particles with different L values. 
It is calculated according to the expression: 
Q - 1/D^/~ Q (dD/dL )dL 
Quality factor (0): a function of linear energy transfer (L ) used to 
weight absorbed doses in such a way as to indicate their significance 
for radiation protection purposes. 
Radiation weighting factor (WR): a dimens ion Iess factor which is 
used to weight the absorbed dose. The appropriate WR values are 
specified in this Annex. 
Tissue weighting factor (wT): a dimensionless factor used to weight 
the equivalent dose. The appropriate values are specified in this 
Annex . 
Unrestricted Linear energy transfer (Loo 1: the unrestricted linear 
energy transfer is defined as 
L«,-i£ 
dl 
where dE is the mean energy lost by a particle of energy E in 
traversing a distance dl. In the Directive Leo is denoted by L. 
- 85 -
B. Values of radiation weighting factor, wR 
Values of radiation weighting factor, wR, depend on the type and 
quality of.the external radiation field or on the type and quality 
of the radiation emitted by an internally deposited radionuclide. 
When the radiation field is composed of types and energies with 
different values of wR, the absorbed dose must be sub-divided 
into blocks, each with its own value of wR and added to give the 
total equivalent dose. Alternatively, it may be expressed as a 
continuous distribution in energy where each element of absorbed 
dose from the energy element between E and E + dE is multiplied by 
the value of wR from the relevant entry in the Table below. 
Type and energy range Radiation weighting 
factor, wR 
Photons, all energies 
Electrons arid muons, all energies 
Neutrons, energy < 10 keV 
10 keV to 100 keV 
> 100 keV to 2 MeV 
> 2 MeV to 20 MeV 
> 20 MeV 
Protons, other than recoil 
Protons, energy > 2 MeV 
Alpha particles, fission 
fragments, heavy nuclei 1 
1 
5 
10 
20 
10 
5 
20 
In calculations involving neutrons, difficulties may arise in applying 
step function values. In these cases it may be preferable to use the 
continuous function described by the following mathematical 
relationship: 
wR « 5 + 17e -<ln(2E))2/6 
where E is the neutron energy in MeV. 
- 86 -
A direct comparison of the two approaches is given .in Figure 1 
25 r 
v. 20;r 
u 
o 
?..15 
XL 
c o. ibt-
o oe 
10 X .-/-
-t-
V 
_-s X 
10 10 -3 X 
-2 X \ 
^ 
X 
-1 10 10" 10 10 10 10 
Incident neutron energy I MeV I 
l-'ijî. Y. Radiation ^clçhtinc factors fur neutrons. The smooth curve i> to be treated a^ an approximation. 
For radiation types and energy which are not included in the table, an 
approximation of wR may be obtained by calculation of 0 at a 10 mm 
depth in a 30 cm diameter, tissue-equivalent sphere with a density of 
1 cm""3 and a mass composition of 76.2% oxygen, 11.1% carbon, 10.1% 
hydrogen and 2.6% nitrogen: 
• • If' CO 
X | Q(L)D(L)dL 
where D(L)dL is the absorbed dose at 10 mm between I inear energy 
transfer L and L + dL; and 0(L) is the quality factor of L at 10 
mm. The Q-L relationships are given in B. 
- 87 -
C. Relationship between the quality factor, Q(L), and unrestricted 
linear energy transfer, L 
Unrestricted linear energy 
transfer, L in water 
(keV fair1) Q(L) 
< 10 
10 - 100 
> 100 0.32L - 2.2 
300/y£ 
D. Values of tissue weighting factor, wj^1^) 
((D) The values have been developed from a reference population of 
equal numbers of both sexes and a wide range of ages. In the 
definition of effective dose they apply to workers, to the 
whole population, and to either sex. 
- 88 -
Values of tissue weighting factor, wT, are shown below: 
Tissue or organ Tissue weighting 
factors, Wj 
Gonads 
Bone marrow (red) 
Colon 
Lung 
Stomach 
Bladder 
Breast 
Liver 
Oesophagus 
Thyroid 
Skin 
Bone surface 
Remainder 0.20 
0.12 
0.12 
0.12 
0.12 
0.05 
0.05 
0.05 
0.05 
0.05 
0.01 
0.01 
0.05 (<2))((3)) 
((2)) For the purposes of calculation, the remainder is composed of 
the following additional tissues and organs: adrenals, brain, 
upper large intestine, small intestine, kidney, muscle, 
pancreas, spleen, thymus and uterus. The list includes organs 
which are likely to be selectively irradiated. Some organs in 
the list are known to be susceptible to cancer Induction. If 
other tissues and organs subsequently become identified as 
having a significant risk of induced cancer they will then be 
included either with a specific WT or in this additional list 
constituting the remainder. The latter may also include other 
tissues or organs selectively irradiated. 
((3)) In those exceptional cases in which a single one of the 
remainder tissues or organs receives an equivalent dose in 
excess of the highest dose in any of the twelve organs for 
which a weighting factor is specified, a weighting factor of 
0.025 should be applied to that tissue or organ and a weighting 
factor of 0.025 to the average dose in the rest of the 
remainder as defined above. 
-89 -
ANNEX III 
Arrangements for assessing the effective doses due to intakes 
The limits on effective dose set out in Articles 9, 12 and 14 apply to 
the sum of the effective dose received in the specified period and the 
committed effective dose due to intakes in the same period. The 
relationship between intake and committed effective dose depends on the 
age of the individual, on the physical and chemical form of the 
radioactive material and on the route of intake. 
These relationships can then be used to estimate the relevant effective 
doses. If derived limité are used for external exposure and for 
intakes, the limit on effective dose can be applied by the following 
expression for each of the relevant age groups: 
(This Annex will contain for all relevant radionuclides dose 
coefficients (Sv/Bq) for inhalation and ingest ion'for different age 
categories regarding the population and for workers. For the 
exposures to noble gases coefficients in the unit Svy1/Bqm~3 
wi 11 be given). 
ISSN 0254-1475 
COM(93) 349 final 
DOCUMENTS 
EN 04 05 
i Catalogue number : CB-CO-93-381-EN-C 
ISBN 92-77-58078-X 
Office for Official Publications of the European Communities 
L-2985 Luxembourg