CELEX: 51978PC0605
Language: en
Date: 1978-11-20
Title: proposal for a Directive (Euratom) of the Council amending the Directive laying down the Basic Safety Standards for the health protection of the general public and workers against the dangers of ionizing radiation (Submitted by the Commission to the Council)

ARCHIVES HISTORIQUES
DE LA COMMISSION
COLLECTION RELIEE DES
DOCUMENTS "COM"
COM (78) 605
Vol. 1978/0234
 ---pagebreak--- Disclaimer
Conformément au règlement (CEE, Euratom) n° 354/83 du Conseil du 1er février 1983
concernant l'ouverture au public des archives historiques de la Communauté économique
européenne et de la Communauté européenne de l'énergie atomique (JO L 43 du 15.2.1983,
p. 1), tel que modifié par le règlement (CE, Euratom) n° 1700/2003 du 22 septembre 2003
(JO L 243 du 27.9.2003, p. 1), ce dossier est ouvert au public. Le cas échéant, les documents
classifiés présents dans ce dossier ont été déclassifiés conformément à l'article 5 dudit
règlement.
In accordance with Council Regulation (EEC, Euratom) No 354/83 of 1 February 1983
concerning the opening to the public of the historical archives of the European Economic
Community and the European Atomic Energy Community (OJ L 43, 15.2.1983, p. 1), as
amended by Regulation (EC, Euratom) No 1700/2003 of 22 September 2003 (OJ L 243,
27.9.2003, p. 1), this file is open to the public. Where necessary, classified documents in this
file have been declassified in conformity with Article 5 of the aforementioned regulation.
In Übereinstimmung mit der Verordnung (EWG, Euratom) Nr. 354/83 des Rates vom 1.
Februar 1983 über die Freigabe der historischen Archive der Europäischen
Wirtschaftsgemeinschaft und der Europäischen Atomgemeinschaft (ABI. L 43 vom 15.2.1983,
S. 1), geändert durch die Verordnung (EG, Euratom) Nr. 1700/2003 vom 22. September 2003
(ABI. L 243 vom 27.9.2003, S. 1), ist diese Datei der Öffentlichkeit zugänglich. Soweit
erforderlich, wurden die Verschlusssachen in dieser Datei in Übereinstimmung mit Artikel 5
der genannten Verordnung freigegeben.
 ---pagebreak--- COMMISSION OF THE EUROPEAN COMMUNITIES
                                          COM(78)605 final
                                          Brussels , 20 November 1978
                 , proposal for a Directive ( Euratom) of the Council
                       amending the Directive laying down the
                 Basic Safety Standards for the health protection
                    of the general public and workers against    .
                         the dangers of ionizing radiation
                  (Submitted "by the Commission to the Council )
COM(78 ) 605 final
 ---pagebreak---              EXPLANATORY MEMORANDUM
       The Basic Safety Standards for the health protection of the general
public and workers against the dangers of ionizing radiation were re­
vised in 1976 ( Council Directive of 1 June 1976 , published in O.J.
No L 167 of 12 July 1976). Since then , the International Commission on
Radiological Protection - a scientific body whici ; is recognized as an
authority throughout the world and to which tho Furatom Commission
and , subsequently , the Commission of the European Communities have
always referred for the purpose of laying down the Basic Safety Stan­
dards for the health protection of the general public and workers against
the dangers of ionizing radiation - has issued Publication 26 , published
in June 1977.
       This publication contains a certain number of recommendations
which , while not calling into question the fundamental principles of
radiation protection or the manner in which the latter is organized ,
define new concepts and units and provide those whose task it is to
protect the health of individuals against any possible exposure risk
with a number of new values ; these values are conceived in a more
coherent way , since they take account of new metabolic data , and are
calculated in a more logical manner , since they take account for the
first time of the additivity of the radiation to which the various organs
or tissues In question are exposed .
       In fact , the values proposed differ only slightly from previous
ones . Some of them , particularly those relating to the transuranic
elements , are generally more strict . Others are slightly less so . The
result is a new , more coherent system of calculation which corresponds
more closely to actual biological and metabolic processes ; if the latest
scientific knowledge is to be made use of , this system should be adopted
without delay .
       Other international organizations , notably the IAEA, the OECD ,
the WHO and the IL.O , are working out - on the basis of Publication 26
mentioned above - a joint recommendation addressed to the States members
of these organizations and incorporating the ICRP recommendations.
       That being so , the Commission cannot dissociate itself from these
other international organizations . Neither can it accept that the laws of
the Member States of the European Communities should be out of step
with the latest scientific and technical knowledge . This view is shared
by the Economic and Social Committee which , at its plenary session on
 12.7.78 , regretted the fact that there was an appreciable time lag before
workers and the general public benefited from this scientific and technical
progress and deplored the slowness with which national laws were
modified to take account of the ICRP principles , which , be it said , the
Directive of 1 June 1976 takes up in more legal terms .
                                  χ
                              x         x
5712 / 78 e
 ---pagebreak---                          - 2 -
       The main changes contained in the proposal for a directive may
be summarized as follows :
       Title I introduces three new units but , in doing so , gives users
the option of using the old units for some time to come. The Commission ,
indeed , is aware of the dangers - particularly in the area of medicine
and of monitoring - of a sudden and premature introduction of units
with which most users are still largely unfamiliar .
       Title II remains fundamentally unchanged. Titles III and IV take
account of the approach described above . In addition , the dose limits
for workers and the public remain the same , except that the formula
D = 5 (N-18 ), the maximum permissible dose during one quarter and
the dose limit of 5 rem/ 30 years per head of the population as a whole
are dispensed with . The non-retention of the latter limits does not ,
however , imply a relaxation. In fact , the basic standards lay down
that any exposure must be justified and that protection measures must
be made as effective as possible. What is more , it is precisely because
these two principles of optimization and justification are also – and for
the first time - applicable to the medical field that it would have been
impossible and illogical to lay down a dose limit for the population as
a whole.
       Titles V, VI and VII on the organization of radiation protection
measures remain virtually unchanged .
       As regards Annex 111 , It will contain the figures for maximum
permissible intake laid down by the ICRP. The other annexes remain
virtually unchanged .
       With a view to keeping the annexes in question in line with scientific
 and technical progress and to obtaining the most appropriate figures as
 quickly as possible , the final articles of the Directive provide for the
 setting up of a standing committee on amendment and updating, referred
 to as 'the Committee' .- It is anticipated that Member States will have to
 take special measures to incorporate the values laid down by the Committee
 into their own national legislation as rapidly as possible .
       That is why the Commission is forwarding to the Council of
 Ministers of the Member States of the European Community the enclosed
 proposal for a directive , which makes some slight , but not fundamental ,
 amendments to the Directive of t June ! 976.
 5712/78 e
 ---pagebreak---                                                                               Doc . Nr 5020/78v e
                                                                              Revised May . 1978
                                                          11
                                      ( Acts whoBe publication is not obligatory)
                                                        COUNCIL
                                                Proposed revision (Oct 1977 )
                                                 of the Council Directive
                                                       of 1 June I976
                  laying down the revised basic safety standards for the health protection of . the
                  general public and workers against the dangers of ionizing radiation
                                                       (76/579 * Euratom )
THE COUNCIL OP THE EUROPEAN COMMUNITIES ,
Having regard to the Treaty establishing the European Atomic Energy Community , and in parti­
cular Articles 31 and 32 thereof ,
Having regard to the proposal from the Commission , worked out 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 Parliament                       ,
Having regard to the opinion of the Economic and Social Committee                        ,
Whereas the Treaty establishing the European Atomic Energy Community prescribes that the'
basic standards for the protection of the health of the general public and workers against
the dangers arising from ionizing radiations , as provided for in particular in Article 30
thereof , must be laid down in order to enable each Member Stat , in accordance with Article
33 , to lay down the appropriate provisions by legislation , regulation or administrative action
to ensure compliance with the basic , standards to take the necestary measures with regard to
teaching , education and vocational training and to lay down such provisions in harmony with the
provisions applicable in this field in the other Member States ;
Whereas the Council , on 2 February 1959 » adopted Directives laying down such basic standards
( l ) and whereas these were last amended by Directive 76/579/Euratom ( 2);
Whereas the usefulness of some modifications of the last Directive                      has become apparent in
the light of new scientific knowledge of radiation protection
Whereas the protection of the health of workers and the general public requires that any
activity involving danger arising from ionizing radiations                          be made subject to regulation ;
Whereas the basic standards must be adapted to the condition under which nuclear energy is
used and whereas they vary according to whether they are concerned with the individual safety
of workers exposed to ionizing radiations or with the protection of the general public ;
ai,1,2 )) OJOJ NoNo L11187, 20.2.1959 » p . 221/59 .
                             of 12.7.1976
 ---pagebreak---  Whereas the protection of the health of workers exposed to ionizing radiationB requires , on
 the one hand, the organization of measures to restrict exposure and procedures for measuring
 exposure and , on the other hand , an adequate degree of medical surveillance ;
 Whereas the protection of the health of the general, public entails a system of surveillance ,
 inspection , and in the case of accident , intervention
                                                                          ι
 HAS ADOPïiDû THIS DIRECTIVE }
 TITLE I - HEFiyiTIOKS
 Article 1
 For the purposes of this Directive , the following terms have the meaning hereby assigned to
 themt                                          •     -
  ( a) Physical terms , quantities and units
  Ioni^ing^radiatlom. radiation consisting of photons or of particles capable of producing ions
 directly or indirectly .
  Activity ( a)j_ the quotient of dN by dt , where dW is the number of spontaneous nuclear trans-
  formatioris-which occur in a quantity of a radionuclide in the time interval dt ,
                                                   dN
                                              A " dt
  This definition does not apply to the words • activity * and 'activities' in Articles 2 , 3 »
  4 , 6 , 6bis and 12 .
  Becquerel ( Bct )j the special name of the SI unit of activity
                                              1 Bq - 1 e"1
  In this Directive the values to fee used when the activity is expressed in curies are also
 given .
                                              1 Ci m 3<>7 * 10 ^ Bq (exactly)
                                              1 Bq - 2.7027 x 10     Ci
t Ab£orb£d_dose jD^i the quotient of d? by dm, where d*e is the mean energy imparted "by ionizing
  radiation to matter in a volume element and dm is the mass of matter in that volume element *
                                              D-fidm                                      .
  2r^y_(2y) « tha special name of the SI unit of absorbed dose .
                                              1 qy « 1 J kg"1
  In this Directive the values to be used when the absorbed dose is expressed in rads are-
  also given .
                                              1 rad ■ 10*" Qy
                                              1 &r « 100 rads
 ---pagebreak--- Linear energy trannf£r_or re£trict£d_linear £olli_si_on stop£i ng_p n v yr_ ( LaJ.• the quotient of dB
by"dl , where dl is the distance traversed by a charged particle in a medium and dE 1b the
energy loss due to collisions with energy transfers less than a given value •£' .
