Basic Safety Standards for Radiation Protectiongnssn.iaea.org/Superseded Safety Standards/Safety_Series... · 2012. 8. 1. · Australian Atomic Energy Commission Australia Representatives

- tv iSAFETY g S E R I E S

No. 9

Basic Safety Standardsfor

Radiation Protection

I N T E R N A T I O N A L ATOMI C ENERGY AGENCY

VIENNA 1962

This publication is no longer valid Please see http://www-ns.iaea.org/standards/


BASIC SA FETY STANDARDS FOR RADIATION PROTECTION


The following States are Members of the International Atomic EnergyA gency:A FG H A N IST A NA LB A N IAA R G E N T IN AA U S T R A L IAA U S T R IAB E L G IU MB R A Z ILB U L G A R IAB U R M AB Y E L O R U S S IA N S O V IET

SO CIA LIST R E P U B L IC CAM BODIA CANADA C E Y L O N C H IL E CH IN A COLOM BIACONGO (L E O P O L D V IL L E ) C U BACZECH O SLO V A K SO CIA LIST

R E P U B L IC D EN M A R KDOM INICAN R E P U B L ICECU A D O RE L SALV AD O RE T H IO P IAF IN L A N DFR A N C EF E D E R A L R E P U B L IC

O F G ER M A N Y GHANA G R E E C E G U A TEM A LA H A IT I H O L Y S E E H O N D U RA S H U N G A R Y IC EL A N D IN D IA IN D O N ESIA IR A N IR A Q

IS R A E LIT A L YJA P A NR E P U B L IC O F K O R E AL EB A N O NL IB E R IAL U X E M B O U R GM A LIM EX IC OMONACOMOROCCON E T H E R L A N D SN E W ZEA LA N DN ICARAG UAN O R W A YPA K IS T A NPA R A G U A YP E R UP H IL IP P IN E SPO LA N DPO R T U G A LROM ANIASEN E G A LSO U TH A FR IC ASPA INSUDANS W E D E NSW IT Z E R L A N DT H A ILA N DT U N ISIAT U R K E YU K R A IN IA N SO V IET

SO CIA LIST R E P U B L IC U N IO N O F SO V IET

SO CIA LIST R E P U B L IC S U N IT E D A R A B R E P U B L IC U N IT E D KINGDOM O F G R E A T

B R IT A IN AND N O R T H E R N IR E L A N D

U N IT E D ST A T ES O F A M ER ICA V E N E Z U E L A V IET-N A MYU G O SLA V IA

The A gency’s S ta tu te was approved on 26 October 1956 a t an international conference held a t U nited Nations headquarters, New Y ork , and the A gency cam e into being when the S tatute entered into force on 29 Ju ly 1957. The first session of the General Conference was held in Vienna, A ustria, the perm anent seat of the A gency, in O ctober, 1957.

The m ain objective of th e Agency is “to accelerate and enlarge the contribution of atom ic energy to peace, health and prosperity throughout the world” .

© I A E A , 1962Permission to reproduce or translate the information contained in this publication m ay be obtained b y writing to the International A tom ic Energy A gency, K aern tner R ing 11, Vienna I.

P rin ted in A ustria by Globus, D ruck- un d V erlagsanstalt, V ienna N ovem ber 1962


SAFETY SERIES No. 9

BASIC SAFETY STANDARDS FOR RADIATION PROTECTION

IN T E R N A T IO N A L ATOMIC E N E R G Y A G EN C Y

V IE N N A 1962


TH ESE STANDARDS A RE ALSO

PU BLISH ED IN FRENCH, RUSSIAN AND

SPANISH

B A S IC S A F E T Y STAN D A RD S F O R R A D IA T IO N P R O T E C T IO N , IA E A ,V IE N N A , 1962

STI/PUB/26


FOREWORDPursuant to the provisions of its Statute relevant to the adoption

and application of safety standards for protection against radiation, the Agency convened a panel of experts which formulated the Basic Safety Standards set forth in this publication. The panel met under the chairmanship of Professor L. Bugnard, Director of the Franch Institut N ational d ’Hygikne, and representatives of the United Nations and of several of its specialized agencies participated in its work.

The Basic Safety Standards thus represent the result of a most careful assessment of the variety of complex scientific and administrative problems involved. Nevertheless, of course, they will need to be revised from time to time in the light of advances in scientific knowledge, of comments received from Member States and of the work of other competent international organizations.

The Agency’s Board of Governors in June 1962 approved the Standards as a first edition, subject to later revision as mentioned above, and authorized me, as Director General, to apply the Standards in Agency and Agency-assisted operations and to invite Governments of Member States to take them as a basis in formulating national regulations or recommendations on protection against the dangers arising from ionizing radiations.

I t is mainly for this last purpose that the Basic Safety Standards are now being published in the Safety Series; but it is hoped that this publication will also interest a much wider circle of readers.

November 1962SIGVARD EKLTJND

Director General



I n t r o d u c t i o n .................................................................................................................................................. 9A c k n o w l e d g e m e n t s ........................................................................................................................ 1 0

1 . E x p l a n a t i o n o f t e r m s u s e d .................................................................................................. 1 32 . S c o p e .............. .................................................................................................................................................... 1 53 . M a x i m u m p e r m i s s i b l e d o s e s ............................................................................................... 1 6

3 .1 . W o r k e r s d i r e c t l y e n g a g e d i n r a d i a t i o n w o r k ................................................... 1 63 .2 . W o r k e r s w h o a r e n o t d i r e c t l y e n g a g e d i n r a d i a t i o n w o r k ............... 1 73 .3 . I n d i v i d u a l m e m b e r s o f t h e p u b l i c ........................................................................... 1 73 .4 . T h e w h o l e p o p u l a t i o n ........................................................................................................... 1 8

4 . T h e p r a c t i c a l c o n t r o l o f r a d i a t i o n d o s e s ......................................................... 1 84 .1 . W o r k e r s d i r e c t l y e n g a g e d i n r a d i a t i o n w o r k ........................ .. ................. .. . 1 84 .2 . W o r k e r s n o t d i r e c t l y e n g a g e d i n r a d i a t i o n w o r k a n d i n d i v i d u a l

m e m b e r s o f t h e p u b l i c ........................................................................................................ 2 15 . F u n d a m e n t a l o p e r a t i o n a l p r i n c i p l e s ........................ ............................................ 2 2

5 .1 . G e n e r a l r e q u i r e m e n t s ........................................................................................................... 2 25 .2 . I n s p e c t i o n a n d i n t e r v e n t i o n .......................................................................................... 2 8A n n e x I : T a b l e s ............................................................................................................................. 2 9A n n e x I I : E s t i m a t i o n o f t h e d o s e to t h e l e n s o f t h e e y e . . . . 5 3A n n e x I I I : M i x t u r e s o f r a d i o n u c l i d e s .................................................................. 5 3

CONTENTS



INTRODUCTION1. Under Article I I I A. 6 of its Statute the Agency is authorized to establish or adopt, in consultation and, where appropriate, in collaboration with the competent organs of the United Nations and with the specialized agencies concerned, standards of safety for protection of health and minimization of danger to life and property (including such standards for labour conditions), and to provide for the application of these standards to its own operations as well as to the operations making use of materials, services equipment, facilities and information made available by the Agency or at its request or under its control or supervision; and to provide for the application of these standards, at the request of the parties, to operations under any bilateral or multilateral arrangement, or, at the request of a State, to any of that State’s activities in the field of atomic energy.2. The document in which are set forth the Agency’s Health and Safety Measures as approved by the Board of Governors on 31 March I960*, states in part that Agency safety standards shall include:

(a) The Agency’s basic safety standards—standards prescribing maximum permissible levels of exposure to radiation and fundamental operational principles; and

(b) The Agency’s detailed operational standards.3. This publication contains the Agency’s Basic Safety Standards as defined above. They are based, to the extent possible, on the recommendations of the International Commission on Radiological Protection (ICRP) and are in accord, to the extent possible, with standards published by other international organizations.4. In October 1958 the ICRP issued recommendations with respect to the maximum permissible accumulated dose for occupational radiation exposures and for exposures to the population. In 1959 the Commission released recommendations for the maximum permissible concentrations of radioactive materials in air and water. Both sets of recommendations were based upon the information available at that time concerning the biological effects of exposure to radiation from external sources and from concentrations of radioactive material in air and in water.5. The Agency believes that the limits established in the following Basic Safety Standards, based on the recommendations of the ICRP, provide an appropriate regulatory basis for protection of the health and safety of employees and the public without imposing undue burdens

* IA E A General Conference D ocum ent IN F C IR C /18

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upon users of radioactive material. The recommended limits on exposure, based upon extensive scientific and technical investigation and upon years of experience with the practical problems of radiation protection, represent a consensus of opinion as to the measures generally considered desirable to provide appropriate degrees of safety in the situations to which these standards apply.6. The Agency recognizes that the ICRP recommendations cannot be converted into regulations without loss of flexibility in their application to individual situations. I t is, however, the policy of the Agency to minimize this loss of flexibility both in the formulation of its regulations and in their administration, to the greatest extent compatible with the nature of the problem and with good regulatory practice.

Other publications of the Agency in its Safety Series should be consulted for practical detailed guidance in implementing these Standards : for example, guidance on maximum permissible levels for surface contamination is to be found in Safety Series No. 1*.

When applied to the Agency’s operations or to operations assisted by the Agency, this document is to be read in the light of the Agency’s Health and Safety Measures* *.

ACKNOWLEDGEMENTSThe Agency’s thanks are due to the following members of a panel of

experts convened by the Director General to discuss the original draft of the Basic Safety Standards prepared by the Secretariat:

Chairman:Prof. L. Bugnard+Institut National d’Hygiene F rance

Members:Dr. D. BeninsonAtomic Energy CommissionArgentina

Dr. H. T. Dunster++United Kingdom Atomic Energy

Authority United K ingdom

Dr. A. Hedgran Radiofysiska Institutionen Sweden

* Safe H andling of Radioisotopes (F irst Edition with Revised Appendix I) Safety Series No. 1, IA E A , Vienna, 1962* * IA E A General Conference docurrent IN F C IR C /18

+ Accom panied by Dr. H . Ja m m e t of the Commissariat a l ’Energie A tomique++ Accom panied b y Mr. A. H . K . Slater of the United Kingdom Atom ic E n ergy A uthority

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Dr. G. C. Butler (1st session)Mr. G. W. C. Tait (2nd session) Atomic Energy of Canada Ltd. C anada

Dr. L. L. Larsson (1st session)Dr. W. Binks (2nd session) International Commission on Radiological Protection

Prof. A. A. LetavetUnion o f Soviet Socialist Republics

Dr. A. S. RaoAtomic Energy Establishment In d ia

Prof. E . KowalskiPolska Akademia Nauk, InstytutBadan Jq,drowychPoland

Dr. L. TaylorNational Bureau of Standards United States of A m erica

Dr. S. WatariAtomic Energy Commission J a p a n

Dr. A. R. W. Wilson Australian Atomic Energy Commission A ustralia

Representatives of the United Nations, the specialized agencies and other inter-governmental organizations:Dr. Z. Ahmed United Nations

Dr. R . L. Dobson World Health Organization

Mr. E. HellenInternational Labour Organisation

Dr. P. RechtEuropean Atomic Energy Commis

sion

Dr. E . Wallauschek European Nuclear Energy Authority

of the O.E.E.C.

Mr. G. WortleyFood and Agriculture Organization of the United Nations

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1.1. PHYSICAL AND RADIOLOGICAL TERMS

Ion izing rad iation :Electromagnetic radiation (X-ray or y-ray photons) or corpuscular radiation capable of producing ionization in its passage through matter.

Source,:Apparatus capable of producing or substance producing ionizing radiation.

N u clide:A species of atom characterized by its mass number, atomic number, and when necessary nuclear energy state.

