CELEX: 51993PC0349
Language: en
Date: 1993-07-20
Title: 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

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)
 ---pagebreak---                                      - 2 -
                            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 ) .
 ---pagebreak---                                     - 3 -
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).
 ---pagebreak---                           - 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).
 ---pagebreak---                                  - 5 -
    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).
 ---pagebreak---                                        - 6 -
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.
 ---pagebreak---                                        - 7 -
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;
                                 M
          introduction of the      dose 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.
 ---pagebreak---                                         - 8 -
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.
 ---pagebreak---                                   - 9 -
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
 ---pagebreak---                                 - 10 -
    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;
 ---pagebreak---                           - 11 -
     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 10 3 and 5 x 10 6 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.
 ---pagebreak---                        - 12 -
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.
 ---pagebreak---  ---pagebreak---                                    - 13 -
                          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 Parliaments 1 ^,
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
 ---pagebreak---                                 - 14 -
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;
 ---pagebreak---                                    - 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).
 ---pagebreak---                                        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).
 ---pagebreak---                                         - 17 -
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;
 ---pagebreak---                                     - 18 -
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:
 ---pagebreak---                                   - 19
                                 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.
 ---pagebreak---                                      - 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
 ---pagebreak---                                     - 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 t 0 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   H T 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.
 ---pagebreak---                                         - 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 « 2 w T H T - S w T J w R 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.
 ---pagebreak---                                          - 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:
                                   H
                                     T,R " W R D
                                                 T.R
where
    D       is  the
~     T,R            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 w R , the total equivalent dose, H T , is given by
                                   H
                                     T - S WR DT.R
The   appropriate w R     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.
 ---pagebreak---                                   - 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 Gy - 1 J kg-1
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.
 ---pagebreak---                                    - 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 -
 ---pagebreak---                                      - 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.
 ---pagebreak---                                     - 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.
 ---pagebreak---                                       - 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.
 ---pagebreak---                                   - 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
 ---pagebreak---                                      - 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;
 ---pagebreak---                                  - 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.
 ---pagebreak---                                       - 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.
 ---pagebreak---                                  - 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.
 ---pagebreak---  ---pagebreak---                                   - 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:
 ---pagebreak---                                   - 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.
 ---pagebreak---                                     - 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 cm 2 , 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.
 ---pagebreak---                                    - 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.
 ---pagebreak---                                    - 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.
 ---pagebreak---                                  - 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 cm 2 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.
 ---pagebreak---                                    - 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.
 ---pagebreak---                                    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.
 ---pagebreak---                                      - 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.
 ---pagebreak---  ---pagebreak---                                     - 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.
 ---pagebreak---                                    - 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.
 ---pagebreak---                                   - 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;
 ---pagebreak---                                    - 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.
 ---pagebreak---                                  - 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.
 ---pagebreak---                                        - 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.
 ---pagebreak---                                     - 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.
 ---pagebreak---                                    - 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-,
 ---pagebreak---                                   - 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:
 ---pagebreak---                                         - 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.
 ---pagebreak---                                    - 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.
 ---pagebreak---                                    - 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.
 ---pagebreak---                                   - 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.
 ---pagebreak---                                     - 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.
 ---pagebreak---                                       - 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.
 ---pagebreak---                                       - 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.
 ---pagebreak---                                     - 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.
 ---pagebreak---                                    - 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.
 ---pagebreak---                                    - 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.
 ---pagebreak---                                   - 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.
 ---pagebreak---                                      - 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.
 ---pagebreak---                                    - 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.
 ---pagebreak---                                      - 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;
 ---pagebreak---                                      - 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.
 ---pagebreak---                                    - 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.
 ---pagebreak---                                     - 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.
 ---pagebreak---                                       - 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,
 ---pagebreak---                                   - 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.
 ---pagebreak---                               - 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.
