Proposal for a Council Directive laying down the basic safety standards for the protection of the health of workers and the general public against the dangers arising from ionizing radiation
Date: 1993-07-20
Institutions: European Commission
Subjects: health legislation, health risk, ionising radiation, occupational health, public health, radiation protection

COMMISSION OF  THE EUROPEAN  COMMUNITIES 

C0M(93) 349 final 

Brussels, 20 July 1993 

Amended proposal  for a 

COUNCIL DIRECTIVE 

LAYING DOWN THE BASIC SAFETY STANDARDS 

FOR. THE PROTECTION OF THE HEALTH 

OF WORKERS AND THE GENERAL PUBLIC 

AGAINST THE DANGERS ARISING FROM  I ON IZING RAD I AT I ON 

Jsp 

(presented by the Commission pursuant  to Article 149(3) 
of the EEC-Treaty) 

-  2 -

EXPLANATORY  MEMORANDUM 

Article  2(b) of  the Euratom  Treaty  provides  for  the establishment 

within  the Community  of  uniform  basic  safety  standards  to protect 

the health of workers and of  the general  public against  the dangers 

of  ionizing  radiation.  These  basic  safety  standards  were  first 

adopted  in  1959  by  means  of  a  Council  Directive*1*  and  have 

subsequently  been  amended  on  several  occasions  to  take  account  of 

developments  in  scientific  knowledge  in  the  field  of  radiation 

protection.  The  version  of  the  basic  standards  currently  in force 

dates  back  to  1980,  with  amendments  mainly  affecting  their 

technical  annexes being made  in  1984(2). 

(1) Directives  laying  down  the  basic  safety  standards  for  the  health 

protection of  the general  public and workers  against  the dangers of 

ionizing  radiation  (0J of  20.2.1959). 

(2) Council  Directive  80/836/EURATOM  of 

15.7.1980  amending  the 

Directives  laying  down  the  basic  safety  standards  for  the  health 

protection of  the general  public and workers  against  the dangers of 

ionizing  radiation  (0J L 246 of  17.9.1980,  p.1). 

Council  Directive  84/467/EURATOM  of  3.9.1984  amending  Directive 

80/836/Euratom as regards  the basic  safety  standards  for  the health 

protection of  the general  public and workers  against  the dangers of 

ionizing  radiation  (0J L 265 of  5.10.1984. p. 4 ). 

- 3 -

2.  Until  1986, the only  legal  instruments adopted by the .Community in 

the radiation protection field, based on Article 31 of  the EURATOM 

Treaty,  were  these  basic  safety  standards  together  with  a 

Directive  laying down basic measures for the protection of persons 
undergoing  medical  examination  or  treatment*3*.  Since  then, 

following  the  accident  at  Chernobyl,  a  number  of  additional 

measures have been introduced  to reinforce and complement existing 

Community  provisions for  the protection of health against  ionizing 
radiâtion<4>. 

(3) Council  Directive  84/466/EURATOM  of  3.9.1984  laying  down  basic 

measures for the radiation protection of persons undergoing medical 

examination or treatment  (OJ L 265 of 5.10.1984, p.1). 

(4) Council  Decision  87/600/EURATOM  of  14.12.1987  on  Community 

arrangements for the early exchange of  information  in the event of 

a radiological emergency  (OJ L 371 of 30.12.1987, p.76). 

Council  Directive  89/618/EURATOM  of  27.11.1989  on  informing  the 

general  public about  health protection measures  to be applied and 

steps  to be taken  in the event  of  a  radiological  emergency  (OJ L 

357 of 7.12.1989, p. 31). 

Council  Directive  90/641/EURATOM  of  4.12.1990  on  the  operational 

protection  of  outside  workers  exposed  to  the  risk  of  ionizing 

radiation during their activities  in controlled areas  (0J L 349 of 

13.12.1990, p. 21). 

Council  Directive 92/3/EURATOM of  3.2.1992  on  the  supervision and 

control of shipments of radioactive waste between Member States and 

into and out of the Community  (0J L 35 of 12.2.1992). 

Council  Regulation  87/3954/EURATOM  of  22.12.1987  laying  down 

maximum permitted  levels of radioactive contamination of foodstuffs 

and of feedingstuffs following a nuclear accident or any other case 

of radiological emergency  (OJ L 371 of 30.12.1987, p. 11). 

- 4 -

(4 continued) 

Commission  Regulation  89/944/EURAT0M  of  12 April  1989, laying 

down maximum permitted  levels of  radioactive contamination in 

minor foodstuffs following a nuclear accident or any other case 

of radiological emergency (OJ L 101 of 13.4.1989, p. 17). 

Council  Regulation  89/2218/EURAT0M  of  18.7.1989  amending 

Regulation 87/3954/EURATOM  laying down maximum permitted levels 

of radioactive contamination of foodstuffs and of feedingstuffs 

following a nuclear accident or any other case of radiological 

emergency (OJ L 211 of 22.7.1989, p.1). 

Council  Regulation  89/2219/EEC  of  18.7.1989  on  the  special 

conditions for exporting foodstuffs and feedingstuffs following 

a nuclear accident or any other case of radiological  emergency 

(OJ L 211 of 22.7.1989, p.4). 

Council  Regulation  90/737/EEC  of  22  March  1990  on  the 

conditions  governing 

imports  of  agricultural  products 

originating  in third  countries  following  the  accident  at  the 

Chernobyl nuclear power station (OJ L 82 of 29.3.1990, p. 1). 

Commission  Regulation  90/770/EURATOM  of  29  March  1990  laying 

down maximum  permitted  levels of  radioactive  contamination of 

feedingstuffs following a nuclear accident or any other case of 

radiological emergency (0J L 83 of 30.3.1990, p. 78). 

Council Regulation 93/1493/EURATOM of 8 June  1993 on shipments 

of  radioactive  substances between  Member  States  (0J  L  148 of 

19.6.1993, p. 1). 

Commission  Regulation  93/1518/EEC of  21  June  1993  (replacing 

C.R.  92/598/EEC  of  9  March  1992)  establishing  a  list  of 

products  excluded  from  the  application  of  Council  Regulation 

90/737/EEC on the conditions governing  imports of agricultural 

products originating  in third  countries following the accident 

4t  the Chernobyl  nuclear power station  (0J L 150 of 22.6.1993, 

p. 30). 

- 5 -

There  is  also  a  Commission  Recommendation  issued  in  1990  which 

draws the attention of  the Member  States to the risks of exposure 
to radon  inside dwelIings*5>. 

(5) Commission  Recommendation  90/143/EURATOM  of  21.2.1990  on  the 

protection of the public against  indoor exposure  to radon  (OJ L 80 

of 27.3.1990, p. 26). 

- 6 -

3.  The  Community's  basic  safety  standards  have  always  taken  into 

account  to  a  large  extent  the  ICRP's  recommendations,  which 

represent  the  state-of-the-art  as  regards  radiation  protection  and 

also  form  the basis  for  the  recommendations of  other  international 

organisations  with  responsibilities  in  this  area.  The  ICRP 

published  its  latest  recommendations  at  the  beginning  of  1991  in 

its  Publication  60  (replacing  Publication  26,  which  appeared  in 

1977). The Commission,  for  its part, has reviewed  the provisions  in 

the  existing  Directive  in  the  light  not  only  of  the  ICRP's 

recommendations  but  also  of  the  experience  gained  in  implementing 

those  provisions.  The  revision  is,  moreover,  in  line  with  the 

undertaking made  to the Council  in 1987 at  the time of  the adoption 

of  Regulation  87/3954  (see  footnote  4 ). While  the  basic  structure 

of  the  existing  Directive  has  been  retained,  the  following  aims 

have been pursued  in the  revision: 

to  provide  radiation  protection  based  on  the  most  up-to-date 

scientific  Knowledge,  which  should  be  utilised  to  the  benefit 

of workers and  the general  public; 

to provide a sound  technical  and scientific basis and a uniform 

approach  to  radiation  protection,  and  to  ensure  technical 

consistency  with 

the  recommendations  of 

international 

organisations, such as  IAEA, NEA-OECD, WHO and  ILO; 

to update  the provisions of  the existing  Directive, bearing  in 

mind  the basic structure on which  the regulations  in the Member 

States are modelled; 

- 

with  a view  to the completion of  the Single Market,  to preserve 

a  high  degree  of  harmonisation  in  the  radiation  protection 

measures provided  for under  the Euratom  Treaty; 

to  strengthen  the  provisions  on  control  of  radioactive 

materials  in  accordance  with  the  undertaking  made  to  the 

Council  in  1992,  at  the  time  of  the  adoption  of  Directive 

92/3/EURATOM  on  the  supervision  and  control  of  shipment  of 

radioactive waste between Member  States and  into and out  of  the 

Commun i t y. 

- 7  -

4.  Taking  into  account  all  these  factors,  the  most  - important 

amendments  contained  in  the  proposal  for  a  new  Directive  are  as 

fol lows: 

use  of  the  definitions,  quantities  and  units  as  well  as  the 

radiation  and  tissue  weighting  factors  set  out  in  the  latest 

ICRP  recommendations; 

the  inclusion  of  more  restrictive  dose  limits  taken  from  the 

latest  ICRP  recommendations,  which  take  account  of  the  most 

recent  estimates  of  cancer  risk  associated  with  exposure  to 

ionizing  radiation,  together  with  the complex  concept  of  health 

detriment; 

the  introduction  of  provisions  concerning  radiation  protection 

in certain  cases of  occupational  exposure  to  natural  radiation 

sources ; 

the prohibition of  certain unjustified  uses of  radioactivity; 

expansion  of  the  provisions  concerning  protective  measures  to 

be taken  in the event  of  a radiological  accident; 

introduction  of  the  Mdose  constraint" concept  in  relation  to a 

given source; 

changes  to  the  radioactivity  levels  associated  with  the 

authorisation/reporting provisions  laid down  In the Directive; 

5.  The  impact  of  the proposed  modifications on business  is expected  to 

be  limited,  as  a  consequence  of  their  evolutive  character  with 

respect. to  an  existing  Directive.  The  introduction  of  provisions 

concerning  radiation  protection  in  certain  cases  of  occupational 

exposure  to  natural  radiation  sources  is made  in  a  flexible  way, 

especially  to allow  their  progressive  application. 

6.  The  following section consists of  comments on  the  various Titles  in 

the  proposed  new  Directive,  explaining  its  rationale,  scope  and 

aims. 

- 8 -

6.1  Compared  with  the  existing  Directive,  the- scope  of  the  proposed 

Directive  is  to  be  widened  (Title  II).  It  now  covers' expI icitly 

the  placing  on  the  market  and  the  exportation  of  radioactive 

substances  as  well  as  the  operation  of  electrical  equipment 

emitting  ionizing  radiation  and  containing  components  operating  at' 

a  potential  difference of  more  than  5  kV.  It also  covers  exposure 

to natural  radiation sources at  work. 

6.2  The system of  reporting  and  prior  authorisation of  practices  (Title 

III)  has  been  modified:  the  requirements  for  the  application  of 

this  system  have  been  laid  down  more  explicitly  than  in  the 

existing  Directive,  and  in  particular,  the  conditions  in  which 

these requirements may be waived  have been  thoroughly  reconsidered. 

This  will  contribute  to  a  further  harmonisation  of  authorisation 

procedures  within  the Community,  which  will  also  have  an  impact  on 

the achievement  of  the Community's  internal  market. 

6.3  Title  IV  maintains  the  three  basic  principles  of  radiation 

protection 

(Justification, 

optimisation 

(ALARA) 

and 

dose 

limitation),  specifying  that  the  dose  limits  shall  not  apply  to 

medical,  accidental  or  emergency  exposures  or,  in  general,  to 

exposures  from natural  radiation sources at  work. 

As regards  the dose  limits, the  following  steps have been  taken: 

- 

for workers, the new  limit on effective dose  is 20 mSv  per  year 

averaged  over  five  consecutive  years  (100  mSv  in  five  years) 

with  the  further  provision  that  the  effective  dose  shall  not 

exceed  50  mSv  in any  single  year). 

for members of  the public,  the new  limit  for  the effective  dose 

is 1 mSv  per  year.  However,  in special  circumstances, a higher 

value  may  be  authorised  in  a  single  year,  provided  that  the 

average  over  five  consecutive  years  does  not  exceed  1 mSv  per 

year. 

i 

- 

Member  States  will  be  allowed  to  introduce  exceptional 

derogations  from  the  dose  limits  in  accordance  with  the 

procedure  laid down  in Title  X. 

-  9  -

As  regards-the  protection  of  pregnant  women  exposed  at  work,  the 

relevant  provisions  have  been  modified  in  order  to  protect  the 

foetus  as  if  it were  a member  of  the public. 

In  the  case  of  nursing  mothers,  the  competent  authorities  must,  if 

necessary,  establish  dose  constraints  so  as  to  provide  the  child 

with  better  protection  against  radioactive  contamination. 

6.4  Title  V  deals  with  methods  used  for  the  calculation  of 

effective  dose and  refers  to Annexes  II and  III. 