                                                   ■(fi)
                                              la "\ JTI      a
For radiation protection calculations , all the transferred energies are included , so that
                                                  becomes
Fluence £<P_)_of £arti_ele£j the quotient of dN by da, where 4N is the number of particles which
enter a Bphere of cross-sectional area da.
                                               ^
                                               a)   M
                                                  m r–
Fluence rajte–(jpX* the <luotient of d<p by dt f where dxp is the increment of particle fluence
in the time interval dt#
                                                    d<D
                                                9 - dt
(b ) Radiologica! t biological and medicai terms
£rradiation « any irradiation of persons by ionizing radiation . A distinction is made betweeni
- external irradiationi irradiation resulting from sources outside the body ;
- internal irradiation ! irradiation resulting from sources inside the bodyj
- total irradiation ! the sum of external and internal irradiatior. >
Continuou8_exposur£i External irradiation where the sources of r*. Mation subjects the body
to prolonged irradiation although its intensity may vary with +• .me or internal irradiation, due
to continuous intake al hough its level may vary with time .
Single_expo8ure : External irradiation of short duration , or internal irradiation following
intake of radionuclides over a short period .
         factor_(£)j_ a function of linear energy transfer ( Loo), used 'to weight absorbed doses
in such a way as to indicate their significance for radiation protection purposes .
D^^e^uivalent            thfc product of the absorbed dose ( D), the quality factor (q) and the-"
product of all other modifying factors ( N ). Where the word 'dose' is used alone the meaniijg'.'
ia always that of 'dose equivalent' .
Sievertt the special name of the unit of dose equivalent when the absorbed doee is expressed
in grays . In this Directive the values to be used when the dose equivalent is expressed in
reins are also given
                                                          _2
                                              1 rem « 10      Sv
                                              1 Sv m 100 rems
SPSP-ASPSL ecQiiva^lent^inde^x^        at_a_pointj^ the maximum 6 .s equivalent within the 28 cm
diameter core , of a 30 diameter sphere centred, at this point a- ■ ' consisting of material equi­
valent to soft tissue with a density of 1 g.cnf"-' .
Shallow do8e_ejjuival£nJt index ,       ,_at a £oint 1 the jcaximuai dose equivalent within the volume
between 0.07 mm and 1 cm from the surface of a cm diameter sphere centred at this point and
consisting of material equivalent to soft tissue -with a density of 1 g.cm--' . It is not neces­
sary to determine the dose equivalent in the outer lay-ov of thiokneao 0.07 mm .
 ---pagebreak---                                                 - 4 -
ETrrt j'-e dopes the veis-htsd mean of tbs average dos':^ in the various organs or tisBv^s
evaluate'd by t.he method set out in Annex II , Section E.
Whole body irradiation ! irradiation regarded as uniform through the whole body .
Partial bodv irradiationt irradiation predominant ly of part of /the body or of one or more
orranK~~or"TIsBueF™or irradiation which is not regarded as uniform through the whole body.
Committed dose ! the dose to e.n crpan or to a tissue over a period of 50 years , resulting from
an~inta*ce~of~cne or more radionuclides .
Genetic doses the penetic doee to a population is the dose which , if - it were received by
earir"rerson~frorn contention to the wean ape of childbearinp , vould result in the same genetic
burden to the whole copulation ae do the actual doses received by the individuals of thie
nooula+ion . The penetic dose can be aseeeeod as the annual genetically significant doee mul­
tiplied by the mean age of childbearing, which is taken to be 30 years .
Annual renetic.allv eimif leant doee to a population t the average of the individual annual
^nad~d06e£7"weij3rtecl in the case of each individual doee for the expected number of children
conceived Bubse<Tuent to irradiation .
C ollective dose i the collective dose 'a' to a population or group 1B given by the summa­
tion                  <v             .                                                       J
                  3 - V Bi pi
where H is t^e dose to the whole body or to a specified organ averaged over the           mem­
bers of the i      subgroup of the population or group .
Radioactive contamination ! the contamination of any material , surface or environment or of a
uerson by radioactive substances .
In the specific     case of the human body , this contamination includes both external skin conta­
mination and internal contamination irrespective of method of intake .
Do se limits ! The limits th * •; are established in "this Directive for the doses resulting from
the exposure of exposed woricere , apprentices and students , and members of the public , exclu­
ding the doses resulting from natural background radiation and irradiation of individuals as
a result of medical examination and treatment undergone by them . The dose limits apply to the
sum of the doses received from external irradiation during the period considered and the
committed doses resulting from the intake of radionuclides during the saine period.
 Intake ! the activity entering the body from the external environment .
 Limit of annual i ntake ! for a given individual , the activity which , when introduced into th«
 body , results in a committed dose errual to the appropriate limit of annual dose laid down
 in Articles 7 » 8 , 9 and 11 .
 Derived lim it of concentration of radionuclide s in the a ir inhaled expressed in units of
 activity per unit volume is the annual mean concentration in the air which , inhaled , over a
 2000 hours' work , gives an intake etrual to the limit of annual intake.
 Radi'otoxlcity ! the toxicity attributable to ionizing radiation emitted by an incorporated
 radionuclide and its daughters ; radiotoxicity is related not only to the radioactive charac­
 teristics of the radionuclide but also to its chemical and . physical state and to the metabo­
 lism of the "element in the body or in the organ.
 ---pagebreak---                                                  -  5   -
(c ) ôther terme
Source^. an apparatus or substance capable of emitting ionizing r?/liation .
Sealed_s£urce : a source consisting of radioactive substances              incorporated in solid
and effectively inactive materials , or sealed in an inactive ■: onta?.ner of sufficient strength
to prevent , tinder normal conditions of use , any dispersion of radioactive substances and any
possibility of contamination .
Radi£acti.ve ^ubstancei any substance that contains o'he or more radionuclides of which the
activity or the concentration cannot be disregarded as far as radiation protection is concer­
ned .
Natural background_radi_at i onj_ consists of all ionizing radiation from natural terrestrial and
coBinic sources , to the extent that the irradiation which it causes is not significantly in­
creased by man .
Critic al_as a embl£t an assembly of fissile materials in which it is feasible to maintain a
chain reaction .
Whole £0£ul_at^i£n_j_ the entire population , including exposed worki.8 , apprentices , students ,
and members of the public .                                . .
Erased workers^ persons subjected , as a result of 'their work , to an exposure liable to
result in an annual dose greater than l/lOth of the limits of the annual dose laid down for
workers .
Critic al_group£ £f_t he_popu1 at ion j gToups comprising persons whose exposure is' reasonably
uniform and representative of that of the more highly exposed individuals in the population .
Member£ of_the_public » individuals in the population excluding exposed workers , apprentices
and students , during their working hours .
                                                                                           ■M
£cmt r°_l l£d_are a t an area subject to special rules for the purp' i .a of protection against io­
nizing radiation aid to which access is controlled .
Su£ervi 8£d_are a: an area Bubject to appropriate supervision for the purpose of protection
against ionizing radiation .
Intcrventi^levelj. a value of absorbed dose or dose equivalent of a derived value fixed in
connection with the drawing up of emergency plans .
Ap£rov£d_m£di_cal_pra£titioners a medical practitioner responsible for the medical surveillance
of workers of category A as defined in Article 23 , whose capacity to act in this respect is
recognized by the competent authorities .             -
SuaHfied ex£crts : persons having the knowledge and training needed to carry out physical or
technical tests , or radiochemical tests , or to give advice in order to ensure effective protec
tion of individuals and correct operation of protective i ; 'filiations , aa the case may be ,
whose capacity to act as a qualified expert is recognised .• '>3 competent authority.
Accident_t, an unforeseen event that causes damage to an inui, l:a'ion or disrupts the normal
operation of an installation , and is likelj to result for on<; or mors persons in a dose exce •
ding the dose limits .
Planned sp£cial £X£omiro_s_ s,n exposure causing an annual dose +o exceed a limit of annual do - ■>
for exposed workers , permitted exceptionally in certain situations daring normal operations
when alternative techniques which do not involve suc',i oxpotsurea cannot be used .
 ---pagebreak--- Accidental exposures exposure which ie of a fortuitous and involuntary nature and in which
a doM~liu.lt for exposed workars ie exceeded .
Phierfcijc^r exposure i an exposure , justified, in abnormal conditions , in the interests of brin­
ging help to "endangered individuals , preventing exposure of a large number of people , or
saving a valuable installation , and in which a dose limit for exposed workers is exceeded ,
and in which the limits for planned special exposures may also be exceeded . Emergency expo­
sures shall apply only to volunteers .,
TITIE II ~ SCOPE . REPORTING AND AUTHORIZATION
Article 2
This Directive shall apply to the production , processing , handling, use , holding , storage ,
transport and dieposal of natural and artificial radioactive subetances and to any other ,
activity which involves a hazard arising from ionizing radiation .
Article 3
Each Member State 'shall make the reporting of the activities referred to in Article 2
compulsory .                                                                       *
Without prejudice to Article 5 and in the light of possible dangers and other relevant consi­
derations , these activities shall be subject to prior authorization in cases decided upon by
each Member State .
Article 4
Without prejudice to Article 5 , these requirements for reporting and obtaining prior authori­
zation need not be applied to activities involvings
 (a) radioactive substances when the amounts do not exceed in total the values given in
       Annex I j
 (b) radioactive substances of a concentration of less than 100 Bq g""'- (0.0027 yuCi g"**) this
       limit, being increaard to 500 Bq g~l (0.014 /uCi              for solid natural radioactive
  4    substances :                                       '
 ( c ) the use of navigation instruments or timepieces containing radioluminescent paint , but .
       not their manufacture or repair except as provided for in paragraph ( a)j
 (d ) apparatus emitting ionizing radiations and containing radioactive substances in amounts
       greater than the values specified in ( a), provided thati
       il)2 ) itit possesses
                   is of a typeadvantages
                                  approvedinbyrelation
                                               the competent
                                                       to the authority?
                                                               potential hazard that ,              " •
                                                                                       in the opinion of
              the competent authority , justify its use ;
       ( 3 ) it is constructed in the form of Bealed sources ensuring effective protection against
              any contact with the radioactive substances and against any leakage of them ; and
       ( 4 ) it does not cause at any point situated at a distance of 0.1 m from the accessible
              surface of the apparatus and under normal operating conditions , a dose rate exceeding
                     1 /u Sv h"    (0«1 mrem h7 )
 (e ) apparatus other than television receivers emitting ionizing radiation but not containing
       any radioactive substances , provided thati
        ( 1 ) it is of a tye approved by the competent authority;
        ( 2) it possesses advantages in relation to the- potential hazard that , in the opinion of
              the competent authority , justify its use ; and
 ---pagebreak---                                                -     7 -
     (3 ) it does not cause , at any point situated at a distance of 0.1 m from the accessible
          surface of the apparatus and under normal operating conditions , a dose rate exceeding
                      1 Ai Sv h" (0.1 mrem h""^);
(f) television receivers which do not cause , at any- point situated at a distance of 0*05 o
     from the accessible surface of the receiver , a dose rate exceeding
                                -i    .      .- 1 »
                      5 /u Sv h    (0.5 mrem h    ).