R adioactivity:Spontaneous disintegration of a nuclide.

A ctivity:Number of spontaneous disintegrations per unit time.

Specific activ ity :The number of disintegrations per unit time per unit mass of material.

R adiotoxicity :The toxicity attributable to the radiation emitted by a radioactive substance within the body.

External rad iation :Radiation reaching the body from external sources.

In ternal radiation :Radiation arising from radioactive substances within the body.

N atural rad iation :The various natural radiation sources include:

(a) External sources of extra-terrestrial origin (cosmic rays) and external sources of terrestrial origin, i.e. the radioactive isotopes naturally present in the crust of the earth and in air;

1. EXPLANATION OF TERMS USED

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(b) Internal sources, i.e. the radioisotopes K 40 and C14 which, exist as a small percentage of these elements and are normal constituents of the body, and other isotopes such as R a226 and Th232 and their decay products th a t are taken up from the natural environment.

Controlled area:An area scheduled as such for the purpose of controlling individual exposure to personnel and which is under the supervision of a person who has the knowledge and responsibility to apply appropriate radiation protection regulations.Qualified expert:A person having the knowledge and training required to give advice on protective measures and operating procedures which will ensure effective protection of the health of any persons exposed to ionizing radiation.Competent authority:A governmental or international authority having jurisdiction with respect to the activities under consideration.Emergency exposure:A planned exceptional exposure in the case of compelling or overwhelming necessity.Accidental exposure:An unforeseen exposure resulting in a radiation dose or intake of radioactive m aterial exceeding the maximum permissible values.U n i t s :

curie:The un it of quantity of radioactive material evaluated according to its radioactivity. 1 c is the quantity of a radioactive nuclide for which the number of disintegrations/s is 3.700XlO10.rad:The un it of absorbed dose—1 rad is 100 erg/g.

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rem:The rem is the absorbed dose of any ionizing radiation which has the same biological effectiveness as one rad of X radiation. A dose in rem is equal to the dose in rad multipled by the appropriate factor as listed in Table I or Table IA in Annex I.D o s e s :

Absorbed dose:Absorbed dose of any ionizing radiation is the energy im parted to m atter by ionizing particles per un it mass of irradiated m aterial a t the place of interest.Genetically significant dose:The genetically significant dose to a population equals the average gonad dose weighted for the expected number of children.

2. SCOPE2.1. These standards shall be applied to the production, pro

cessing, handling, use, storage and transport of natural and artificially produced sources and to the disposal of radioactive substances.

2.2. These standards shall not be applied to operations exempted from notification, registration or licensing under 5.1.1.4.

2.3. The aims of these standards are the protection of health and maintenance of safety. They apply to :(a) Workers directly engaged in radiation work;(b) Workers who are no t directly engaged in radiation

work, b u t who remain or pass where they m ay be exposed to ionizing radiation or radioactive substances ;

(c) Individual members of the public; and(d) The whole population as defined by the competent

authority.2.4. Doses referred to in these standards include the doses

received from both internal and external radiation. They do not include:(a) Doses to patients resulting from medical examinations

or treatm ent;(b) Doses resulting from natural radiation.

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3. MAXIMUM PERMISSIBLE DOSES3.1. W ORKERS DIRECTLY ENGAGED IN RADIATION

W ORK3.1.1. Except as provided in 3.1.3, 3.1.4, and subject to the proce

dures in 4.1.1.2, 4.1.1.3, 4.1.2.2 and 4.1.2.3, the to ta l dose accumulated to the whole body, gonads, blood-forming organs and lenses of the eyes received by an individual shall no t exceed the maximum permissible value derived from the basic formula

D = 5 ( N — 18)where D is the maximum permissible dose in rem, and N is the individual’s age in years. Age in years may, for adm inistrative purposes, be reckoned as from any selected date of the year. Maximum permissible doses for single organs other th an the blood-forming organs, gonads and lenses of the eyes are specified in 3.1.6.

3.1.2. Provided the accumulated dose does not exceed the m aximum permissible value derived from the basic formula, referred to in 3.1.1, a worker may be perm itted to receive in a quarter of a year a dose to the whole body, gonads, blood-forming organs and lenses of the eyes not exceeding 3 rem. 3 rem m ay be received as a single dose within a quarter of a year, bu t this should be avoided as far as practicable, especially in the case of women of reproductive age.

3.1.3. I f the dose previously accumulated in radiation work by the worker over a given period is no t known, it shall be assumed th a t the worker has received the maximum permissible dose as laid down in this document for th a t period. W hen the previous occupational exposure history of an individual is no t known, it shall be assumed th a t he has already accumulated the maximum dose for his age as perm itted by the formula.

3.1.4. Workers who were exposed in accordance with the former IC R P maximum permissible weekly dose of 0.3 rem and who have accumulated a dose higher th an th a t perm itted by the formula, should no t be exposed a t a rate higher than 5 rem in any one year, until the accumulated dose a t a subsequent tim e is lower th an th a t perm itted by the formula.

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3.1.5. I f a worker begins to be directly engaged in radiation work a t an age of less than 18 yr, provided the requirements of 3.1 are fulfilled, the dose to the whole body, gonads, blood-forming organs or lenses of the eyes shall not exceed 5 rem in any one year while the age is less than 18 yr, and the dose accumulated a t the age of 30 shall not exceed 60 rem.

3.1.6. For organs other th an the gonads, the blood-forming organs and th e lenses of the eyes, a worker shall no t receive in a quarter of a year a dose in excess of the values listed below :

Any single organ excluding the gonads, the blood-forming organs, bone, thyroidand skin 4 remBone 8 remThyroid 8 remSkin of the whole body 8 remHands, forearms, feet and ankles 20 rem

3.2. W ORKERS WHO ARE NOT DIRECTLY ENGAGED IN RADIATION W ORKA worker who is no t directly engaged in radiation work b u t who remains or passes where he m ay be exposed to ionizing radiation or radioactive substances, shall not receive in any one year a dose in excess of the values listed below :

Whole body GonadsBlood-forming organs Lenses of the eyesAny single organ, excluding blood-forming organs and lenses of the eyes, gonads, bone, thyroid and skin Bone ThyroidSkin of the whole body Hands, forearms, feet and ankles

3.3. INDIVIDUAL MEMBERS OF THE PUBLIC An individual member of the public shall not receive in any one year a dose in excess of the values listed below:

1.5 rem1.5 rem1.5 rem1.5 rem

1.5 rem 3 rem 3 rem 3 rem7.5 rem

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Whole body GonadsBlood-forming organs Lenses of the eyesAny single organ, excluding blood-formingorgans and lenses of the eyes, gonads, bone,thyroid and skinBoneThyroidSkin of the whole body

0.5 rem 0.5 rem 0.5 rem 0.5 rem

1.5 rem 3 rem 3 rem 3 rem

3.4. THE W HOLE POPULATION3.4.1. The genetically significant dose to the whole population

over a period of 30 yr shall not exceed 5 rem. Any allocation of the genetic dose among the various sections of the population will depend on circumstances which m ay vary from country to country and should, therefore, be made by the competent national authorities.

4. THE PRACTICAL CONTROL OF RADIATION DOSESThe exposure of individuals and the number of individuals exposed

m ust be kept as low as practicable. In the case of exposure to both external and internal radiations, the combination of both exposures shall be considered and, if necessary, the corresponding maximum permissible values shall be reduced in an appropriate way.

4.1. W ORKERS DIRECTLY ENGAGED IN RADIATION W ORK(i) No worker under the age of 16 shall be directly engaged

in work involving ionizing radiation (cf. 3.1.5).(ii) The to ta l dose to any organ or tissue shall comprise

the doses contributed by external sources during working hours and by the intake of radioactive m aterials into the body during working hours.

4.1.1. Exposure to external radiation only4.1.1.1. N o r m a l w o r k i n g c o n d i t i o n s

(i) Exposure to external radiation of workers directly engaged in radiation work shall be limited so as to

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ensure th a t the doses received shall no t exceed the maximum permissible doses listed in 3.1. The exposure to external radiation which will lead to these maximum permissible doses shall be determined on the basis of the data listed in Table I and Table IA of Annex I. For the purpose of estimating the dose to the lenses of the eye the procedure in Annex I I may be used,

(ii) For the purpose of planning and design a maximum weekly dose to the whole body of 0.1 rem shall be used.

4.1.1.2. E m e r g e n c y e x p o s u r e

Emergency work involving exposure above permissible limits shall be planned on the basis th a t the worker will not receive emergency doses in excess of 12 rem to the whole body in any one year. Emergency doses shall be added to the to ta l dose accumulated up to the tim e of the emergency exposure. I f the sum then exceeds the maximum value perm itted by the basic formula, the excess shall be compensated for by lowering the subsequent exposure rate so th a t within a period no t exceeding 5 yr, the accumulated dose will conform with the limit set by the formula. Women of reproductive age shall not be subjected to such emergency exposure.

4.1.1.3. A c c i d e n t a l e x p o s u r e

The dose from all accidental exposure shall be added to the individual accumulated dose. I f the sum then exceeds the maximum value perm itted by the basic formula, any excess up to 25 rem to the whole body shall be compensated for by lowering the subsequent exposure rate so th a t, within a period not exceeding 10 yr, the accumulated dose will conform w ith the limit set by the formula. Any worker receiving an accidental dose to the whole body greater th an 25 rem shall be referred to competent medical authorities for special medical surveillance.

4.1.2. Exposure to internal radiation only4.1.2.1. N o r m a l w o r k i n g c o n d i t i o n s

4.1.2.1.1. The quarterly intake of radionuclides by inhalation or ingestion shall be limited to th a t obtained by multiplying the concentrations for workers directly engaged in radiation

2* 1 9


work by the quarterly intake of air and water for the standard man given in Table IB of Annex I.

(i) I f only one radionuclide is present in air or water, then the intake of this radionuclide over a period of a quarter of a year shall not exceed the to ta l intake over the same period a t the maximum permissible concentration for workers directly engaged in radiation work listed in Table I I of Annex I.

(ii) In the case of a mixture of known composition of radionuclides the combined action of the resulting exposures shall be taken into account as indicated in Annex III .

(iii) I f a mixture- of radionuclides of unknown or partly known composition is present in air or water, then the intake of this mixture over a period of a quarter of a year shall not exceed the to ta l intake over the same period a t the maximum permissible concentrations listed in Table I I I of Annex I.

4.1.2.2. E m e r g e n c y e x p o s u r eEmergency work involving intakes of radioactive material in excess of those specified in 4.1.2.1 shall be planned on the basis th a t the to ta l emergency intake of radioactive m aterial in 1 yr shall not exceed th a t which would result from exposure for 1 yr a t the maximum permissible concentra tion for workers directly engaged in radiation work listed in Table I I of Annex I. The occurrence of such planned emergency exposure and where practicable an estimate of the intake or resulting body burden shall be entered on the worker’s record. I f the estim ated to ta l intake exceeds th a t permissible in 1 yr the worker shall be referred to appropriate medical authorities and measures shall be taken to prevent further exposure during the period of tim e which would be required for the accumulation of this excess intake a t the constant maximum permissible concentrations for workers directly engaged in radiation work listed in Table I I of Annex I.Women of reproductive age shall not be subjected to such emergency exposures.

4.1.2.3. A c c i d e n t a l e x p o s u r eWhere practicable in cases of accidental exposure, an estimate of the intake or resulting body burden shall be

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entered on the worker’s record. I f the estim ated to ta l intake exceeds th a t permissible in 1 yr, the worker shall be referred to appropriate medical authorities and measures shall be taken to prevent further exposure during the period of time which would be required for the accumulation of this excess intake a t the constant maximum permissible concentrations for workers directly engaged in radiation work listed in Table I I of Annex I.