6.5  In  the  proposed  Directive,  as  in  the  existing  version,  the 

fundamental  principles  governing  operational  protection  of 

exposed  workers  are  set  out  in  Title  VI.  They  are  also 

applicable  to  apprentices  and  students,  since  these  two  groups 

may  engage  in activities  involving exposure.  Compared  with  the 

existing  Directive,  the classification of  areas  (controlled  and 

supervised) according  to  the  level  of  risk  associated  with  them 

has  been  preserved,  whilst  the  criteria  for  making  this 

classification 

have 

been 

simplified 

and 

additional 

responsibilities have been  assigned  to  the  employer/operator. 

As  regards  the  classification  of  exposed  workers  into  category 

A and  category  B workers,  this  is no  longer  found  in the  latest 

ICRP  recommendations but  the Commission's  proposal  has  retained 

it  since  it  has  proved  its  value  over  a  period  of  several 

years,  particularly  where  the  organisation  of  radiation 

protection  is concerned. 

6.6  There  are  special  provisions  in  the  proposed  Directive  (Title 

VII)  concerning  exposure  to  natural  radiation  sources  at  work. 

Title  VII  requires  that  the  Member  States  should  first  carry 

out  surveys  to  identify  in which  areas  of  their  territory  and 

for  which  practices  and  working  conditions  workers  are  exposed 

in  a  significant  manner  to  gamma  radiation  or.  radon  from 

natural  sources.  On  the  basis of  the  results of  these  surveys, 

the  measures  described  in  the  new  Directive  must  be  taken.  As 

-  10 -

examples  of  activities  to be  the object  of  such  surveys, and  as 

a  result  of  which  measures may  need  to be  taken,  the proposal 

mentions  operations  in mines  or  other  underground  workplaces, 

operations  with  materials  containing  significant  traces  of 

natural  radionuclides,  and  the  operation  of  Jet  aircraft  in' 

flight. 

6.7  Title  VIII  sets  out  the  fundamental  principles  governing 

operational 

protection 

of 

the 

population 

in 

normal 

circumstances.  Among other  things, this Title provides for  the 

establishment  in the Member  States of a system of  inspection  to 

keep  under  review  the  radiation  protection  of  the  population 

and check compliance with  the national  regulations  implementing 

the new Directive.  In this connection, a number of obligations 

are placed on the operator/employer. 

6.8 Title  IX  represents  an  expansion  of  its  earlier  counterpart, 

owing  to the experience gained  from  the  accident  at Chernobyl. 

It  now  covers  potential,  accidental  and  emergency  exposures. 

The  Member  States  are  required  to  consider  the  development  of 

all  radiological  emergencies on  their  territory  before, during 

and after  the event. 

The  Member  States  must  also  establish  relations  with  other 

Member  States and with  third  countries  to ensure  that  they  are 

better  prepared  for  any«eventuality  and  that  measures  taken  to 

deal with any emergency are  harmonised. 

6.9  Title X contains the final  provisions, the main points of which 

are as fol lows: 

- 

A  procedure  has  been  laid  down  for  modifying  the  lists of 

practices  included  in  Articles  3  and  4  and  for  allowing 

exceptional  derogations  from the dose  limits. 

- 

Each Member  State  shall  report  to  the Commission every  two 

years  on  the  implementation  of  the  Directive, so  enabling 

the  Commission  to  prepare  reports  for  the  European 

Parliament,  the  Council  and  the  Economic  and  Social 

Committee; 

-  11  -

Member  States  must  transpose  the  Directive  into  national 

law within the deadline  specified; 

the above deadline  is meant  to be a single  time'limit, any 

time  limits  appearing  in  the  previous  Directives  being 

superseded. 

6.10 

Annexes 

The  proposal  for  a  Directive  refers  to  values  set  out  in 

its three annexes, which have been revised  in  line with the 

provisions of  the proposed  Directive. 

As  regards  Annex  I,  in  the  existing  Directive  the 

exemptions  from  the system  of  reporting/authorisation  have 

been  defined  in  terms  of  total  activity  (values  ranging 
between  5 x 103  and  5 x 106  Bq 
radiotoxicity  categories,  as  set  out  in  Annex  I  to  the 

spread  over  four 

existing  Directive) and  in terms of  mass  specific  activity 

(100  Bq/g  for  artificial  radionuclides  and  500  Bq/g  for 

solid  natural  radionuclides).  It was  recognised  that  this 

type of  classification did  not  fully  reflect  the potential 

hazard  to workers and  to members of  the public  associated 

with  the  use,  misuse  and  disposal  of  radioactive 

substances.  Consequently,  the  revised  version  of  Annex  I 

sets out nuclide-specific activity  levels and mass specific 

activity values, on a provisional  basis at  this stags. 

-  12 -

Annex  II  .includes  the  radiation  and  tissue  weighting 

factors  in  accordance  with  the  latest  recommendations  of 

the  ICRP. However,  re-examination of  relationships  between 

dosimetric  quantities  and  progress  in  radiation  research' 

may  lead to modification of  these values  in the future. 

The  derived  limits  which  appeared  in .Annex  III  to  the 

existing  Directive  need  to  be  revised  to  take  account  of 

the new  tissue weighting  factors and new metabolic  data  and 

to  achieve  greater  consistency  with  the  proposed  dose 

limits.  Nevertheless,  since  a  re-assessment  of  metabolic 

models  is  in progress,  and  it would  not  be  appropriate  to 

suspend  the  revision  of  the Basic  Standards,  nor  to  embark 

upon  a  revision  of  the  tables  at  this  moment.  Annex  III 

indicates provisionally the methods  to be  applied. 

-  13 -

Amended  proposal  for a 

COUNCIL  DIRECTIVE 

laying down  the basic safety standards  for  the protection  of  the 

health of workers and  the general  public  against  the 

dangers arising  from  ionizing  radiation 

THE COUNCIL  OF THE EUROPEAN  COMMUNITIES 

Having  regard  to  the  Treaty  establishing  the  European  Atomic  Energy 

Community,  and. in particular Articles 31  and  32  thereof, 

Having  regard  to  the  proposal  from  the  Commission,  drawn  up  after 

obtaining  the opinion of a group of persons appointed  by  the Scientific 

and  Technical  Committee  from  among  scientific  experts  in  the  Member 

States, 

Having  regard  to the opinion of  the European  Parliaments1^, 

Having  regard  to the opinion of  the Economic  and  Social  Committee*2*, 

Whereas  the  Treaty  provides  in  Article  2b  that  uniform  basic  safety 

standards  to  protect  the  health  of  workers  and  of  the  general  public 

shaII  be  laid down ; 

(1) O.J. n*  ... 

(2) O.J. n* C  108, 19.4.1993, p. 48 

- 14 -

Whereas Article 30 of  the Treaty defines the basic standards for the 

protection of the health of workers and the general public"against the 

dangers arising from ionizing radiation as: 

(a) maximum permissible doses compatible with adequate safety; 

(b) maximum permissible levels of exposure and contamination; 

(c) the  fundamental  principles  governing  the  health  surveillance  of 

workers; 

-  15 -

Whereas 

each  Member  State  is required  by  Article  33  to  lay  down  the 

appropriate  provisions,-  whether  by 

legislation,  regulation  or 

administrative  action,  to  ensure  compliance  with  the  basic  standards 

which  have  been  established  and  shall  take  the  necessary  measures  with 

regard  to teaching, education and  vocational  training; 

Whereas  in  order  to  perform  its  task  the  Community  laid  down  basic 

standards  for  the  first  time  in 1959 pursuant  to Art.  218 of  the Treaty 

(3)f  and  has since  revised*4) 

(3) O.J. n"  11,  20.2.1959, p. 211/59 

(4) - 

Council  Directive of 5.3.1962  (O.J. of  6.7.1962); 

Council  Directive  66/45/EURATOM  of  27.10.1966  (O.J.  of 

26.11.1966); 

Council  Directive  76/579/EURATOM  of  1.6.1976  (O.J.  L-187  of 

12.7.1976); 

Council  Directive  79/343/EURATOM  of  27.3.1979  (O.J.  L-83  of 

3.4.1979); 

Council  Directive  80/836/EURATOM  of  15.7.1980  (O.J.  L-246  of 

17.9.1980); 

Council  Directive  84/467/EURATOM  of  3.9.1984  (O.J.  L-265  of 

5.10.1984). 

and  supplemented  them*5*; 

16 -

Whereas  the  development  of  scientific  knowledge  concerning  radiation 

protection makes  it necessary  to revise  the basic  standards  and  to  lay 

them 

down 

in  a  new 

legal 

instrument,  replacing 

Directives 

76/579/Euratom  and  80/836/Euratom; 

(5) - 

Directive 84/466/EURATOM of  3.9.1984  laying  down  basic  measures 

for  radiation  protection  of  persons  undergoing  medical 

examination or  treatment  (O.J. L-265 of  5.10.84); 

- 

Directive 89/618/EURATOM of  27.11.1989 on  informing  the general 

public about  health  protection measures  to be applied  and  steps 

to  be  taken  in  the  event  of  a  radiological  emergency  (O.J.  L-

357 of  7.12.89); 

Directive  90/641/EURATOM  of  4.12.1990  on  the  operational 

protection  of  outside  workers  exposed  to  the  risk  of  ionizing 

radiation during  their  activities  in controlled  aresas  (O.J. L-

349 Of  13.12.90); 

Regulation  87/3954/EURATOM  of  22.12.1987  laying  down  maximum 

permitted  levels of  radioactive  contamination of  foodstuffs and 

feedingstuffs following a nuclear  accident  or  any other  case of 

radiological  emergency  (O.J. L-371 of  30.12.87); 

- 

Directive  92/3/EURATOM  of  3.2.1992  on  the  supervision  and 

control  of shipments of  radioactive waste between Member  States 

and  into and out of  the Community  (O.J. L-35 of  12.2.92); 

Regulation  93/1493/EURATOM  of  8.6.1993  on  shipments  of 

radioactive  substances  between  Member  States  (O.J.  L-148  of 

19.6.93); 

Recommendation 90/143/EURATOM of  21.2.1990 on  the protection of 

the  public  against  indoor  exposure  to  radon  (O.J.  L-80  of 

27.3.90); 

Council  Decision  87/600/EURATOM  of  14.12.1987  on  Community 

arrangements  for  the early exchange of  information  in the event 

of  a radiological  emergency  (O.J. L-371  of  30.12.87). 

-  17 -

Whereas  this  development  has  given  rise  to  a  reappraisal  of  the  risks 

involved  in  the  usé  of  ionizing  radiation,  to  the  recognition  of  the 

need  to reinforce  the protection of  health  at  the workplace  against  the 

dangers  arising  from  exposure  to  natural  radiation  sources  and  to  an 

increased  awareness  of  the  need  to  provide  for  precautionary  measures 

to be applied  in the event  of  an  accident; 

Whereas  the  basic  standards  to  be  laid  down  within  the  Community  have 

to take due account  of  the requirements of  the nuclear  common market  as 

set  out  in Title  Two, Chapter  IX of  the Treaty  and  the  internal  market 

created  under  the Treaty  establishing  the  European  Economic  Community, 

subject  to  Art. 232  (2) of  that  Treaty; 

Whereas,  in  order  to  attain  the  objectives  set  out  above,  it  is 

necessary  to  define  the  scope  of  the  basic  standards  by  including  the 

placing  on  the  market  of  radioactive  substances,  the  operation  of 

certain  electrical  equipment  and  exposure  to natural  radiation  sources 

at  the workplace; 

Whereas  the Member  States,  in order  to ensure compliance with  the basic 

standards,  are  required  to  prohibit  certain  practices  involving  a 

hazard  from  ionizing  radiation  or,  according  to  the  degree  of  hazard 

involved,  to  submit  them  to  a  system  of  reporting  and  prior 

authorization; 

Whereas  a system  of  radiation  protection  for  practices  should  be  based 

on  the  principles  of  Justification  of  exposure,  optimisation  of 

protection  and  dose  limitation  taking  into  account  the  particular 

situation  of  the  different  groups  of  persons  exposed  such  as  workers, 

nursing  and  pregnant  women,  apprentices,  students  and  members  of  the 

public;  whereas  to  this  end  limitations  of  doses  and  limits  derived 

therefrom  must  be fixed; 

-  18 -

Whereas  the operational  protection  of  exposed  workers,  apprentices-and 

students  requires  the  implementation  of  measures  at  the' workplace; 

whereas  these measures must  include  the prior  evaluation of  the  hazard 

involved,  the  classification  of  workplaces  and  workers, monitoring  of 

areas and working  conditions as well  as medical  surveillance-. 

Whereas  it has become apparent  that workers should  be protected  against 

exposure  to  natural  radiation  sources  at  their  workplace;  whereas  to 

this  end  the  Member  States  should  be  required  to  carry  out  surveys  to 

identify  the  areas, practices  and  working  conditions where  workers  are 

exposed,  in  a  significant  manner,  to  such  sources;  whereas,  on  the 

basis  of  such  surveys,  the  Member  States  should  take  the  appropriate 

protective measures-. 

Whereas  the  operational  protection  of  the  population  in  normal 

circumstances  requires  the  establishment  of  a  system  of  inspection  to 

keep  under  review  the  radiation  protection  of  the  population  and  to 

check  compliance with  the basic standards; 

Whereas,  owing  to  the  experience  gained  from  the  Chernobyl  accident, 

the  Member  States  should  consider  the  development  of  all  radiological 

emergencies on  their  territory  before, during  and  after  an accident  and 

should  take  all  necessary  measures  to  reduce  their  consequences; 

whereas  cooperation  between  Member  States  and with  third  countries  has 

proved  capable of  assuring  increased  preparedness; 

HAS ADOPTED  THIS  DIRECTIVE: 

-  19 

TITLE I 

DEFINITIONS 

Article 1 

For  the purpose of  this Directive, the following  terms  have  the meaning 

hereby  assigned  to  them. 