Article 5
Apart from the prohibitions provided for by national law, and irrespective of the degree of
danger involved , a system of prior authorization must be applied in respect of t
( a) the administration of radioactive substances to personB for purposes of diagnosis ,
     treatment or research ;
(b ) the use of radioactive substances in toys and the importation of toys containing radio­
     active substances ;                                 ,
(o ) the addition of radioactive substances in the production and manufacture of foodstuffs ,
     medicinal products , cosmeticB and products for household use ( except for the instruments
     and timepieces referred to in Article 4 (<s ) and the importation for commercial purposes
     of such goods if they contain radioactive Bubstances*
TITLE III - LIMITATION OP DOSES POH CONTROLLABLE EXPOSURES
Article 6
The limitation of individual and collective doses resulting from controllable exposures
shall be based on the following general principles t
( a) Every activity resulting in an exposure to ionizing radiation shall be justified by the
     advantages which it produces ..
(b ) All exposures ..hall be kept as low as reasonably achievable .
(c ) Without prejudice to Article 10 , the sum of the doses and committed doses received shall
   . not exceed the dose limits for exposed workerB , members of -!: he public , apprentices and
     students , as the case may be , as specified in this title .
The principles set out in ( a) and (b ) above apply to all exposures to radiation and include
medical exposures . The principle set out in ( c) does not apply to the exposure of individuals
as a result of medical examination and treatment undergone by them .                        ,
Chapter I – Limitation of doses for exposed workers
Article 6b1n
1 * Workers under 18 years of age may not carry out any act.ivity v;hich would result in their
    being exposed workers .
2. IXrring .pregnancy or the nursing period, women must no i "L i t .ployed in vork involving a
    risk of high exposure ; if necessary , a special watch          .» kept for bodily radioactive
    contamination .
 ---pagebreak--- Article 7 - Whole body irraoia-;ion
1 „ The does limit for whole "body irradiation of exposed workers shall 1)6 50 mSv (5 rems )
    in a year .
2 . For women of repioductive capacity, the doss "to the abdomen shall not exceed 13 tsSv
    ( 1.3 rems ) in a quarter .
3 « As soon ess pregnancy is declared , measures shall be taken to ensure that exposure of
    the woman oonceracd in the context of her employ® eut is t?uch that the dose to the foetus ,
    accumulated over the period of time between declaration of pregnancy and the date of
    delivery, reaiains as small as is reasonably practicable and in no ca.se exceeds 10 mSv
    (l rem ). In general , this limitation can be achieved by employing the woman in working
    conditions appropriate to category B workers *
Article 8
In the case of partial body irrediationj
( a) the dose limit for the effective dose evaluated by the method set out in Annex II r
      Section E , shall be 50 ®Sv (5 rems ) in a years the average dose in each of the organs
      or tissues involved shall not exceed 500 mSv ( 50 rems ) in a year .
(b) In addition»                                          . .
      - the dose limit for the lens of tha eya shall be 300 mSv t30 rens ) ia a year ;
      - the dose limit for the skin shall be JOQ mSv ( 50 rems ) in a year, and Bhall apply''
        to the dose averaged over any area of 100 cm^|
      - the dose limit for the hands , forearms , feet and ankles shall be 300 mSv ( 50 reins )
        in a year .
Chapter II - Limitation of doses for aunrentices and students
Article 9
1 . The dose limits for apprentices and students aged 18 years or over who are training
   •for employment involving exposure to ionizing radiation or who , in the course of their
    studies , are obliged to use sources , shall be equal to the dose limits for exposed wor­
    kers laid down in Articles 7       8.
20 The dose limits for apprentices and students aged between 16 and 18 years who are trai­
    ning for employment involving exposure to ionizing radiation or who , in tha course of
    their studies , are obliged to use sources , shall be acru&l to 3/ 10ths of the limits of
    aanual dose for exposed workers laid down in Articles 7 aai 8 .
3o The dose limits for apprentices and students aged 16 years or over who are not subject
    to the pre ^isionc of paragraphs 1 and 2 and for apprentices and studeuts aged less than
    16 years , shall be the same as the dose limits for oembers of the public specified in
    Article 11 . However , the contribution to the annual doses that they are liable to receive
    by virtue of the training shall not exceed one–tenth of the do6e limits specified in
    Article 11 and each single exposure shall not exceed one-hundredth of those dose limits . •
 ---pagebreak---                                                 - 9   -
Chapter III - Planned special exposures
Article 10
1 . Only workers of category A defined in Article 23 may be subjected to planned special
    exposures . Each planned special exposure must be the subject of an appropriate permit .
    Such a permit shall be given only in exceptional situations during normal operations when
    alternative techniques which do not involve such exposures cmot be used * Account shall
    be taken of the age and health of the workers involved .
2. The doses or committed doses received as a result, of planned special exposures must not
    in any year exceed twice the limits of annual dose laid down in Articles ^ and 8 or , in
    a lifetime , five timeB those dose limits .
3 * Planned special exposures must not be authorized :
    ( a) if , during the previous 12 months , the worker has received an exposure giving rise
         to doses in excess of the limits of annual dose laid down in Articles 7 and 8 , or
    (b) if the worker has previously received accidental or emergency exposures , the sum of
         the doses from which exceeds five times the limits of annual dose laid down in - Articles
         7 and 8 } or
    (o ) if the worker is a woman of reproductive capacity.                                .
4 > The exceeding of dose limits as a result of planned special exposure shall not in itself ,
    be a reason for excluding the worker from his usual occupation . Subsequent conditions
    of exposure shall be Bubject to the agreement of the approved medical practitioner .          '
5. All planned special exposures must be entered in the medical record provided for in Article
    33, in which the . estimated value of the dose of the activities taken into the body shali
    also be entered .                                                ,•
6. Before receiving a planned special exposure , the worker shall be given appropriate infor­
    mation about the risks involved and the precautions to be taken during the operation .
Chapter IV - Limitation of doses for the population
Article 11 - Dose limits for members of the public                                    *
1 . She following dose limits shall apply without prejudice to Article 12.
2. In the case of the whole body irradiation the dose limit shall be 5 mSv (0.5 rem) in a
    year .                                                                               -
3 . In the case of partial body irradiationi                                                 '
    (a) the dose limit for the effective dose evaluated by the method set out in Annex il,
         Section E , shall be 5 mSv (0.5 rem ) in a year ; the average dose in each of the organs
         or tissues involved shall not exceed 50 mSv (5 rems ) in a year .
    0>) In additions
         – the dose limit for the lens of the eye shall be 30 n ■■•r (3 rem. ) in a year .
         – the dose limit for the skin shall be 5° mSv (5 remn } in a year, and shall apply
           to the dose averaged over any area of 100 cm^.
         – the dose limit for the hands , forearms , feet and ankles shall "b ? 5^ EiSv (5 rems )
           in a year.
Article 12 - Exposure of the population as a whole
1 . Each Member State shall see that the contribution to the irradiation of the population
    as a whole from each activity is kept to -the minimum amount necessitated by that activity ,
    taking account of the principles set out in Article 6 .
 ---pagebreak---                                                -   10 -
  2. The total of all Buch contributions shall be kept under review and in particular the
      gehetio dose resulting from all these contributions shall be estimated.
 3 „ Member States shall regularly transmit the results of thase review and estimates to
       the Commission .
 TTTIS IV - B3RIVED LIMITS                       -                   -
  Article 13
  1 . The setting of derived limits in this Title shall' not exclude the use of other methods
       of verifying compliance with the dose limits .
  2 . The values of the quality factors to be used in evaluating dose equivalent for different
       types of radiation shall be those laid down in Annex II .
  Article 14 – Extern al irradiation only
  In the case of external irradiation of the whole body or of a substantial fraction of the
  body, the dose limits fixed in Articles 7 , jB and 11 shall be deemed to be complied with if
  the deep dose equivalent index does not exceed the dosa limit laid down for the whole body
  irradiation , and if the shallow dose equivalent index does not exceed the dose limit laid
  down for the skin *
  In the case of irradiation by neutrons or protons the dose limits shall be deemed to have
  been complied with if the doses assessed using the conversion factors laid down in Annex IT ,
  Sections C and D, do not exceed the dose limits fixed for whole body irradiation®
  Article 15 - Internal irradiation only
  The values of intake and concentration of radionuclides in the air, to be used in implemen­
  ting the requirements of Articles 1, 8 and 11 , shall be those laid down in Annex III .
  (a) The tables listed in Annex III ( l ) give :
        - the limits of annual intake by inhalation of radionuclides for exposed workers ;
      . - the derived limits of concentration of radionuclides in the air inhaled for exposed
          workers . They must be considered as average values for one year ;
        - the limits of annual intake by inhalation and by ingestion of radionuelid.es for-
          members of the public .
, (b) Where contamination is caused by a mixture of radionuclides the methods given in
        Annex III ( 2 ) shall be used .
  Article 16 - Combinations of external and internal irradiation
  In the case of combinations of external irradiation of the whole body or of a substantial
  fraction of the body, and internal contamination by one or more radionuclides , the limits of
  Articles 7 » 8 and 11, shall be deemed to have been met if both the fallowing conditions are
  satisfied !
 ---pagebreak---                                            -   11  -
Where
EL . is the annual deep dose equivalent index, HL is the limit of annual dose for the whole
   '   body, Ij is the annual intake of the radionuclide j , and I - ^ is the limit of annual
       intake of that radionuclide ; and                            '
       (b) the limitations in the doses laid down in Articles 8(b ) wd 11(3 ) (b) as appropriate
           are applied .
Article 17
The derived limits relating to apprentices and students shall be derived from the limitations
of dose laid down in Article 9 .
TITLE V - ACCIDENTAL AND EMERGENCY EXPOSURES OP WORKERS
Article 18
All accidental and emergency exposures shall be entered in the Radical record of the worker ,
provided for in article 33 « Whereever possible doses and .committed doses received volunta^-
rily or involuntarily in the course of accidental and emergency exposures must be recorded
separately on the exposure record provided for in article 30. The procedures set-out in f
Article 36 shall also be applied . '                                                         " *
                                                                                  • •
TITLE VI - FUNDAMENTAL PRINCIPLES GOVERNING OPERATIONAL PROTECTION OP EXPOSED WORKERS      ' <
Article 19
Operational protection of exposed workers shall be "based on the Tollowing principles :
( a) classification of places of work into different areas ;
(b) classification of workers into different categories ;
(c) implementation of control measures and monitoring relating to these different areas
     and to the different categories of workers .