 ---pagebreak---                             - 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               10 8                10 6
        Be-7              10 8                10 2
        C-14              10 6                10 4
        0-15              109                 10 3
        F-18              10 5                10
        Na-22             10 5                1
                             5
        Na-24             10                  1
        Si-31             10 5                10 2
        P-32              10 5                10 2
        P-33              10?                 10 5
        S-35              10?                 10 5
        CI-36             10 5                10 3
        CI-38             10 5                1
        Ar-37             1012                107
                             9
        Ar-41             10                  10 3
        K-42              10 6                10
                             5
        K-43              10                  10
                             6
        Ca-45             10                  10*
                             5
        Ca-47             10                  10
                             6
        Sc-46             10                  1
                              6
        Sc-47             10                  10
        SC-48             10 5                1
        V-48              10 5                1
        Cr-51             10?                 10 2
        Fe-52             10 5                10
        Fe-55             10  6
                                              10 4
        Fe-59             10 6                1
                              5
        Mn-51              10                 10
        Mn-52              10 5                1
                              5
        Mn-52m             10                  1
 ---pagebreak---                            73
     \   1
Nuc1i de   Q u a n t i t y (Bq) C o n c e n t r a t Ion
                                   (kBq/kg)
 Mn-53              108                104
 Mn-54              106                10
 Mn-56              10*                1
 Co-55              105                1
 Co-56              10*                1
 Co-57              105                10
 Co-58              105                10
 Co-58m             107                104
 Co-60              10 4               1
 Co-60m             10*                103
 Co-61              105                10
 Co-62m             105                1
 Ni-59              10?                104
 Ni-63              10?                10 5
 Ni-65             105                 10
 Cu-64              106                10
 Zn-65             105
                                       10
 Zn-69              105
                                       102
 Zn-69m            10®
                                       10
 Ge-71              109
                                       103
 Ga-72              105
                                       1
 As-73             106                 103
 As-74             105                 10
 As-76             105                 10
 As-77             105                 102
 Se-75              106                10
 Br-82             105                 1
 Kr-74             10*                 103
 Kr-76              10™                103
 Kr-77              10«                103       "
 Kr-79                                     4
                    10™                10
 Kr-81              ion                105
 Kr-83m             ion                106
 Kr-85              10™                106
 ---pagebreak---                   74
Nuclide Quantity (Bq) Concentrat ion
                        (kBq/kg)
 Kr-85m      10™          104
 Kr-87       109          103
 Kr-88       10»          103
 Sr-85       106          10
 Sr-85m      106          10
 Sr-87m      106          10
 Sr-89       105          102
                4
 Sr-90+      10           10
 Sr-91       10*          10
 Sr-92       10*          1
 Y-90        10*          10
 Y-91        105          102
 Y-91m      107           10
 Y-92        10*          10
 Y-93       105           10
 Rb-86      105           10
 Zr-93+     106           10 3
 Zr-95      106           10
 Zr-97+     105           10
 Nb-93m     107           103
 Nb-94      106           1
 Nb-95      106           10
 Nb-97      105           10
 Nb-98      105           1
 Tc-96      106           1
 Tc-96m     108           102
 Tc-97      107           10 3
 Tc-97m     106           10 3
 Tc-99      106           10 4
 Tc-99m     107           10
 Mo-90      105           10
 Mo-93      10?           103
 Mo-99      105           10
 Mo-101      105          1
 ---pagebreak---                    75
Nuclide  Quantity (Bq) Concent rat ion
                         (kBq/kg)
 Ru-97        107          10
 Ru-103       10*          10
 Ru-105       10*          10
 RU-106+      105          10
 Rh-103m      108          10 3
 Rh-105       106          102
 Pd-103       107          10 3
 Pd-109       105          102
 Cd-109       106          10 3
 Cd-115       105          10
 Cd-115m      105          102
 Ag-105       106          10
 Ag-110m      106          1
 Ag-111       105          102
 ln-111       106          10
 ln-113m      105          10
 ln-114m      105          102
 ln-115m      105          10
 Sn-113       106          102
 Sn-125       105          10
 Sb-122       105          10
 Sb-124       105          1
 Sb-125       106
                           10
 1-123        107
                           10
 1-125        105          102
 1-126        105          10
 1-129        10 4         102
 1-130        105          1
 1-131        105
                           10
 1-132        105
                           1
 1-133        105
                           10
 1-134        105
                           1
 1-135        105
                           1
 ---pagebreak---                  - 76 -
Nue Ii de Quantity (Bq) Concentrât ion
                          (kBq/kg)