Absorbed  dose  (D): the energy  absorbed  per unit  mass 

D -  de 

dm 

Where - de is  the  mean  energy  imparted  by  ionizing  radiation  to  the 

matter  in a volume  element 

-  dm  is the mass of  the matter  in this volume  element. 

in  this  Directive,  absorbed  dose  denotes  the  dose  averaged  over  a 

tissue or  an organ. The unit  for absorbed  dose  is the gray. 

Accelerator: apparatus or  installation  emitting  ionizing  radiation  with 

an energy  higher  than  1  Mev. 

Accident:  an  unintended  event  that  causes  damage  to  a  source  or  that 

results or  could  result  in exposure  of members  of  the  public  in excess 

of  the  appropriate  intervention  level  or  in exposure  of  workers  above 

the appropriate dose  limits. 

Accidental  exposure:  a  fortuitous  and  involuntary  exposure  of 

individuals  as a result  of  an  accident. 

-  20 -

Activation: process  through  which  a stable  nuclide  is transformed  into 

a  radionuclide  by  irradiating  with  particles or  high-energy  gamma  rays 

the material  in which  it  is contained. 

Activity(A):  the  activity  A,  of  an  amount  of  a  radionuclide  in  a' 

particular  energy  state  at  a  given  time,  is  the  quotient  of  dN  by  dt, 

where  dN  is the expectation  value of  the number  of  spontaneous  nuclear 

transitions  from  that  energy  state  in the time  interval  dt: 

dN 

dt 

The unit  for  activity  is the becquerel. 

Apprent ice:  a  person  receiving  training  for  employment  involving 

exposure  to  ionizing  radiation and  instruction within  an undertaking. 

Approved  medical  practitioner:  a  medical  practitioner  responsible  for 

the medical  surveillance of workers of category  A as defined  in Article 

21,  whose  capacity  to  act  in  this  respect  is  recognised  by  the 

competent  authorities. 

Approved  occupational  health  services: a body or bodies responsible for 

the radiation protection  and medical  surveillance of exposed workers as 

defined  in  Article  21  whose  capacity  to  act  in  this  respect  is 

recognised  by  the competent  authorities. 

Becquerel  (Ba):  the  special  name  of  the  unit  of  activity.  One 

becquerel  is equivalent  to one  transition  per  second: 

1 Bq -  1 s -1 

-  21  -

Committed  effective  dose  (Efjc)):  the  sum  of  the  committed  organ  or 

tissue  equivalent  doses  resulting  from  an  intake,  each  multiplied -by 

the appropriate  tissue weighting  factor  W_.  It  is defined  by: 

E(x) -  2 wTHT(-c!) 
T 

In  specifying  E(rC).  -c is given  in  the  number  of  years  over  which  the 

integration  is  made.  The  unit  for  committed  effective  dose  is  the 

sievert. 

Committed  equivalent  dose  (Hyf/tr)):  the  integral  over  time  (t) of  the 

equivalent  dose  rate  in  tissue  or  organ  T  that  will  be  received  by  an 

individual  resulting  from  an  intake.  It  is given  by: 

h^Cx) -  \ 

ÎLf(t)dt 

for  an  intake at  time t0 where 

H—(t)  is  the  relevant  equivalent  dose  rate  in  organ  or  tissue  T 

at  time t 

t 

is the  time over  which  the  integration  is  performed. 

In  specifying  HT 

it), 

t  is  given  in  years.  When 

is  not  given,  a 

period  of  50 years  is assumed  for  adults and  up  to age 70  for  children. 

The unit  for  committed  equivalent  dose  is the  sievert.. 

Consignee:  any  natural  or  legal  person  to whom  a  radioactive  substance 

is shipped. 

-  22 -

Controlled  area:  an  area  subject  to  special  rules  for  the  purpose  of 

protection  against  ionizing  radiation  or  of  preventing  the  spread  of 

radioactive  contamination, to which access  is controlled  and  restricted 

to workers who have received  appropriate  instructions. 

Dose  constraint:  a  restriction  on  the  doses  to  individuals  resulting 

from defined  sources for  the purposes of optimisation  of  protection. 

Dose  I imits:  the  limits  laid down  in Title  IV  for  the  doses  resulting 

from  the exposure  of workers, apprentices  and  students, and  members  of 

the  public  to  ionizing  radiation  from  the  practices  covered  by  this 

Directive. 

Effective  dose  (E): the sum of  the weighted  equivalent  doses  in all  the 

tissues  and  organs of  the body  specified  in Annex  II  from  internal  and 

external  irradiation.  It  is defined  by  the  expression: 

E  « 2 wTHT  - S wTJ wR  DT>R 

T 

T 

"ft 

where 

Dj  R  is the organ absorbed  dose  from  radiation  R, 

- 

WR 

is the radiation weighting  factor  and 

- 

Wj  is the t issue weight ing factor  for  tissue or organ  T. 

The  appropriate  w-j- and  WR  values  are  specified  in  Annex  I I .The  unit 

for  effective dose  is the sievert. 

-  23 -

Emergency  exposure:  an  exposure  Justified  in  abnormal  conditions  in 

the  interests  of  bringing  help  to  endangered  individuals,  preventing 

exposure  of  a  large  number  of  people  or  saving  a  valuable  undertaking 

or  source, whereby one of  the dose  limits  laid down  for exposed  workers 

could  be  exceeded. 

Equivalent  dose  (Hj):  the  absorbed  dose,  in  tissue  or  organ  T 

weighted  for  the type and quality of  radiation  R.  It  is given  by: 

HT,R  " WR  DT.R 

where 

~ 

DT,R  is  t he  absorbed  dose  in  tissue  or  organ  T  from  radiation  R 

and 

wR  is the radiation weighting  factor. 

When  the  radiation  field  is  composed  ofv  types  and  energies  with 

different  values of wR,  the total  equivalent  dose, HT,  is given by 

HT -S  WR  DT.R 

The  appropriate  wR  values  are  specified  in  Annex  II.  The  unit  for 

equivalent  dose  is the sievert. 

Exposed  workers: persons, aged  18 years or more, subject  to an  exposure 

incurred  at work  from practices covered  by  this Directive  and  liable  to 

result  in doses  exceeding  one  or  other  of  the  dose  limits  for  members 

of  the pub Iic. 

- 24 -

Exposure: the process of being exposed to ionizing radiation 

Gray  (Gy): the special  name of the unit of absorbed dose. One gray  is 

equal  to one Joule per kilogram: 

1 Gy - 1 J kg 

-1 

Harm: clinically  observable  deleterious effects  that  are expressed  in 

individuals or  their descendants. It  includes the probability  of such 

effects. 

Holder : any natural or  legal person who, before carrying out a shipment 

of radioactive substances, has the  legal responsabiIity under national 

law  for  such  materials  and  intends  to  carry  out  a  shipment  to  a 

consignee. 

Intake:  the  activities  of  radionuclides  entering  the  body  from  the 

external environment. 

Intervention: a human activity that decreases  the overall  exposure of 

individuals  to  radiation  by  removing  existing  sources,  modifying 

existing  exposure  pathways  or  reducing  the  number  of  individuals 

exposed to an existing source. 

.Intervention  level: a  value of  equivalent  dose, effective  dose  or  a 

derived value, at which  intervention measures should be considered. The 

dose  or  derived  value  is  solely  that  associated  with  the  exposure 

pathway to which the intervention measure  is to be applied. 

-  25 -

Ionizing  radiation:  the  transfer  of  energy  in  space  in  the  form-of 

electro-magnetic  waves  or  particles with  quantities  of  energy  higher 

than  12.4  eV  corresponding  to  a  wavelength  of  100  nanometer  or  a 

frequence of  3x10(15) Hertz. 

Members of  the public:  individuals  in the population, excluding  exposed 

workers, apprentices and students during  their  working  hours. 

Natural  radiation  sources:  sources of  ionizing  radiation  from  natural 

terrestrial  or  cosmic origin. 

Other  relevant  sources:  any  radioactive  substance  not  being  a  sealed 

source  intended  for direct  or  indirect  use of  the  ionizing  radiation  it 

emits  for  medical,  veterinary,  industrial,  commercial,  research  or 

agricultural  applicat ions. 

Placing  on  the  market:  any  supply,  whether  in  return  for  payment  or 

free of  charge, other  than  for storage  followed by exportation  from  the 

territory of  the Community  or  by disposal.  Importation of  a radioactive 

substance  or  products  containing  such  substances  into  the  territory  of 

the  Community  shall  be  deemed  to constitute  placing  on  the  market  for 

the purposes of  this Directive. 

Potential  exposure:  exposure which  has a probability of occurrence  and 

magnitude  that  may  be  predicted  for  an  event  such  as  an  accident  or 

failure of  equipment. 

Practice:  a  human  activity  that  can  increase  the  overall  exposure  of 

individuals  to radiation  from  a source. 

Ï>7  -

-  26 -

Quai if led expert:  a person having  the knowledge  and training needed  to 

carry  out  physical,  technical,  or  radiochemical  tests  and  to  assess 

doses,  and  to  give  advice  in order  to  ensure  effective  protection  of 

individuals  and  correct  operation  of  protective  equipment,  whose 

capacity  to  act  as  a  qualified  expert  is  recognised  by  the  competent' 

authorities. 

Radiological  emergency:  the consequence of  an accident  for which  Member 

States  decide  to  take  measures  of  a  widespread  nature  in  order  to 

protect  the public. 

Radioactive  contamination:  the  contamination  of  any  material,  surface 

or  environment  or  of  an  individual  by  radioactive  substances.  In  the 

specific  case  of  the  human  body,  this  radioactive  contamination 

includes  both  external  skin  contamination  and  internal  contamination, 

irrespective of  route of  intake. 

Radioactive  substance:  any  substance  that  contains  one  or  more 

radionuclides,  the  activity  or  the  concentration  of  which  cannot  be 

disregarded  as far as radiation protection  is concerned. 

Reference  group of  the population: a group comprising  individuals whose 

exposure  to  a  source  is reasonably  uniform  and  representative  of  that 

of  the  individuals  in the population who are  the most  highly  exposed  to 

that  source. 

Sealed  source:  a source  whose  structure  is such  as  to  prevent,  under 

normal  conditions  of  use, any  dispersion  of  the  radioactive  substances 

into the  environment. 

-  27 -

Shipment:  the  transport  operations  from  the  place  of  origin  to -the 

place  of  destination,  including  loading  and  unloading,  of  radioactive 

substances. 

Sievert  (Sv):  the special  name of  the unit  of equivalent  and  effective 

dose. One sievert  is equivalent  to one  Joule per  kilogram: 

1 Sv -  1 J Kg"1 

Source:  an  apparatus,  substance  or  installation  capable  of  emitting 

ionizing  radiation  or  radioactive  substances,  other  than  natural 

radiation sources. 

Supervised  area:  an  area  in  which  the  working  conditions  are  kept 

under  review  but  special  arrangements  such  as  those  enforced  in 

controlled areas are not normally  needed. 

-  28 -

TITLE II 

SCOPE 

Article  2 

This  Directive  shall  apply  to  any  practice  or  intervention  which 

involves a hazard  from  ionizing  radiation, notably: 

a)  the  production,  processing,  handling,  use,  holding,  storage, 

transport,  placing  on  the  market,  exportation  and  disposal  of 

radioactive substances; 

b)  the  operation  of  any  electrical  equipment  emitting  ionizing 

radiation  and  containing  components  operating  at  a  potential 

difference of more  than 5 kV; 

c)  exposure  to natural  radiation sources at work 

(i)  in uranium mines; and 

(ii) in other  workplaces as specified  in Title VII. 

- 29 -

TITLE III 

REPORTING AND AUTHORISATION 

Article 3 

Reporting 

1. Each Member  State shall  make  it compulsory  for  each person who or 

undertaking which carries out the practices referred to in Article 2 to 

report those practices. 

2. However, no reporting shall be required for the following practices: 

(a) the use of radioactive substances or  their  subsequent  disposal  if 

the quantities involved do not exceed  in  total the values given in 

column 2 of table A in Annex  I ; or 

(b) the use of radioactive substances or  their  subsequent  disposal  if 

the  concentrations of  activity  per  unit  mass  do  not  exceed  the 

values given in column 3 of table A  in Annex  I ; or 

(c) the  use  of  apparatus  containing  radioactive  substances  exceeding 

the  quantities  or  concentration  values  specified  in  (a) or (b), 

provided that: 

1.  it  is of  a  type  approved  by  the  competent  authority  of  the 

Member State; and 

2.  it  is  constructed  in  the  form  of  sealed  sources  ensuring 

effective protection  against  any  contact  with  the radioactive 

substances and against any  leakage of them; and 

3.  it does not cause, in normal operating conditions, a dose rate 
exceeding  1 /zSv  h-1  at  a  distance  of  0.1  m  from  any 

accessible surface of the apparatus; or 

- 30 -

(d) the operation of any electrical  equipment  to which  this Directive 

applies, provided that: 

1.  it  is of  a  type  approved  by  the  competent  authority  of  the 

Member State; and 

2.  it does not cause, in normal operating conditions, a dose rate 
exceeding  1 j*Sv  h_1  at  a  distance  of  0.1  m  from  any 

accessible surface of the apparatus; or 

(e) the operation of any cathode ray tube  intended  for  the display of 

visual  images provided that  it does not cause, in normal operating 
conditions, a dose rate exceeding  1 ftSv h-1  at  a distance of  0.1 

m from any accessible surface of the apparatus; or 

(f) the occupancy of dwellings and other exposures to natural sources, 

without prejudice to Article 2 (c). 