4.2. W ORKERS NOT DIRECTLY ENGAGED IN RADIATION W ORK AND INDIVIDUAL MEMBERS OF TH E PUBLIC

4.2.1. Exposure to external radiation only4.2.1.1, W o r k e r s n o t d i r e c t l y e n g a g e d i n r a d i a t i o n w o r k

The exposure to external radiation of workers who are no t directly engaged in radiation work, bu t who rem ain or pass where they m ay be exposed to ionizing radiation or radioactive substances, shall be limited so as to ensure th a t the doses received shall not exceed the maximum permissible doses listed in 3.2.

4.2.1.2. I n d i v i d u a l m e m b e r s o e t h e p u b l i cThe exposure to external radiation of an individual member of the public shall be limited to ensure th a t the doses received do no t exceed the maximum permissible doses listed in 3.3.

4.2.2. Exposure to internal radiation only4.2.2.1. W o r k e r s n o t d i r e c t l y e n g a g e d i n r a d i a t i o n w o r k

The exposure to internal radiation of workers who are no t directly engaged in radiation work, bu t who remain or pass where they may be exposed to ionizing radiation or radioactive substances, shall be limited to ensure th a t the annual intake of radionuclides which affect the whole body or the gonads shall not exceed 3/10, and the annual intake of radionuclides which do not affect the whole body or the gonads shall not exceed 1/10, of the annual intake by workers directly engaged in radiation work, exposed constantly a t the maximum permissible concentrations as for single radionuclides or for unidentified radionuclides listed in Table I I and Table I I I of Annex I respectively.

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The annual intake of radionuclides by inhalation or ingestion shall be calculated by applying the limits specified in this sub-paragraph to the concentrations listed in Table I I or Table I I I of Annex I as appropriate for workers directly engaged in radiation work, and multiplying by the yearly intake of air and water for the standard man given in Table I B of Annex I.

4.2.2.2. I n d i v i d u a l m e m b e k s o f t h e p u b l i c

(i) The exposure of an individual member of the public shall be limited so as to ensure th a t the intake of a known radionuclide in 1 yr shall not exceed the intake resulting from continuous exposure a t the maximum permissible concentrations for individual members of the public as listed in Table I I of Annex I.

(ii) The exposure of an individual member of the public shall be limited so as to ensure th a t the intake of an unidentified radionuclide in 1 yr shall not exceed the intake resulting from continuous exposure a t the m aximum permissible concentration for individual members of the public listed in Table I I I of Annex I.

5. FUNDAMENTAL OPERATIONAL PRINCIPLES5.1. GENERAL REQUIREMENTS

5.1.1. Notification, registration, licensingExcept as provided in 5.1.1.4, operations referred to in 2.1 shall be notified or registered as required by the competen t authority and, if necessary, licensed by th a t authority in the light of the health hazard involved.

5.1.1.1. In making such notification or in applying for such registration or licensing of the operation all information which the competent authority m ay deem necessary for evaluating the health hazard involved shall be provided.

5.1.1.2. Insofar as the operation is no t subject to specialized regulations enforced by the competent authority, th a t authority shall, using the services of qualified experts, evaluate the health hazards involved, taking into account the necessary elements such as siting of installation, demographic, geological, hydrological, agricultural and

2 2


meteorological factors and shall prescribe any necessary measures to be taken in respect of the operation.

5.1.1.3. I t shall always be necessary to apply to the competent authority and to receive prior authorization for operations involving:(i) The use of radioactive nuclides for medical purposes;

(ii) The intentional addition of radioactive nuclides in the manufacture of consumer goods such as foodstuffs, pharmaceutical goods, cosmetics and toys.

The competent authority shall not grant any authorization under sub-paragraph (ii) above unless it is established that no harm will result to individuals or to the population from the operation in respect of which an application is made.

5.1.1.4. Except for those operations referred to in 5.1.1.3, the notification, registration and licensing of operations referred to in 2.1 may be waived with respect to the following:

(i) Operations which do not involve the use of radioactive substances having total activities in excess of those listed in Table I I (last column);

(ii) Operations which do not involve the use of radioactive substances at a concentration exceeding 0.002 [xc/g or solid natural radioactive substances at a concentration exceeding 0.01 jxc/g;

(iii) Use of apparatus of a type approved by the competent authority, provided that any radioactive substances present are effectively protected against any contact and leakage and that the dose-rate at any external point situated at a distance of 0.1 m from the surface of the apparatus does not exceed 0.1 mr/h or the fi or neutron flux which would result in an equivalent R B E dose at that point;

(iv) Use of equipment in which electrons are accelerated to an energy not exceeding 5 keV;

(v) Use of television sets to which members of the public are likely to be in close proximity and for which the dose-rate at any readily accessible point, 5 cm from the surface of such sets, does not exceed 0.5 mrem/h under normal working conditions.

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5.1.2. Radiation protection within establishments where radiationsources are present

5.1.2.1.5.1.2.1.1.

5.1.2.1.2.

5.1.2.1.3.

5.1.2.1.4.

5.1.2.1.5.

5.1.2.2.

Radiation protection within an establishment shall include administrative organization, physical surveillance, medical surveillance and the keeping of adequate records and shall be the responsibility of the authority in charge of the establishment. The nature of the measures employed shall be related to the magnitude of the risk of exposure involved.

A d m i n i s t r a t i v e o r g a n iz a t io n

A technically competent person shall be designated to oversee the application of appropriate radiation protection regulations. This person shall call upon the advice of qualified experts whenever necessary. The authority in charge of the establishment shall consult this person on all relevant aspects of radiation safety.Only workers medically fit for such work shall be permitted to be directly engaged in radiation work.No person employed shall be exposed to ionizing radiation unless he has received appropriate instructions (to the extent that is necessary, having regard to the circumstances of his employment) concerning the hazards involved and the precautions to be observed.Any necessary administrative, technical and medical instructions concerning the radiation risk and safe working practices relevant to the type of installation and the work involved shall be made available. In addition all necessary protective equipment shall be made available and provision made to ensure its use by all workers directly engaged in radiation work and by all other persons who may occasionally be exposed to radiation within the establishment.In the event of accidental exposure of an individual, a study shall be made of the circumstances in which that exposure occurred and it shall be reported to the authority in charge of the establishment.

P h y s ic a l s u r v e i l l a n c e

Physical surveillance shall be established in order to determine the nature of the precautions to be taken to ensure compliance with these Basic Safety Standards and to assess the effectiveness of the precautions taken.Such physical surveillance shall comprise:

24


5.1.2.2.1. Examination and control of protective measures, including:(i) The approval of new installations or modifications to

existing installations from the point of view of radiation safety;

(ii) The assessment of the adequacy of the working methods and the effectiveness of protective devices; and

(iii) The checking of the performance and correct use of all relevant instruments.

5.1.2.2.2. 'Surveying and monitoring, including:(i) The assessment of exposure levels at all appropriate

locations within the establishment, and of the nature and quality of the radiation involved; and

(ii) The adequate assessment of radioactive contamination with a view to ensuring continued compliance with these Basic Safety Standards.

5.1.2.2.3. Establishment of controlled areasControlled areas shall be established where workers directly engaged in radiation work could receive doses in excess of the values given in 3.2. Such areas shall be marked out and warning signs posted at the entrances to and, as appropriate, within them.

60 °

2 5


Such warning signs shall:(i) Include the basic symbol shown in Mg. 1 indicating

the presence of ionizing radiation;(ii) Contain, in addition to the basic symbol referred to in

paragraph (i), such additional inscriptions or symbols as may be required to indicate in a manner understandable to all concerned the magnitude or particular nature of the exposure risk.

5.1.2.2.4. Assessment of doses received in controlled areas by workers directly engaged in radiation work(i) The doses received from external radiation shall be

evaluated by the use of one or more individual radiation detectors carried continuously on the person while in the controlled area.

(ii) The doses received from internal radiation shall be evaluated where necessary by any physical or chemical methods which enable the intake or body burden of radioactive materials to be evaluated.The frequency of assessments shall be such that compliance with the Basic Safety Standards is ensured.

5.1.2.3. Medical surveillanceMedical surveillance shall be established in order to provide the necessary medical supervision of workers directly engaged in radiation work as well as a suitable medical casualty service.

5.1.2.3.1. All workers directly engaged in radiation work shall be subjected to an appropriate medical examination prior to, or shortly after, taking up such work.Such medical examinations shall include an enquiry into personal history covering family, medical and occupational background, and the usual clinical tests. In addition the worker shall be subjected to special investigations of those organs and functions which are considered particularly vulnerable to radiation hazards, according to the class of work.

5.1.2.3.2. Routine medical examinations during employment shall be carried out periodically as the competent authority may require. They may include the types of examination mentioned in 5.1.2.3.1 as well as special examinations desirable in view of the radiation hazards involved in each particular case.

2 6


5.1.2.3.3. No worker shall be employed or shall continue to be employed in work by reason of which he might be subject to exposure to ionizing radiation contrary to qualified medical advice.

5.1.2.3.4. In addition to routine medical examination, exceptional medical surveillance comprising any further. examination, decontamination procedures and urgent medical treatment deemed necessary by an appropriate medical practitioner shall be made available. Any worker receiving art accidental dose from external radiation greater than 25 rem to the whole body or an accidental intake of radioactive material exceeding that permissible in 1 yr shall be subjected to exceptional medical surveillance.

5.1.2.3.5. A medical casualty service shall be provided. The extent of this service shall depend on the radiation risks involved in the establishment.(i) First-aid facilities and advice shall be immediately

available.(ii) Arrangements for referring casualties and contaminated

personnel to medical services at an appropriate stage should be clearly defined and made known.

5 .1 .2 .4 . R e c o r d s

5.1.2.4.1. Records shall be kept of the results of the surveys and monitoring of the controlled area and shall be made available for inspection by the competent authority.

5.1.2.4.2. A personal record shall be kept, in a form and in a manner to be approved by the competent authority, for every worker directly engaged in radiation work. Such records shall contain relevant data and information on:

(i) The general nature of the work involving exposure to radiation and the type of radiation involved;

(ii) The extent to which the worker has been or is assumed to have been exposed to radiation, as indicated by individual or area monitoring methods. In particular the accumulated radiation dose received shall be regularly computed;

(iii) The results of medical examinations.5.1.2.4.3. Records of the assessment of individual doses shall be

preserved during the lifetime of the person concerned and in any case for at least 30 yr after cessation of the work involving exposure to ionizing radiation.

27


The competent authority shall ensure that adequate surveillance is undertaken outside establishments in which radiation sources are present and physical control should be established to that effect. The management of the establishment shall be responsible for compliance with any requirements of the competent authority aimed at providing radiation protection outside the establishment. Physical control shall include the surveying and monitoring of those areas outside the establishment where external radiation or radioactive contamination can occur as a result of operations within the establishment, and the control or release of radioactive waste.

5.1.3.1. Surveying and monitoring shall include measurements of the external radiation levels and of contamination of the environment, including food-stuffs, with a view to assessing, as far as practicable, the resulting doses to individual members of the public.

5.1.3.2. The control of release of radioactive waste to the environment shall be such as to conform with the basic safety standards. For the release of radioactive waste to the environment at levels above those fixed by the competent authority, prior authorization and approval of .proposed procedures shall be obtained from that authority.

5.2. IN SPEC T IO N AND IN T E R V E N T IO N

An appropriate system of inspection shall be established by the competent authority for the supervision of safety precautions both within and outside establishments in which radiation sources are present, and for the enforcement of the standards to be applied.

5.2.2. The competent authority shall assume the necessary power to intervene in the case of non-compliance with the standards to be applied.

5.2.3. Provision shall be made for action to be taken in the event of accident.

5.2.4. Any situation which has resulted or is expected to result in doses in excess of those laid down in the Basic Safety Standards shall be reported in a manner prescribed by the competent authority.