These principles of protection shall also apply to the apprentices and students referred to
in Article 9 ( l ) and ( 2).
                                                                                        t
Chapter I - Measures for th9 restriction of exposure
Section 1^ – £ljW£ifixation and demar£atiori_of areas                           *
Article 20
For the purposes of radiation protection , each Member Stat r^-all make arrangements as regards
all placeB of work where there is a risk of exposure to ioni .ig radiation .
In working areas where the exposure is not liable to exceed or-o–'tenth of the limits of .
annual dose for exposed workers , it shall not be necessary to make special arrangements for
the purposes of radiation protection.
In working areas where the exposure is liable to exceed one-tenth of the limits of annual
dose laid down for exposed workers , the arrangements must be appropriate to the na+ure of
the installation and Bources and to the magnitude and nature of the hazards . The scope of
the precautions and monitoring, as well ac their type and quality, muct be appropi^iate to the'
 ---pagebreak---                                                   -  12
    hazards associated with the work involving exposure to ionizing radiation.
    A distinction ehall te made between »
    ( a) controlled areas .
    Any area in which doses are liable to exceed three-tenths of the limits of annual dose laid
    down for exposed workers shall constitute or be included in a controlled area.
    Annex IV lists examples of establishments and plants in which the presence of generators and
    sources liable to be the cause of exposure generally justifies the demarcation of one or more
    controlled areas .
    (b) supervised areas .
    Any area which is not considered as a controlled area and in which doses are liable to exceed
    one-tenth of the limits of annual dose laid down for exposed workers shall be 'considered as
    a supervised area.
    Article 21
    Controlled areas must be demarcated .
    Taking into account the nature and extent of the radiation hazards.:
    ( a) radiological environmental surveillance shall be organized in controlled and supervised
         areas , andj in particular , activities , doees and dose rates as . the case may.be shall be ,
         monitored and results recorded ;           ,                                             ^
    (b ) in controlled and supervised areas , working instructions appropriate to the radiation
         hazard shall be laid down ;
    (c ) the hazards inherent in the sources shall be indicated in controlled areaa ;
    (d) signs indicating sources shall be displayed in controlled and supervised areas .
    Qialified experts shall be concerned in the discharge of these duties#                    ,     .
    Article 22
    The minimum requirement for a controlled area shall "be the control of access by appropriate
    warning signs *
         «                                                                                  s
    Section 2 - Classification of exposed workers
«                                   .                                           •        >
    Article 23                                                                          *
    For the purposes of monitoring and surveillance , a distinction shall be made between two
    categories of exposed workers <
    - category Ai those who are liable to receive a dose greater than three-tenths of a limit
       of annual dose *
    - category B: those who are not liable to receive this dose .
    Article 24
    Exposed workers must be informed of the health risks involved in their work, the precautions ,
    to be taken, and the importance of complying with the technical and medical requirements .
    Apprentices and students referred to in Article 9 ( l )      (2) shall also be given adequate
    training in the field of radiation protection and appropriate information regarding the risks
  . involved in their work .
 ---pagebreak---                                                -  13 -
                                                                                                   1
 Section ^ – Examination and testing £if_JP£9i®£tive devi£esj and measuring ^ri^tniments
 Article 25
 The examination and testing of protective devices and measuring instruments shall "be the
 responsibility of qualified experts .
 The examination and testing shall comprise ?
  ( a) prior critical examination of plans for installations from the point of view of radiation
       protection ;
  (b) the acceptance of new installations from the point of view of radiation protection ;
  (c ) regular checking of the effectiveness of protective devices and techniques ;
  (d) regular checking that measuring instruments are serviceable and correctly used .
  Chapter II – Assessment of exposure
  Article 26
  The nature and "frequency of assessment of exposure shall "be such as to facilitate compliance
  with this Directive in each case .                                                      »
  Section 1 - Collective nonitoring
  Article 27
  Taking into account the radiological hazards , measurements shall Ve carried outt
  (a) of dose rates and fluence rates , indicating the nature and the quality of the radiation
       in question ;
  (b ) of the atmospheric concentration and surface density of contaminating radioactive sub­
       stances , indicating their nature and their physical and chemical states .
  Where appropriate , the results of these measurements shall be used for estimating individual
  doses .
  Section 2 – ^ndi^dual_m£rût£riri2                                                    ,.
  Article 28
' The assessment of the individual doses must be systematic for workers of category A. This
  assessment shall be based on individual measurements or , in cases vhere these are impossible
  or inadequate , on an estimate arrived at either from individual measuraments made on other
  exposed workers , or from the results of the collective monitoring provided for in Article 27 •
  Article 23
  In the case of accidental or emergency exposure , the absorbed dose shall, be aapessed , whether
  a whole or a partial body irradiation has occurred .
  Article 29bis
  The results of individual monitoring shall be submitted to the approved medical practitioner
  with a view to their interpretation under his responsibility in relation to the health of
  the workers .
 ---pagebreak---                                               -   14
Sec tion 3 - Recording £f_results_
Article 30
Tha following shall be kept in the archives for a period of at least 30 years :
(a) the results of collective monitoring measurements used to assess individual doses ;
(b) the exposure record containing documents relating to the assessment of individual donee }
(c) in the case of accidental or emergency exposure, tb.e reports relating to the circumsten-
      oes and to the action taken *
For the documents referred to in (b ) and (c), the period of 30 years shall start at the time
of cessation of work involving exposure to ionising radiation.
Chanter III - Medical surveillance of exposed workers
Article 31
The medical surveillance of exposed workers shall be based cn the principles that govern
occupational medicine generally. It shall include , as appropriate , pre-emplojnnent medical
examinations and periodic review of health , the frequency, and the form of the latter being
determined by the worker 's state of health, the conditions of work and the incidents that
may accompany it .
Article 32                                                                                    >
No worker may be employed for any period as • an exposed worker if the medical findings are
unfavourable .
Section _1 - Medical, eurvei 11anca_of worker^ ofjcategorjr A
Article 33
The medical surveillance of workers of category A shall be the responsibility of approved
medical practitioners .   .
It shall include :
(a) a pre-employment medical examination
The purpose of this examination shall be to determine the worker 's fitness for the first post
for which he is being considered . It shall include an inquiry into his medical history inclu­
ding all known previous exposures to ionizing radiation resulting either from his employment
or from medical examination and treatment , and also the clinical and other investigations •.
necessary for assessing his general state of health .
 (b ) general medical surveillance
The approved medical practitioner must have access to any information he requires in order
to ascertain the state of health of workers under surveillance and to assess the existing
environmental conditions in the working premises , in so far as they might affect the fitness
of workers for the tasks assigned to them.
 (o ) periodic reviews of health
The health of workers shall be subject to review' as a matter of routine to determine whether
they remain fit to perform their duties . The nature of this review shall depend on the type
 ---pagebreak---                                                - 15 -
and extent of exposure to ionizing radiation and on the individual worker 's state of health .
The state of. health of each worker shall be reviewed at least one a year and more frequently
if the worker 's exposure conditions or state of health so requiro .
The approved medical practitioner may indicate the need for medical surveillance after cess ac­
tion of work for as long as he considers it necessary to safegusr i the health of the person
concerned .
Article 34
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 ;
- unfit .
Article 35
1 . A medical record shall be opened for each worker of category A and kept up to date BO long
    as he remains a worker of that category . Thereafter it shall be retained in the archives
    for a period of at least 30 years .
2. The medical record Bhall include information regarding* the nature of the employment , the
    results of the pre-employment medical examination and periodic reviews of health , the
    record of doses that ia used to check that the values laid down in Articles 7 , 8 and 10
    have not been exceeded , and the record of doses received in the course of accidental and
    emergency exposures .
Section 2 - Special surveillance of exposed workers
Article 36
Special surveillance shall be provided in each case where the dose limits laid down in Artic­
les 7 and 8 are exceeded . Subsequent conditions of exposure shall lie subject to the agreement
of the approved medical practitioner .
Article 37 •
In addition to the routine review of health provided for in Article 33 , provisions shall be
made for any further examinations , decontamination measures or urgent remedial treatment
considered necessary by the approved medical practitioner .
Section ^ - Apgeal^s
Article 38
Each Member State shall lay down the procedure for appeal against the findings and decisions
made in pursuance of articles 32 and 36 .
Chapter IV
Article "V?
1 « Each Member State shall take all necessary measures to ensure the effective protection
    of exposed workers * It shall make provisions relating to the classification of places of
 ---pagebreak---                                                -   16 -
    work, to the classification of workers , to the implementation of arrangements aimed at
     restricting exposure and to monitoring. It shall also establish a system or systeirs of
     inspection to supervise the examinations and monitoring specified in this Directive and
     to initiate surveillance and intervention measures whereever necessary ,
2, Each Member State shall make the necessary arrangements to recognize the capacity of the
     experts responsible for the examination and control of the various protective devices and
     measuring instruments and to approve medical practitioners responsible for the medical
     surveillance of category A workers . To this end, each Member Sts.te shall arrange for the
     training of such specialists .
3 . Each Member State shall make sure that the means necessary for proper protection are
     placed at the disposal of the ■ departments responsible. The creation of a specialized
     radiation protection unit shall be required for all establishments in which there is a
     serious risk of exposure or contamination . This unit , which may be Bhared by several
     establishments , shall bo distinct from production, and operation units .
4o Each Member State shall facilitate appropriate access within the Community to all relevant
     information concerning the posting of each exposed worker and the doses received.
5. For the guidance of medical practitioners responsible for the medical surveillance of
     exposed workers , each Member State shall draw up a list , which need not be exhaustive ,
     of the criteria which should be taken into account when judging a worker 's fitness to be
     exposed to ionizing radiation .                          *
TITIE VII » FUNDAMENTAL PRINCIPLES GOVERNING OPERATIONAL PROTECTION OF THE POPULATION
Article 4P
1 . Operational protection means all arrangements and surveys for detecting and reducing the
     factors which , in the production and use of ionizing radiation or in the course of any
     operation involving exposure to its effects , are liable to create an unjustifiable risk
     of exposure for the population . The extent of the precautions taken shall depend upon
     the magnitude of the- risk of exposure , especially in the event of an accident , and upon
     demographic datL. Operational protection has application in the medical field as well as
      in other fields .
     «
2# Protection shall include the examination and testing of protective arrangements ana the
     dose determinations to be carried out for the protection of the population*
Article 41
The examination and testing of protective arrangements shall includes                       •■
 (a) examination and approval of proposed installations involving a radiation hazard, ■ and of
        the proposed Bitting of installations in the State ;
 (b) acceptance into service of new nuclear installations with regard to protection against
      . any radiation or contamination liable to extend beyond the perimeter of the installations
        taking into account demographic , meteorological , geological , hydrological and ecological
   • conditions ;
 (c ) checking the effectiveness of technical protective devices ;
 (d ) acceptance , from the point of view of surveillance of radiological hazards , of equip­
        ment for measuring radiation and contamination ;
 (e ) checking that measuring instruments are serviceable and correctly used ;
 (f ) whenever necessary, the establishment of emergency plans and their approval ;
 (g) the establishment and application of waste discharge formulae and provisions to be made
        for measurement .