3. The  list of practices,  laid down  in paragraph  2, may be revised in 

accordance with the procedure  laid down in Article 56. 

Article 4 

Authorization 

1. Prior authorization shall be required for the following practices: 

(a) the construction, operation and decommissioning of any undertaking 

of the nuclear fuel cycle; 

(b) the  disposal  of  radioactive  substances  or  the  recycling  of 

materials  containing  radioactive  substances,  arising  from  any 

industrial,  medical,  veterinary  or  research  undertaking,  unless 

conditions laid down by the competent authorities are met; 

- 31 -

(c) the deliberate addition of radioactive substances  fn the product ion 

and  manufacture of medicinal  products  and  consumer  goods  and  the 

placing on the market of such goods; 

(d) the deliberate administration of  radioactive substances to persons 

and  animals  for  the  purpose  of  medical  or  veterinary  diagnosis, 

treatment or research; 

(e) the use of X-ray  sets or  radiation sources containing radioactive 

substances for industrial radiography or processing of products and 

the use of accelerators except electron microscopes; 

(f) the use of accelerators, X-ray  sets or radioactive sources for the 

exposure of persons for medical  treatment or research. 

2. Prior  authorization may be required  for other  practices than those 

listed  in  paragraph  1,  to  be  determined  in  accordance  with  the 

procedure-laid down in Article 56. 

3. Authorizations may be  issued for a continued practice and cover the 

use of several radiation sources over a specified period of  time. They 

may be renewable. 

Article 5 

Prohibited practices 

The deliberate addition of radioactive substances  in the production of 

foodstuffs,  toys,  personal  ornaments  and  cosmetics,  the  deliberate 

activation  of  such  goods  and  their  placing  on  the  market  shall  be 

prohibited. 

-  32 -

Article  6 

Shipment  of  radioactive  substances 

1.  Each  Member  State  shall  make  arrangements  to  ensure  that  shipments 

of  radioactive  substances  within  its  territory  can  be  made  only  to 

consignees  which  have  complied  with  all  applicable  provisions 

implementing  this Directive and with  relevant  national  requirements for 

use,  treatment,  handling,  safe  storage or  disposal  of  such  radioactive 

substances. 

2.  A  holder  of  sealed  sources  who  intends  to  carry  out  a  shipment  of 

such  sources  to a consignee  in another  Member  State, or  to arrange  for 

such  a  shipment  to  be  carried  out,  shall  obtain  a  prior  written 

declaration  by  the  consignee  of  the  sealed  sources  to  the  effect  that 

the  consignee  has  complied,  in  the  Member  State  of  destination,  with 

all  applicable provisions  implementing  this Directive  and with  relevant 

national  requirements  for  use,  treatment,  handling,  safe  storage  or 

disposal  of  that  class of  source. 

The  declaration  shall  be  sent  by  the  consignee  to  the  competent 

authorities of  the  Member  State  to  which  the  shipment  is  to  be  made. 

Receipt  of  the  declaration  shall  be  acknowledged  thereon  by  the 

competent  authority  and  the  declaration  shall  then  be  sent  by  the 

consignee  to the holder. 

-  33 -

3. A holder of sealed sources or other  relevant  sources who has carried 

out  a  shipment  of  such  sources  to a consignee  in another  Member  State, 

or  arranged  for  such  a  shipment  to  be  carried  out,  shall,  within  21 

days  of  the  end  of  each  calendar  quarter,  provide  the  competent 

authorities  in  the  Member  State  of  destination  with  the  following 

information  in respect of deliveries during  the quarter: 

- 

names and addresses of  consignees; 

- 

the  total  activity  per  isotope delivered  to each  consignee  and 

the number of such deliveries made; 

- 

the  highest  single  quantity  of  each  isotope  delivered  to each 

consignee; 

the type of substance: sealed source or other  relevant  source. 

- 34 -

TITLE  IV 

SYSTEM OF  RADIOLOGICAL 

PROTECTION FOR  PRACTICES 

CHAPTER I 

GENERAL  PRINCIPLES 

Article  7 

1.  Each  Member  State  shall  establish  and  require  the  application  of  a 

system  of  radiological  protection  for  practices  based  on  the  following 

general  principles: 

(a) all  practices  resulting  in exposure  to  ionizing  radiation  shall  be 

Justified  in advance  by,  and  kept  under  review  as  to  the  benefits 

which they produce;. 

(b) all  exposures  shall  be  kept  as  low  as  reasonably  achievable, 

economic  and  social  factors being  taken  into account; generic  dose 

constraints  for  particular  types  of  practice  shall  be  established 

by  the competent  authorities; 

(c) without  prejudice  to  Article  13,  the  sum  of  the  doses  from  all 

relevant  practices  shall  not  exceed  the  dose  limits  laid  down  in 

this  Title  for  exposed  workers,  apprentices,  students  and  members 

of  the pub Iic. 

2. The principles set out  in paragraph  1 (a) and  (b) shall  apply  to all 

exposures  to  ionizing  radiation  including  medical  exposures.  The 

principle* set  out  in  paragraph  1  (c)  shall  not  apply  to  any  of  the 

following exposures: 

- 35 -

(a) the exposure of  individuals as part of  their own medical  diagnosis 

or treatment; 

(b) emergency exposures, without prejudice to Article 55; 

(c) exposures from natural sources other  than  in uranium mines and as 

specified in Title VII; 

(d) the exposure of  individuals knowingly and willingly  helping (other 

than  as part  of  their  occupation)  in the  support  and  comfort  of 

patients  undergoing  medical  diagnosis  or  treatment, either  in a 

hospital or at home, without prejudice to paragraph 3; 

(e) the exposure of volunteers participating  in medical  and biomedical 

research programmes, without prejudice to paragraph 3. 

3. Each Member State shall establish guidance on appropriate procedures 

to be applied to the individuals referred to at 2 (d) and 2 (e) above. 

It shall  also establish  appropriate  constraints  to be  applied  to the 

doses received by the volunteers referred to at 2 (e) above. 

CHAPTER II 

LIMITATION OF DOSES FOR EXPOSED WORKERS 

Article 8 

Age limit for exposed workers 

Without prejudice to Article 12 (2), persons under  18 years of age may. 

not be assigned  to any work which would result  in their  being exposed 

workers. 

-  36 -

Article 9 

Dose  limits for exposed  workers 

1. The  limit on effective  dose  for exposed  workers  shall  be 20 mSv  per 

year  averaged over  five consecutive years  (100 mSv  in five years), with 

the  further  provision  that  the  effective  dose  shall  not  exceed  50 mSv 

in any single year. This  limit applies  to the sum of  the relevant  doses 

from  external  exposure  in  the  specified  period  and  the  50-year 

committed equivalent  dose from  intakes  in the same period. 

2. Without  prejudice  to paragraph  1, the  following  limits  for  the  lens 

of  the eye, skin and extremities apply: 

- 

the  limit  for  equivalent  dose  for  the  lens  of  the  eye  shall  be 

150 mSv  in a year; 

the  limit  for  equivalent  dose  for  the  skin  shall  be  500 mSv  in a 

year. This  limit shall  apply  to the dose averaged  over  any  area of 

1 cm2, regardless of  the area exposed; 

the  limit  for  equivalent  dose  for  the  hands,  forearms,  feet  and 

ankles shall  be 500 mSv  in a year. 

Article  10 

Protection of pregnant  women 

As  soon  as  a  pregnant  woman,  in  accordance  with  national  legislation 

and/or  national  practice,  informs  the management  of  her  condition,  the 

foetus shall  be protected  as far  as possible as though  it were a member 

of  the public. The exposure of  the pregnant  woman  in the context  of  her 

employment  shall  be  as  low as  reasonably  achievable  and  the  conditions 

of  her  work  shall  be such  as  to ensure  that  the equivalent  dose  to  the 

foetus does not exceed  1 mSv during  the remainder  of  the pregnancy. 

-  37 -

Article 11 

Protection of nursing mothers 

1.  Nursing  mothers  shall  not  be  employed  in work  involving  a  risk  of 

radioactive contamination. 

2.  Special  attention  will  be  paid  to  the  possibility  of  bodily 

radioactive  contamination.  If  necessary,  the  competent  authorities 

shall  establish  relevant  dose constraints. 

CHAPTER  III 

LIMITATION OF DOSES FOR 

APPRENTICES AND STUDENTS 

Article  12 

1. The  dose  limits  for  apprentices  aged  18 years  or  over  and  students 

aged  18 years or over  who,  in the course of  their  studies, are obliged 

to use sources shall  be the same as the dose  limits for exposed  workers 

laid down  in Article  9. 

2. The  limit  for  effective  dose  for  apprentices  aged  between  16 and  18 

years and  for  students aged between  16 and  18 years who,  in the  course 

of  their  studies, are obliged  to use  sources, shall  be 6 mSv  per  year. 

The dose  limits  for  the  lens of  the eye, skin and  extremities  shall  be 

equal  to  three-tenths of  the dose  limits  for exposed  workers  laid  down 

in Article 9  (2). 

3. The  dose  limits  for  apprentices  and  students who  are  not  subject  to 

the  provisions  of  paragraphs  1  and  2  shall  be  the  same  as  the  dose 

limits for members of  the public specified  in Article 14. 

-  38 -

CHAPTER  IV 

SPECIALLY AUTHORIZED  EXPOSURES 

Article  13 

1.  In exceptional  circumstances, evaluated  case by case, the  competent 

authorities  may,  where  some  specific  opération  so  requires,  authorize 

individual  occupational  exposures of  some  identified  workers  exceeding 

the  dose  limits  set  out  in  Article  9,  but  within  maximum  exposure 

levels  defined  for  the  particular  case  by  the  competent  authorities. 

The  following conditions shall  apply: 

a) only  workers  of  category  A  defined  in Article  23 may  be  subject  to 

specially authorized exposures; 

b) pregnant  and nursing women are excluded  from such exposures; 

c)  these  exposures  shall  be  carefully  justified  and  thoroughly 

discussed 

with 

the  management, 

the  relevant 

workers,  their 

representatives,  the approved  occupational  health  services  or  approved 

medical  practitioner  and  the qualified  expert; 

d)  information  about  the risks  involved and  the precautions  to be  taken 

during  the operation shall  be provided; 

e) all  closes related  to such  exposures  shall  be  separately  recorded  in 

the health  record. 

2.  The  exceeding  of  dose  limits  as  a  result  of  specially  authorized 

exposures  shall  not  necessarily  be  a  reason  for  excluding  the  worker 

from his usual  occupation. 

- 39 -

CHAPTER V 

LIMITATION OF DOSES FOR THE POPULATION 

Article 14 

Dose limits for members of the public 

1. Without prejudice to Article 15, the dose  limits for members of the 

public shall be as laid down in paragraphs 2 and 3. 

2. The  limit for effective dose shall be 1 mSv  in a year.  However, in 

special  circumstances, a higher  effective dose may  be authorized  in a 

single year, provided that the average over five consecutive years does 

not  exceed  1  mSv  per  year.  This  limit  applies  to  the  sum  of  the 

relevant  doses from external  exposure  in the specified  period and the 

50-year  committed equivalent  dose  (to age 70 years for children) from 

intakes in the same period. 

3.  in addition: 

The limit for the equivalent dose for the lens of the eye shall 

be 15 mSv  in a year; 

- 

the  limit for the equivalent dose for.the skin shall be 50 mSv 
in a year averaged over  any 1 cm2 area of skin, regardless of 

the area exposed; 

- 

the limit for the equivalent dose for the hands, forearms, feet 

and ankles  shall be 50 mSv  in a year. 

-  40 -

Article 15 

Exposure of  the whole population 

1. Each Member  State shall  ensure  that  the contribution  to the exposure' 

of  the whole population  from each practice  is kept  as  low as  reasonably 

achievable,  taking  account  of  the  principles  set  out  in Article  7  (1) 

(a) and (b). 

2. The  total  of all  such contributions shall  be regularly  assessed. 

3.  Each  Member  State  shall  regularly  transmit  the  results  of  these 

assessments  to the Commission. 

CHAPTER VI 

Article  16 

If  exceptional  circumstances  so  require,  dose  limits  different  from 

those  fixed  in  this  Title  may  be  authorised  in  accordance  with  the 

procedure  laid  down  in  Article  56.  Such  authorization  shall  be  duly 

justified  and  limited  in  its  scope,  duration  and  geographical 

applicabiIity. 

TITLE V 

ESTIMATION OF EFFECTIVE  DOSE 

Article  17 

For  the  estimation  of  effective  dose  the  methods  referred  to  in  this 

Title or  any other  appropriate methods shall  be used. 