5.1.3. Radiation protection surveillance outside establishmentsin which radiation sources are present

2 8


ANNEX IT a b l e I

VALUES OF R ELA T IV E BIOLOGICAL EFFECTIV EN ESS USED

IN DEFINING MAXIMUM PER M ISSIBLE DOSES*

R adiation R B E

X-rays, y-rays, electrons and (3-rays of Emax greater than 30 keV ......................................... 1.0Fast neutrons and protons up to 10 MeV** .. 10Naturally occurring a-particles........................ 10Heavy recoil nuclei............................................. 20

*) These values o f R B E are those chosen specifically for use in defining m axim um perm issible doses. O ther values o f R B E will be m ore appropriate in the assessm ent o f any specific in ju ry caused b y radia tion .

**) W hen the neu tron energy is m ore closely defined, th e values of R B E in Table I A m ay be used.

T a b l e I A

RELATIONSHIP B E T W E E N DOSE AND NEUTRON FL U X

N eutron energy R B E F lu x equivalent to 2.5 m rem /h (n/cm 2 s)

In teg ra ted flux equivalent to 1 rem

(n/cm 2)

Therm al.................. 3.0 670 9.6 X 1085 K e V ...................... 2.5 570 8.2 X 10s

20 K e V ...................... 5.0 280 4.0 x 10s100 K e V ...................... 8.0 80 1.2 x 108500 K e V ...................... 10.0 30 4.3 x 107

1 M eV ...................... 10.5 18 2.6 x 1075 M eV ...................... 7.0 18 2.6 x 107

10 M eV ...................... 6.5 17 2.4 X 107

29


(a) W orkers during working hours

T a b l e I B

STANDARD INTAKE OF AIR AND WATER BY ADULTS:

In tak e during working hours in a q u arte r o f

a yearAnnual in take during

working hours

W ater (1)................................ 7 1 .5 27 5

Air (m 3) ................................... 6 5 0 2 5 0 0

(b) Members of the general public

In ta k e during 1 y r

W ater (1)............................................................................... 800

Air (m3) .................................................................................. 7300

30


T a b l e I I

MAXIMUM PERM ISSIBLE CONCENTRATIONS IN A IR OR W A T ER FO R SINGLE RADIONUCLIDES

applicable to workers direetly engaged in radiation work and to individual members of the public, and the m axim um permissible activity for exemption from notification, registration or licensing.

The underlined isotopes are those affecting the whole body or gonads. In com puting the permissible intake of those radionuclides for workers n ot directly engaged in radiation work, the factor of 0 .3 should be applied to the m axim um permissible concentration values as listed in this table for workers during working hours.

F o r the other radionuclides, (not underlined), a factor of 0.1 should be applied to the m axim um permissible concentration values.

Radionuclide

M ax. perm issible concentrations (nc/cm 3)

M ax.perm iss. ac tiv ity for exem ption

from notification , reg istra tion or

licensing (lie)

W orkers during w orking hours

Ind iv idu al m em bers of th e public**

W ater* Air W ater Air

XH 3 (H T O o rH 320) (sol.)

! l l 23 (submersion)

0.1 5 X 10- 6 2 x 10“3

3 x 10- 3 2 x 10-7 4 x 10-5 1000

4B e 7 (sol.)(insol.)

0.050.05

6 x 10-6 10-6

2 x 10-3 2 x 10-3

2 x 10-7 4 x 10- 8 100

6C14 (C 0 2) (sol.) (submersion)

0.02 4 x 10-®5 x 10~6 8 x 10-4 io-7

io-« 100

9F 18 (sol.)(insol.)

0.020.01 5 x 10- 6 3 x 10-®

8 x 10-4 5 x 10- 4 2 x 10-7

9 x 10- 8 100

n N a1! (aol.)(insol.)

10-39 x 10- 4

2 x 10- ’ 9 x 10- 9

4 x 10- 5 3 x 10~5

6 x 10~9 3 x 10- 10 10

* The concentrations listed in th is colum n are n o t given for th e purpose o f regulating d rink ing w ater supplies for workers, who shall no t norm ally consum e w ater having higher concentrations o f radionuclides th a n w ater for th e general public. T he aim o f listing these concentrations is to enable the calculation o f perm issible in takes by ingestion.

* * F o r practica l purposes these figures can be applied to th e population a t large providedth a t th e m axim um perm issible genetic dose to th e whole population is no t exceeded.

31


Table I I , Continued

R adionuclide

M ax. perm issible concentrations ( |ic/cm 3)

Max. permiss. ac tiv ity for exem ption from notifi. cation , registra tion or

licensing (M

W orkers during working hours

Ind iv idu al m em bers . o f th e public * *

W ater* | Air W ater Air

n W (sol.)(insol.)

6 x 10-3 8 x 10-4 io -»10-7 2 x 10-43 x 10~5 4 x 10- 8

5 x 10-» 10

14Si31 (sol.)(insol.)

0.03 6 x lO - 3 6 x 10-6io -»

9 X 10- 4 2 x 10-4 2 x 10-73 x 10“8 100

15P 3* (sol.)(insol.)

5 x 10- 4 7 x 10- 4 7 x 10- 88 x 10-8 2 X 10-52 x 10~5 2 x lO"9

3 x 10- 9 10

i.S*» (sol.)(insol.)

2 x 10~3 3 x 10- 7 6 x 10-6 9 X 10- 9 108 X 10-3 3 x 10- 7 3 x lO - 4 9 x 10- 917C138 (sol.)

(insol.)2 x 10-3 2 x 10-3

4 x 10- 7 2 x 10-8

8 x 10-6 6 x 10“6

i o - 88 x 10-10 10

17C138 (sol.)(insol.)

0.010.01 3 X 10-o 2 x 10- '4 x 10- 4 4 x 10- 4 9 x 10- 8

7 x 10“8 100

JSA r37(submersion) 6 x 10-3 io - 4 100

i8A r«(submersion) 2 x 10-" 4 x 10- 8 10

„ K « (sol.)(insol.)

9 x 10- 3 6 x 10-4 2 x 10~6i o - 7

3 x lO - 4 2 x 10-5 7 x 10- 8 4 x 10-» 10

20Ca45 (sol.)(insol.)

3 x 10- 4 5 x 10- 3 3 x 10- 8

i o - 79 x 10-« 2 x 10-4 i o - 9

4 x 10- 9 10

20Ca47 (sol.)(insol.)

io - 3i o - 3

2 x 10-7 2 x 10-7 5 x 10- 6 3 x 10- 6 6 x 10-9 6 x 10-9 10

21Se48 (sol.)(insol.)

i o - 3i o - 3

2 x 10-7 2 x 10-8 4 x 10- 5 4 x 10~5 8 x 10-9 8 x 10-10 10

21Sc47 (sol.)(insol.)

3 x 10- 3 3 x 10- 3 6 x 10-7

5 x lO - 7 9 x 10 - 5 9 x 10- 6 2 x 10-8 2 x 10-8 10

* ** See notes p. 313 2


Table I I , ContinuedMax. perm issible concentrations

( uo/cms)M ax. perm iss. ac tiv ity for exem ption

from notification , reg istra tio n or

R adionuclide W orkers during w orking hours

Ind iv idu al m em bers o f th e public * *

W ater* Air W ater Air licensing(t«>)

21Sc48 (sol.)(insol.)

8 x 10-" 8 x 10"4 2 x 10~7io -7

3 x 1 0 -s 3 x 10- 5 6 x 10-°

5 XlO - 9 10

23v 48 (sol.) 9 x 10~4 2 x lO - 7 3 x 10~5 6 x 10-9 10(insol.) 8 x 10~4 6 x 10-« 3 x 10- 5 2 x 10-924Cr“ (sol.)

(insol.)0 .050 .05

io-62 x lO - 6

2 x 10-3 2 x 10-3

4 x 10- 7 8 x 10-8 100

26Mn52 (so l.)( in so l .)

10-39 x 10~4 2 X 10- 7

io-73 x 10- 5 3 x lO - 5 7 x 10' 9

5 x 10- 9 10

„M n “ (so l.)(insol.)

4 x 10- 3 3 x 10- 3 4 x 1 0 - ’

4 x 10~8 io - 1io-4

io-8io-9 10

jjM n6' (so l.)(insol.)

4 x 10 - 3 3 x 10~3 8 X 10"7

5 X 10- 7 io-4io-4

3 x lO' 8 2 x 10'8 10

2«Fe65 (sol.) (insol.)

0.020.07

9 x 10- 7io-»

8 x lO"4 2 x lO"3 3 x 10- 8 3 x 10- 8 100

2«Fe6» (so l.)(insol.)

2 x lO"3 2 x 10-3 io-75 x 10*0

6 x 10-6 5 x 1 0r6 5 x 10- 9 2 x 10-9 10

2?Co67 (so l.)(insol.)

0.020.01 3 XlO-« 2 X 10-7 5 x 10- 4 4 x 10"4 io-7 6 x 10 '9 10

„ C o 68“ (so l.)(insol.)

0.080 .06

2 X 1 0 -‘ 9 X 1 0 - ‘

3 x 10- 3 2 x 10-3 6 x 1 0 '7 3 X lO"7 10

. i C o « (so l.)(insol.)

4 x 10- 3 3 x lO"3

8 XlO - 7 5 X 10-®

io-49 x 10- 5

3 x 10- 8 2 x 10- '

10

27Co»» (so l.)( in s o l .)

io-3io-3

3 x lO"7 9 x 10-»

5 x 10- 6 3 x 10- 5

io-«3 x 10 ' 10 10

28Ni«» (sol.) (insol.)

6 x 10-3 0.06

5 x 10- 7 8 x 10-7 2 x 10-4 2 X 10- 3 2 x 10-*

3 x 10 '» 10

* ** See notes p. 313 3 3


Table. I I , Continued

M ax. perm issible concentrations ( nc/cm 3)

M ax. perm iss. a c tiv ity for exem ption

from no tification , reg istra tio n or

Radionuclide W orkers during w orking hours

Ind iv idual m em bers o f th e public**

W ater* Air W ater Air licensing(uc)

28N i«3 (sol.)(insol.)

8 x 10~4 0.02 6 x 10-s 3 x 10- 7 3 x 10- 5

7 x 10- 4 2 x 10-®io-8 10

28Ni°5 (sol.)(insol.)

4 x 10- 3 3 x 10- 3 9 x 10- 7

5 x 10- 7 io-4io-4

3 x 10- 8 2 x 10-8 10

29Cu84 (sol.)(insol.)

0.01 6 x 10-3 2 x 10-8io-8

3 x 10- 4 2 x 10-4 7 x 10- 8 4 x 10- 8 100

3oZn«6 (sol.)(insol.)

3 x 10- 3 5 x 10- 3

io-7 6 x ro-8

io-42 x 10-4

4 x 10- 9 2 x 10-»

10

30Zn6“m (sol.)(insol.)

2 x 10-3 2 x 10-3

4 x 10- 7 3 x 10- 7

7 x 10- 5 6 x 10-6

10“8io-8

10

30Zn89 (sol.) (insol.)

0.050.05

7 x 10- 8 9 x 10- 8

2 x 10-3 2 x 10-3

2 x 10~73 x 10- 7 100

, iG a « (sol.)(insol.)

io-3io-3

2 x 10-7 2 x 10-7 4 x 10- 5 4 x 10~5 8 x 10-» 6 x 10-» 10

. .G e « (sol.)(insol.)

0 .050.05

io-56 x 10-8 2 x 10-3 2 x 10-3 4 x 10- 7 2 x 10-7 100

33As73 (sol.)(insol.)

0.010.01

2 x 10-8 4 x 10- 7

5 x 10- 4 5 x 10- 4

7 x 10- 8 10“8 10

3 3 As71 (sol.)(insol.)

2 x 10-3 2 x 10-3 3 x 10- 7io-7

5 x 10- 6 5 x 10- 5 10-8

4 x 10- 9 10

ssA s78 (sol.)(insol.)