 ---pagebreak---                                                -  17   -
The .tasks listed in ( a) to (g) shall be carried out in accordance with rules laid down by
the competent authorities on the basis of the extent of the radiation hazard involved .
Article 42
1 . The health surveillance of the population shall be 'based , in particular , on the assess­
    ment of the doses received by critical groups of the population and lay the population as
    a whole , both in normal circumstances and in the event of an accident .
2 . Surveillance shall be carried outj
    (a) on the critical groups of the population and , in particular, in all places where such
          groups may occur ;
    (b) over the whole area for which the dose limit is that laid down for the .whole popu­
          lation .                                   •               v
3 * Taking into account the radiological hazards , the dose determinations to be carried out
    for the protection of the population shall include i
    ( a) assessment of external exposure , indicating , where appropriate , the quality of the
          radiation in question ;
    (b) assessment of radioactive contamination , indicating the nature and the physical and
          chemical state of the radioactive contaminants and determination of their activity and
          their concentration ;                                                     •
    (o ) assessment of the doses that the critical groups of the population are liable to
          receive in normal or exceptional circumstances , and specification of the characteris­
          tics of these groups ;
    (d) assessment of the genetic dose and of the annual genetically significant dose , taking
          demographic characteristics into account .
          Doses due to exposure to various sources must be added together wherever possible .
    ( e ) The frequency of assessments shall be such as to facilitate compliance with this
          Directive .
    (f ) Records relating to measurements of external . exposure and radioactive contamination
          and the assessment of *he doses received by the population , shall be kept in the
          archives and shall include accidental and emergency expoTurras .
Article 43
1 . Each Member State shall establish a system of inspection to supervise ths protection of
    the health of the population , to interpret in terms of the effocts on health the results
   'of the assessments required by Article 42 (3 )» and to test compliance with the dose
    limits laid down in Article 11 .
2. Each Member State shall initiate action in regard to surveillance and intervention
    wherever necessary .
3 » Each Member State shall take measures to ensure and effectively coordinate the health
    surveillance of the population , shall decide the frequency of assessments and shall take
    all necessary steps to identify the critical groups of t' ■; copulation , taking into account
    the effective pathway of transmission of the radioactive       . erial . These measures may ,
    if necessary , be taken by one Member State jointly with ct'-i >r Member States .
4. In relation to possible accidents , each Member States
    ( a) shall stipulate intervention levels , measures to be taken by the competent authorities
          and surveillance procedures with respect to the population groups that are liable to
          receive a dose in excess of the dose limits laid down in Article 11 .
    (b) shall determine and provide the necessary resources both in personnel and in equipment
 ---pagebreak---                                         - ne ~
           to enable action, to be taksn ic safeguard and maintain the heal+.h of the
           population . Thees measures may , if nac-ssa&ry , be taken by one Member State
           jointly with other Member Sta.tea ,
  5, Any accident involving exposure of the population to radiation must be notified
       as a matter of urgency , when the circumstances so require , to neighbouring Member
       Statas and to the Commission of the European Communities .
  Article 44
  Any amendments required to adapt the harmonized 8+e.ndards to scientific progress
  shall be adopted in accordance with the procedure laid down in Article 46 .
  Article 45
  1 . A Committee responsible for adapting the Annexes in this Directive to technical
       progress (hereinafter called 'the Committee' ) is hereby set Tip . It ehall consist
       of representatives of the Kember States and be chaired by a representative of the
       Commission .
  2 <> Th® Committee shall draw up its rules of procedure .
  Article 46
  1 . Where the procedure laid down in this Article iB to be followed , matters shall be
       referred to the Committee by the chairman , either on his own initiative or at the
       request , of the representative of a h'smber State . .
  2, The representative of the Commission shall submit to ths Committee a draft of the
       measures to be adopted . The Conmittee shall deliver itB opinion on the draft within
       a time limit which may be determined by the chairman according to the urgency of
       the matter . It shall decide by a majority of 41 votes , the votes of thp Member
       States being weighted as provided for in Article 148 ( 2 ) of the Treaty . . The
       chairman shall not vote .
  3* (a) The Commission shall adopt the measures envisaged where these are in accordance
     /      with the opinion of the Committee .
       (b ) Where the measures envisaged are not in accordance with the opinion of the
            Committee , or if no opinion has been given , the Commission shall forthwith
            propose to the Council the measures to be adopted . The Council shall act by
            a qualified majority .
•      (c) If, within three months of the proposal being submitted to it , the Council
            has not acted, the measures proposed shall be adopted by the Commission
  Article 47
  1 . Each Member State Bhall put into effect the necessary measures to conform
       to this Directive within a period of two years from the date of notification.
  2 . Bach Member State shall inform the Commission of the arrangements it has made
       to comply with this Directive *
  Article 48
  This Directive is addressed to the Member States *                                 v
  Done at Brussels ,
                                                                                          •<
                        .                                  Por the Council
                                                             The President
           5020778e
 ---pagebreak---                                                                    ^■ '-'ΤίίΓΝΕΧ Τ
   Values of activities not to be exceeded, in compliance with Article 4 ( a)» for the radio­
   nuclides (*) listed in the left -hand column a^e indicated by an X in the various columns
   of the following table :
                                                                                                                I
                     ..     ..                 ...     Group I                Grouo II          Grouo III             Group I V .
                                !                       5kBq                  50 k3q g .     500       k3q            5000 kBq .
                                                       1 tU' -j- ÎO                           1 . "*r x1 Q~\, .       1 . h X 10~ C
                               Ridionudid-»                         Ci                                      01
                     1         H    – 3                                          - ^                                      X
                     4   ■     Bs –     7   ' ' '                                                •     X
                     6         C    – 14-                                             - I "            x–!
                     8 V O          – 15      "                                          I-                   • !         X
                     9    " F       – 18                                                  I            X        f
                    Il         Na – 22                                            X
                    11         Na – 24             [                                                   X
                    11         5i   – 31                                                               v        I
                                                                                                       A
                    15         P    - 32                                                               X
                    lô         S    – 35                                                               X
                    17         Ct – 3S                                         •  X
                    17     : Cl - 33                                                                   X
                    18         Ar – 37                                                                            !       x
                    18         Ar – -il                                                                Χ
                    19         K    - -'.2                                                             X
                    19         K    – 43                                                  I            x-
                    20         Ca - Î5                                            X
                    20 .       Ca – 47
                    21         Sc – 46                                            Χ         Γ             :
                    21          Sc –17                                                                 χ __^              :       :
                    2i          Sc -•!-»                                                    I          >'
                    23          V   – il S                                !              J             x
                     2-t        Cr – 51                                                                X
                     2^         Μη – 52                                                     I          X
                     J-3        Mn – 54                                           X
                     2j         Ma – 56                                                                 *
                     25         Fe – 52                                                                 X
                     26          Fc – 55             1                                       L          *
                     25          Fe – 59                                                                5
                     27           Co - 56                                   I      x         !
                     27           Co – 57                                   !                I          x         1_
                     27           Co - 53                                            __J                *
                      27          Co – 58m                                                    I        •- •         I       χ
                      27          Co – 60                                          χ        Τ
                      28          Ni – 59                                                                           1       x
                   . 2S           Ni – t>3                                                    1         *
'' '(^IWalphabetical list of elements appears at the end of . this Annex
                                                                                                                             »«
 ---pagebreak---                                                      -       20     -