41 -

Article  18 

1. For  external  radiation,  the  values  given  in Annex  II may  be used  to 

estimate  the relevant  equivalent  and effective  doses. 

2.  For  internal  exposure  from  a  radionuclide  or  from  a  mixture  of 

radionuclides,  the methods  given  in Annexes  M  and  III may  be used  to 

estimate  the effective doses. 

-  42 -

TITLE VI 

FUNDAMENTAL  PRINCIPLES GOVERNING OPERATIONAL PROTECTION 

OF EXPOSED WORKERS, APPRENTICES AND  STUDENTS 

Article  19 

Operational  protection  of  exposed  workers  shall  be  based  on  the 

following principles: 

a)  prior  evaluation  to  identify  the  nature  and  magnitude  of  the 

radiation  hazard  to exposed workers; 

b)  classification  of  workplaces 

into  different 

areas,  where 

appropriate,  by  reference  to  an  assessment  of  the  expected  annual 

doses  and  of  the  expected  frequency  and  possible  consequences  of 

minor mishaps; 

c)  classification of workers  into different  categories; 

d)  implementation  of  control  measures  and  monitoring  relating  to  the 

different  areas and  to the different  working  conditions; 

e)  medical  surveillance. 

-  43 -

CHAPTER I 

MEASURES  FOR  THE  RESTRICTION 

OF  EXPOSURE 

SECTION 1 

CLASSIFICATION AND  DELINEATION OF  AREAS 

Article  20 

Arrangements  in workplaces 

1.  For  the  purposes  of  radiation  protection  and  having  regard  to 

Titles  M  and VII, arrangements  shall  be made  as regards all  workplaces 

where  there  is a  risk  of  exposure  to  ionizing  radiation  in excess  of 

the  relevant  dose  limits  for  members  of  the  public.  Such  arrangements 

must  be  appropriate  to  the  nature  of  the  undertakings  and  sources  and 

to  the  magnitude  and  nature  of  the  hazards.  The  scope  of  the 

precautions and monitoring, as well  as  their  type  and  quality, must  be 

appropriate  to  the hazards  associated  with  the work  involving  exposure 

to  ionizing  radiation. 

2. A  distinction  shall  be made  between  controlled  areas  and  supervised 

areas. 

3.  Specific  arrangements  shall  be  made  in  controlled  areas,  wherever 

there  is a significant  risk of  the spread of  radioactive  contamination. 

4.  The  competent  authorities  shall  establish  guidance  on  the 

classification of  controlled  and  supervised  areas  which  is relevant  to 

the particular  circumstances. 

-  44 

5.  The  management  shall  keep  under  review  the  working  practices  in 

controlled  and supervised areas. 

Article 21 

Requirements for controlled  areas 

The  minimum  requirements  for  a  controlled  area  are  that  it  shall  be 

delineated  and  that access to  it shall  be controlled  in accordance with 

written procedures provided  by  the management. 

Article 22 

Discretionary measures for control led and  supervised  areas 

Taking  into  account  the nature  and  extent  of  radiation  hazards  in  the 

controlled  and supervised areas: 

a)  signs  indicating  type  of  area,  nature  of  the  sources  and  their 

inherent  hazards shall  be displayed; 

b)  working  instructions appropriate to the radiation  hazard  associated 

with  the sources and  the operations  involved shall  be  laid down; 

c)  radiological  environmental  surveillance  shall  be  organized  in 

accordance with  the provisions of Article 26. 

These duties shall  be within  the competence of qualified  experts. 

- 45 -

SECTION 2 

CLASSIFICATION OF EXPOSED WORKERS. APPRENTICES AND STUDENTS 

Article 23 

Categorisation of exposed workers 

For the purposes of monitoring and surveillance, a distinction shall be 

made between two categories of exposed workers: 

category A: those who work routinely  in controlled areas and those 

who are  liable to receive an effective dose greater  than 6 mSv per 

year  or  an equivalent  dose greater  than  three-tenths of  the dose 

limits for the  lens of  the eye, skin and extremities  laid down in 

Article 9 (2); 

-  category B:  those  exposed  workers  not  classified  as  workers  of 

category A, routinely working  in supervised  areas or occasionally 

in controlled areas. 

Article 24 

information and training 

Exposed workers, apprentices and students shall: 

(a) -  be informed of the health risks involved  in their work; 

-  be  informed of the general  radiation protection procedures and 

precautions to be taken and, in particular, those involved with 

operational  and  working  conditions  in  respect  of  both  the 

undertaking  in general and each type of work station or job; 

-  46 -

-  .- be  informed  of  the  importance  of  complying  with  the  technical, 

medical  and administrative  requirements; 

(b) - 

in  the  case  of  women,  be  informed  about  the  specific  health 

risks; this  information  shall  be supplemented  in the event  of a 

pregnancy; 

(c) - 

be given  training  in the field of  radiât ion .protect ion. 

SECTION 3 

ARRANGEMENTS  FOR THE RADIOLOGICAL PROTECTION 

OF  EXPOSED WORKERS 

Article 25 

1.  An  assessment  of  arrangements  for  the  radiological  protection  of 

exposed workers shall  be made by  the management. 

2.  The  examination  and  testing  of  protective  devices  and  measuring 

instruments shall  be the task of qualified experts and shall  comprise: 

a)  prior  critical  examination  of  plans  for  sources  from  the  point  of 

view of  radiation protection; 

b)  the  acceptance  into  service  of  new  or  modified  sources  from  the 

point  of view of  radiât ion protection; 

c)  regular  checking  of  the  effectiveness  of  protective  devices  and 

techniques; 

d)  regular  calibration  of  measuring  instruments  and  regular  checking 

that  they are serviceable  and correctly  used. 

-  47 -

CHAPTER  I I 

ASSESSMENT OF  EXPOSURE 

SECTION 1 

MONITORING OF THE WORKPLACE 

Article  26 

1.  The  radiological  environmental  surveillance,  mentioned  in  Article 

22, shall  comprise: 

a)  the measurement  of  dose  rates,  indicating  if necessary  the  nature 

and  the quality of  the radiation  in question; 

b)  the  measurement  of  the  air  concentration  and  surface  density  of 

contaminating  radioactive  substances,  indicating  if necessary  their 

nature and  their  physical  and  chemical  states. 

2.  The  results  of  these  measurements  snail  be  recorded  and  shall  be 

used,  where  appropriate,  for  estimating  individual  doses,  as  required 

in section 2. 

-  48 -

SECTION 2 

INDIVIDUAL MONITORING 

Article 27 

Monitoring - General 

1.  Individual  monitoring  shall  be  systematic  for  exposed  workers  of 

category  A.  This monitoring  shall  be  based  on  individual  measurements 

or,  in cases where  these  are  impossible  or  inadequate, on  an estimate 

arrived  at  either  from  individual  measurements  made  on  other  exposed 

workers  or  from  the  results  of  the  surveillance  of  the  workplace 

provided  for  in Article 26. 

2.  The  competent  authority  shall  provide  general  guidance  for 

identifying  those  workers  of  category A  liable  to  receive  significant 

internal  contamination,  in order  to set up an adequate  system  for  their 

mon i tor i ng. 

3.  Category  B  workers  shall  be  individually  monitored  when  entering  a 

controlled  area.  In other  circumstances, where  individual  measurements 

have not  been made, an estimate of  individual  doses  shall  be made  from 

the  results  of  the  surveillance  of  the  workplace  provided  for  in 

Article 26. 

Article  28 

Investigations after  accidental  exposures 

In the case of accidental  exposures an  investigation shall  be conducted 

with  the  aim  of  identifying  the  circumstances  and  assessing  and 

recording  the relevant  doses and  their  distribution  in the body. 

-  49 -

Article  29 

Recording of emergency  exposures 

In  the  case  of  emergency  exposures,  the  results  of  individual 

monitoring  or  dose  assessments  shall  be  separately  and  individually 

recorded. 

Article 30 

Reporting of  results 

1.  The  results  of  individual  monitoring  required  by  Articles 27  to  29 

shall: 

-  be made  available  to the competent  authorities,  to  the management  and 

to the worker  as required by Article 41 (2); 

-  be  submitted  to  the  approved  occupational  health  services  or 

approved  medical  practitioner.  In the  case of  an  accident  or  emergency 

the results shall  be submitted as soon as possible. 

2.  It  shall  be  the  responsibility  of  the  management  to  ensure 

compliance  with  the requirements of  this Article. 

-  50 -

SECTION 3 

MONITORING FOR THE PURPOSE OF OPTIMISATION 

Article 31 

Provision shall  be made  for monitoring,  in addition  to that  required  by 

Articles  26  to  29,  whenever  it  is  needed  to  confirm  optimisation  of 

radiation  protection. 

SECTION 4 

RECORDING OF  RESULTS 

Article  32 

1.  A  record,  referred  to  as  the  radiation  exposure  section  of  the 

health record, and containing  the results of  the  individual  monitoring, 

shall  be made  for each exposed  worker  of  category  A. 

2.  The  following  shall  be  retained  during  the  working  life  involving 

exposure  to  ionizing  radiation of exposed workers, and  afterwards until 

the  individual  has or  would  have  attained  the  age  of  75  years, but  in 

any  case  not  less  than  30  years  from  the  termination  of  the  work 

involving exposure: 

a)  a  record  of  the  exposures  measured  or  estimated,  as  the  case  may 

be, of  individual doses  in pursuance of Articles 27 to 29; 

b)  in  the  case  of  exposures  referred  to  in  Articles  28  and  29,  the 

reports  relating  to the circumstances  and  to the action taken-, 

- 51 -

c)  any  results  oif workplace  monitoring  that  have  been  specifically 

used  in the assessment or estimation of  the dose .to an  individual 

for whom an exposure record  is required  by virtue of  subparagraph 

(a) above,  shall  be annexed  to that exposure  record and  retained 

accordingly. 

CHAPTER III 

MEDICAL SURVEILLANCE OF EXPOSED WORKERS 

Article 33 

Taking  into account  the specific  features of  radiation protection and 

without  prejudice  to Articles 34  to  39, the medical  surveillance of 

exposed  workers  shall  be  based  on  the  principles  that  govern 

occupational medicine generally. 

SECTION 1 

MEDICAL SURVEILLANCE OF CATEGORY A WORKERS 

Article 34 

Medical surveillance 

1.  The  medical  surveillance  of  workers  of  category A  shall  be  the 

responsibility  of  approved  occupational  health  services  or  approved 

medical practitioners. 

2. Medical surveillance shall include: 

-  52 -

a)  a-pre-employment  medical  examination 

The  purpose of  this examination  shall  be  to determine  the worker's 

fitness  for  the  first  post  within  the  current  employment  for  which 

he  is being  considered  and  for  each  new  post  involving  a change  in' 

type of  risk.  It shall  include an  inquiry  into his medical  history 

including  all  known  previous  exposures  to  ionizing  radiation 

resulting  either  from  his  employment  or  from  medical  examination 

and  treatment,  a clinical  examination  and  any  other  investigations 

necessary  for assessing  his general  state of  health; 

b)  general  medical  surveillance 

The  approved  occupational  health  services  or  approved  medical 

practitioner  must  have  access  to  any  relevant  information  they 

require  in order  to ascertain  the state of  health of  workers under 

surveillance and  to assess the environmental  conditions existing  in 

the  working  premises  insofar  as  they  might  affect  the  fitness  of 

workers  for  the tasks assigned  to them; 

c)  periodic reviews of  health 

The  health  of  workers  shall  be  reviewed  as  many  times  as  the 

approved  occupational 

health  services  or  approved  medical 

practitioner  consider  necessary  to  determine  whether  they  remain 

fit  to  perform  their  duties.  The  nature  of  this  review  shall 

depend  on  the  type of work  and on  the  individual  worker's  state of 

health.  The  state  of  health  of  each  worker  shall  be  reviewed  at 

least once a year. 

3.  The  approved  occupational  health  services  or  approved  medical 

practitioner  may  indicate  the need  for medical  surveillance  to continue 

after  cessation  of  work  for  as  long  as  they  consider  it  necessary  to 

safeguard  the health of  the person  concerned. 

-  53 -

Article  35 

Medical  classification 

The  following  medical  classification  shall  be  adopted  with  respect  to 

fitness  for work  as a worker  of  category  A: 

- 

fit; 

fit, subject  to certain  conditions; 

unf it. 

Article  36 

No worker  may  be employed  for  any  period  as a category  A worker  if  the 

medical  findings are unfavourable. 

Article  37 

Medical  records 

1.  A  medical  section  of  the  health  record  shall  be  opened  for  each 

worker of  category A and kept  up  to date so  long as he remains a worker, 

of  that  category.  Thereafter  it shall  be retained  until  the  individual 

has  or  would  have  attained  the  age  of  75  years,  but  in  any  case  not 

less  than  30 years  from  the  termination of  the work  involving  exposure 

to  ionizing  radiation. 

2.  The  medical  section  of  the  health  record  shall  include  information 

regarding  the  nature  of  the  employment,  the  results  of  the  pre-

employment  medical  examinations and  the periodic  reviews of  health. 

- 54 -

SECTION 2 

EXCEPTIONAL MEASURES OF MEDICAL SURVEILLANCE 

Article 38 

Spec 1a I med i caI survei11ance 

1.  Special  medical  surveillance  shall  be  provided  in  each  case  of 

exposure where  the effective dose of 50mSv as  laid down  in Article 9 

(1), or any of the other dose  limits  laid down  in Article 9  (2), have 

been exceeded. 