6 x 10-4 6 x 10-4 io-7io-7

2 x 10-5 2 x 10~5 4 x 1 0 - ’ 3 x 10-» 10

33A s77 (sol.)(insol.)

2 x 10-3 2 x lO"3 5 x 10- 7 4 x 10- 7 8 x 10-6 8 x 10-5 2 x 10-»

io-8 10

31S e 75 (sol.)(insol.)

9 x lO- 3 8 x 10-3

io-8io-7

3 X 1 0 - 4 3 x 10- 4

4 x 10- 8 4 x 10- 9 10

* ** See notes p. 3134



Radionuclide

Max. perm issible concentrations ( |ic/cm 3)

M ax. perm iss. a c tiv ity for exem ption


licensing (nc)


Ind iv idual m em bers of th e public**


asBr82 (sol.)(insol.)

8 x 10-3 io-3

10-6 2 x 10- ’

3 x 10- 44 x 10- 5

4 X 10- 8 6 x lO - 9 10

36K r85m(submersion) 6 x 10-6 10-7 100

36K r86(submersion) 10~5 3 x 10- 7 100

36K r8’(submersion) io-« 2 x 10-8 100

37R b 86 (sol.)(insol.)

2 x 10-3 7 x 10- 1

3 x 10~7 7 x 10- 8

7 x 10- 5 2 x 10-6

io-82 x 10-9 10

37R b 87 (sol.)(insol.)

3 x 10~3 5 x 10- 3

5 x 10- 7 7 x 10- 8

io-42 x 10-4

2 X 10- 8 2 x 10-9 10

38Sr85m (sol.)(insol.)

0.20.2 4 x 10~6 3 x 10~5 7 x 10- 3

7 x lO"3 io-«1 0 - o 100

38Sr85 (sol.)(insol.)

3 x 10- 3 5 x lO - 3

2 x 10-7io-7

io-42 x 10-4

8 x 10-9 4 x lO - 9 10


3 x 1 0 -‘ 8 x 10-4

OO 00

1 1 O

©X

X CO io-6

3 x 10- 5 io-9io-9 10


4 x 10- 6io-3

3 x 10- 10 5 x 10- 9 io-7

4 x 10- 6 io-u 2 x 10-10 1

38S r91 (sol.)(insol.)

2 x 10~3io-3

4 x lO - 7 3 x lO - 7 7 x 10- 6

5 x 10- 6 2 x 10-8 9 XlO - 9 10


2 x 10-3 2 x 10-3 4 x lO - 7 3 x 10- 7 7 x 10- 6 6 x 10-5 2 X 10- 8

io-8 10

39 Y 90 (sol.)(insol.)

1 i

O O

X X

: co

CD

io-7io -7

2 x 10-6 2 x 10-6 4 x 10- 9 3 x lO - 9 10

* ** See notes p. 313 5


Table 11, Continued

M ax. perm issible concentrations ( no/cm3)

M a x . p e r m i t s .activ ity for exem ption from notification , registra tion or


Ind iv idual m em bers of th e public**

W ater* Air W ater Air licensing(no)

a, Y “ "> (sol.)(insol.)

0.10.1 2 XlO - 6 2 X 10- 5 3 x 10-3

3 x 10-3 8 XlO - 7 6 XlO - 7 100

39 (sol.)(insol.)

8 x 10-4 8 x 10-4 4 x l 0 - 8 3 X 10- 8 3 x 10- 6

3 x 10- 6 io-9io-9 10

V92 39 -1 (sol.)

(insol.)2 x 10-3 2 x 10~3 4 x 10- 7

3 x 10- 7 6 x 10-5 6 x 10-5 lO- 810-8 10V 9 3

39 x (sol.)(insol.)

8 x 10-4 8 x 10-4 2 x 10-7 io-7

3 x 10- 6 3 x lO- 5 6 x 10-9

5 x 10- 9 10

4oZr93 (sol.)(insol.)

0.020.02 io-73 x 10- 7 8 X 10-4 8 X 10~4 4 x 10- 9

10-3 10


2 x 10-32 x lO- 3

io-73 x l 0 - 8

6 x 10-6 6 x 10*3

4 x 10~9io-9

10


5 x 10- 4 5 x 10- 4 io-7

9 X lO- 8 2 x 10-6 2 x 10-6 4 x 10- 9 3 x 10- 9 10

4 iN b » 3m (sol.)(insol.)

0.010.01 io-72 x lO - 7 4 x 10- 4

4 x 10- 4 4 x 10- 95 x 10-» 10

41N b 96 (sol.) 3 x lo - 3 5 x 10- 7 io - 4 2 x 10-3 10(insol.) 3 x lO- 3 10-7 io - 4 3 x 10~»

41N b 97 (sol.)(insol.)

0.030.03

6 x 10- ' 5 x 10-*

9 x 10- 4 9 X 10- 4 2 x 10-7

2 x lO - 7 100

4„M o " . (sol.) (insol.)

5 x 10-3 lO- 3 7 x 10- 7 2 x 10-7 2 XlO - 4

4 x 10- 6 3 x lO- 8 7 x 10- 9 10

43To96m (sol.)(insol.)

0.40.3

8 x 10~6 3 x 10- 6 0.010.01 3 x 10- 6 10- “ 100

43TC96 (sol.)(insol.)

3 x lo - 3 IQ-3

6 x 10-7 2 x 10-7 io-45 x lO- 6 2 x 10- s 8 x lO - 9 10




Max. perm issible concentrations ( M-c/cm3)


from notification , registra tion or

Radionuclide W orkers during working hours

Ind iv idu al m em bers of the public * *

W ater* Air W ater Air licensing .(M-C)

43T c 97m (sol.)(insol.)

0.01 5 X 10- 3 2 x 10-o 2 x 10-7 4 x 10- 4

2 XlO - 4 8 x 10-8 5 X 10- 9 10

43T c 87 (sol.)(insol.)

0.050.02 10-63 x 10- 7 2 x 10-3 8 x 10-4 4 x 10- 710-8 10

43T e 99m (sol.)(insol.)

0.20.08

4 X 10- 510-6 6 x 10-3 3 x 10- 3 10-6

5 x 10- 7 100

43T c" (sol.)(insol.)

0.01 5 X 10- 3 2 X 10-o 6 X 10- 8 3 x IO- 4 2 x l 6 -4 7 X 10- 8 2 x 10-9 10

14R u 97 (sol.)(insol.)

0.010.01 2 x 10-6 2 X 10- 6 4 x lO"4

3 x 10- 4 8 x 10-8 6 XlO - 8 10


2 x lO - 3 2 x lO "3 5 x 10- 7 8 X 10- 8 8 x 10-5 8 x 10-5 2 x lO - 8

3 X 10- 9 10

44R u 1»6 (sol.)(insol.)

' 3 x 10- 3 3 x 10- 8 7 x 10- 7

5 X 10- 7 10-410-4 2 x 10-8 2 x 10-8 10


4 x 10-* 3 X 10~4 8 X 10-8 6 X 10-9 io~610-6 3 x 10- 9 2 x lO"10 1

46R h 103m (sol.)(insol.)

0.40.3 -

8 x 10- ' 6 x lO - 6 0.010.01 3 x 10- 6 2 x 10-6 106

)tR h 105 (sol.)(insol.)

4 x 10- 3 3 X lO"3 8 X lO - 7

5 XlO - 7 10-410-4 3 x 10- 8 2 x 10-8 10

4«Pd103 (sol.) (insol.)

0.01 8 X 10- 3 10-87 x lO - 7 3 x 10- 4

3 x 10- 4 5 x lO - 8 3 x lO - 8 10

46P d 109 (sol.)(insol.)

3 X 10- 3 2 x lO - 3 6 XlO - 7

4 x lO - 7 9 x 10- 5 7 x lO - 6 2 x 10-810-8 10

47A g106 (sol.)(insol.)

3 x 10- 3 3 x 10- 3 6 x lO - 7 8 x lO - 8 10-410-4 2 x 10-8

3 x 10- 9 10




Max. perm issible concentrations ( nc/cm 3)

M ax.perm iss. a c tiv ity for exem ption

form notification, registra tion or

R adionuclide W orkers during working hours

Ind iv idu al m embers o f the public**


47Ag110m (sol.)(insol.)

9 x 10~4 9 x 1 0 -4

2 X lO -7 1 0 -8

3 x 1 0 -6 3 x 1 0 -5

7 x 1 0 -9 3 x 1 0 -10 10

(sol.)(insol.)

10-3io-3

3 x 1 0 -7 2 x lO -7

4 x 1 0 -6 4 x 1 0 -5

10"8 8 x 1 0 -9 10

48Cd1°9 (sol.)(insol.)

5 x lO -3 5 x 1 0 -3

5 X l o - 8 7 x 1 0 '8

2 x 1 0 -4 2 x 1 0 -4

2 x 1 0 -93 x 10-o 10

48Cd115m (sol.)(insol.)

7 x 1 0 -4 7 x 1 0 -4

4 X 1 0 -8 4 X 1 0 -8

3 x 1 0 -6 3 x 1 0 -5

io-9io-° 10

48Cd115 (sol.)(insol.)

io-3io-3

2 x 1 0 -7 2 x 1 0 '7

3 x 1 0 -64 x 1 0 -6

8 x 1 0 -9 6 x lO -9 10

49In 113m (sol.)(insol.)

0.040.04

8 x 1 0 -6 7 x 1 0 -6

1 x 1 0 -3 1 x 1 0 -3

3 x 1 0 -7 2 x lO -7 100

48I n l l lm (sol.)(insol.)

! *3

T*I

1 O

OX

X !

io m io-7

2 x lO '82 x 1 0 -6- 2 x 1 0 -6

4 x 1 0 -9 7 x 1 0 -10 10

48In 116m (sol.)(insol.)

0.010.01

2 x lO -6 2 x 1 0 -6

4 x 1 0 -4 4 x lO -4

8 x 1 0 -8 6 x 1 0 -8 100

4 9l n » 6 (sol.)(insol.)

3 x 1 0 -3 3 x 1 0 -3

2 x lO -73 x lO-8

9 x lO"6 9 x 1 0 -5

9 x 1 0 -9io-9 uiilim.

5»Sn113 (sol.)(insol.)

2 x 1 0 -3 2 x 1 0 -3

4 x lO '75 x lO -8

9 x 1 0 -5 8 x 1 0 -5

lO -8 2 x 1 0 -9 10

. oS hl1" (sol.)(insol.)

5 x 1 0 -4 5 x 1 0 -4

i o - 78 x lO '8

2 x 1 0 -5 2 x 1 0 -5

4 x 1 0 -9 3 x 1 0 -9 10

51Sb122 (sol.) (insol.)

8 X lO"48 x 10~4

2 x lO -7i o - 7

3 x 1 0 -5 3 x 1 0 -5

6 x 1 0 -9 5 x 1 0 -9 10

51Sb124 (sol.)(insol.)

7 x lO -4 7 x 1 0 -4

2 x 1 0 -7 2 x lO -8

2 x 10~5 2 x lO"5

5 x 1 0 -9 7 x 1 0 -10

1



Table I I , ContinuedM ax. perm issible concentrations

( tic/cm3)Max. perm iss. ac tiv ity for exem ption



Ind iv idu al m em bers of th e public**


. i S b « (sol.)(insol.)

3 x 1 0 -3 3 x 1 0 -3

5 x 1 0 -7 3 x lO -8

1 0 -41 0 -4

2 x 1 0 -8 9 x l O - 10

10

52Te125m (sol.)(insol.)

5 x 1 0 -3 3 x 1 0 -3

4 X lO -710-7

2 x lO -4 1 0 -4

10-84 x lO"9

10

62T e127m (sol.)(insol.)

2 x lO -3 2 x 1 0 -3

10-74 X lO -8

6 x 1 0 -5 5 x lO -6

5 x 1 0 -9 10-»

10

T«127 5 2 ® (sol.)(insol.)