                                          Croup f         Crctp Q                C>T*ipfu      |          GlfUlp IV
              Rairotwcn;#»           |    io   a            «)-' Ci
                                                                                  i'.>- Ci     j           !«>-» Ci
28          Ni – fvï                 T                                               x
29          Cu –64-        -         T                                                X
30          Zr» – G.1»            • !                                                 X
30          Zn –ôl>m                  j                                               x        !
30          Zti – 69          • -     J                                                                       X
31           Ga – 79.                 T                               i               X
                                                                                                                   Τ
32           Ge – 71                                                                                           Χ
33       - As - 73                    I                                    '          X      . |
33           Aj –71                  1                                       .        X
33        ■ As – 76                  T                 -
33           As – 77                                                                  X
Z*      - Se – 75 ■'                                                                  X                I
35 •         Br – 82 .            ..                                                  X          I
36           Kr –&>m * - • j                                        '  i              X
3o           Kr – 8.5                                                                                          X
 36    ... Kr – 87       -.                                                                    J
 37        • Rb – 86          !                                         i      ■      X    '
 33           Sr –85rn            ■1                                                                           X
 38           Sr – 55                                                                 X              .  .    .   .   •
                                                                                                  i
 38         - Sr – 8!)                            I     .       X
 38           Sr –90                                            X
 33           Sr –91                                                                   X
 33           Sr – 92                                                                  X
                                                             ♦
 3')          Y   - SO                                                                 X
 39           Y   – 91m        •.                                                                              X
 39           Y -91                                             X
 39           Y –92
  39          Y - - 93                                                  r              x
  40          Zr - 93       ,                                                                      I            X
  *0          Zr - 95 .                                   ■     X
  40          Zr - 97                                                                  X
  4'.          Nb –93 m                                                                X
  •i !         Nb –93                                                                  *
  41           Nb –97                                                                             Γ *
  42           Mo –99                                                                  X
  43           Te –96m                  J    :                                                                  X
   43          Te – 56                                                                 X
   43          Te – 97m                                                                 X
   43          Te -97                               I                     Γ             χ
   43          Te – 99m                             i                                                           X
   43          Te –99                                                     Ι             X
   44          Ru –97                                                     r             *
    44          Ru – 103                                                Γ               *
    44          Ru – 105                                                                X
    44          Ru – 10H                                         X
 ---pagebreak---                                      - 21    -
                              CrAupt              ÏI   Groo¡>lü         Croup IV
                              HW Cl         l*r* L*    " lO-i U          If »-» U
45        Rh – IQjin     I                                                  X
 45       Rh – ïOj      J
 46       Pel – 103      [                                 *
45        Pd – ioy
 47       Ag – 105       I                                 X
 47 . Ag – 1 10m •                             X
 47       A~ – 111
 43       Cd - 10'J
 48 .     Cd – U5ai                            X
 4»       Cd – 115      j
 49 _ In –* 1 13 rrt     I                                                  X
 49 - In – 1 14» m        I                    X
.49       In – 115 m      I                                χ
 50       Sn – 1 13                                              1
 50       Sa – 125                                         Χ      I
 51       Sb – 122                                         X
 51       Sb – 124                             X
 51    • Sb - 125                         •    χ
 52       Te – 125 m                                       X
 52       Te – 127m                            X
 52       Te – 127                                         X
 52        Ts – I 2i) m                        X
 51       Te - 123                                         X
  52      Ts – 131m                                        X
                                  "
  52      Te – 132                                         X
  53    " I    - 124                           X
  53       ï – 125                             X
  53       !   - 12'J                                                 "      x
  53       I - 130 !        |                        Γ     χ    __
  53       I   - 131                           5
  53       I   – 132                                       ï
  53       !   – 133                           X
  53       I   – 134                                        X
  53       I   – 135                                        X
  5V       Xe – 131 ni                                                       X
  54        Xe – 133                                                         X
  Ot        Xe – 135                                        X
  55        Cs – 131
   55       Cs – 134m          •                                    1   - x
   55       Cs - 134                            X
   55       C» – l-'.j                                                       X
   5a       C» – I3 (>                                      X
   55       Cs – 137                            X
   5ri      Ba – 131                                 J
   56       Ba - 140                            X
 ---pagebreak---                                                 -   22   -
                                      O-o'-ip S        Cm»»j»U       Croup iil          Cr)np IV
           RM:ionuc/ id«9                               m-» Ci        !!>-•'• Ci          « 0 -» Ci
 57       La – 110              M                                        *
 5^       Ce – 141                                                       *_1
 53       Ce – U3                I                                       X
 58       Ce – 144                                        X
 59       Pr – 142               [
 5'J      Pr – 1-13         " •                                          X
 60     - Nd – 147                                                       X_
 60       Nd – H9                                                  _X               1
 61       Pm – 147                                                        X
 61       Pm – 149 -
 62 ■ * Sm – 151                  I                                       X
 6'> > Sm – 153                 -J                                        X
 63       Eu – Î52m(9 h) 1                                                x
 63       Eu – 152 ( 13 a)                      ■ I       X.     I
 63       Eu – 154            • j                         X
 63       Eu – ! 55 •              I                                      X
  64      Cd – 153                                                        X
  64      Gd – 159                                                 r^<
  65   • Tb – 160                                   !     X                             •       •
  66      Dy – 165           v                                            Χ
  66      Dy – 16o                                                        X
  67      Ho – 166-                                                       X
  63      Er – 169                                                         X
  63       Er – 171       -                                                Χ
  63      Tm – 1 70                 |                      X   "
  CO      Tm – 171                                                         X      ·
  70       Yb – 175                                                        X
  71       Lu – 177                                                        Χ
   72      Hf – 181                                        *
   73      Ta  – 182                                       _■                 *
   7j      \y  – mi                                                        X
^ 74       W   – 195                                                        X    '
   7'r     W   – 137                                                        Χ
   75      Re – 133                                                        χ
   75      Re – 135                                                         Χ
   75      Re – 188                                                         X
   75      Oj – loo                                                         X
   76      Os – 19!rn
                                                                                      '        X
   76       Os - 191                                I_^                     X
    76      Ο» – 193                                                        X
    77      Ir – 190
    77      Jr – 192                                J
    77      Ir – 194                                               L         x
    78      Pt - 191                                               HZ*
    78      Pc – 193m
                                                                                               X
 ---pagebreak---                                            - 23     -
                                   Orouol    Gro'jp U        Crou ^ LU          Croup IV
       "   Ruio)iiKl'.d*i
                                   IO-' CI   lo-* C i         lî#-* Ci           ro -» ci
 78        Pc - 193
 78        Ft – 197m                                                               X
 78        Pt – 197                                               X
 79        Au – 196
 79        Au – 193
 79        Au – 199 •                                             >'
 EO            – 197
 80        Hj – 197ra                                      __ *         I
 80        H3 - 203         -                                     X
 8!        Tl – 200                                 "             X
 81      • Tl – 201       :           -
                                                                  X     I
 81        Tl – 20*2                                    _X             J
 81 ·· . Ή – 204                                X
 82 •      Pb – 203                                               Χ
 êl        Pb – 2!0                  X
 82        Pb – 212           |                 X
 83        Bi – 206                                               X
 83        Bi – 207                             X     •
  83       Bi – 210                        !    X
  83       Β: – 212                                               X
  8-1      Po – 210                   X
  S5       Ai – 211                              X
  85        Rn – 220                                               X      I
  Sä        Rn - 2-22 •        !                                   X
  Si        Ra – 223
  83        Ra – 224                             X
  88        Ra – 2-15                  X
  88        Ra-22S               ι     χ                 I                  I
  S î.      Ac – 227                   X                r                               ■ .
   89       Ac – 22^                              X
   9-3      Th - 227                   X
   90        in – 223                  Χ
   90       Th – 230                 ■x
   90       Th – 231                                               X
   C0       TU – 232                                                                  X
   90       Th – 234                              X
                                                                                      X
   90       Th rati 4)
   91        Pa – 230                      n *
    91       Pa – 231                   X                                     1     '
    91       Pa – 233                                            -.X
    92       U – 230            1
    92       U – 232                    X  1            J
(•) One becquerel of natural thorium corresponds to 1 alpha disintegrate p, r
second (0.5 disintegrations per second of Th-?32 and 0.5 disintegrations <,er
second of Th-228 ). One curie of natural ttogium corresponds to 3-7 x 10
alpha disintegrations per second ( 1.85 x 10 ,u disintegrations per secona
Th-232 nnd 1 .85 x 101° disintegrations per second of Th-223 )
 ---pagebreak---                                                                 -         24   -
                                                                                                       .
                              |v*cî.O"<K.«irîrt
                                                       I1       Cm:p (
                                                                Itl -» Ci
                                                                                       OrvipU
                                                                                       ' ;1 -" Ci
                                                                                                       j
                                                                                                       '
                                                                                                         C.-y.ip Lit
                                                                                                          I'-1 Ci
                                                                                                                          Ctonp IV
                                                                                                                           10 - « Ci
                 m       u – -*>-*                           ______                                                  j
                 ;:v     '0 – 234                                    x'        !
                                                                               L
                                                                                                     • L             s
                 VI' U - ^5                                                                                                   X
                 <ï'2 U – 235                           j                                   X
                 P2 - U – 238                            |                                                                    X
                 92 U nal {"')                          [                                                                     X
                 Cj> Û – 240 +■ 93»Mp~240j                                                                    X       I
                 03 Np-237                      "        [           «i/
                                                                     A
                 93 Np – 239                                                                                  X.
                 94 Pu –23.S                        -"j            • X
                  9+      Pu - 239              •  .                 X
                  94      Pu –240              :•  ■.*
                                                                                               *
                  94      F<< – 2+1                                  X
                  91      Pu – '242                                   X                            "
                  94      Pu –243                                                                             X
                  D l P» T -244                    :                                          X
                  95 Am–241                            l              Χ        Ί
                  95 Α-τπ–2-12η*                  ■ 1                 Χ
                  9.5     Am – 242                                                   :        χ       Π
                  95      Am – 2-ki                          __>CIJ
                  95      Am –244-                                                                            X
                   95 Cm –242                              |          X
                   95     Cm - 243                                     x     .   !
                   55      Cm–244                                      x-        !
                   05 .Cm –24.Î                                        X
                " 95       Cm –24(>                                    X
                   36      Cm -247                                                            X
                   96 Cm–248                                           X
                   yci     Cm -249                                                                                      ι    . V
                    97     Bk –241)                                                           X
                    97 P,k –250                                                                                X
                    9-j    Cf _:» 4!>                                   X
                    PS     Cf - 250                                     X
                    9H     Cf – 251                                     X
                    93     Cf - 252
                    m       Cf – 253                                               Γ          χ '
                     93     Cf - 254                                     X
                     9!»    Es - 253                                                          X
                     99     Es – 254m                                                     * X
                     90     F.s - 254                                   X
                                                                                   ■             «
(*) One becquerel of natural uranium corresponds to 1 alpha disintegration per
cecond (0.*f89 disintegrations per second of U-238 , 0.^89 disintegrations per
second of U-23^ and 0.022 disintegrations per second of U-235 ).
One curie of natural uranium corresponds to 3-7 x 10^® alpha disintegrations per
second (1.81 x 1010 disintegrations per second of U-238, 1.81 x 1010 disintegrations
per second of U-23** and 8 . 31 x 10^ disintegrations per second of U-235 )*
 ---pagebreak---                                          -  25  -
 Radionuclides
                               Group I      Group II   j Group III   Group IV
                               10~7 Ci      10~6 Ci    ! 10* 5 Ci    10"4 Ci
   99    Es - 255                  X
 100     Fta - 254                                            X
  100    Fta - 255                              X
  100     Fta - 256                             Χ
2 . In the case of the nuclides In - 115 , Nd - 144 » Rb - 87 , Re - 187 and am - 147
    the requirement for reporting and obtaining prior authorization may be waived ,
    irrespective of the quantities used .
3 . In the case of a mixture of radionuclides belonging to different radiotoxicity
    groups , the requirements for reporting and obtaining prior authorization may be
    waived only if the sum of the ratios between the activity of each of the radio­
    nuclides and the limit laid down in paragraph 1 for the group to which it belon ,-rs
    is less than or equal to 1 .
4 « For radio luminescent paint , the requirement for reporting and obtaining prior
    authorization need not be applied if the overall activity in radioactive subr.Uu
    ces does not exceed 2000 MBq ( 54 mCi ) of tritium , 100 MBq ( 2.7 mCi ) of Pra - 147
    or 0.5 MBq ( 14 /uCi ) of Reu-226 , and where this paini; is kept or used for the
    manufacture or repair of the instruments and timepieces referred to in Article
    4 ( c ).
5 . Radionuclides not included in this Annex shall , where necessary , be assigned
    to a toxicity group by the competent authority .
 ---pagebreak---                                                       ** 26
                         ALPHABETICAL MSi OP "R'iE ELMSNT3
            ÎVraiixr          .
                                    MNime
                                      , .                                 " K«R.i«rMt.fr.ic           K»mc
  Ac              89              Actinium                    M                           7         Kirro^in
  t\z             47              Siivef                      Na                         11        Sodium
  A               13       . ' Aluminium                      i\'b                       il         fciobiurn
  Am              95              Acnsridum                   Nd               .        60          Necdymiufn
  Ar *    • " W                 . Areon •                     Ne                   ■    10          Neon
 As                               Arsenic .                   N                      ■ 28           Nickel
 Ac •             85              Ascatirie                   No .                    102          NobeUum
 Au               75!     ; • Goid         - •    .           Np                        93         Neprtinium
 Β                  S        : coron            .