2., Subsequent conditions of exposure shall be subject  to the agreement 

of  the  approved  occupational  health  services  or  approved  medical 

practitioner. 

Article 39 

Additional medical surveillance 

In addition to the medical surveillance of exposed workers provided for 

in  Articles  33  and 34,  provision  shall  be  made  for  any  further 

examinations,  decontamination  measures  or  urgent  remedial  treatment 

considered  necessary  by  the approved  occupational  health  services or 

approved medical practitioner and for any further action  in relation to 

the health protection of the exposed individual. 

-  55 -

SECTION 3 

APPEALS 

Article 40 

Each  Member  State  shall  lay  down  the  procedure  for  appeal  against  the 

findings and decisions made  in pursuance of Articles 35, 36 and 38. 

CHAPTER  IV 

TASKS OF MEMBER  STATES  IN RESPECT 

OF PROTECTION OF  EXPOSED WORKERS 

Article 41 

1. Each  Member  State  shall  establish  a system or  systems  of  inspection 

to enforce  the provisions  introduced  in compliance  with  this  Directive 

and  to  initiate  surveillance  and  intervention  measures  wherever 

necessary. 

2.  Each  Member  State  shall  require  that  workers  have  access  on  their 

request  to  the  results of  their  individual  monitoring  measurements  or 

assessments  of  their  doses  made  as  a  result  of  workplace  measurements 

or biological  monitoring. 

3. Each Member  State shall  make  the necessary  arrangements  to  recognise 

the capacity  of: 

-  the qualified experts-, 

-  the  approved  medical  practitioners  and  approved  occupational 

health services. 

-  56 -

To  this end,  each  Member  State  shall  arrange  for  the  training  of  such 

specialists. 

4. Each Member  State  shall  require  the management  of  an undertaking  to 

provide  the  worker  with  the  means  necessary  for  proper  radiation 

protection.  If necessary  a specialized  radiation  protection  unit  shall 

be  set  up.  This  unit,  which  may  be  shared  by  several  undertakings, 

shall  be  the responsibility of  the management  and  shall  not  be part  of 

any production or operation unit. 

5. Each Member  State shall  facilitate  the exchange  within  the  European 

Community  of  all  relevant  information on  the doses  previously  received 

by a worker,  in order  to control  the further  exposure of  the worker  and 

to  perform  the  pre-employment  medical  examination  required  by 

Article 34. 

CHAPTER V 

OPERATIONAL  PROTECTION OF APPRENTICES AND  STUDENTS 

Article 42 

1. Articles  10 and  19 shall  also  apply  to  the apprentices  and  students 

referred  to  in Article  12 (1) and  12 (2). 

2. The operational  protection of apprentices and  students aged  18 years 

or over  shall  be equivalent  to that of exposed workers of category A or 

B as appropriate. 

3. The operational  protection of  apprentices  and  students  aged  between 

16  and  18  years  shall  be  equivalent  to  that  of  exposed  workers  of 

category B. 

- 57 -

TITLE VI I 

EXPOSURE TO NATURAL RADIATION SOURCES AT WORK 

Article 43 

Applicat ion 

1. This Title shall apply to exposures to natural  radiation sources at 

work  to  the  extent  that  the  competent  authority  has  declared, 

fol lowing.a survey carried out under Article 44  (1), that exposure to 

these natural  radiation sources is subject to control. 

2. In particular  this Title  shall apply to: 

a)  operations  in identified workplaces where  it has been declared 

that  radon  or  gamma  radiation  needs  attention  such  as: 

operations  in spas, caves, mines (other than uranium mines) and 

other underground workplaces; 

b)  identified operations with and storage of materials not usually 

regarded  as  radioactive, but  which  contain significant  traces 

of natural radionuclides; 

« 

c)  identified operation of jet aircraft  in flight. 

3.  Without  prejudice  to  the  above  paragraphs,  it  does  not  apply  to 

potassium-40  in  the  body,  cosmic  rays  at  ground  level,  and 

radionuclides in the earth's crust. 

-  58 -

Article 44 

Surveys and protective measures 

1.  Each  Member  State  shall  require  surveys  to  be  carried  out  to' 

identify  in which  areas of  its  territory,  and  for  which  practices  and 

working  conditions,  workers  are  likely  to  experience  significant 

exposures due to gamma  radiation or  radon gas and  its daughters, or due 

to operations with materials containing  significant  amounts of  natural 

radionuclides. 

2.  Member  states  shall,  on  the  basis  of  such  surveys  and  for  each 

identified  area,  practice  and  working  conditions,  require,  as 

appropriate: 

a)  arrangements  for  measurements  to assess  the  doses  received  by  the 

workers; 

b)  the  application  at  the  workplace  of  the  principles  laid  down  in 

Ar t i cIe 7 ; 

c)  the  establishment  of  regulations,  standards  or  codes  of  practice 

for construction of new workplaces; 

d)  the opening of a radon section of  the health  record  for workers. 

Article 45 

Protection of Aircrew 

Each  Member  State  shall  make  arrangements  for  the  assessment  of 

exposure  of  aircrew  involved  in  the  operation  of  jet  aircraft, 

identified  under  Article  43  (2)  (c),  by  their  employers  and  shall, 

where appropriate, classify aircrew as exposed  workers. 

- 59 -

TITLE VIII 

FUNDAMENTAL PRINCIPLES GOVERNING OPERATIONAL 

PROTECTION OF THE POPULATION IN NORMAL CIRCUMSTANCES 

Article 46 

Basic Principle 

Each  Member  State  shall  take  all  necessary  measures  to  ensure  the 

protection of the population. 

Article 47 

Conditions for authorization of practices 

involving a hazard from  ionizing radiation 

for the population 

In cases decided upon by each Member  State  in the  light of the extent 

of the exposure hazard  involved, the competent  authorities shall carry 

out  the  following  tasks  concerning  practices  subject  to  prior 

authorization: 

a)  examination  and  approval  of  plans  for  undertakings  involving  an 

exposure  hazard, and of  the proposed  siting  of  such  undertakings 

within the territory concerned, from the point of view of radiation 

protection; 

b)  acceptance  into  service  of  such  new  undertakings  subject  to 

adequate  protection  against  any  exposure  or  radioactive 

contamination  liable  to extend  beyond  the  perimeter,  taking  into 

account,  if  relevant,  demographic,  meteorological,  geological, 

hydro logical and ecological conditions; 

c)  examination and approval of plans for  the discharge of radioactive 

waste. 

- 60 -

Article 48 

Estimates of population doses 

The competent authorities shall: 

1.  ensure that dose estimates from all sources are made for the whole 

population of  the area concerned  and  for  reference groups of  the 

population in all places where such groups may occur; 

2.  decide on the frequency of assessments and take all necessary steps 

to  identify  the  reference  groups of  the  population,  taking  into 

account  the effective pathways of  transmission of  the radioactive 

mater ials*, 

3.  ensure  that,  taking  into  account  the  radiological  hazards,  the 

estimates of the population doses include: 

a)  assessment of the doses due to external  radiation, indicating, 

where appropriate, the quality of the radiation  in question; 

b)  assessment  of  the  intake  of  radionuclides,  indicating  the 

nature  of  the  radionuclides  and,  where  necessary,  their 

physical and chemical states, and déterminât ion of the activity 

and concentrations of these radionuclides; 

c)  assessment  of  the  doses  that  the  reference  groups  of  the 

population  are  liable  to  receive  and  specification  of  the 

characteristics of these groups; 

4.  require  records  to be  kept  relating  to measurements  of  external 

exposure,  estimates  of  intakes  of  radionuclides  and  radioactive 

contamination as well as the results of the assessment of the doses 

received by reference groups and by the population. 

- 61 -

Article 49 

Inspection 

1. Each Member State shall establish a system of  inspection to: 

-  keep under review the radiation protection of the population; 

check  compliance  with  the  national  regulations  implementing  this 

Directive. 

2.  Inspections  of  shipments  of  sealed  sources  and  other  relevant 

sources,  pursuant  to  Community  or  national  law,  for  the  purpose  of 

radiation  protection  shall  be  performed  as  part  of  the  control 

procedures  applied  in  a  non-discriminatory  manner  throughout  the 

territory of the Member State. 

- 62 -

Article 50 

Tasks within undertakings 

1.  Each- Member  State  shall  require  the  management  responsible  for 

practices  as  referred  to  in  Article 2  to  conduct  them  in  accordance 

with  the general  principles of  health  protection  of  the  population  and 

in particular  to carry out  the following  tasks within  its undertaking: 

a)  achieving  and maintaining  an optimal  level  of  protection; 

b)  checking  the effectiveness of  technical  devices  for  protecting  the 

environment  and  the population; 

c)  acceptance  into service,  from  the point  of  view of  surveillance of 

radiation  protection,  of  equipment  and  procedures  for  measuring 

exposure  and  radioactive  contamination  of  the  environment  and  the 

population; 

d)  regular  calibration  of  measuring  instruments  and  regular  checking 

that  they are serviceable and correctly  used. 

2. The  tasks provided  for  in paragraph  1 shall  be  the responsabiIity of 

qualified experts. 

- 63 -

TITLE  IX 

POTENTIAL. ACCIDENTAL AND EMERGENCY  EXPOSURES 

Article 51 

Tasks of  the competent  authorities 

1. Each  Member  State  shall  require  that  the possibilities of  accidents 

and  the  potential  exposures  due  to  those  accidents  affecting 

undertakings or  sources within  its jurisdiction are considered  and  that 

intervention  plans  are  drawn  up  and  are  tested,  to  an  appropriate 

extent,  at  regular  intervals. 

2.  In  particular,  intervention  plans  shall  take  into  account  the 

following aspects: 

a) The  general  principles  of  radiation  protection  for  intervention 

mentioned  hereafter  shall  be  respected: 

» 

-  the reduction  in health  detriment  due  to radiation,  resulting 

from  the reduction  in dose, should  be sufficient  to  justify  the 

harm  and costs,  including  social  costs, of  the  intervention; 

-  the  form,  scale  and  duration  of  the  intervention  should  be 

optimised  so  that  the  benefit  of  the  reduction  in  health 

detriment,  less the detriment  associated  with  the  intervention, 

will  be maximised; 

-  dose  limits, as  laid down  in Articles 9 and  14,  do not  apply 

to  intervention.  However,  guidance  on  the  situations  in  which 

intervention  is appropriate  will  be  given  by  the  intervention 

levels adopted under  sub-paragraph  (c) below. 

-  64 -

b)  Each  Member  State  shall  require  provision  to  be  made  for 

interventions related  to: 

-  the  source,  to  reduce  or  stop  the  direct  radiation  and 

emission of  radionuclides; 

-  the  environment,  to  reduce  the  transfer  of  radioactive 

substances  to  individuals; 

-  individuals,  to  reduce  the  accidental  exposure  and  organize 

the treatment  of victims. 

c)  Each  Member  State  shall  adopt  intervention  levels,  taking 

account  of  any  intervention  levels  established  by  Community 

legislation. 

d)  Each  Member  State  shall  arrange,  where  necessary,  for  the 

designation  of  special  teams  for  technical,  medical  and  health 

interventions  on  a  national  basis  and  for  their  training  in 

accordance  with  Article  7  of  Directive  89/618/Euratom.  If 

necessary,  these  arrangements  shall  be  made  in  cooperation  with 

competent  organizations  in other  States. 

e)  Each  Member  State  shall  provide  for  the  organization  of 

intervention  in  case  of  a  major  accident  in  or  outside  its 

territory. 

f)  Each  Member  State  shall  assess  and  record  the  consequences  of 

any accident  and the effectiveness of  the  intervention. 

-  65  -

Article  52 

Cooperation with other  States 

1.  Without 

prejudice 

to  relevant 

Community 

legislation  and 

international  agreements, each  Member  State  shall,  in  the  event  of  a 

radiological  emergency  at  an undertaking  on  its territory  or  likely  to 

have radiological  consequences on  its territory, establish  relations to 

obtain  cooperation  with  any  other  Member  State  or  non-member  State 

which may be  involved. 

2.  Each  Member  State  shall  require  emergency  plans  to  be  drawn  up  in 

its  territory  in  relation  to  possible  radiological  emergencies  at 

undertakings  outside  its  own  territory,  in  accordance  with  the 

provisions of Article  51. 

3.  Each  Member  State  shall  seek  to  cooperate  with  other  Member  States 

or  non-member  States  in  relation  to  possible  radiological  emergencies 

at  undertakings  on  its  own  territory,  in  order  to  facilitate  the 

organization  of  radiological  protection  in these  States,  in accordance 

with  the provisions of Article 51. 

Article  53 

Potential  exposures 

Each Member  State shall, where appropriate: 

consider  the probability  and  magnitude  of  potential  exposures  from 

practices  carried  out  by  persons  and  undertakings  subject  to  the 

system of reporting or authorization  laid down  in Title  III; 

-  66 -

seek  to  assess  the  spatial  and  temporal  distribution  of-  the 

radioactive  substances  dispersed  following  possible  accidents, 

recognizing  the  increasing  difficulties  when  the  probability  of 

occurrence of  the accident  decreases; 

establish  technical  standards  for  the  undertakings  or  sources, 

intervention plans  for  the different  kinds of accident  and  training 

of  special  emergency  teams. 