 Cs-129        10 6         10
 Cs-131        10 6         102
 Cs-132        10 6         10
 Cs-134m       10 5         102
 Cs-134        10 5         1
 Cs-135        10 6         10 4
 Cs-136        10 5         1
                   5
 CS-137+       10           10
                   4
 Cs-138         10          1
                   6
 Te-123m        10           10
                   6
 Te-125m        10           102
                   5
 Te-127         10           102
                   6
 Te-127m        10           10 3
 Te-129         10 5         10
                   5
 Te-129m        10           102
                   5
 Te-131         10           10
                   6
 Te-131m        10           1
                   6
 Te-132         10           10
 Te-133         10 5         10
                   5
 Te-133m        10           1
 Te-134         10 5         10
 Xe-131m        1010         10 5
 Xe-133         1010         10 4
 Xe-135         1010         10 4
 Ce-139         10 6         10
 Ce-141         10 6         102
                    5
 Ce-143         TO           10
 Ce-144+        10 5         10
                    6
  Ba-131        10           10
  Ba-140+       10 5         1
                    5
  La-140        10           1
  Pr-142        10 5         10
                    6        102
  Pr-143        10
 ---pagebreak---                      77
 Nuclide Quantity (Bq)  Concentration
                          dcBq/kg)
Pm-147        10           10<
Pro-149       ios          102
Nd-147        105          10
Nd-149        10*          10
Sm-151        107          10s
Sm-153        105          102
Eu-152        10*           1
Eu-152m       105          10
Eu-154        10*           1
Eu-155        10*          102
Gd-153        10*          10
Gd-159        105          102
Tb-160        105           1
Dy-165        105          102
Dy-166        10*          102
Ho-166        105          10
Er-169        10*          10«
Er-171        10*            10
Tm-170        10«            102
Tro-171       107            10^
Yb-175        106            102
Lu-177        10®            102
Ta-182        10*              1
Hf-181        105            10
W-181         107            102
W-185         10«            104
W-187         10*            10
Re-186        10*            102
Re-188        105            10
Os-185        10©            10
Os-191        10*            102
0s-191m       10®            103
Os-193        1Q5            102
lr-190        106              1
 ---pagebreak---                      78
 Nuclide Quantity (Bq)    Concentration
                             (kBq/kg)
Jr-192        10*            10
lr-194        105            10
Pt-191        106            10
Pt-193m       106            102
Pt-197        10*            102
Pt-197m       105            102
Hg-197        10®            102
Hg-197m       105            102
Hg-203        10»            10
Au-198        105            10
Au-199        10*            102
TI-200        106             1
TI-201        106            10
T1-202        10«            10
T1-204        105            102
Bi-206        105             1
Bi-207        106             1
Bi-210        10*            102
BJ-212+       105             1
                 6
Pb-203        io        :    10
                 3
Pb-210+       10             10
Pb-212+       105             1
Po-203        105             1
Po-205        10*             1
Po-207        106 %    :      1
Po-210        10 3           10         i
At-211        10» •          102
Rn-220+       107            10 4
Rn-222+       108             1
Ra-223+       10 4           10
Ra-224+       10 4            1
Ra-225        10 4           102
 ---pagebreak---                        79
 Nuclide  Quantity (Bq)   Concentration
                             (kBq/kg)
Ra-226+        10 3           1
Ra-227         105           10
                  4
Ra-228+        10            10
Th-226+        106           102
                  4
Th-227         10            10
Th-228+        10 4           1
                  3
Th-229+        10            10
Th-230         10 3          10
Th-231         107           102
Th-232sec      102            1
Th-234+        10*           10
AC-227+        10 3          10
Ac-228         105           10
Pa-230         106           10
                  3
Pa-231         10            10
Pa-233         106           10
                  4
U-230+         10            102
U-231          106           102
                  3
U-232+         10             1
                  4
U-233          10            102
                  4
U-234          10            102
                  4
U-235+         10            102
                  4
U-236          10            10 2
U-237          105           10
                  4
U-238+         10            10
                  3
U-238sec       10             1
U-239          105           102
U-240          106           10 3
U-240+         105            1
                  3
Np-237+        10            10
Np-239         106           10
 ---pagebreak---                      80
 Nuclide Quantity (8q)    Concentration
                             (kBq/kg)
Np-240        105             1
Pu-234        108            102
PU-235        108            102
PU-236        10*            102
Pu-237        107            102
Pu-238        103            10
Pu-239        103            10
Pu-240        103            10
Pu-241        105            103
Pu-242        103            10
Pu-243        106            102
Pu-244        103            10
Am-241        103            10
Am-242        106            102
Am-242m+      103            102
Am-243+       103            10
Cm-242        10s            103
Cm~243        103            10
Cn-244        10*            102
Cm-245        103            10
Cm-246        103            10
Cm-247        103            10
Cm-248        103       i    10
Bk-249        106            10«
Cf-246        106            103
Cf-248        10 4           102