 Ba               56 ■                                        O          .                S        Oxygen
                                  Barium
 Bî   .             4                                         Os           •            76         Osmium
                                 Béryllium
 Ut              83         . ' Bismorh
 Bk              97          ■ Berkefium                      Ρ                         15 »       Phosphorus-
 Br                      . • Bromine                          Pa                        91         Procactmium
                                                             Pb                         82         Lsad
                    6            C.irbon                     Pd                        46          Palladium
 Ca              20              Calcium                     Pm                        61          Promcrfuum
 Cd              t3              Cadmium                     Po                        84          Polonium
 Ce              53              Cerium                      Pr                        59          Praseodymium
 Cf              98            . Califoraium                 Pc         :    .         73          Pîacinum
 C               17              Chlorine                    Pu                        9+          Plutonium
 Cm              56              C-urium •     . . •<
 Co              27              Cobalt                      Ra                   * 88             Radium
 Cr              24              Chromium                    Rb                        37          Rub(dium
 Cs              55              Caesium/Cesium              Re                        75          Rhenium
 Cu              29              Copper                      Rh                                    Rhodium
 Dy              66                                          Rr»                       S6      ' Radon
                                 Dysprosium                  Ru                        44          Ruthenium
 Er              68              Erbium
 Es              99             Einsteinium                  s •                       16          Sulphur
 Eu              63             Europium                     Sb                  . 51              Antimony
                                                             5c                        21         Scandtttcn
F                  9            Fluorine                     Sc                        34         Selenium
Fe               26             Iron                         Si                        14         Silicon
Fm         . 100                Fermium                      Sm                        61         Sam?r«um
Fr               87             Francium-                    Sn                       50          Tîn
Ca              31     i        Gallium                      Sr                        SS .       Strontium
Gd              64              Gadolinium
Ge              32              Germanium                    Ta                       73          Tar.ralum
                                                            To                        65          Terbium
Η                  1            Hydrotren                   Te                        43          Technetium
He                2             Helium                      Te                        52          Tcllurium
Hf              72              Mafniurrt                   Th                        90           Thorium
Hg              80             Mercury                      T        .                22
Ho
                                                                                                  Titanium
                67              Holmium                      n                        SI          Thalliurtt
        •       53                                           1 m                      69          Thulium
                               Iodine
In              49             înditim
Ir              77             Iridium                      U          '              92          Uranium     ■
κ               19             Potassium                    V                         23        " Vanadium
Kc            ■ 36             Krypton
                                                            \V                        74     <
i-a             57                                                                                Tungstens
                              Lanthanum
Li                3           Lithium-                      Xe     *                  54          Xenon
Lu              71            Lutecium
                                                            Y                         39         Yttrium
Md           ! 0i             fttandelevitim                Yb                       70          Yeterbium
MS                            Magnesium
Mn              25            Manganese                     Zn                       30          Zinc
Mo              42            Molybdenum                    Zf                       40          Zircouium
 ---pagebreak---                                               ANNEX  II
A. Relationship between the quality factor Q tad linear energy transfer 1^,
              Lo, in water                                  Q (*)
                ( keV/ /um )
           3*5 and. less                                      1
            7                                                 2
           23                                                 5
           53                                                10
         175 and above                                       20
        (*) Intermediate values are to be obtained from the curve in Figure 1 .
B * Values of effective quality factor Q
    Values of effective quality factor Q depend on the conditions of irradiation , aa well
    aa on the type and energy of the incident radiation . For uniform irradiation of the
    whole body by external irradiation , the following values axe to be applied . The same
    values will usually be adequate for other irradiation conditions . If other values art
    needed , they ar'e to be calculated from the values of Q given in A and from the curves
    in Figure 2 .
                          Radiation                                     Q
         X-rays , yrays , prays , electrons and positrons               1
         Neutrons of unknown energy                                    10
 ---pagebreak---                                                    -    28  -
              Conversion factors (neutron fluer.ce rate, c.-n" 2 s~1 corresponding
              to a dose equivalent rate cf 1 yuSv h"1 arid 1 mrera h~1 ) a_nd
              eflective quslicy factor Q as function of neutron energvj" ?
              (The factors may also be used to relate neutron fluence rate
              and dose equivalent index rate .)
                                    Conversion factor ^          ^ -     Effective
  Neutron energy                                                         qual-ity   factor
               MeV               (cm § ^ ) per       (
                                                     ( cn-2 3.-1 ). pei* Q (2 ) ( 3 ) .
                                  . CuSv     )       (nrem h~ 1 )
 2 '5 • 10 9 (chernw)                26                    250                  2-3
    1 • lû-*                         2k                    240                  2
    î • Î0-"                       . 22                    220                  2
    1 " 10~*                         23                    230                  2 .
    s • î<y~*       -■■ ■ \          ?Μ                    240 .                2
    ι - ίο-*                         27                    270                  2
    ! • 10-*                         23                    2S0                  2 •
   2 • ÎO"*              : !         17                    170                  3-3
    5 - 10-®                                                S5
    1 - 10-»                                                                    5-7
                                                            43                  74
   5 - 10-*                          1.4·                   14
    1                                0.85                                      11
                                                             8-5               10-6
   2                                 0.70                    70
   5                                                                            9-3
                                     0.63                    6-S                78
  10                         !       0.68                    6-3                6-8
  20                .                0.65                    6-S                6-0
 iO                                  0.61                    61                 5-0
    1 • If; 1              j         0.56                    5-6                4-4
   2 • 10-                           0.51                    51
   5-10 2                            0.%                                        3-8
                                                             3-6                3-2
    î • jO1                          0.22                    2-2                2-8
   2 10»                             0.16                     1-6               2-6
    3 - 10»                          0.1U                    .1-4               2-5
 ( ) j?or        undirectional broad
           incidence .                    *
                                            beams of monoenergetic neutrons at normal
.(2 ) At the point where the doss .equivalent rate is maximum .
 ( 3 ) Figures
          Intermediate 3 and
                               values are to bs obtained frora the curves ia
 ---pagebreak---                                               -  29   -
                                                                     -2    -1
                D      Conversion factors ( protjn fluence rate , cm     s    ) corresponding to
                       a dose equivalent rate of 1 ^uSv h ^ and 1 mrera h-''") and effective
                       quality factor Q as function of proton energy ( l ). (The factors may
                       alBO be used to relate proton fluence rate and dose equivalent index
                       rate) .
«
                        I
                                  Conversion factor ( 2) ( 3 )        j
                          /    –2    –1 \           ( -2 - lx
  Proton energy           ( cm     s    ; per       ( cm   s ; per      Effective quality
        MeV               ( /uSv h"1 ) t            (mrem               factor Q     ( 2)
  2 to 60                       0.040                    0.40                   1.4
           2
  1   . 10                      0.041                    0.41                   1.4
  1.5 . 10                      0.042                    0.42                   1.4
  2   . 10                      0.043                    0.43                   1.4
  2.5 . 10                      0.21                     2.1                    1.4
           2
  3   . 10                      0.24                     2.4                    1.5
  4   . 102               .     0.25                     2.5                    1.6
  6   . 10                      0.24                     2.4                    1.7
  8   . 10                      0.22                     2.2                    1.8
  1   . 103                     0.20                     2.0                    1.9
  1.5 . 103                     0.16                     1.6                    2.0
  2   . 103                     0.14                     1.4                    2.1
                                                                   \
  3   . 103                     0.11                     1.1                    2.2
                ( 1 ) Calculated for unidirectional broad beams of monoenergetio
                      protons as normal incidence
                ( 2) At the point where the dose equivalent rate is maximum
                (3 ) Intermediate values are to be obtained from the curve in figure 5 .
 ---pagebreak---                            30   -
E   The method of evaluating the effective doee .
    The effective dose is equal to
                Τ
    Where H^, is the average dose equivalent in the organ or tissue ,
    T and     is the weighting factor for the organ or tissue , T.
    The valueB of the weighting factors are shewn belowi
    Gonads                    0.25
    Breast                    0.15
    Red Done marrow           0.12
    Lung                      0.12
    Thyroid                   0.03
    Bone ( surfaces )         0.03
    Remainder ( l )           0.30
    In assessing the contribution from this remainder , the average
    dose is to be evaluated to each of the five most highly exposed
    organs or tissues of the remainder ( excluding the lens of the eye ,
  ♦ the skin , and the hands , forearms , feet and ankles ). A weighting
    factor of 0.06 is to be used for each of these organs or tissues *
    The exposure of all other organs can then be neglected .
 ---pagebreak---     2o                                                               A
    15
             *
             %
                                                               Z^J
    lo
                                                                                                    ι
                                                                                                   L>J
€    _
p.   5
8
c+-
O
                                       1     I   II    M       ,        L–1 I I I III
                            10
                                                   Linear Energy Transfer in Water (Loo ), keV/^um
       Figure Is Quality factor as function of Linear Energy Transfer in Water (L <*»)
 ---pagebreak---                         1   !–                              1        I     I ΓΗΓΊΓΠΤ"                  1         !      I ΓΤΊΓΠ
               "                            1       . \     \                                  1         » electrons
               –                                         \ \                                             b muon* • ' ■
               ~                                           \ \                                      . • c pions .... . * 1             . ~"
                                                                       \                                 d kiions " .•                   –  . • ■ »
                                                                  \                   '•         '       e protons ■                     _
                                                            '          \ \               '       •'      f dcutcron'i '
            15    :   '              .      r~ '                   '     \\                              5 triioiK ,
                .                           I                              XX .                I         T M.T - » * '           I •     •-
                               '                                -          \ \                           h He Ion*
                                                                                                         i alpha particles         r.    –
H
    CM
    m  1
\ \
l :
ii
         O
         fc
         W
         S
         ÎS
              0Γ    ι     !  I... I Μ1Μ                      1        1 1 1 1 Μ ΓΙ                     1––1–-1–1111 '1(>
         0>    10
                                                                                                                       Pnriiclc cncTgy, McV
                             Ftwt 2: Qurdhy factor* of charged particles a$ a function ofenergy
 ---pagebreak---                                                                                                                                                                  r.eutrcn cnerry , i-:ev .
          q3■ –i–[–rTrrmr~ i ' m-rrrr~ ■ 1 ... rry                                                           '-–t–r-^-^rr, r–rT-TTrrVp^^T^ 'C
                                                                                       .                               -                                   .                 .         .                           -               1          ~
                -                                   .           ,· .                ·           .                              .                                          1                         ν.                                     .·-
                                           . Use uppor scale                              *                   -                                                                ■                       '          •                 ho5 v
   . io2                            J                     –                                                                                                                                                                       i- b
 ^                                    1                                     »                                   •                             J                                                                ■                  j            w
 A
               E
               U
                                               i                                         •                                             •                         .
                                                                                                                                                                                                      . .           ..