Article 54 

Tasks of management 

1. Each  Member  State  shall  require  the management  to draw up  plans  for 

intervention within  the undertakings under  its responsibility. 

2.  Each  Member  State  shall  make  provision  for  the  immediate 

notification  to  its  competent  authorities,  by  the  management 

responsible  for  the  practice  involved,  of  accidents  occurring  on  its 

territory  and  require  all  appropriate  actions  to  reduce  the 

consequences. 

3. Each Member  State shall  require  that  in the event  of  an accident  the 

responsible  management  shall  make  an  initial  provisional  assessment  of 

the  consequences  of  the  accident  and  successive  assessments  based  on 

subsequent  measurements of  radioactive contamination. 

-  67 -

Article 55 

Emergency  exposures 

1.  Each Member  State  shall  make  provision  for  situations where  workers 

or  intervention  personnel  involved  in  different  kinds  of  intervention 

are  liable  to. be subjected  to emergency exposures  resulting  in doses  in 

excess of  the dose  limits for exposed workers. To  this end, each  Member 

State shall  establish  exposure  levels taking  into account  the  technical 

obligations  and  the  health  risks;  these  levels  shall  be  operational 

guides.  An  exposure  above  these  special  levels  may  be  admitted 

exceptionally  to  save  human  lives  and  only  for  volunteers  who  are 

informed  about  the risks  involved  in their  intervention. 

2.  Each  Member  State  shall  require monitoring  and  medical  surveillance 

of  the persons exposed  in the emergency  teams. 

-  68 -

TITLE X 

FINAL PROVISIONS 

Article  56 

Accelarated  procedure 

1. Where the procedure  laid down  in this Article  is to be followed, the 

Commission  shall  submit  to  the  Council  a  proposal,  after  consultation 

of  the  group  of  experts  instituted  under  Article  31  of  the  Euratom 

Treaty. 

2.  The  Council  shall, acting  by  a  qualified  majority,  decide  upon  the 

proposal  within three months. 

3.  The  Commission  shall  examine  any  request  for  a  proposal  made  by  a 

Member State. 

Article  57 

Reports on  implementation 

1.  Every  two  years,  and  for  the  first  time  on 

(date  to  be 

specified), each Member  State shall  forward  to  the Commission  a  report 

on  the  implementation of  this  Directive,  including  the  results  of  the 

assessments made under Article 15. 

2.  On  the  basis  of  these  reports,  the  Commission  shall  prepare  a 

summary  report  for  the  European  Parliament,  the  Council  and  the 

Economic and Social  Committee. 

-  69 -

Article  58 

Implementation  in Member  States  law 

1.  Member  States  shall  bring  into  force  the  laws,  regulations  and 

administrative provisions necessary  to comply  with  this Directive on 31 

December  1994. They  shall  immediately  inform  the Commission  thereof. 

When  Member  States  adopt  these  provisions,  these  shall  contain  a 

reference  to  this  Directive  or  shall  be  accompanied  by  such  reference 

at  the  time  of  their  official  publication.  The  procedure  for  such 

reference  shall  be adopted  by Member  States. 

2.  Member  States  shall  communicate  to  the  Commission  the  main 

provisions  of  national  law  which  they  adopt  in  the  field  covered  by 

this Direct ive. 

Article 59 

Repeals 

Directives 

76/579/Euratom 

and 

80/836/Euratom 

and 

Regulation 

93/1493/Euratom  are  repealed  with effect  from  31  December  1994. 

Article  60 

This Directive  is addressed  to the Member  States 

Done at Brussels 

199... 

For  the CounciI, 

The President, 

-  70 

ANNEX I 

Values of quantities and concentrations of  radionuclides to be used 

for  the application of Article 3. 

1.  Table  A  below  presents  the  values  of  quantities  and 

concentrations  of  activity  per  unit  mass  not  to  be  exceeded  in 

compliance  with  Articles  3  (a)  and  (b)  respectively  for  the 

principal  radioactive nuclides concerned. 

2. For  radionuclides not  listed  in Table A, the competent  authority 

shall 

assign  appropriate 

values 

for 

the  quantities  and 

concentrations  of  activity  per  unit  mass  where  the  need  arises. 

Values thus assigned  shall  be complementary  to those  in Table A. 

3. The  values  laid down  in Table A apply  to  the  total  inventory  of 

radioactive substances held by a person or undertaking at any  point 

i n t i me. 

4.  The  values  laid down  in Table  A  column  3  for  the concentration 

of activity per unit mass pertain to the use of moderate amounts of 

radioactive  substances;  they  shall  not  be  applied  to  other 

practices  involving  low  levels  of  radioactivity  unless  it  can  be 

demonstrated  that  the  same  values 'are  justified;  levels  laid  down 

by  the  competent  authorities  for  the  general  or  specific 

authorization  of  waste  disposal  or  of  recycling  shall  be 

constrained  so  as  to  ensure  that  materials  released  to  the 

environment  shall  not exceed  the values specified  in Table A. 

- 71 -

5.  Nuclides  carrying  the  suffix  * + ' or  'sec'  in Table  A  represent 

parent  nuclides  in  equilibrium  with  their  corresponding  daughter 

nuclides  as  listed  in  Table  B.  In  this  case  the  values  given  in 

Table  A  refer  to  the parent  nuclide  alone  but  already  take  account 

of  the daughter  nuclide(s) present. 

6.  In  all  other  cases  of  mixtures  of  more  than  one  nuclide  the 

requirement  for  reporting  may  be  waived  if  the  sum  of  the  ratios 

for  each  nuclide  of  the  total  amount  present  divided  by  the  value 

listed  in Table  A  is  less  than  or  equal  to  1.  This  summation  rule 

also  applies  to activity  concentrations where  the  various  nuclides 

concerned  are contained  in the same matrix. 

- 72 -

1. 

Table A: Values of quantities and of concentrations of  activity 

per  unit  mass  not  to  be  exceeded  in compliance  with  Article  3 

(2)  (a)  and  (b)  respectively,  for  the  principal  radioactive 

nuclides  Iisted below: 

NucIi de 

Quantity  (Bq) 

Concentrât ion 

(kBq/kg) 

H-3 

Be-7 

C-14 

0-15 

F-18 

Na-22 

Na-24 

Si-31 

P-32 

P-33 

S-35 

CI-36 

CI-38 

Ar-37 

Ar-41 

K-42 

K-43 

Ca-45 

Ca-47 

Sc-46 

Sc-47 

SC-48 

V-48 

Cr-51 

Fe-52 

Fe-55 

Fe-59 

Mn-51 

Mn-52 

Mn-52m 

108 

108 

106 

109 

105 

105 

105 

105 

105 

10? 

10? 

105 

105 

1012 

109 

106 

105 

106 

105 

106 

106 

105 

105 

10? 

105 

106 

106 

105 

105 

105 

106 

102 

104 

103 

10 

1 

1 

102 

102 

105 

105 

103 

1 

107 

103 

10 

10 

10* 

10 

1 

10 

1 

1 

102 

10 

104 

1 

10 

1 

1 

73 

\ 

1 

Nuc1i de 

Q u a n t i ty 

(Bq) 

C o n c e n t r at  Ion 

( k B q / k g) 

Mn-53 

Mn-54 

Mn-56 

Co-55 

Co-56 

Co-57 

Co-58 

Co-58m 

Co-60 

Co-60m 

Co-61 

Co-62m 

N i - 59 

N i - 63 

N i - 65 

Cu-64 

Zn-65 

Zn-69 

Zn-69m 

Ge-71 

Ga-72 

As-73 

As-74 

As-76 

As-77 

Se-75 

B r - 82 

K r - 74 

K r - 76 

K r - 77 

K r - 79 

K r - 81 

Kr-83m 

K r - 85 

108 

106 

10* 

105 

10* 

105 

105 

107 

104 

10* 

105 

105 

10? 

10? 

105 

106 

105 

105 

10® 

109 

105 

106 

105 

105 

105 

106 

105 

1 0* 

10™ 

10« 

10™ 

i on 

i on 
10™ 

1 04 

10 

1 

1 

1 

10 

10 

1 04 

1 

1 03 

10 

1 

1 04 

105 

10 

10 

10 

102 

10 

1 03 

1 

1 03 

10 

10 

102 

10 

1 

1 03 

1 03 

103 
1 04 
1 05 

1 06 

1 06 

" 

74 

Nuclide 

Quantity  (Bq) 

Concentrat  ion 

(kBq/kg) 

Kr-85m 

Kr-87 

Kr-88 

Sr-85 

Sr-85m 

Sr-87m 

Sr-89 

Sr-90+ 

Sr-91 

Sr-92 

Y-90 

Y-91 

Y-91m 

Y-92 

Y-93 

Rb-86 

Zr-93+ 

Zr-95 

Zr-97+ 

Nb-93m 

Nb-94 

Nb-95 

Nb-97 

Nb-98 

Tc-96 

Tc-96m 

Tc-97 

Tc-97m 

Tc-99 

Tc-99m 

Mo-90 

Mo-93 

Mo-99 

Mo-101 

10™ 

109 

10» 

106 

106 

106 

105 

104 

10* 

10* 

10* 

105 

107 

10* 

105 

105 

106 

106 

105 

107 

106 

106 

105 

105 

106 

108 

107 

106 

106 

107 

105 

10? 

105 

105 

1 04 

1 03 

1 03 

10 

10 

10 

102 

10 

10 

1 

10 

102 

10 

10 

10 

10 
103 

10 

10 
1 03 

1 

10 

10 

1 

1 
1 02 

103 
103 

104 

10 

10 
1 03 

10 

1 

75 

Nuclide 

Quantity (Bq) 

Concent rat ion 

(kBq/kg) 

Ru-97 

Ru-103 

Ru-105 

RU-106+ 

Rh-103m 

Rh-105 

Pd-103 

Pd-109 

Cd-109 

Cd-115 

Cd-115m 

Ag-105 

Ag-110m 

Ag-111 

ln-111 

ln-113m 

ln-114m 

ln-115m 

Sn-113 

Sn-125 

Sb-122 

Sb-124 

Sb-125 

1-123 

1-125 

1-126 

1-129 

1-130 

1-131 

1-132 

1-133 

1-134 

1-135 

107 

10* 

10* 

105 

108 

106 

107 

105 

106 

105 

105 

106 

106 

105 

106 

105 

105 

105 

106 

105 

105 

105 

106 

107 

105 

105 
104 

105 

105 

105 

105 

105 

105 

10 

10 

10 

10 
103 

102 

103 

102 
103 

10 

102 

10 

1 

102 

10 

10 

102 

10 

102 

10 

10 

1 

10 

10 
102 

10 

102 

1 

10 

1 

10 

1 

1 

-  76 -

Nue Ii de 

Quantity  (Bq) 

Concentrât ion 

(kBq/kg) 

Cs-129 

Cs-131 

Cs-132 

Cs-134m 

Cs-134 

Cs-135 

Cs-136 

CS-137+ 

Cs-138 

Te-123m 

Te-125m 

Te-127 

Te-127m 

Te-129 

Te-129m 

Te-131 

Te-131m 

Te-132 

Te-133 

Te-133m 

Te-134 

Xe-131m 

Xe-133 

Xe-135 

Ce-139 

Ce-141 

Ce-143 

Ce-144+ 

Ba-131 

Ba-140+ 

La-140 

Pr-142 

Pr-143 

106 

106 

106 

105 

105 

106 

105 

105 

104 

106 

106 

105 

106 

105 

105 

105 

106 

106 

105 

105 

105 

1010 

1010 

1010 

106 

106 

TO5 

105 

106 

105 

105 

105 

106 

10 

102 

10 

102 

1 

104 

1 

10 

1 

10 

102 

102 

103 

10 

102 

10 

1 

10 

10 

1 

10 

105 

104 

104 

10 

102 

10 

10 

10 

1 

1 

10 

102 

77 

Nuclide 

Quantity (Bq) 

Concentration 

dcBq/kg) 

Pm-147 

Pro-149 

Nd-147 

Nd-149 

Sm-151 

Sm-153 

Eu-152 

Eu-152m 

Eu-154 

Eu-155 

Gd-153 

Gd-159 

Tb-160 

Dy-165 

Dy-166 

Ho-166 

Er-169 

Er-171 

Tm-170 

Tro-171 

Yb-175 

Lu-177 

Ta-182 

Hf-181 

W-181 

W-185 

W-187 

Re-186 

Re-188 

Os-185 

Os-191 

0s-191m 

Os-193 

lr-190 

10 
ios 
105 

10* 

107 

105 

10* 

105 

10* 

10* 

10* 

105 

105 

105 

10* 

105 

10* 

10* 

10« 

107 

106 

10® 

10* 

105 

107 

10« 

10* 

10* 

105 

10© 

10* 

10® 

1Q5 

106 

10< 

102 

10 

10 
10s 
102 

1 

10 
1 
102 

10 

102 

1 
102 

102 

10 

10« 

10 
102 
10^ 
102 
102 

1 

10 
102 

1 04 

10 
102 

10 

10 
102 
103 
102 

1 

78 

Nuclide 

Quantity (Bq) 

Concentration 

(kBq/kg) 