8 x lO -3 5 x 10~3

2 x 10-" 9 X 1 0 -7

3 x 1 0 -4 2 x 1 0 -4

6 x 1 0 -8 3 x 1 0 -8 10

62T e129m (sol.)(insol.)

1 0 -3.6 x 1 0 -4

8 x 1 0 -8 3 x 1 0 -8

3 x 1 0 -5 2 x 1 0 -5

3 x lO -9 1 0 -9

10

62T e129 (sol.)(insol.)

0.020.02

5 x 1 0 -‘ 4 x 10-«

8 x 1 0 -4 8 x lO -4

2 x lO -7 1 0 -7 100

62T e131m (sol.) 2 x 1 0 -3 4 x 1 0 -7 6 x 10~5 10-8 10(insol.) 1 0 -3 2 x 1 0 -7 4 x 10-6 6 x lO -9

52T e132 (sol.)(insol.)

9 x 1 0 -4 6 x 1 0 -4

2 x 1 0 -7 1 0 -7

3 x 1 0 -5 2 x 1 0 -5

7 x 1 0 -9 4 x l 0 “9 10

S3I 126 (?ol.) (insol.)

5 x 10~5 3 x 1 0 -3

8 x 1 0 -9 3 x lO -7

2 ^ io-«9 x lO -6

3 x 1 0 -1010-8 1

53I 129 (sol.)(insol.)

1 0 -5 6 x 10~3

2 x lO -9 7 x 1 0 -8

4 x 1 0 -7 2 x 1 0 -4

6 x l O - 11 2 x 1 0 -9 1

53I 131 (sol.)(insol.)

6 x lO -5 2 x 1 0 -3

9 x 1 0 - ‘ 3 x 1 0 -7

2 x lO -6 6 x 10~5

3 x 1 0 -1010-8 1

53l132 (sol.)(insol.)

2 x 1 0 -3 5 x 1 0 -3

2 x lO -7 9 x lO -7

6 x 1 0 -6 2 x 10-"

8 x 1 0 -9 3 X 1 0 -8 10

63I 133 (sol.) (insol.)

2 x 1 0 -4 1 0 -3

3 x 1 0 -8 2 x 1 0 -7

7 x 1 0 -6 4 x lO"5

1 0 -9 7 x 10-» 10

* * * §ee no tes p. 3139



Radionuclide

Max. permissible concentrations ( [j:c/cm3)Max. permiss. a c tiv ity for exem ption


licensing ( txc)


Ind iv idual m em bers of the public**


63I m , (sol.)(insol.)

4 X 1 0 - 3

0.025 X 1 0 - ’ 3 x 1 0 -6

lO '4 6 x 1 0 -4

2 x 1 0 '8 10- ’ 10

63I 136 («ol.)(insol.)

7 X 1 0 -4 2 X IO- 3 10- ’

4 x 1 0 -’2 x 1 0 -6 7 X l o - 6

4 x lO -910-8 10

MX e m m(submersion) 2 x 1 0 -5 4 x 1 0 -’ 10

(subtnersion) 10-6 3 x lO - ’ 10

64X e 136(submersion) 4 x 1 0 -“

• 10- ’ 10

jjC s131 (sol.)(insol.)

0.070.03

10-63 x 10-«

2 X 10-3 9 X 1 0 -4

4 X 1 0 - ’10- ’

100

66Cs134m (sol.)(insol.)

0 .020.03

4 x 10~66 X 1 0 -8

6 X 10-3 1 X 10-3

10-62 x 1 0 - ’ 100

65Cs^4 (sol.)(insol.)

3 x 10-4 IO- 3

4 X 10-®10-8

9 X 10-« 4 X 1 0 -6

io -»4 x 1 0 -10

10

56Cs136 (sol.)(insol.)

3 X 10-3 7 x 10-3

5 x 1 0 - ’ 9 x 10-»

1 0 -4 2 X 1 0 - 4

2 x 1 0 -83 x 1 0 -9

10

65Cs138 (sol.)(insol.)

2 x IO- 3 2 x l o - 3

4 x 1 0 -’ 2 x 1 0 - ’

9 X 1 0 -5 6 X 1 0 -5

10-86 x 1 0 -9

100

56Csi3’ (sol.)(insol.)

4 x 1 0 -4 6 x 1 0 -8 2 X 10~5 2 x 1 0 -9 1010-3 10-8 4 X 10~5 5 x 1 0 -10

56B a m (sol.)(insol.) Cn

SJl

X X

1—< I—*

0 0 1

1 <•>

w 1 0 -o4 x 1 0 - ’

2 x 1 0 -4 2 X 1 0 -4

4 x 1 0 -810-8 10

56B a U0 (sol.)(insol.)

8 x 1 0 -4 7 x 1 0 -4

10- ’4 x 1 0 -8

3 X 1 0 -5 2 X 1 0 -6

4 x 1 0 -9 1 0 -9 10

• ** See notes p. 3140


Table I I , ContinuedMax. perm issible concentrations

(nc/cms)M ax. periniss. a c tiv ity for exem ption

from no tification , reg istra tion or

R adionuclide W orkers during working hours

Ind iv idual m em bers o f th e public * *


5, L a 140 (sol.)(insol.)

7 x 10- 4 7 x 10~4 2 x 10- ’

io-72 X lO- 5 2 x 10-6 5 x 1 0 ' "

4 x 10"9 10

saCe141 (sol.)(insol.)

3 x 10- 3 3 x 10- 3 4 XlO - 7

2 X 10- 7 9 X 10- 6 9 X 10- 5 2 x lO ' 8

5 x 10 ' 9 10

58Ce“ 3 (sol.)(insol.)

io-310-3 3 x lO"7 2 X 10-7 ■i x 10-5 4 x 10-6 9 X lO ' 9

7 X 10' 9 10

68Ce144 (sol.)(insol.)

3 x 10- 4 3 x 10"4 io-s

6 X 10-"10_sio-6

3 x 10' 10 2 x 10-10 1

59Pr142 (sol.)(insol.)

9 x 10- 4 9 x 10- 4 2 X lO"7 2 x 10-7 3 x 10- 6

3 x lO - 6 7 x 10' 9 5 x 10- 9 10

69P (sol.)(insol.)

io-3io-3

3 X 10- 7 2 x 10-7 5 x 10- 6 5 x 10-*

10-s6 x 10'9 10

«0N d144 (sol.)(insol.)

2 x 10-3 2 x 10-3 8 x 10- u 3 XlO - 10 7 x 10^?8 x 10-*

3 x 10- 12 10"11 unlim.

e o N d 147 (sol.)(insol.)

2 x 10-3 2 x 10-3 4 X 1 0 - 7 2 x 10-7 6 x 10-5 6 x 10-6 lO- 8 8 x 10-9 * 10

eoNd>4» (sol.)(insol.)

8 x l 0 -3 8 x lO - 3 2 x 10-«io-«

3 x 10- 4 3 x 10- 4 6 x lo - 8

5 x 10-8 100

61P m 147 (sol.)(insol.)

6 x lO- 3 6 x 10-3 6 x 10- “io-7

2 x 10-4 2 x 10"4 2 x lO - 93 x 10- 9 10

61P m 149 (sol.)(insol.)

io-»io-»

■ 3 X 1 0 - 7 2 x lO - 7 4 x 10- 6

4 x 10- 6 10-8 8 x 10-9 10

62Sm147 (sol.)(insol.)

2 x 10-*2 x 10-3 7 X 1 0 -” 3 XlO - 10 6 x 10~6

7 X 1 0 - 5 2 x 10-12 9 x 10- 12 1

e2Sm 151 (sol.)(insol.)

0.010.01 6 x 10-8io-7 X

Xo

o 1 1 #*

• 2 x 10-9 5 x 10'» 10




Max. perm issible concentrations ( (ic/cm3)

Max. permiss. ac tiv ity for exem ption



Ind iv idu al m em bers of th e public * *

W ater* Air W ater* Air licensing(nc)

62S m 163 (sol.)(insol.)

2 x 10-3 2 X 10-3

5 xlO-7 4 x 10-7

8 X 10~5 8 x 10-5

2 x 10-8i o -8 10

63®U1529.2 h

(sol.)(insol.)

2 x 10-3 2 x l0“3

4 x 10-7 3 xlO-7

6 x 10-5 6 x 10-5

i o -8i o - 8 10

e a E u 152 13 yr

(sol.)(insol.)

2 x 10-3 2 x 10-3

i o -82 xlO-8 00

00X

Xo

o1

1 e*

cn 4 x 10-10 6 xlO-10

1

(sol.)(insol.)

6 x 10-4 6 x 10-4

4 x 10-9 7 x 10-9

2 x 10-6 2 x 10-5

lO -io2 x 10-10

1

(sol.)(insol.)

6 x 10-3 6 x 10-3

9 x lO"8 7 x 10-8

2 x 10-4 2 x 10-4

3 x 10-9 3 x 10-9

10

64Gd153 (sol.)(insol.)

6 X 10-3 6 x 10-3

2 x 10-7 9 x 10-8

2 x 10-4 2 x 10-4

8 x 10-9 3 x 10-9

10

.*OdM» (sol.)(insol.)

2 x 10-3 2 x 10-3

5 x 10-7 4 x 10-7

8 x 10-5 & x 10-6

2 x 10-8io -8 10

66T b “ ° ^ (sol.)

(insol.)

io - 310-3

i o -73 x 10-8

4 x 10"5 4 x 10-5

3 xlO-9io -9 10

86D y166 (sol.)(insol.)

0.010.01

3 x 10-«2 X 10-o

■cj* *9

1 t

o ©

X X 9 x 10-8

7 X 10-810

e e D y 168 (sol.)(insol.)

10-310~3

2 X 10-7 2 X lO-7

4 x 10~5 4 x 10-5

8 X 10-9 7 X 10-9

10

67H o 168 (sol.)(insol.)

9 x 10-4 9 x 10-4

2 xlO-7' 2 xlO“7

3 x 10-5 3 x 10-5

7 x 10-9 6 xlO-9

10

..Er«“ (sol.)(insol.)

3 xlO"3 3 x 10-3

6 x 10-7 4 x 10-7

9 x 10-5 9 x 10~6

2 x 10-8io -8 10

68®rl?1 (sol.)(insol.)

3 x 10-3 3 x 10-3

7 xlO-7 6 xlO-7

io -4io -4

2 xlO-8 2 x 10-8

10




M ax. perm issible concentrations (nc/cm 3)




Ind iv idu al m em bers o f th e public**

W ater* Air W ater* Air licensing(liO)

(so l.)( in s o l .)

10-31 0 - 3

4 x 10-8 3 x 10-»

5 x 10~5 5 x 10-5

10-910-9

1

„ T m > « (so l.)( in so l .)

0.010.01

10-’2 x 10-7

1 1

o o

X X

io VO 00 X X

o o 1 1

to fO

10

7oY b176 (so l.)( in s o l .)

3 x 10-3 3 x 10-3

7 x 10-7 6 x 10~7

io -4io -*

2 x 10-8 2 x 10-8

10

71Lu”7 (so l.)( in so l .)

3 x 10-3 3 x 10-3

6 x lO"7 5 x 10-7

io - 4io - 4

2 x 10-8 2 x 10-8

10

nHf181 (so l.)( in s o l .)

2 x 10-3 2 x 10“3

4 x 10-8 7 X10-8

7 x 10-5 7 x 10-5

i o - 93 x 10-9

10

73Ta18a (so l.)( in s o l .)

i o - 3i o -3

4 x 10"8 2 x 10-8

4 x 10-5 4 x 10-5

i o -97 x 10-10

10

71W 181 (so l.)( in so l .)

0.010.01

2 x 10-6i o - 7

4 x 10-‘ 3 x 10-4

8 x 10-8 4 x 10-9

10

74W 185 (so l.)( in s o l .)