Cf-249        103            10
Cf-250        10*            102
Cf-251        103            10
Cf-252        10*            102
Cf-253        106            10*
Cf-254        103            10
 ---pagebreak---                    - 81 -
 Nuclide Quantity (Bq)    Concentration
                             (kBq/kg)
Es-253        10 5           10 3
Es-254        104"           10 2
Es-254m       10 s           10
                 7
Fm-254        10             10 4
Fm-255        10 6           10 3
 ---pagebreak---                                - 82
Table B: List of nuclides in secular equilibrium as referred to in
pt. 5
              Parent                Daughter nucI ides
              nucIi de
            Sr-80+        Rb-80
            Sr-90+        Y-90
            Zr-93+        Nb-93m
            Zr-97+        Nb-97
            RU-106+       Rh-106
            CS-137+       Ba-137
            Ce-134+       La-134
            C6-144+       Pr-144
            Ba-140+       La-140
            B1-212+       TI-208,Po-212
            Pb-212+       Bi-212,TJ-208,Po-212
            Rn-220+       Po-216
            Rn-222+       Po-218,Pb-214,BI-214
            Ra-223+       Rn-219,Po-215.Pb-211.Bi-211
            Ra-224+       Rn-220,Po-216,Pb-212tBi-212,TI-208,
                          Po-212
            Ra-226+       Rn-222,Po-218fPb-214tBi-214,Pb-210,
                          Bi-210,Po-210
            Ra-228+       Ac-228
            Th-226+       Ra-222,Rn-218, Po-214
            Th-228+       Ra-224,Rn-220,Po-216,Pb-212,Bi-212,
                          TI-208,Po-212
            Th-229+       Ra-225,Ac-225,Fr-221,At-217,B i-213,
                          Po-213,Pb-209
            Th-232sec     Ra-228,Ac-228,Th-228,Ra-224,Rn-220,
                          Po-216,Pb-212,Bi-212,TI-208,Po-212
 ---pagebreak---                 - 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
 ---pagebreak---                                    - 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 (w T ):    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.
 ---pagebreak---                                       - 85 -
B.  Values of radiation weighting factor, w R
     Values of radiation weighting factor, w R , 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 w R 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 w R from the relevant entry in the Table below.
Type and energy range                          Radiation weighting
                                                  factor,     wR
Photons, all energies                           1
Electrons arid muons, all energies              1
Neutrons, energy < 10 keV                       5
          10 keV to 100 keV                    10
        > 100 keV to 2 MeV                     20
        > 2 MeV to 20 MeV                      10
        > 20 MeV                                5
Protons, other than recoil
Protons, energy > 2 MeV
Alpha particles, fission
fragments, heavy nuclei                        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:
                          w R « 5 + 17e -<ln(2E))2/6
where E is the neutron energy in MeV.
 ---pagebreak---                                                         - 86 -
A direct comparison of the two approaches is given .in Figure 1
           25
              r
      v. 2 0 ; r                                              .-/-
      u
      o
      ?..15
     XL
           ibt-                                           -t-
      c
      o.                                                                             \
                                                                                       ^
                                                     V
      o
     oe
                       X                    X        X         X         X
                                             -3        -2       -1
            10        10_-s    10         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:
                                                                 CO
                                                          X | Q(L)D(L)dL
                                                 • • If'
          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.
 ---pagebreak---                                 - 87 -
C. Relationship between the quality factor, Q(L), and unrestricted
    linear energy transfer, L
   Unrestricted linear energy            Q(L)
      transfer, L in water
           (keV fair1)
             < 10
            10 - 100                           0.32L - 2.2
             > 100                             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.
 ---pagebreak---                                     - 88 -
    Values of tissue weighting factor, w T , are shown below:
Tissue or organ                                      Tissue weighting
                                                        factors, Wj
    Gonads                                     0.20
    Bone marrow (red)                          0.12
    Colon                                      0.12
    Lung                                       0.12
    Stomach                                    0.12
    Bladder                                    0.05
    Breast                                     0.05
    Liver                                      0.05
    Oesophagus                                 0.05
    Thyroid                                    0.05
    Skin                                       0.01
    Bone surface                               0.01
    Remainder                                  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 W T 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.
 ---pagebreak---                                   -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   Svy /Bqm~ 3
                                                                    1
    wi 11 be given).
 ---pagebreak---                                                                       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
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