Jr-192 

lr-194 

Pt-191 

Pt-193m 

Pt-197 

Pt-197m 

Hg-197 

Hg-197m 

Hg-203 

Au-198 

Au-199 

TI-200 

TI-201 

T1-202 

T1-204 

Bi-206 

Bi-207 

Bi-210 

BJ-212+ 

Pb-203 

Pb-210+ 

Pb-212+ 

Po-203 

Po-205 

Po-207 

Po-210 

At-211 

Rn-220+ 

Rn-222+ 

Ra-223+ 

Ra-224+ 

Ra-225 

10* 

105 

106 

106 

10* 

105 

10® 

105 

10» 

105 

10* 

106 

106 

10« 

105 

105 

106 

10* 

105 
io6 
103 

105 

105 

10* 

106 % 
103 

10» • 

107 

108 
104 
104 
104 

: 

: 

10 

10 

10 

102 

102 

102 

102 

102 

10 

10 

102 

1 

10 

10 

102 

1 

1 

102 

1 

10 

10 

1 

1 

1 

1 

10 

102 
104 

1 

10 

1 

102 

i 

79 

Nuclide 

Quantity (Bq) 

Concentration 

(kBq/kg) 

Ra-226+ 

Ra-227 

Ra-228+ 

Th-226+ 

Th-227 

Th-228+ 

Th-229+ 

Th-230 

Th-231 

Th-232sec 

Th-234+ 

AC-227+ 

Ac-228 

Pa-230 

Pa-231 

Pa-233 

U-230+ 

U-231 

U-232+ 

U-233 

U-234 

U-235+ 

U-236 

U-237 

U-238+ 

U-238sec 

U-239 

U-240 

U-240+ 

Np-237+ 

Np-239 

103 

105 
104 

106 
104 
104 
103 
103 

107 

102 

10* 
103 

105 

106 
103 

106 
104 

106 
103 
104 
104 
104 
104 

105 
104 
103 

105 

106 

105 
103 

106 

1 

10 

10 

102 

10 

1 

10 

10 

102 

1 

10 

10 

10 

10 

10 

10 

102 

102 

1 

102 

102 

102 
102 

10 

10 

1 

102 

103 
1 

10 

10 

80 

Nuclide 

Quantity (8q) 

Concentration 

(kBq/kg) 

Np-240 

Pu-234 

PU-235 

PU-236 

Pu-237 
Pu-238 
Pu-239 
Pu-240 
Pu-241 
Pu-242 
Pu-243 
Pu-244 
Am-241 

Am-242 
Am-242m+ 

Am-243+ 
Cm-242 

Cm~243 

Cn-244 
Cm-245 

Cm-246 
Cm-247 
Cm-248 
Bk-249 
Cf-246 
Cf-248 
Cf-249 

Cf-250 

Cf-251 

Cf-252 

Cf-253 

Cf-254 

105 
108 
108 
10* 
107 
103 
103 
103 
105 
103 
106 
103 
103 
106 
103 
103 
10s 
103 
10* 
103 
103 
103 
103 
106 
106 
104 
103 
10* 
103 
10* 
106 
103 

i 

1 
102 
102 
102 
102 
10 
10 
10 
103 
10 
102 
10 
10 
102 
102 
10 
103 
10 
102 
10 
10 
10 
10 
10« 
103 
102 

10 
102 

10 

102 

10* 

10 

- 81 -

Nuclide 

Quantity (Bq) 

Concentration 

Es-253 

Es-254 

Es-254m 

Fm-254 

Fm-255 

105 
104" 
10s 
107 
106 

(kBq/kg) 

103 
102 

10 
104 
103 

- 82 

Table B:  List  of  nuclides  in  secular  equilibrium  as  referred  to  in 

pt. 5 

Parent 

nucIi de 

Daughter nucI ides 

Sr-80+ 

Sr-90+ 

Zr-93+ 

Zr-97+ 

RU-106+ 

CS-137+ 

Ce-134+ 

C6-144+ 

Ba-140+ 

B1-212+ 

Pb-212+ 

Rn-220+ 

Rn-222+ 

Ra-223+ 

Ra-224+ 

Rb-80 

Y-90 

Nb-93m 

Nb-97 

Rh-106 

Ba-137 

La-134 

Pr-144 

La-140 

TI-208,Po-212 

Bi-212,TJ-208,Po-212 

Po-216 

Po-218,Pb-214,BI-214 

Rn-219,Po-215.Pb-211.Bi-211 

Rn-220,Po-216,Pb-212tBi-212,TI-208, 

Po-212 

Ra-226+ 

Rn-222,Po-218fPb-214tBi-214,Pb-210, 

Ra-228+ 

Th-226+ 

Th-228+ 

Bi-210,Po-210 

Ac-228 

Ra-222,Rn-218, Po-214 

Ra-224,Rn-220,Po-216,Pb-212,Bi-212, 

TI-208,Po-212 

Th-229+ 

Ra-225,Ac-225,Fr-221,At-217,B i-213, 

Po-213,Pb-209 

Th-232sec 

Ra-228,Ac-228,Th-228,Ra-224,Rn-220, 

Po-216,Pb-212,Bi-212,TI-208,Po-212 

- 83 -

Daughter nucI ides 

Pa-234m 

Fr-223,Ra-223,Rn-219,Po-215,Pb-211, 

Bi-211 

Th-226,Ra-222,Rn-218,Po-214 

Th-228,Ra-224,Rn-220,Po-216,Pb-212, 

Bi-212,TI-208,Po-212 

Th-231 

Th-234,Pa-234m 

Parent 

nucIi de 

Th-234+ 

AC-227+ 

U-230+ 

U-232+ 

U-235+ 

U-238+ 

U-238sec 

Th-234,Pa-234m,U-234,Th-230,Ra-226, 

Rn-222,Po-218,Pb-214,Bi-214,Pb-210, 

B i - 2 1 0 , P o - 2 10 

U-240+ 

Np-237+ 

Am-242m+ 

. 

AB1-243+ 

Np-240 

Pa-233 

Am-242 

Np-239 

- 84 -

ANNÇ* I» 

A.  Definitions of terms used  in this ANNEX 

Effective quality factor  (0): average value of the quality factor where 

the dose absorbed  is delivered  by particles with  different  L  values. 

It is calculated according to the expression: 

Q - 1/D^/~ 

Q (dD/dL  )dL 

Quality factor  (0): a function of  linear energy transfer  (L  ) used to 

weight  absorbed doses  in such a way as to  indicate  their  significance 

for radiation protection purposes. 

Radiation  weighting  factor  ( W R ):  a  dimens ion Iess  factor  which  is 

used  to  weight  the  absorbed  dose.  The  appropriate  WR  values  are 

specified  in this Annex. 

Tissue  weighting  factor  (wT):  a  dimensionless  factor  used  to weight 

the  equivalent  dose.  The  appropriate  values  are  specified  in  this 

Annex . 

Unrestricted  Linear  energy  transfer  (Loo 1: the  unrestricted  linear 

energy transfer  is defined as 

L « , - i£ 
dl 

where  dE  is  the  mean  energy  lost  by  a  particle  of  energy  E  in 

traversing a distance dl.  In the Directive Leo is denoted by L. 

- 85 -

B.  Values of  radiation weighting  factor, wR 

Values  of  radiation  weighting  factor,  wR,  depend  on  the  type  and 

quality  of.the external  radiation  field or  on  the  type  and  quality 

of  the radiation emitted  by an  internally deposited  radionuclide. 

When  the  radiation  field  is  composed  of  types  and  energies  with 

different  values  of  wR,  the  absorbed  dose  must  be  sub-divided 

into  blocks,  each  with  its own  value  of  wR  and  added  to  give  the 

total  equivalent  dose.  Alternatively,  it  may  be  expressed  as  a 

continuous  distribution  in  energy  where  each  element  of  absorbed 

dose  from  the energy  element  between  E and  E + dE  is multiplied  by 

the value of wR  from  the relevant  entry  in the Table  below. 

Type and energy  range 

Radiation  weighting 

factor, 

wR 

Photons, all  energies 

Electrons arid muons, all  energies 

Neutrons, energy  < 10 keV 

10 keV  to 100 keV 

>  100 keV  to 2 MeV 

> 2 MeV  to 20 MeV 

>  20 MeV 

Protons, other  than recoil 

Protons, energy > 2 MeV 

Alpha particles, fission 

fragments, heavy  nuclei 

1 

1 

5 

10 

20 

10 

5 

20 

In calculations  involving  neutrons, difficulties  may  arise  in applying 

step  function  values.  In  these  cases  it may  be  preferable  to  use  the 

continuous 

function 

described 

by 

the 

following 

mathematical 

relationship: 

wR  « 5 + 17e -<ln(2E))2/6 

where E  is the neutron energy  in MeV. 

- 86 -

A direct comparison of the two approaches is given .in Figure 1 

25 r 

v.  2 0;

r 

u 
o 
? . . 15 

i b t-

XL 

c 
o. 

o 
oe 

. - /-

-t-

V 

\ 

^ 

10 

X 
_-s 

10 

10 

X 
-3 
10" 

X 
10 

-2 

X 
-1 
10 

X 
10 

10 

10 

Incident  neutron  energy  I  MeV I 

l-'ijî. Y.  Radiation ^clçhtinc factors fur neutrons. The smooth curve i> to be treated a^ an approximation. 

For radiation types and energy which are not  included  in the table, an 

approximation  of  wR  may  be obtained  by  calculation  of  0  at  a  10 mm 

depth  in a 30 cm diameter, tissue-equivalent sphere with a density of 
1  cm""3 and  a mass composition  of  76.2% oxygen,  11.1% carbon, 10.1% 

hydrogen and 2.6% nitrogen: 

CO 

X | Q(L)D(L)dL 

• • If' 

where  D(L)dL  is the absorbed  dose at  10 mm between  I inear energy 

transfer  L and L + dL; and 0(L)  is the quality  factor of L at  10 

mm. The Q-L relationships are given in B. 

- 87 -

C.  Relationship  between  the  quality  factor,  Q(L),  and  unrestricted 

linear energy transfer, L 

Unrestricted  linear energy 

Q(L) 

transfer, L in water 
(keV  fair1) 

< 10 

10 - 100 

> 100 

0.32L - 2.2 

300/y£ 

D.  Values of tissue weighting factor, wj^1^) 

((D)  The values have been developed  from a reference  population of 

equal  numbers of both sexes and a wide range of  ages.  In the 

definition  of  effective  dose  they  apply  to  workers,  to  the 

whole population, and to either sex. 

- 88 -

Values of  tissue weighting  factor, wT, are shown below: 

Tissue or organ 

Tissue weighting 

factors, Wj 

Gonads 

Bone marrow  (red) 

Colon 

Lung 

Stomach 

Bladder 

Breast 

Liver 

Oesophagus 

Thyroid 

Skin 

Bone surface 

Remainder 

0.20 

0.12 

0.12 

0.12 

0.12 

0.05 

0.05 

0.05 

0.05 

0.05 

0.01 

0.01 

0.05  (<2))((3)) 

((2))  For  the  purposes  of  calculation,  the  remainder  is composed  of 

the  following  additional  tissues  and  organs:  adrenals, brain, 

upper  large  intestine,  small  intestine,  kidney,  muscle, 

pancreas,  spleen,  thymus  and uterus.  The  list  includes organs 

which  are  likely  to be selectively  irradiated.  Some organs  in 

the  list  are  known  to be  susceptible  to  cancer  Induction.  If 

other  tissues  and  organs  subsequently  become  identified  as 

having  a  significant  risk  of  induced  cancer  they  will  then  be 

included  either  with  a  specific  WT  or  in  this  additional  list 

constituting  the  remainder.  The  latter  may  also  include other 

tissues or organs selectively  irradiated. 

((3)) 

In  those  exceptional  cases  in  which  a  single  one  of  the 

remainder  tissues  or  organs  receives  an  equivalent  dose  in 

excess  of  the  highest  dose  in  any  of  the  twelve  organs  for 

which  a  weighting  factor  is  specified,  a  weighting  factor  of 

0.025 should be applied  to that  tissue or organ  and a weighting 

factor  of  0.025  to  the  average  dose  in  the  rest  of  the 

remainder  as defined above. 

- 89  -

ANNEX III 

Arrangements for assessing the effective doses due to intakes 

The  limits on effective dose set out  in Articles 9, 12 and 14 apply to 

the sum of the effective dose received  in the specified period and the 

committed  effective  dose  due  to  intakes  in  the  same  period.  The 

relationship between  intake and committed effective dose depends on the 

age  of  the  individual,  on  the  physical  and  chemical  form  of  the 

radioactive material and on the route of intake. 

These relationships can then be used to estimate the relevant effective 

doses.  If  derived  limité  are  used  for  external  exposure  and  for 

intakes, the  limit on effective  dose can be applied  by  the following 

expression for each of the relevant age groups: 

(This  Annex  will  contain  for  all  relevant  radionuclides  dose 

coefficients (Sv/Bq) for  inhalation and  ingest ion'for different age 

categories  regarding  the  population  and  for  workers.  For  the 
exposures  to  noble  gases  coefficients  in  the  unit  Svy1/Bqm~3 

wi 11 be given). 

ISSN 0254-1475 

COM(93) 349 final 

DOCUMENTS 

EN 

04  05 

Catalogue number : CB-CO-93-381-EN-C 

i 

ISBN 92-77-58078-X 

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