                                                                                                                                                                                                                                  3
                                                                                                                                                                                                                                  j
                                                                                                                                                                                                                                                  ^
                                                                                                                                                                                                                                                  a>
   >           r                                i             ■                             •
                                                            ■                                                      •                              . . v.:ï                                               X.                               s' »
   S                     *                                                                                                   :                              ■ • ■                        I                    X                     J 10 r\j
   Q,                                                                                                -               ■                      ■                      1        " – 11 - I              ■            *■– * vv     ' 1             I
 ^
          10 • C=                                                                :                                . •                                   ;«               t      .                      *
                                                                                                                                                                                                              . \x. -"                        'Ho
r-               -                                                                    \ r*                                                               ;    M •                                     < ;                       >»A           w
 1«           n                                                                                     "                    "                                            •           •               ; !-                            V               w
               TX.V
               T  \v       ^                                             :                                                                              ;                                      ,■                                 .+i             C
\  n
               f\       N»
                                         .                      •                                                      ..          •                                                                  ■
                                                                                                                                                                                                                         ■        - -8         ■*->
   O             .    •  \.                                                                                                 •                                                                                                                    »
                                                                                                                                                                                                       1                                          O
   – • -■ -i                                                                                  '                                                                                                           i                           tO
      2    1                                                                                         –                                   ■–                                                                                       :    ,w          ..
      ^ '                       1 • n;                    ^                                                                                                                                             i                                         ^
      fe"       r                                                                           .                                                                        • .                                               .   1      .
     ô
    . V<J                            ,
                                                                                                   ^4»..                                            , •                                                    •
                                                                                                                                                                                                                                                  r>
                                                                                                                                                                                                                                                . »■*
    W.                                                                                                                                                                                                                                            O
      Ç                                               '                                                                                                                                                   '                       "            «H
     ,x                        •*              v                              \                                                                                                                                                                   (0
      c                                      Uce lower scale                                    •                   ^2»                                                                      ■ • ' ■                                  1           Jh
      > 0.1-1           I I I i I M il      I i i l i ini        I i 1 i I ti li           I I,,', U.U'l.          1 1 I .1 I.M il                    1 1. .Ili I.1M                                   -1 L-L.l. Il II )                          £
    Â          i /i-l                  I                iO                    . 10'                       J03             •      . .       < l>"                                                                             . . ,,               g
    O          J0                     1                                                                                                                                            .              neutron energy, McV
                                                                                                                                                                                                           I
                                                                                                                                                                                                                                                  o
                                                                                                           '                                    '              '                                          *»      -,                     •'  '
                                                  •                                                    . •                           t                                                       ,             «ç
                                                    Fi"urt    Factors for eonvcriing nculron Hucnce role to dose équivalent nie                                  !..                               . !             "
                                                                                                                                                                  :                  "     •        •- f         • ... .    • ■
                                                                                                                                                                        ,                     . .i . \                      v;
 ---pagebreak---               Mi                   ΠΓΤΤΤΤίΤ     ΓΤΤΤΠΊ1 –Γτττττπ ί                   1   ΓΓΓΤΠΊ        ί ΓΤΤρ'ΙΊ                !  1 ΓΠΤ1Τ              1   ΓΊΤΤΠΤ
                      1  ΓΤΤΤΤΓΓ
                                                         [
                                                                                                                 /
              12
     :■·
»
i    ■
 i ;                                                                                                                    I
 j ;
 1    i       10
                                                                                                                            / .   .. :      *
 ί I":                                                                                                    '            I                             1
  ί                                                                                                         * 1 I
  i   »                                                                                                                                •*! ' i
  Ï ;;                                                                                                                                           I
  u:
        H                                                                                                                                              ~–_–J
    il
                                                    7
                                 i                /
    i1 1  ÎO                , V
        »
     i'    S
            c
    il     SÏ
                                                               ,  · ·        I
                                                                             ]
                                                                             I                                           ,         *
                                                I Mill !      I   1 I I MU      ,    i 1 1 i uni       u I 1 1.1 u              i i i niii              L,J„,U.Li.D.
        M   υ
                 , i_LJLJ_LLLU     L-/ / 1111,1                                                                    \ i   ii                   ii
           S                                                                                                                                       neutron euer^y, Mev :
                                                       Fi'm <1: Infective quality f.-.clorj jo? ncuuws
 ---pagebreak---                                                                                                                                                           7. C,
            0Ô5         1   1     1   1    ΓΠΤ                               .     [– !    | | | Γ                    1      Γ      ΓΙ I          ι   I ί
            0.3                                                                 ;                      I
                                                                                                         •            *        » ■.    '     . ',   *
                                                                                                                                                                :   x!
                                                                                                                                                                     B
                                                                                                                                                                     o
             0.25                                                     \                              _                                                               u
                                                                                                                                                                     E
                                                                                                                                                                 i    h
                                                                                                                                                                      o
              0.2             ' '
       >                      ■     .             .  I                                                                                                                (0
      02
                                                                                                                                                                   ru
                      ν                              ι
       <u                                             I
                                                                                                                                                           1.5-
                                                                                                                                                                      (0
LTs                                                                                                                                                                   c
rO                                                                                                                                                                    o
                                                                                                                                                                     4J
       io                                                                                                                                                              O
    ru
                                                                                                                                                                       P<
       ε '
     - ι.                                                                                                  '       ■» • . • ""  ' .*     * •   "t                      O
                                                                                                                                                                      4J
           »                                                                         r
                                                                                                                                                                       o
           c                                                                                                                                                           (S
           ?                                                                                                                                                          «M
                    –     Ψ                                                                                                                               .0.5
           [70.05 1                                                                                                                                                    fi
                                                                                                                                                                       o
                                                                                                                                                                      •H
                                                                  1                                          0  .                         «
          £                                                                                                                                                            (0
           C
           0                                                                                                                                                           0)
          *v>                                                                                                                                                          > '
                                                                                                                                                                       G
           î <          I   I     I   1    I  I  M                  I   ·    I     ι   I   1   ι I I                  i _i          i      i i 1 1 r                  O
                                                                                                                                                                       O
          υ
                                                                                                                                      proton cncrgy, McV *
                                        Fiyvre 5: Factors for converting proton fiucnce rate to dou* equivalent rato
 ---pagebreak---                                                     -   .36       -
                                                 Annex III
1 Limits of annual intake by inhalation , and derived limits of concentration, of
radionuclides in the air inhaled for exposed workers , and limits of annual intake
 by inhalation and ingestion for members of the public .
      The figures it Tables 'la and 1b correspond with the limits of annual dose laid
down in Articles 7t 8 and 11 &r exposed workers and members of the public .
      The figures in Table 2 are those laid down in the Directive of June 1976 .
They do not correspond exactly to the limits of annual doee laid down in Articles 7 »
8 and 11 , but as an interim measure compliance with these values shall be deemed
to achieve compliance with the limits of annual dose laid down in Articles 7 * 8 and 11
      The values of Tables 1 and 2 relate to adults .                     In the case of children
account must be taken of anatomical and physiological characteristics which may
require modification to these values .
                                                    Table 1a
                                                 Exposed Workers               Members of tljePublic
                                        I Lirait of             Derived         Limit of       Limit of
                                        i emnual intake         limit of the    ànnual        annual
                                           by                   concentration   intake by      intake by
  PadionUclxdes            Form
                                           inhalation      j    in air for an   inhalat ion    ingestion
                                                       " I exposure of
                                    ■ I
                                                            I
                                                                2000 h/y
                                    "I         kBq         j      – kBq            kBq           kBq
                            i   i
                      hO-H O
                      Cr4 *(4
                    • rt - rl 73
                    -a xi . as
                      e 3      u
              *       <DrH
                      O-O      <D
                      a> to x
                    "0 =      +»
                                   <D
                           a>     x>
                         .CO -H
                      O           rH
                    -pro
                           C >> 3
                    r O +> fl
                                         ι                    I
 ---pagebreak---                                                                        α          -
                                                      Table 1b
                                                                                                            !              ,                       _   • I
                                                      E:ccossd V/orker s                                    I        Members of , the Public             |
                                                                             Derived                                 dirait of           ; Limit of  j
                !                                                                                                    annual                annual    \
                 i                     * Lirait 01                 j         limit of the
                                                                                                                                         ' intake by
Radionuclides   I                       . annual                                                                     intake
                         Form j      i
                                         ; intake by
                                                                             concentration
                                                                             in air for                       '       by                   ingestion
                                    I   I inhalation                         an exposure                              inhala­
                                         i
                                         I .                                 of 2C00 h/y                              tion
                                    i   4. >
                                                  juCx                    /UCi cm                                       ïiCi
                                                                                                                                         –    1
                                                                                                                                               pCi
                                                                                                                      -j
                      to ^
                     e -S*
                   • H -H
                   TJ     r~{
                     C     H !
                     <l>  £> O
                     P«    3-rl
                     O    iHtl
                   •o      o d
                                  C
                           a o
                     - XX
                     o        +J P­
                   4-»            C
                           C«w
                   t-      o  o   c
                                                                                            «
                                                         Table 2
                                                                                                    Maitturi w oub*«c '
                                                                                                                   ι
                         Uotils »T                            Soiu of
                                                . tO«<en»r»t;w;«.?» ^se- A4*
                                                                               II     Sinîts oC
                                                                                     btù** by iaiwi .. t<Q«
                                                                                                                         îimtit oX
                                                                                                                       LW»9 l>/ )i. .*^fW
                                                      for ei9ui<ii« J
                                                       lCOtth/ ror
              [                pa            !|      Ci m-->                        . .     i»a                 -I
 ---pagebreak---                                    -  38 -
2    Mixture of radionuclidoe
     i' a) if the composition of the mixture is not kao^-n but the presence of
     certain radionuclides can be positive1/ excluded , use &hall be made of
     the lowest limit laid down for the radionuclides that may be present ;
     (b ) if the exact composition of the mixture is not known , but the radio­
     nuclides in it have been identified , use shall be made of the lowest
     limit laid down for the radionuclides present ;
      (c ) if the concentration and toxicity of one radionuclide in the mixture
     predominate , the limit of annual intakes to be used are those given for
     the radionuclide concerned in Section 1 }
  •' (d ) when dealing with a radionuclide mixture of known composition one of
     the following conditions shall be met *
                r ■" ^
                                      or
      where I. is the annual intake of radionuclide j and I. T is the limit of
               0
       annual intake of that radionuclide ,    is the annual average concentration
       in air of radionuclide j and C. r is the derived limit of concentration of
                                      &
       that radionuclide in air *
 ---pagebreak---                          -   39  -
                         ANNEX IV
ESTABLISHMENTS AND PLANTS REFERRED TO IN THE SECOND PARAGRAPH OP
ARTICLE 2 0(a)
1.   Establishments and plajnts including reactors and critical
     assemblies .
2.   Establishments and plants including accelerators and X-ray
     generators .
3«   Establishments and plants including sealed sources used in radio
     therapy , gammagraphy , and industrial irradiators .
4*   Industrial plants involving work with thorium and natural or
     enriched uranium :
     - uranium refining plants ,
     - ore concentration plants .
5.   Plants for manufacturing fuel elements .
6.   Plants for processing irradiated fuels .
7*   Uranium and thorium mine workings .
8.   Radioactive waste processing plants and storage sites *
9.   High activity laboratories and plants .