4 x 10-3 3 x 10-3

8 x 10-7io - 7

i o - 4i o - 4

3 x 10-84 x 10-9

10

71W 187 (so l.)( in so l .)

2 x 10"3 2 x 10~3

4 x 10-’ 3 x 10-7

7 x 10-5 6 x 10-5

2 x 10-8io - 8 10

75Re183 (so l.)( in so l .)

0.02

8 x 10-3

3 X10-6

2 x 10-’

6 x 10-4

3 x 10-4

9 x 10-8

5 X 10-910

7JRe188 (so l.)( in s o l .)

3 x 10-3io -3

7 7

© oX X

«0 M xlO-5 5 x 10-=

2 x 10-8 8 X 10-9

10

, 5R e 187 (so l.)( in so l .)

0.070.04

9 x 10-° 5 x 10-’

3 x 10-3 2 x 10"3

3 x 10-7 2 x 10-8

1000

75Re188 (so l.)( in so l .)

2 x 10-3 9 x 10-*

4 x 10-7 2 x 10-7

6 x 10-5 3 x 10-5

i o - 86 x 10-9

10




Max. perm issible concentrations (iic/cm3)

M ax.perm iss. a c tiv ity for exem ption

from notification , registra tio n or


Ind iv idu al m em bers o f th e public**

W ater* Air W ater* Air licensing(nc)

,60s186 (sol.)(insol.)

2 XlO-3 2 X 10-3

5 xlO-’ 5 x lO-8

7 x lO-5 7 xlO-6

2 x 10-® 2 x 10-o

10

760s191m (sol.)(insol.)

0.070.07

2 x 10-6 9 x 10-6

3 x 10-3 2 x 10-3

6 x 10-7 3 x 10-7

100

760s191 (sol.)(insol.)

5 x 10-3 5 x 10-3

io-«4 x 10-7

2 x 10-4 2 x 10-4

4 x 10-®io -8 10

760s193 (sol.)(insol.)

2 x 10-3 2 x 10-3

4 x 10-7 3 xlO-7

6 x 10-6 5 x 10-6

io-®9 x 10-9

10

77Ir 190 (sol.)(insol.)

6 x 10-3 5 x 10-3

io -64 x 10~7

2 x 10-4 2 x 10-4

4 X 10-8io -8

10

77Ir192 _ (sol-)(insol.)

io - 3io - 3

i o -7 3 xlO-8

4 x 10-6 4 X 10-6

4 x 10-9 9 x lO"10

10

,,Ir184 (sol.)(insol.)

io - 39 XlO"4

2 x 10-7 2 xlO-7

3 x 10-6 3 x 10-6

8 xlO-9 5 x 10-9

10

76Pt191 (sol.) (insol.)

4 x 10-3 3 x 10-3

8 x 10-7 - 6 XlO-7

i o - 4io -4

3 x 10-® 2 x 10"8

10

? g P ti93m (sol.)(insol.)

0.030.03

7 x 10-o 5 xlO-6

1 xlO-3 1 xlO-3

2 x 10-7 2 x 10-7

100

,8Pt193 (sol.)(insol.)

0.030.05

io-«3 x lO"7

9 x 10-4 2 x 10-3

4 xlO-8io-®

10

78p t i«7m (sol.)(insol.)

0.030.03

6 x lO"6 5 x 10-o

1 x 10-3 9 x lO"4

2 x 10-7 2 x 10-7

100

,.Pt187 (sol.)(insol.)

4 x 10"3 3 x 10-3

8 x 10-7 6 x 10-7

io-«i o - 4

3 x 10-8 2 x 10-®

100

, 8A u 19« (sol.)(insol.)

5 x 10-3 4 x 10-3

io - 66 x 10"7

2 x 10-4i o - 4

4 x 10-® 2 x 10-®

10




Max. perm issible concentrations ( |i,c/cm3)

Max. permiss. a c tiv ity for exem ption



Ind iv idual m embers of th e public**


, 9A u 198 (sol.)(insol.)

2 x 10-3 10“3

3 x 10-7 2 x 10~7

5 x 10-5 5 x 10~5

1 0 “ 8 8 x 10-9

10

!9A u 19* (sol.)(insol.)

5 x 10-3 4 x 10~3

10“6 8 x 10-7

2 x 10-4 2 x 10-4

4 x 10-8 3 x 10-8

10

80H g 197m (sol.)(insol.)

6 x 10-3 5 X 10-3

7 x 10-78 x 10-7

2 x 10-4 2 x 10-4

CC 00

1 1

o o

X X

CO CO 10

soHg107 (sol.)(insol.)

9 x 10-3 0.01

10-«3 x 10-6

3 x 10-4 5 x 10-4

4 x 10-8 9 x 10-8

100

(sol.)(insol.)

5 x 10“4 3 x 10~3

7 x 10-8i o - 7

2 xlO-5i o -4

2 x 10-9 4 x 10-9

10

8 1 T 1 2 0 0 (sol.)(insol.)

0.017 x 10-3

3 x 10-» io-6

4 x 10"4 2 x 10-4

9 x 10-8 4 x 10-8

100

81T1201 (so l.)(insol.)

9 x 10-3 5 x 10-3

2 x 10-o 9 x 10-7

3 x 10-4 2 x 10-4

7 x 10“8 3 x 10-8

100

81t i 202 (sol.)(insol.)

4 x 10“3 2 x 10“3

8 x 10-7 2 xlO-7

i o - 47 x 10~6

3 x 10-8 8 X 10-9

10

8 i T p o 4 (sol.)(insol.)

3 x 10-3 2 x 10-3

6 xlO-7 3 x 10-8

io -46 x 10-6

2 x 10-8 9 x 10-10

10

82Pb203 (so l.)(insol.)

0.010.01

3 x 10-« 2 x lO"6 X

XH-

' 1—1

o o 1 1 9 x 10-8

6 x 10-810

82Pb210 (sol.)

(insol.)

4 x 10-6

5 x 10-3

1 0 -io 2 x 10-10

io - 72 x 10-4

4 x 10-12 8 x 10-12

0.1

82Pb2*2 (sol.)(insol.)

6 x 10-4 5 x 10-4

2 x 10-8 2 x 10-8

2 x 10-6 2 x 10-5

6 x 10-107 xlO-lu

1

83Bi206 (sol.)(insol.)

i o - 310“3

2 x 10-7io - 7

4 x 10-5 4 x 10-5

6 x 10-* 5 x 10-9 10

* ** See notes p. 315 45



M ax. permissible concentrations ( |j.c/cin3)

Max. permiss. activ ity for exemption

from notification, registration or

Radionuclide Workers during working hours

Individual members of th e p u blic**

W ater* Air W ater Airlicensing

( M-c)

e3Bi207 (sol.)(insol.)

2 x 10~3 2 x 10-3

2 xlO-7 io -8

6 x 10-5 6 x 10-5

6 x 10-9 5 x 10-10

10


io - 310~3

6 x 10-9 6 x 10-"

4 x 10-5 4 x 10-6

2 x 10~10 2 x lO '10

1


0.010.01

io - 72 x 10-7

4 x 10-4 4 x 10-4

3 x 10-9 7 x 10-9 10

eiPo^» (sol.)(insol.)

2 x 10"6 8 x 10~4

5 x 10-10 2 x 10~10

7 x 10-7 3 x 10-5

2 x 10-11 7 xlO-12

0.1

85At211 (sol.)

(insol.)

5 x 10-5

2 x 10-3

7 x 10-9

3 x 10-8

2 x 10-6

7 x 10~5

2 x lO '10

io -90.1

86Rn220t 3 xlO-7 i o -8 10

86R n 222t 3 x 10-7+ 10-8+ 0.1

T ? q 223ggXYtt (sol.)(insol.)

2 x 10~51 0 - 4

2 x 10-8 2 x 10-10

7 xlO-7 4 x 10-6

6 x 10-11 8 x 10-12

1

88Ra224 (sol.) (insol.)

7 x 10-6 2 x 10“4

5 x 10-9 7 x 10-10

2 x 10-6 5 x 10-6

2 x 10-10 2 x lO '11

1

" R q 226g g r v ti (sol.)(insol.)

4 x 10~7 9 x 10~*

3 xlO-11 2 xlO-7

10“8 3 x 10-6

i o - 126 X 10'9

0.1

* * * See notes p. 31

f The daughter elements o f R n 220 and R n 222 are assumed present to the exten t th a t they occur in unfiltered air. F o r all other isotopes the daughter elements are not considered as p art o f the intake and i f present they m ust be considered on the basis o f the rules for m ixtures.

+ These figures have been provisionally adopted because in certain industrial applications it has been found im practicable to apply the figures presented in the report o f IC R P Comm ittee I I (1959).

46


Table I I , ContinuedMax . permissible concentrations

( n.c/cm3)M ax.permiss. activ ity for exemption


Individual members of the p u blic**

froui notification, registration or


(lie)

l8Ra228 (sol.)(insol.)

8 x 10-7 7 x 10-4

7 x10-u 4 x 10-11

3 x 10_® 3 x 10-6

2 x 10-12i o - 12 0.1

e 9 Ac227 (sol.)(insol.)

6 x 10-5 9 x 10"3

2 xlO-123 x 10-11

2 x 10-63 x 10-4

8 x 10-149 x 10-13

0.1

89Ac22® (sol.)(insol.)

3 x 10-3 3 x 10~3

8 x 10-® 2 x 10-®

9 x 10-5 9 xlO-5

3 x 10-9 6 xlO-10

i

90Th227 (sol.)(insol.)

5 x 10-4 5 x 10-4

3 x lO"10 2 x 10-10

2 x 10“5 2 x 10-5

io -116 x 10-12

i


2 x 10-4 4 x 10~4

9 x 10-12 6 x 10-12

7 x 10-6io -5

3 x 10-13 2 x 10-13

0.1

9„Th28» (sol.)(insol.)

5 x 10-6 9 x 10~4

2 xlO-12i o - u

2 x 10-«3 x 10"5

8 xlO-14 3 x 10-13

0.1


7 x 10-3 7 x 10-3

io - 610-6

2 x 10-4 2 x 10-4

5 x 10-® 4 x 10-®

10

90T h 232* + (sol.)(insol.)

5 x 10~5i o - 3

2 x lO*"12io-11

2 x 10-« 4 x 10-5

*+7 xlO-14 4 xlO-13

0.1


5 x 10~4 5 xlO-4

6 x 10-8 3 x 10-8

2 x 10"5 2 x 10-5

2 xlO-9 10~8

1

* * * See notes p. 31*+ Provisional values for T h m and T h-nat. Although calculations and anim al experi

ments suggest th a t T h-nat, i f injected intravenously, is perhaps as hazardous as P u and indicate the values listed above, experience to date has suggested th a t in industrial cir* cum stances the hazard o f Th-nat is not much greater than th a t o f U -nat. Therefore, pend- ing further investigation the values (MPC) a = 3 x 10-11 [xc/cm3 for workers directly engaged in radiation work during working hours, and (MPC) a = 10-12 {xc/cm3 for individual members o f the public (168 h/week) are recommended as provisional levels, permissible for exposure to inhaled T h-nat or T h 232. However, the values given in Table I I are listed to indicate the possibility th a t further evidence m ay require lower values and to urge especially th a t exposure levels for these radionuclides be kept as low as is operationally possible. I t m ay be possible to show th a t similar considerations apply to other inhaled long-lived thorium isotopes under conditions in which the physical characteristics o f the airborna particles are much the same as in the case o f T h-nat, and where there is a large am ount o f airborne m aterial serving as an effective carrier for the thorium.

5 47



M ax. permissible concentrations ( fic/cm3)

M ax.perm iss. activ ity for exemption


Individual members o f the p u blic**

from notification, registration or


(no)

eoTh-nat+ (sol.)(insol.)

3 x 10“6 3 x 10-"

2 x 10-+12 4 x 10-12

10-910-5

6 X 10“+14i o - 13

llcg++

9lPa230 (sol.)(insol.)

7 x 10-3 7 x 10-3

2 x 10-9 8 x 10-10

2 xlO-4 2 x 10-4

6 x 10-11 3 x 10-11

1

91Pa231 (sol.)(insol.)

3 x 10-6 8 x 10~4

io - 12lO-io

9 x 10-7 3 xlO-5

4 x 10-14 4 x 10“12

0.1

91Pa233 (sol.)(insol.)

4 x 10-3 3 x 10-3

6 xlO-7 2 x 10“7

10"4io -4

2 x 10-8 6 x 10-9

10

02U 23» (sol.)(insol.)

1 0 - 4io -4

3 x 10-10lO-io

5 x 10-6 5 x 10-6

io - n4 x 10-12

1

92U 232 (sol.)(insol.)

8 x 10“4 8 x 10-4

10-io

3 x 10-113 x 10-6 3 x 10-5

3 x 10-12 9 x 10-13

0.1


9 x 10~4 9 x 10-4

5 x 10-10 10-io

3 x 10-6 3 x 10-6

2 x 10-11 4 x 10-12

1


9 x 10-4 9 x 10-4

6 x 10-10 10-io

3 x 10-5 3 x 10-s

2 xlO-11 4 x 10-12

1


8 x 10-4 8 x 10-4

5 x 10-10 10 - io

3 x 10-5 3 x 10-5

2 x 10-11 4 x 10-12

1

92u m (sol.)(insol.)

io - 3io - 3

6 x 10-10io - 10

3 x 10-5 3 x 10-5

2 x 10-11 4 x 10“12

1


io - 31 0 - 3

7 x 10-11lO-io

4 xlO~5 4 x 10~6

3 x 10“12 5 x 10-12

1

* * * See notes p. 31 + See note p. 46 * + See note p. 47++ The exem pt quantity is expressed in kg in view o f the special meaning o f the

curie in the case o f natural thorium. 1 c natural thorium corresponds t o :3.7 x 1010 disintegrations/s o f T h 838 + 3 .7 x 1010 disintegrations/s o f T h 228.

48


Table I I , ContinuedM ax. permissible concentrations

(nc/)msc)Max. permiss. activ ity for exemption from notification, registration or


Individual members o f the p u blic**

W ater* Air W ater Airlincensing

(lie)

g jXJ'ii&t (so l.) ( in s o l .)

5 x 10"4 5 x 10-4

7 x 10-11 6 x10-u

2 x 10-5 2 x 10-6

3 x 10-12 2 x 10-12

1 kg++

MNp*«- (s o l .)(in s o l.)

9 x 10-5 9 x 10-“

4 x 10"12lO-io

3 x 10-« 3 x 10-6

io - 134 x 10-12

0.1

9,Np239 (so l.)( in s o l.)

4 x 10-3 4 x 10-3

8 x 10-7 7 x 10-7

i o -4i o -4

3 xlO-8 2 xlO-8

10

94Pu238 (so l.) ( in s o l .)

io -48 x 10-4

2 x 10-123 x 10-11

5 x 10-® 3xl0-5

7 x 10-14 10"12

0.1

94Pu239 (so l.)( in s o l.)

io -48 X10-4

2 x 10-12 4 XlO-11

5 x 10-6 3 x 10-6

6 x 10-14 io - 12 0.1

94Pu240 (so l.)( in s o l.)

10“4 8 x 10~4

2 x 10-12 4 x 10-11

5 x 10-6 3 x 10-6

6 x 10-14io - 12 0.1

94Pu241 (so l.)( in s o l.)

7 x 10-3 0.04

9 x 10-11 4 x 10-8

2 x 10-4 1 x 10-3

3 x 10-12io - 9 1

94Pu242 (s o l .) , ( in s o l.)

io -49 x 10-4

2 x 10-12 4 x 10-11

5 x 10-6 3 x 10-6

6 x 10-14io - 12 0.1

85A m 241 (s o l .)( in s o l.)

io -48 x 10-4

6 x lO '12 10-io

4 x 10-6 3 x 10-6

2 x 10-13 4 x 10-12

0.1

95A m 243 (s o l .)( in s o l.)

io - ‘8 x 10-4

6 x 10-12 10-io

4 x 10-6 3 x 10-6

2 X 10-13 4 x 10-12

0.1

96Cm242 (s o l .)(in s o l.)

7 x 10-4 7 x 10-4

10-i°

2 x 10-102 x 10-6 2 x 10"5

4 x 10-12 6 x 10-12

0.1

* * * See notes p. 31++ The exem pt quantity is expressed in kg in view o f the special meaning o f the curie

in the case o f natural uranium, l c natural uranium corresponds to :

3.7 x 1010 disintegrations/s o f U 238 + 3.7 x 1010 disintegrations/s o f XJ234 + 1.7 x 10* disintegrations/s o f U 235.

49


Table I I , ContinuedMax. permissible concentrations

( ixc/cm3)M ax.perm iss.

activ ity for exemption

form notification, registration or


Individual members o f the public * *

'W ater* Air W ater Air

licensing( p-c)

96C m » (sol.)(insol.)

1 0 - 47 x 10-4

6 x 10-12lO-io

5 x 10-6 2 x 10"5

2 x 10~133 x 10"12

0.1

(sol.)(insol.)

2 x 10-4 8 x 10-4

9 x 10-12 10-io

7 x 10-6 3 x 10-5

3 x id-13 3 x 10-12

0.1

, (Cm“ (sol.)(insol.)

io -4 8 x 10~4

5 x lO '12 lO-io

4 x 10-» 3 x 10-5

2 x 10-13 4 x 10“12

0.1

96Cm246 (sol.)(insol.)

io - 48 x 10-4

5 x 10-12lO-io

4 x 10-« 3 x 10-5

2 x 10-13 4 x 10“12

0.1

87Bk249 (sol.)(insol.)

0.020.02

9 x 10-10i o - 7

1 I

o o

X X

CO

CO

3 x 10-114 x 10-9

1

08Cf249 (sol.)(insol.)

io -47 x 10-4

2 x 10~12lO-io

4 x 10-6 2 x 10-5

5 x 10"14 3 x 10-12

0.1


4 x 10-4 7 x 10-4

5 x 10-12lO-io

lO-6 3 x 10"5

2 xlO-133 xlO-12

0.1


2 x 10-4 2 x 10-4

6 x 10"12 3 x 10-11

7 x 10-o 7 x 10-«

2 x lO-13' i o - 12 0.1

* * * See notes p. 31

5 0


T a b l e I I I B

MAXIMUM PERMISSIBLE CONCENTRATIONS OF UNIDENTIFIEDRADIONUCLIDES IN AIR

(MPCU)a*, for workers directly engaged in radiation work (40 h/week) and

for individual members of the population (168 h/week)

Lim itationsW orker for 40-h/week (jj.c/cm3 of

air)

A n individual m em ber of population

for 168 h/w eek ([ic/cm 3 o f air)

If there are no a-emitting radionuclides

and if no one of the (3-emitting radio

nuclides Sr90, I129, Pb210, Ac227, Ra228,

Pa230, Pu241 and Bk249 is present, then

the (MPCU)a is

4 x 10-9 10-10

If there are no a-emitting radionuclides

and if no one of the (3-emitting radio

nuclides Pb210, Ac227, Ra228 and Pu241

is present then the (MPCU)a is

3 x 10-10 H-l

o 1If there are no a-emitting radionuclides

and if the (3-emitting radionuclide Ac227

is not present, then the (MPCU)a is

3 x 10-11 i o - 12

If no one of the radionuclides Ac227,

Th230, Pa231, Pu238, Pu239, Pu240, Pu242

and Cf249 is present, then the (MPCU)a

is

4 x 10-12 io -13

If no one of the radionuclides Pa231,

Pu239, Pu240, Pu242 and Cf249 is present,

then the (MPCU)a is

2 x 10-12 7 x 10-14

If no analysis of the air is made, then

the (MPCU)a isio - 12 4 x 10-14

* These (MPCU)a values m ay be m uch sm aller th a n the m ore exact m axi m um permissible concen tration of the m aterials, b u t the determ ination o f th is (MPCU)a requires iden tification of th e radionuclides p resen t and the concentration of each.

51


T a b l e III A

(MPCU)W* for workers directly engaged in radiation work (40 h/week) and

for individual members of the population (168 h/week)

MAXIMUM PERMISSIBLE CONCENTRATIONS OF UNIDENTIFIEDRADIONUCLIDES IN WATER

Lim itationsW orker for 40 h/week (y.c/cm3 of w ater) +

An individual m em ber of

population for 168 h/week

(|ic /cm 3 of w ater)

If no one of the radionuclides Sr90, I126,

I129, I131, Pb210, Po210, At211, Ra223, Ra224,

Ra226, Ra228, Ac227, Th230, Pa231, Th232

and Th-nat is present, then the (MPCU)W

is

9 x 10-6 3 x 10-o


Pb210, Po210, Ra223, R a226, Ra228, Pa231

and Th-nat is present, then the (MPCU)W

is

5 x 10-5 2 x 10-6


Pb210, Ra226 and Ra228 is present, then

the (MPCU)W is

2 x 10~5 7 x 10-7

If neither Ra226 nor Ra228 is present,

then the (MPCU)W is4 x 10“6 io - 7

If no analysis of the water is made, then

the (MCPU)W is4 x 10“7 10“8

* These (MPCU)W values m ay be m uch sm aller th a n the m ore exact m axim um permissible concen tra tion o f th e m aterials, b u t th e determ ination of th is (MPCU)W requires identification o f th e radionuclides presen t and the concen tration of each.

+ The values listed in th is colum n are n o t in tended for th e purpose of regulating d rin k ing w ater supplies for workers b u t for perm itting calculations o f perm issible in takes by ingestion.

52


ANNEX II

PROCEDURES WHICH MAY BE APPLIED FOR THE PURPOSE OF ESTIMATING THE DOSE TO THE LENS OF THE EYE FOR WORKERS DIRECTLY ENGAGED IN RADIATION WORK EXPOSED TO EXTERNAL RADIATION DURING WORKING

HOURS.For the purpose of estimating the dose to the lens of the eye, the

relevant tissue may be taken to be a t a depth of 3 mm below the surface of the eye. Where work involves exposure to (3-rays, eye shields or other suitable shielding may be necessary to keep the dose to the lens within permissible limits. In the case of exposure to [3-rays of energy ( E m a x ) not greater than 2.5 MeV, if the provision of such shielding is impracticable, the small additional [3-ray dose to the lens in excess of the dose permitted for more penetrating radiations, such as y-rays or neutrons, is permissible, provided that the dose in the skin is limited to the appropriate value.

ANNEX III MIXTURES OF RADIONUCLIDES

In the case of mixtures of radionuclides in air or water, the maxim um permissible concentrations of these mixtures may be computed in several ways, examples of which are given below:

(a) If the detailed composition of the mixture is not known but the radionuclides comprising it have been identified, the MPCs to be used can be those of Table I I I of Annex I or tha t of the most restrictive nuclide known to be present. This method may sometimes prove to be .unreasonably restrictive and it may be necessary to seek other methods.

(b) If the concentration and toxicity of one radionuclide in the mixture are such th a t they are predominant and the concentration of th a t nuclide is known, the MPC to be used is th a t given for this radionuclide in Table I I of Annex I.

(c) If several radionuclides are present in known concentrations such, th a t they constitute hazards of the same order of magnitude, their combined biological hazard may be computed by dividing the concentration of each nuclide by its MPC and adding the quotients. The sum must be less than 1.

(d) In other cases where the problem may be more complex and where special assessments may be required other methods of evaluation should be applied by competent authorities.

53



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Basic Safety Standards for Radiation Protectiongnssn.iaea.org/Superseded Safety Standards/Safety_Series... · 2012. 8. 1. · Australian Atomic Energy Commission Australia Representatives